ML11175A228
| ML11175A228 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/15/2011 |
| From: | Mcneil D, David Reeser, Walton R Operations Branch III |
| To: | |
| References | |
| Download: ML11175A228 (97) | |
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 OOS 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 3 I-SRO S/G B Level Transmitter ILT-471 Fails High TS-SRO I-RO 4 I-SRO Pressurize Pressure Channel PT-431 Fails High TS-SRO C-BOP 5 C-SRO 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)
QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)
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.
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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-2891 and 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 Page 4 of 30
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)
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 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 Enters TSAC 3.7.8.C and logs completion of RA verify valve position. Report OPEN or CLOSED to match SRO/BOP what the board operator sees. Strokes SW-2891 and SW-2890 and records data.
BOP Review data recorded by BOP and exit TSAC as SRO required per IT-07G.
Communications: Cue that the 4th licensed operator will make the required log entry End of evolution: Proceed to next event at Lead Examiner discretion.
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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 (CA)
RO Addresses Foldout page and notes.
Communication: When sent out to investigate Charging pump and associated breaker, inform control room Determines Chg Pump trip and goes to Step 3.
breaker is tripped on overcurrent and motor is hot to the Check any charging pump running - A should be running.
touch.
Check Charging Flow Stable - Should answer yes.
Communication: If sent to check charging pump relief, Check Charging Pump relief not lifted - no indication of wait 2 minutes and report charging reliefs on Unit 1 are lifting relief. May dispatch AO.
NOT lifting Check VCT Level - Should be > 17%
Check Charging System response: Should start B Communication: If requested, OS2 will follow up with Charging Pump and adjust lab seals using CV-142. May OI-35C, 480v Electrical Load Conservation due to 1P-2A place C charging pump in pullout.
and 1P-2B Charging Pumps running. Requests DCS Notification.
SRO 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.
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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, S/G level alarms, actual level lowering on the high unaffected channels or the feedwater regulating valve going shut.
SRO Implements AOP-2B, Feedwater System Malfunction RO Maintain Reactor Power<100%
BOP Check Feedwater Regulating Valve response normal.
- No, so take RNO actions and then enter AOP-24 If the crew is slow to take manual control of the Identify failed instrument.
feedwater regulating valve and thus initiates a manual or auto reactor trip, immediately insert the SGTR. Check if failed instrument is controlling, the BOP should determine LT-471 is controlling channel.
Establish manual control as desired. BOP takes manual control of B Feedwater Regulating Valve.
NOTE: IF asked for guidance, the Shift Manager will Return affected parameters to normal.
state OS2 will prepare the required paperwork Determine if failed instrument affects RTO (LT-471 per 0-SOP-IC-001 YELLOW to remove LT-471 doesnt) from service. Prompt OS1 to complete additional actions while OS2 prepares the paperwork. SRO 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 (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 3.3.1.A&D)
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 to be Operable End of evolution: Proceed to next event at Lead Examiner discretion. The intent is to not have the crew perform the actions to remove the channel from service.
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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.
SRO Enters AOP 24 for instrument malfunction.
If the crew is slow to take manual control of the spray RO Identify failed instrument.
valves and thus initiates a manual or auto reactor trip, immediately insert the SGTR. Check if failed instrument is controlling, the RO should determine PT-431 is controlling.
Establish manual control as desired. RO takes manual NOTE: IF asked for guidance, the Shift Manager will control of HC-431 and controls Pressurizer pressure state OS2 will prepare the required paperwork manually.
per 0-SOP-IC-001 BLUE to remove PT-431 from Return affected parameters to normal.
service. Prompt OS1 to complete additional SRO/BOP Determine if failed instrument affects RTO, which PT-actions while OS2 prepares the paperwork.
431 does not (alternate channels).
If RCS pressure gets <2205 PSIG, then LCO 3.4.1 is Communication: IF OS1 determines the need to enter not met.
AOP-21 PPCS Malfunction, The Shift Manager should inform OS1 that OS2 will review AOP-21 and take any necessary actions.
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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 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 Communication: IF OS1 determines the need to enter Table 3.3.1-1 item 7a PZR Pressure-Low AOP-21 PPCS Malfunction, The Shift Manager should Table 3.3.1-1 item 7b PZR Pressure-High inform OS1 that OS2 will review AOP-21 and take any Table 3.3.2-1 item 1d SI-PZR Pressure-Low necessary actions. 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 Action)
Table 3.3.2-1 item 4e-2 SLI-Coincident with SI (No Action)
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)
End of evolution: Proceed to next event at Lead Examiner discretion. The intent is to not have the crew perform the actions to remove the channel from service.
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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.
Subcooling > 30°F.
Communication: If surveys are requested for the (CA STEP) Check Rx Trip Not Required.
steam lines, RP can report after 5 minutes that B steam Rx Critical.
line is slightly above background and A steam line is Chg aligned to VCT.
background (CA STEP) Check PZR Level - Stable or trending to program.
Controls charging to maintain level.
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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.
Identify Leaking SG - uses High Main Steam Line alarm to RO/BOP identify B SG as leaking.
Communications: SM will be asked to notify DCS and Determine Leak Rate - RO should be able to determine implement E-Plan RO leak rate using charging/letdown balance. Otherwise, SRO requests performance of CAMP 014 from chemistry or OI-55 to determine rate.
SRO Addresses note regarding TS leakage requirement and recognizes violation of TS 3.4.13.
Communications: If asked, the SM can let OS1 know Checks RX shutdown required - leakage clearly exceeds he will take care of limited plant evacuation using EPIP 75 GPD and requires a shutdown.
6.1.
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.
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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 ROD 1.3 RO for power reduction boration and rod bank requirements NOTE: If excessive ramp rate is selected, crew will (CA STEP) Check PZR Pressure - Stable or trending to have difficulty maintaining VCT level and may program manually trip due to Charging Pump swap over to (CA STEP) Check PZR Level - Stable at or trending to RWST. program 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 (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 U1 and B SGFP Seal Water Pumps 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.
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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 the Valve failed open 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.
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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 480 V Bus energized.
Rupture with Atmospheric Dump Checks voltage on buses and breaker configuration Valve failed open (contd)
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 Crew Addresses Fold Out Page.
isolate the B S/G Atmospheric Dump BOP/SRO BOP notes the stuck open Atmospheric Dump Valve on Valve, allow three minutes for AO transit the B S/G and isolates feed flow to B S/G per Foldout and 2 minutes to close the valve. Do not Page for faulted S/G (while maintaining at least 200 close the isolation valve until after the crew gpm total AFW flow).
has transitioned to EOP-2. If crew starts to o P-38B PCV is taken to manual and shut push the AO and hurry up inform them the and/or discharge valve to B SG is taken to valve is very difficult to operate and you are Manual and Shut. If 1P-29, TDAFW Pump working on closing it. is running, it may be stopped or isolation valve to B SG shut.
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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 been noted, then the crew might maintain AFW Rupture with Atmospheric Dump flow to the ruptured B S/G per the Fold Out Page Valve failed open (contd) 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.
Verify RCP Seal Cooling - Lab seals on both RCPs should RO be >20.
(CA STEP) Verify RCS Temp Control - RNO actions taken for the uncontrolled cooldown. Ensure not dumping steam.
Lower AFW to A S/G (but ensure at least 200 gpm).
Check PZR PORVs both shut.
RO Check Normal spray valves both shut.
Check Aux spray valve shut.
Check if RCPs should remain running (they should)
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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 should SRO/RO determine that the A S/G is available for cooldown.
Check RCS temperature. The RNO directs stop dumping BOP steam and control AFW flow.
Isolate MSIVs. (will have isolated previously)
Crew If not previously accomplished, the crew may have Determines that 1MS-236, MSIV bypass valve is shut the B S/G Atmospheric Dump Valve isolated under admin control.
locally here. If not, then step 7 explicitly checks the Check if any S/G NOT faulted. (A is intact).
valve shut.
Once isolated, the crew should complete the 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.
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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 pushbutton Valve failed open (contd) and alarm reset buttons to clear LOFWTT alarm.
Isolate Feedwater to faulted S/G.
BOP Ensure B FWRV and Bypass Valves are shut CRITICAL TASK: P-38B AFW Pump is stopped and taken to pullout E A: Isolate the faulted SG before transition 1AF-4000 TAFP discharge to B S/G and AF-4021 B out of EOP-2. SRO MDAFP discharge to B S/G taken to manual and shut.
(Unit 2 will be in TSAC 3.7.5.d when placing P-38B in pullout [2 MDAFW Pumps OOS].)
BOP Isolate flow from S/G.
Ensure 1MS-2015, A ADV shut - is failed open.
The intent is that the crew has taken actions to Shuts 1MS-2019, TDAFW supply if still open.
isolate feed to the B S/G prior to shutting the Shuts 1MS-5959 and 2045 SGBD isolations if open.
Atmospheric Dump Valve isolation valve. They will Dispatches AO to shut 1MS-237 and 238 locally, should then have to decide whether to re-establish feeding remind AO that the SG is ruptured and rad levels may in EOP-3 if level is not >29% by then. be elevated.
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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/ SRO B SG has indications of a rupture (high radiation, 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.
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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 shut.
Rupture with Atmospheric Dump Reset Loss of FW Turbine Trip - previously done Valve failed open (contd) BOP Minimize Steam Dump from Ruptured SG:
1HC-478 in auto at 1050 1MS-2015, A ADV shut - is failed open Shuts 1MS-2019, TDAFW supply - previously shut Communication: When the PAB AO is contacted, insert 1MS-236, MSIV bypass valve - previously addressed Trigger 14 to shut 1MS-237 and report both valves shut, 1MS-238 is not modeled on Simulator. Isolate flow from ruptured SG:
BOP 1MS-5959 and 2045 SGBD previously addressed.
1MS-237 and 238 isolation valves previously addressed (CA STEP) Check if Feed Flow to Ruptured SG should be stopped - level in B SG may be >29%, thus BOP will CRITICAL TASK E3-A: secure P-38B MDAFW pump (in pullout) and shut AF-4021 Isolate feedwater flow into, and steam flow from the BOP and 1AF-4000 to secure feed from MDAFWP and ruptured SG before a transition to ECA-3.1 occurs. TDAFWP. Should recognize impact on Unit 2 and SRO inform U2 operator of action. (TSAC 3.7.5.D).
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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 A Rupture with Atmospheric Dump SG available for cooldown and B MSIV shut.
Valve failed open (contd) Check ruptured SG pressure >430 psig - should be well 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 RO 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.
Check PORVs and Block Valves - PORVs should be shut and block valves open with power.
RO Check PZR safety valves - Shut.
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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 maintain Event 7 and 8: B Steam Generator Tube SG level 29-65% during cooldown.
Rupture with Atmospheric Dump Valve failed open (contd)
SRO Addresses caution regarding loss of offsite power.
Reset SI, CI and 1B-03 and 1B-04 Lockouts - performs BOP 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 -
checks RCS pressure >425 psig and stops both RHR pumps and monitors RCS pressure.
Once action has been taken to start the cooldown, the scenario can be terminated at Lead Evaluators discretion.
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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.
Check only 1 CCW pump running.
Unit 2 will enter TSAC 3.7.8.F when SW-2907 and 2908 are opened. 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.
Communication: When contacted the PAB AO should Verify proper SI valve alignment.
report that SW-LW-61 and 62 radwaste SW isolation valves are both shut.
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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.
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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 Crew:
lead instructor/evaluator
- No debrief or critique due to this being an evaluated scenario.
End the scenario by placing the simulator in freeze 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 to P-38A, MDAFP, is Out of OPERABLE status within 7 days. Service in day 1 of a planned 2 day outage for seal 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-2891, South SW Hdr Xconn Valve and 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) 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.
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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
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 3 I-SRO Turbine First Stage Pressure Instrument PT-485 Fails Low.
TS-SRO I-RO 4 I-SRO Pressurizer Level Instrument LT-428 Fails Low.
TS-SRO N-BOP 5 Restore normal letdown N-SRO C-BOP 6 C-SRO Power Operated Relief Valve 1RC-430 Seat Leakage.
TS-SRO 7 M- ALL Steam Line Break Upstream of the Unit 1 A MSIV.
8 M-ALL Reactor Trip Breakers Fail to Open (ATWS) 9 C-BOP Train A ESF Sequencer Fails to Actuate.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
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 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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Guide Requirements Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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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 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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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 1P-15A 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 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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Event 5: Restore normal Letdown
- 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 8: Reactor Trip Breakers fail to open (ATWS)
- RO recognizes failure of reactor trip breakers in EOP-0
- Crew addresses faulted S/G Event 9: Train A ESF Sequencer fails to actuate
- BOP recognizes failure while implementing Attachment A in CSP-S.1 and starts equipment as directed Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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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 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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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
- Red dot on alarm windows C02 D 2-5, 2-6 and C01 1B 3-5.
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: 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.
End of evolution: Proceed to next event at Lead Examiner discretion.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Briefing on power ascension may be performed in classroom Event 2: Increase power normal rate from 28% Crew prior to beginning of the scenario Withdraws rods and/or Dilute in addition to adjusting steam RO demand as needed to establish power increase NOTE: If asked S/G B/B is 15/15 Klbs/sg directly to the tank.
End of evolution: Proceed to next event at Lead Examiner discretion.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Identifies inward rod motion, recommends placing rod control in Event 3: Turbine First Stage Pressure RO Manual Transmitter PT-485 fails Low 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 (CA STEP) Maintain RCS Tavg - checks Tavg within allowed band 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.
Determines rods are well above minimum insertion limit Verify AFD within limit - Checks DFMOOB Clear. Alarm should RO/SRO be clear. This is a continuous action step which may come into play as rods are driven to stabilize Tavg Check Rod Motion due to Instrument Malfunction. Go to AOP-24 RO SRO End of evolution: Proceed to next event at Lead Examiner discretion.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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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 Crew. RO Low recommends going to minimum charging due to loss of Letdown RO/BOP address the ARBs for alarms associated with the PZR Level failure RO/BOP Directs entry into AOP-1D CVCS Malfunction or AOP-24 Instrument Failure NOTE: AOP-1D gives guidance on stabilizing plant with loss of SRO Letdown as well as restoring it. AOP-24 gives generic guidance to take manual control as needed for the AOP 24 action:
failure. The ARB guidance (ARB 1C04 1C 1-3) is used Identify failed instrument to DEFEAT Blue LT-428 so Letdown can be restored as well as Automatic Charging. RO 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 Return affected parameters to normal paperwork per 0-SOP-IC-001 BLUE to remove LT-428 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.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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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 AOP-1D actions:
SRO (CA STEP) Check RCS Leak NOT in progress RO Determine CVCS Malfunction - Loss of Letdown go to Step 48 SRO Reduce charging to minimum NOTE: AOP-1D gives guidance on stabilizing plant with loss of Letdown as well as restoring it. RO Check if Letdown can be restored (see next event)
AOP-24 gives generic guidance to take Crew Address Technical Specifications for LT-428 using manual control as needed for the failure. The SRO 0-SOP-IC-002 ARB guidance (ARB 1C04 1C 1-3) is used to TSAC 3.3.1.A enter table 3.3.1-1 item 8 immediately. Take LT-DEFEAT Blue LT-428 so Letdown can be 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 restored as well as Automatic Charging TSAC 3.3.3 PAM may be referenced, only 2 PZR level transmitters are required. (no action needed)
Intent is to NOT take the instrument OOS per 0-SOP-IC-001-Blue, shift to auto control per ARB is desired.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 5: Restore normal Letdown Crew Check if Letdown restoration can be performed RO Ensure Letdown Orifice isolation valves - SHUT Ensure Normal Charging In-Service Check PZR Level >20%
Establish Letdown
- Open Letdown CI valves
- Open 1RC-427 NOTE: If asked, the Shift Manager will direct the Crew to
- Ensure CCW cooling established establish Charging back to automatic. This evolution can be completed per Lead Examiner
- Ensure at least 20 GPM charging based on scenario timing.
- Establish Letdown Check PZR Level at program Level SRO Inform DCS Return to Procedure Step in Effect End of evolution: Proceed to next event at Lead Examiner discretion.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 6: 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 RO PORVs using board meters Crew Determines RCS leak rate Crew determines which PORV is leaking and isolates per ARB (1C04 1C 1-4) or AOP-1A Reactor Coolant SRO Leak SRO addresses Technical Specifications for RCS 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 Required Action A.1 Reduce LEAKAGE to within limits (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
End of evolution: Proceed to next event at Lead Examiner discretion.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7: 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 BOP NOTE: Exceeding 1# inside containment exceeds (CA STEP) Determine Secondary leakage Not parametric value, TS lists 2# as the max pressure Hazardous to Personnel or Equipment before not meeting LCO 3.6.4 and the need to RO enter a TSAC. (CA STEP) Maintain Plant Within Limits Crew (CA STEP) Maintain RCS Tavg Crew determines CA Step 1 applies and attempts to trip the Unit Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 8: 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 control rods in RO Directs BOP to trip turbine manually Announces ATWS and contacts AO to go to Unit 1 Rod Drive Room CRITICAL TASK: Insert Negative Reactivity into Crew Trips turbine manually, verifies turbine tripped the core before completing Immediate Action BOP Addresses Fold Out Page Steps of CSP-S.1 SRO Verifies AFW actuation: checks both MDAFW pumps running, checks TDAFW pump running if SG levels <25% [57%]
Communication: When the TH AO is contacted to locally BOP Aligns Charging suction to RWST: Open 1CV-112B, Closes 1CV-open the trip breakers it will take 2 minutes to transit to the 112A Rod Drive Room. If the ATWS is announced over the Establishes Emergency Boration: Establish Max Charging, Start gaitronics the TH AO will report to the Rod Drive Room in BATP, Open 1CV-350, Emergency Borate Valve 2 minutes.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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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, BOP will (contd) 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 < 543ºF, will stop any steam dumping in progress Crew should determine that an uncontrolled cooldown IS in progress and proceed to isolate A S/G Isolate Both Main Steam Lines Communications: If PAB AO contacted to locally verify Identify Faulted S/G - A was previously faulted dilution flowpaths, wait 2 minutes and report dilution Crew flowpaths isolated.
RO/BOP Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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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 Isolate Flow from Faulted S/G - Actions should be taken for A Critical Task: E-2 A Isolate the faulted SG before S/G only completion of scenario.
Check Core Exit TCs and determines they are well under 1200°F Crew determines that the RTBs are now open and power is lowering as expected Communications: When the PAB AO is contacted to locally shut 1MS-235 Radwaste Steam Isolation and 1MS- (CA STEP) Stops Boration since all rods are inserted 228 MSIV Upstream trap insert Trigger 14. Report both valves as closed 2 minutes after being directed. (1MS-228 is not modeled on the simulator) Transitions back to Step 1 of EOP-0 SRO Complete Immediate Actions of EOP-0 Crew Scenario may be terminated at Lead Evaluators discretion any time after transition back to EOP-0.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 9: 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).
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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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 Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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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 evaluated scenario.
End the scenario by placing the simulator in freeze 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.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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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.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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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.
Retention: Life of Plant Retain in: Training Program File Form retained in accordance with record retention schedule identified in NP 1.3.1.
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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. Continued 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 Normal Up-Power N-SRO 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 M-RO Small RCS Leak in A RCS Loop Degrading to Large Break 5 M-SRO 6 M-ALL Large Break LOCA 7 I-BOP Failure of SI to Auto-Actuate 8 C-BOP Failure of Containment Accident Fan W-1A1 to Auto-Start 9 C-BOP Failure of SI-852A to Auto-Open
- (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 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 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
Initiating Event with Core Damage Frequency:
Related PRA Large LOCA CDF 3.4E-08 Information:
Important Components:
Low Head SI 0.4% CDF Component Cooling Water 2.1% CDF ESFAS 0.2% CDF Important Operator Actions with Task Number:
Operator fails to align for LHR Operator Fails to Start CCW Pumps Page 3 of 23
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
- 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 4 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-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
- SRO Addresses Technical Specifications Page 5 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
Event 4: SG Pressure channel PT-478 fails High
- 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 7: Failure of Safety Injection to Auto Initiate
- Crew recognizes failure and manually initiates SI and CI Event 8: Failure of 1W-1A1 Accident Fan to Auto start
- BOP recognizes failure and manually opens valve 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 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 @ 188 steps
- Generator: 145 Mwe Unit 2
- Mode: 1
- Burnup: 8800 MWD/MTU
- Power: 100%
- Boron: 696 ppm (EOL)
- Temperature: NOT
- Pressure: NOP
- Xenon: Equilibrium
- Rods: Bank D @ 184 steps
- Generator: 530 Mwe 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 SIMULATOR SET UP (perform set up per the Simulator
Setup Checklist, including entering action items per the
- Red dot on alarm windows C02 D 2-5, 2-6 and C01A 2-8 and 2-10.
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.
Withdraws rods and/or Dilute in addition to adjusting steam RO/BOP demand as needed to establish power increase of 15%/hr.
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 2: TE-401A Thot fails High RO Recognizes instrument failure for the Red channel Tcold.
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 Check RCS Tave at or trending to program - Crew should discuss current temperature and a plan on how to restore it.
Charging may be taken to manual. With the unit at a Communications: If requested by OS1 inform them OS2 reduced power program level will be raised to the full power will be preparing the 0-SOP-IC-001 RED to remove 1TE-setting based on the circuit selecting auctioneered high 401A from service. RO Tave.
Condenser Steam Dumps may be shifted to steam BOP pressure control mode per Alarm Response Procedure actions. (1C03 1E2 4-2)
RO Check control rods above insertion limits (CA STEP) Verify AFD within limits 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 T-401A, Red Tcold 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 Return affected parameters to desired values NOTE: IF SRO determines the need to enter AOP-21 SRO Using Attachment A verify failed instrument does not affect PPCS Malfunction, The Shift Manager should PPCS RTO inform OS1 that OS2 will review AOP-21 and take any necessary actions. 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.
LCO 3.3.2 ESFAS Instrumentation Table 3.3.2-1 item 4d-3.
NOTE: Intent is to NOT take the instrument out of service per 0-SOP-IC 001 RED.
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 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 start. CCW Pump not auto starting. BOP requests from the SRO to start B CCW Pump manually. (1C03 1D 2-6)
BOP or RO address ARBs as applicable.
Communications: If asked, the PAB AO reports the A SRO 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.
SRO OS1 will ask the SM to call DCS and Emergency Plan.
Communications: If asked, the TH AO will report the A 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 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 Motor Breaker Trip alarm.
SRO End of evolution: Proceed to next event at Lead Examiner discretion.
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: SG Pressure channel PT-478 fails High BOP Determine PT-478 has failed high and respond to alarms.
BOP takes manual control of B MFRV and manually Communications: SM may be requested to contact I&C closes B S/S Atmospheric Dump valve.
to troubleshoot and repair PT-478. SRO Enter AOP-24 for instrument malfunction.
BOP Identify failed instrument Communications: If requested by OS1, SM agrees to let Check if failed instrument is controlling Crew take B FRV to auto per ARB guidance by shifting Establish manual control as required. - B MFRV to controlling feed flow channels (1C03 1E2 3-5).
manual and B S/G Atm Stm Dump to manual/closed Return affected parameters to desired values. - B Communications: If requested by OS1 inform them OS2 MFRV may be placed back in auto if ARB guidance is SRO used to swap controlling feed flow channels. Alarm will will be preparing the 0-SOP-IC-001 BLUE to remove 1PT-478 from service. not be in due to the low power but guidance could still be used. (1C03 1E2 3-5)
Using Attachment A determine if PPCS RTO is NOTE: Crew may enter AOP-2B Feedwater System affected. - RTO not affected.
Malfunction to address feed systems issues. (see Remove instrument per 0-SOP-IC-001 - BLUE.
next page for actions)
Intent is to NOT take the instrument out of service per 0-SOP-IC 001 BLUE.
NOTE: IF SRO 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 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: 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)
Table 3.3.2-1 item 4d-2 SLI-Coincident with SI Table 3.3.2-1 item 4e-2 SLI-Coincident with SI 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 3.3.3-1 item 17 SG Pressure (no action)
Table 3.3.5-1 item 2 CREFS Cont. Isolation (no action)
RO BOP AOP-2B Feedwater System Malfunction steps:
Maintain Reactor Power<100%
Check Feedwater Regulating Valve response normal. - No, so take RNO actions and then enter AOP-24 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: 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 (CA STEP) Check SI not required. Crew should not secondary leak. 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 no action for this step.
SRO 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.
End of evolution: Proceed to next event at Lead Examiner discretion.
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 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 Emergency plan Communications: Shift Manager will be asked to notify DCS and implement E-Plan Steps 7 through 18 in AOP-1A are diagnostic and can be performed in any order as the SRO determines.
NOTE: Steps 7 through 18 are diagnostic and may be performed in any order.
End of evolution: Proceed to next event at Lead Examiner discretion.
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 6: 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 Direct EOP 0 Attachment A to be completed SRO Verify secondary heat sink RO Verify RCP Lab seal D/P 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 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 Start monitoring CSFSTs. SRO should direct the STA monitoring Status Trees, acknowledge request. to perform this function.
SRO (CA STEP) Verify containment sump recirc not required.
NOTE: CSP-P.1 will be identified as requiring entry by the Transition to EOP 1.3 containment sump recirc.
RO STA. Depending on the timing of the notification; Reset SI the Crew may or may not transition to CSP-P.1. If they do transition prior to transition to EOP 1.3, SRO step 1 of CSP-P.1 sends them back to procedure BOP step in effect.
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 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 Direct PAB operator to perform Attachment A Attachment A of EOP 1.3 Transfer to Containment Sump RO/BOP Direct unnecessary personnel to evacuate the PAB Recirc. Acknowledge request. No follow up report is required because the attachment will not be complete BOP Check Control Room fans armed prior to the end of the scenario. 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 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 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 Check Train A ready for recirculation - yes step 16.b in EOP 1.3 to locally shut both SI test line return 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 Check RWST level < 34%
Critical Task ES-1.3-A Transfer to cold leg 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 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 Event 7: 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 out taking action if auto actions have failed or attachment of EOP-0 A of EOP 0 will actuate SI.
Event 8: Failure of 1W-1A1 Accident Fan to Auto start BOP Determine that 1W-1A1 Accident Fan did not auto 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 field. This fan can be started per OM 3.7 which allows taking action if auto actions have failed or attachment A of EOP 0 will check this fan in operation.
Event 9: 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 valve until after immediate actions are completed and Communication: If an AO is requested to locally check verified.
the valve breaker report there is nothing abnormal from 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 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 EOP 0 Attachment A BOP Verify feedwater isolation.
Verify containment isolation Verify AFW actuation.
Check SI pumps running.
Communication: When contacted the PAB AO should Check RHR pumps running.
report that SW-LW-61 and 62 radwaste SW isolation 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 21 of 23
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 65 F and stable.
Page 22 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 evaluated scenario.
End the scenario by placing the simulator in freeze 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 23 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
Facility: Point Beach Nuclear Station Scenario No.: 4 Op-Test No.: 2011301 Examiners: D. McNeil Operators:
R. Walton D. Reeser Initial Conditions: Unit 1 is at 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-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. Due to planned grid configuration changes, ATC has requested a Unit 1 load reduction to ~92% (<500 MWe). The load reduction (at 15% per hour) per OP-2A, Normal Power Operation Attachment A, Guidelines for Load Changes Less than or equal to 10%, is scheduled to be performed immediately after shift turnover.
Event Malf. Event Event No. No. Type* Description R-RO Perform a down-power IAW OP-2A N-BOP 1 N-SRO C-BOP Trip of operating Service Water Pump C-SRO 2 TS-SRO I-RO LT-428, Pressurizer Level Transmitter (controlling channel) fails high I-SRO 3 TS-SRO C-BOP Loss of Condenser Vacuum 4 C-SRO 5 M-ALL Loss of Condenser Vacuum Degrades to Reactor Trip Criteria 6 C-RO Main Turbine Fails to AUTO & MANUALLY Trip 7 C-BOP 1P-29, Turbine Driven Auxiliary Feedwater Pump Trips on Overspeed 8 C-BOP P-38A, Motor Driven Auxiliary Feedwater Pump Fails to start 9 M-ALL Loss of Heat Sink
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 21
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SITE: POINT BEACH SEG # PBN LOI NRC 008E SEG TITLE: 2011 ILT NRC EXAM SCENARIO #4 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING #: PBN LOI TPD COURSE: N/A #: N/A TOTAL TIME: 2.0 HOURS Page 2 of 21
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)
Malfunctions:
Before EOP Entry:
- 1. Loss of a running Service Water Pump
- 1. Failure of turbine to Auto and Manual trip
- 2. Failure of P-38A MDAFW Pump to start
- 1. Lowering Main Condenser Vacuum Major Transients:
- 2. Loss of Heat Sink Critical Tasks:
- 1. RT-7, When a reactor trip is procedurally called for, initiate a manual reactor trip prior to Main Condenser Vacuum reaching 8 in Hg Abs.
- 2. FR-H.1 A Restore feedwater flow into at least one steam generator before RCS bleed and feed is required.
Page 3 of 21
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-98, created from IC-01
- 2. The following equipment is OOS:
- Red dot on G01 alarm windows C02 D 2-5 and 2-6.
- Red dot on P-38B OOS alarm windows C01A 2-8 and 2-10.
SEQUENCE OF EVENTS:
Event 1: Normal Down-Power from 100%
- Crew lowers power 15%/hr per OP-2A Normal Power Operation Attachment A Event 2: Loss of P-32A Service Water Pump
- Crew responds to malfunction and starts additional SW Pump as required
- SRO enters AOP-9A Service Water System Malfunction
- SRO addresses Technical Specifications Event 3: Pressurizer LT-428 fails High
- Crew recognizes failure and manually takes control of the plant
- SRO Addresses Technical Specifications Event 4: Lowering Main Condenser Vacuum
- Crew recognizes failure and takes actions to restore vacuum
- SRO enters AOP-5A Loss of Main Condenser Vacuum Page 4 of 21
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
Event 5: Loss of Main Condenser Vacuum requiring plant trip
- Crew identifies they cannot control vacuum and trips the unit Event 6: Turbine fails to Auto and Manual trip
- RO recognizes failure and takes action per EOP-0 Step 2 RNO Event 7: 1P-29 TDAFW Pump Overspeed trip
- BOP recognizes failure and manually attempts a start Event 9: Loss of Heat Sink
- SRO recognizes Loss of Heat Sink and enters CSP-H.1 Loss of Heat Sink Unit 1 Page 5 of 21
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-98 from IC-01 Unit 1
- Mode: 1
- Burnup: 400 MWD/MTU
- Power: 100%
- Boron: 1447 ppm (BOL)
- Temperature: NOT
- Pressure: NOP
- Xenon: Equilibrium
- Rods: Bank D @ 220 steps
- Generator: 530 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 21
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 1: Normal downpower from 100% per SRO Crew will brief the down power and reactivity control OP-2A requirements prior to taking any actions.
Record pre-load reduction information in OP 2A RO/BOP Attachment A.
An additional letdown orifice may be placed in service.
Communication: When notified, System Control Power BOP System Supervisor acknowledges report of downpower. Crew may elect to start 1P-99A and B SGFP Seal Water Injection Pumps.
Communication: If asked, SM prefers you remain on CREW Lower plant load per OP-2A Attachment A and the one letdown orifice. pre-job briefing.
Communication: When notified, the Auxiliary Operators Monitor the plant during the down power and Acknowledge the downpower and the PAB AO subsequent stabilization.
understands the requirement to monitor S/G blowdown.
End of evolution: Proceed to next event at Lead Examiner discretion.
Page 7 of 21
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 2: Loss of P-32A Service Water Pump BOP Announces pump trip and refers to ARB C01 A 3-5 for Low Service Water Header Pressure. May Note: Preferred SW Header pressure is 50-65 psig per recommend starting an additional SW pump.
OI-70. Pressure should be controlled between 50- SRO Acknowledges alarms/concurs with starting additional 90 psig. SW pump. Enters AOP-9A, Service Water Malfunction.
Note: Unit 2 CO may be asked to obtain values on YR-5832. RO/BOP Checks Forebay Level > -11 Ft.
Checks Pumpbay Level > -11Ft.
Communication: If TH AO asked, the P32-A SW pump motor is hot to the touch and the breaker is tripped on Checks Annunciator for Screen DP - Clear.
overcurrent.
Check SW Header Pressure Low Alarm - Clear.
Communication: If TH AO is dispatched to look at the SRO Start additional SW pumps to maintain header diesel low flow alarm, inform control room <695 gpm pressure (likely already done).
(alarm setpoint) if alarm is in or >695 if alarm is clear.
Place P-32A in Pullout IAW Step 4.d RNO.
BOP Note: Low SW Header Pressure Alarm is currently Direct AO to Shut SW-10, P-32A Discharge Valve.
clear, but SRO and BOP should recognize Proceed to Step 9.
that the alarm was the reason AOP was entered and enter RNO column to ensure SRO Notify DCS and address TSACs (listed next page).
proper actions were taken. Request SM check Emergency Plan.
Communication: If TH AO requested, insert trigger 12 to shut SW-10 and report valve shut.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 2: Loss of P-32A Service Water Pump BOP Check Supply Header Integrity - Satisfactory.
(contd) Check Zurn Strainer Power and Alarms.
Ensure SW header valves - Open.
Communication: If TH AO asked, report that RK 31 and Check Component Alarms - Clear.
32 have power available.
Return to Step 1 of AOP-9A.
SRO Check Forebay Level.
Check Pumpbay Level.
BOP Check Screen Alarm Clear.
Check Header Alarm Clear.
NOTE: Alarm is now clear and crew should proceed Check Zurn Strainers - Normal.
to step 5 Check Component Alarms - Clear.
Crew Check SW System - Intact.
Communication: If TH AO asked to walk down the SW Return to Procedure in effect, exit AOP-9A.
system, report back nothing abnormal has been found.
SRO Addresses Tech Specs for failure. TSAC 3.7.8.A for BOTH units with 1 SW pump inoperable.
End of evolution: Proceed to next event at Lead Examiner discretion.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 3: Pressurizer Level Transmitter LT-428 RO Acknowledges PZR High/Lo Level alarm and informs fails high Crew. RO recommends going to manual on charging.
Also due to level deviation manual control of PZR pressure may have to take place.
RO/BOP address the ARBs for alarms associated RO/BOP with the PZR Level failure.
Directs entry into AOP-24 Instrument Failure.
NOTE: IF asked for guidance, the Shift Manager will SRO state OS2 will prepare the required paperwork per AOP 24 action:
0-SOP-IC-001 BLUE to remove LT-428 from service. Prompt OS1 to complete additional Identify failed instrument.
RO actions while OS2 prepares the paperwork.
Check if failed instrument is controlling, the RO should determine LT-428 is controlling.
Establish manual control as desired. RO takes manual control of charging.
NOTE: IF SRO determines the need to enter AOP-21 PPCS Malfunction, The Shift Manager should Return affected parameters to normal.
inform OS1 that OS2 will review AOP-21 and Determine if failed instrument affects RTO, which LT-take any necessary actions.
428 does not.
Remove instrument from service per 0-SOP-IC-001 Page 10 of 21
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 3: Pressurizer Level channel LT-428 fails RO/BOP Address the level condition with the ARBs.
High (contd) - Controlling channel can be changed over per ARB to return affected parameters to Automatic Address Technical Specifications for LT-428 using SRO 0-SOP-IC-002.
TSAC 3.3.1.A enter table 3.3.1-1 item 8 immediately.
NOTE: AOP-24 gives generic guidance to take manual 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.
control as needed for the failure. The ARB guidance (ARB 1C04 1C 3-3) is used to DEFEAT TSAC 3.3.3 PAM may be referenced, only 2 PZR level Blue LT-428 charging and pressure control can transmitters are required. (no action needed) be restored to automatic.
End of evolution: Proceed to next event at Lead Examiner discretion.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 4: Lowering Main Condenser Vacuum BOP Identify that vacuum is lowering in the Main Condenser. Address Low Vacuum alarm when it comes in.
Communication: If asked, wait 2 minutes then report local air ejector air flow electronic and manometer are Enter AOP 5A for lowering Vacuum.
SRO both reading at their high limit of 25 SCFM. Maintain RCS Tave.
RO Communication: If asked to perform Attachment A, wait Check condenser pressure within limits. - Crew should CREW 3 minutes and have the TH AO report second set of air determine if continued plant operation is allowed and ejectors are lined up. set a limit for when the plant should be taken off line.
BOP Check for excessive air in-leakage. - AO should be NOTE: Vacuum malfunction can be slowed or lessoned to show vacuum is stable or recovering after the dispatched to get the local readings.
second set of air ejectors is lined up. Place all available air ejectors in service. - AO should be dispatched to align second set of air ejectors.
Communication: If asked, the Shift manager will not SRO recommend placing the priming air ejector in service. Check if Priming Air ejector should be used. - SRO should determine this is not required.
Notify DCS, PSS, Regulatory Service Duty Person, Communication: If asked, Shift manager can report he will contact the DCS, PSS, NRC Resident and the Duty CREW and NRC Resident.
Regulatory Services Person. Reduce Load as necessary per AOP-17A.
NOTE: Crew may elect to trip the unit when vacuum goes off scale low on the narrow range meters.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 5: Loss of Main Condenser Vacuum Crew Excessive air in-leakage will cause the backpressure requiring trip in the condenser to violate the operating curve in AOP-5A thus requiring a plant trip.
NOTE: Adjust the vacuum leak to maximum after the SRO Enter EOP 0 after reactor trip reactor trips. RO Verify Reactor Tripped Verify Turbine Tripped (See event 6)
CRITICAL TASK: RT When a reactor trip is procedurally called for, initiate a manual reactor trip Verify Safeguards Busses Energized prior to Main Condenser Vacuum reaching 8 in Hg Check if SI is actuated Abs Crew Verify Foldout Page SRO Verify Automatic Actions per Attachment A.
NOTE: Attachment A of EOP-0 will be handed off and the next step will transition Crew to CSP-H.1 at which point a new Attachment A will be completed.
Attachment A of EOP-0 will not be performed.
Event 6: Main Turbine fails to Auto and Manual RO Determines the Turbine did not trip.
trip Depress the manual trip button Manually runback the turbine Place the EH Pumps to pullout If turbine still not tripped, then shut both MSIVs Page 13 of 21
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7: 1P-29 TDAFW Pump fails on Overspeed Crew Crew should notice failure of 1P-29 TDAFW Pump and send an AO to look at resetting pump.
Communication: If TH AO contacted, wait 2 minutes and report the 1P-29 TDAFW Pump Overspeed linkage is broken and on the floor in pieces.
Event 8: P-38A MDAFW Pump fails to start BOP Crew should try to start P-38A and then send an AO to investigate cause of failure.
Communication: If the TH AO is contacted to look at the pump and/or breaker, wait 2 minutes and report everything appears normal.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 9: Loss of Heat Sink Crew Verify Secondary Heat Sink Available - Crew should determine that Heat Sink is NOT available and transition to CSP-H.1.
BOP BOP to perform Attachment A per foldout page RO NOTE: Crew should recognize the need to shift Check if Secondary Heat Sink is Required - YES Condenser Steam Dumps to pressure control Check if RCS Bleed and Feed is required - NO mode after going to natural circulation.
Verify S/G B/D and Sample isolation Check CR for AFW failure NOTE: Crew should determine there is a Heat Sink as Check total Feed Flow >200 gpm - NO long as they have water in the S/G(s) with RCS loop T.
Dispatch AO to perform Attachment B Stop BOTH RCPs Check Condensate Pumps - Running (CA Step) Maintain Hotwell Level Communication: When asked, TH AO will acknowledge task to perform CSP-H.1 Attachment B. Check piping INTACT Establish Feedwater flow path Page 15 of 21
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 9: Loss of Heat Sink (contd) BOP Check MFPs at least one running - NO Locally start 1P-99A and B Communication: When notified, the TH Auxiliary Operator acknowledges the request to start 1P-99A and Ensure 1P-73A AC Oil Pump running B, then 2 minutes later reports the pumps are started. Manually open 1CS-2273 FWH Bypass Valve Start one MFP - SGFPs will not start go to Step 16 RO Check no Active SI signal present Depressurize the RCS to 1765 PSIG - Crew may need to use Aux Spray depending on the air left in the IA header inside Containment.
RO/BOP Block SI RO (CA Step) Maintain Stable RCS Conditions BOP Depressurize One S/G to Less than 350 PSIG Establish Feedwater Flow Path Communication: When notified, the TH Auxiliary Prepare for Condensate Flow While Depressurizing Operator acknowledges the request to standby and open One S/G either CS-2189 or CS-2190 SGFP Discharge MOV breakers on 1B-41.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 9: Loss of Heat Sink (contd) BOP Verify Condensate Flow Path to Depressurized S/G Control Condensate Addition to Depressurized S/G -
Stable or Trending Higher NOTE: Depressurizing S/G will take some time. SRO may elect to do a crew briefing while waiting for Establish S/G Levels pressure to lower below shutoff head of a Return to Procedure Step in Effect - Which should be Condensate Pump. SRO EOP-0 Step 6.
NOTE: Crew may not see significant feed flow to the depressurized S/G on control board meters. More than likely they will use PPCS to see the required flow and change in S/G level.
CRITICAL TASK: FR-H.1 A Restore feedwater flow into at least one steam generator before RCS bleed and feed is required.
NOTE: Scenario can be stopped any time per Lead Evaluator after feed flow has been established to the depressurized S/G.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS CSP-H.1 Attachment A BOP Check Safeguards Busses Energized Verify feedwater isolation Verify containment isolation Unit 2 will enter TSAC 3.7.8.F when SW-2907 and Check SI pumps running 2908 are opened.
Check RHR pumps running 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 Check CR ventilation in accident mode Check if main steam lines can remain open (CA STEP) Verify containment spray not required.
(CA STEP) Check 4160 Safeguards busses Both Energized by Offsite Power Page 18 of 21
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.
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Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) 1.0 PLANT CONDITIONS:
UNIT 1 UNIT 2 Time in core life 400 14960 (MWD/MTU):
Reactor power (%): 100% 100%
Boron concentration 1447 ppm 16 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 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:
Due to planned grid configuration changes, ATC has requested a Unit 1 load reduction to ~92% (<500 MWe). The load reduction (at 15% per hour) IAW OP-2A, Normal Power Operation, Attachment A, Guidelines for Load Changes Less Than or Equal to 10%, is scheduled to be performed immediately after shift turnover.
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.
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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.
- Clock time is real time and you have the normal shift complement.
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