ML051400134
| ML051400134 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/17/2005 |
| From: | Wilson M Dominion Nuclear Connecticut |
| To: | D'Antonio J Operations Branch I |
| Conte R | |
| References | |
| Download: ML051400134 (129) | |
Text
c-Millstone Station Unit 2 Operator Training SIMULATOR EXERCISE GUIDE I.
Title:
LOlT Simulator Evaluation #I ID Number: ES041,I 1 Revision: 0
- 11. Initiated:
0 1/24/2005 Developer Date 111. Reviewed:
Reviewer Date 1V. Approved:
Date
Title:
Simulator Evaluation ID Number: ES04LI 1 Revision: 0 TABLE OF CONTENTS SECTIONS LISTED IN ORDER:
- 1. Cover Page
- 2. Table of Contents 9
- 3. Exercise Overview
- 4. Instructor Guide / Summary
- 5. Scenario Initial Conditions At taclments 0 Validation Checklist Training Turnover Sheet EXERCISE OVERVIEW 1.
Purpose:
1 . Evaluate the licensees' ability, as a team and individually. to safely and responsibly operate the plant during normal plant operations, abnormal operating conditions and emergency operating conditions.
- b. Evaluate iicensees in the following areas. as applicable:
Ability of the crew to perform crew-dependent (and time-critical) tasks.
Ability of individuals to perform critical tasks.
Ability of the crew to:
a) Understandhterpret alarmdannunciators b) Diagnose eventdconditions based on signalsheadings c) Understand plant/systems response d) Comply w i t h h e procedures and Technical Specifications e) Properly communicate informatiodproper crew interactions f) Perform control board operations Ability of each individual to:
2
Title:
Simulator Evaluation ID Number: ES04LIl Revision : 0 a) Respond and correctly interpret annunciators b) Correctly diagnose events c) Properly interpret integrated system response d) Comply with and use Technical Specifications e) Comply with and use procedures f) Properly perform control board operations g) Demonstrate a responsible attitude h) Properly communicate information and interact with the rest of the crew
- 2. Exercise Brief:
The simulator will be prepared for the evaluation and the licensees will be briefed on the conduct of the evaluation and the areas in which they will be evaluated.
The simulator will be initialized in Mode 1, NOP/NOT. EOL, Equilibrium Xe, 35 ppm boron. 2 2 protected and 24E tied to 24D.
Four hours prior to taking the shift. an minor earth quake < 0.09g ZPA was felt and verified by the USGS Earthquake Information Center.
All actions for the AOP 2562, Earth Quake have been performed.
Due to a slow rise in CTMT Sump. AOP 2568 RCS Leak was implemented.
A CTMT entry was made per AOP 2.568. step .5.2.d, and there is a sinal1 flange leak on 2-CH-442 Letdown Is0 Vlv.
Leakage is categorized as Identified Leakage - 5.0 gpm.
The crew is periodically pumping the CTMT Sump to ensure RCS leak does not degrade.
Management has determined that the next crew will shutdown the plant. This will provide time for engineering to develop a repair plan, notify the necessary people and brief the next crew.
Unit 3 declared an UE/D1 . The event is now terminated.
SP-2654B Forcing Sprays is scheduled for the beginning of shift.
RC-200 AVMS (Pzr Safety Vlv) is Out of Service 7
- 3. Scenario Summary:
Shortly after taking the shift, the crew will experience the following:
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Tit le : Simulator Evaluation ID Number: ES04LIl Revision : 0
- - ~___ - -~ _____ ~~~ __
- Loss of "C" SW Pp. requiring the "B" SW Pp. be started on Z2.
Failure of 6A Heater High Level Dump valve requiring the i d v e placed in manual and controlled from the Foxboro screen.
The Pzr PORV "RC- 402" will develop a leak. This will puts the cren into TSAS TSAS 3.4.2 "Safeties Valves" and require the Block VI\, to be closed.
- After the block valve is closed per the ARP. the leak on CH-442 n i l 1 increase and the crew will enter AOP-2575 "Rapid Downpower"
- The crew commences a Rapid Downpower per "AOP 2575" and AOP 2568 "RCS Leakage".
- During the Rapid Downpower, leak degrades forcing the cren' to trip.
EOP 2525 will be followed by EOP 2532 "LOCA".
- The crew will start the cooldown in EOP 2532.
While in EOP 2532, the "A" CAR Fan will experience high \ ibrations requiring it to be tripped.
During the cooldown in EOP 2532. a SGTR occurs in # I S/G. forcing the crem into EOP 2540.
The crew will select success path "CI-1" and transition to EOP 2540E.
The scenario can be terminated when the "A" CAR is secured and the crew has successfully isolated the # I S/G.
- 4. Plnnt/Simulator differences that may affect the scenario are:
None
- 3. Duration: 2.0 hours
,,IllControl Room Conduct: Operations and Communications shall be in accordance with Master Manual 14 (MP-14). Review the Simulator Operating Limits (design limits of plant) and Simulator Modeling Limitations and Anomalous Response List prior to performing this training scenario. The instructor should be aware if any of these limitations may be exceeded.
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SECTION 4 ID Number ES041,Il Revision:
Task Time 1LINMalf Instructor Inforinntion / Actii it! Assign Expected Actions Standard Utilizing an open rooin. brief the crew on the INST conduct of the evaluation and the areas in which they will be evaluated.
For Turnover Brief: INST Read Exercise Brief on pg. 36 to the examinees.
100% power, EOL. Equilibrium Xenon 35 ppin boron / Blend ratio - 165 PMW/1 BA SG Blowdown - -25 gpm each 24E aligned to bus 24D Provide and review T/O sheet SP-2654B Forcing Sprays. is scheduled for beginning of shift.
Work Control is available to perform tasks outside the control room.
Read Dynamic Simulator Examination Briefing Sheet from NTP 144 Simulator Setup and Initial Conditions: INST EOC Eq Xe. LL = 6.80. SGBD = 25/25. EB Purge
- Hang the 22 Protected Sign
- Shift the Xties for KBCCW, SW and HPSI
- Close SI-41 1 & 655, Open SI 412 & 653 (C-01)
- CloseRB211C,OpenRF3211D(C-06) 5
i SECTION 4 TD Number LSO-IL 1 Re\,ision: 0 Task Time IL)A/hlalf Instruct or Inforniat i on / Act i1.i t y Assign Expected Actions s tandard
- Close SW 97A. Open SW 97B (C-06)
EDRl4 (RO) BKR 24E from 24C (A305)
EDRl5 (RI) BKR 24E from 24D (A408)
SWR22 (22F) B SW Pp. Strainer power supply .
CVRl 1 (22F) B SW Pp. Charging Pp. kirk key supply RC-27 RC 200 AVMS failure.
On the Foxboro display. insure you can bypass the 6A Feedwater Heater level detector L5043A.
Ensure RC200 AVMS does not alarm or cause the annunciator on C-02 or indicate on RCOSE Ensure BKR A408 24E to 24D is closed.
~
Reset the RCS Leak Rate, verify at 0 gpm.
RC-04 @ 0.5% RCS Head Vent Leak - 3.5 gpm.
RUN Go to RUN If the crew is delaying forcing sprays. call as Jim LJS US directs the PPO to coiiinience forcing SP-3654B Kunze and prompt the cren to start. sprajs.
- Crew iiiay ha\^ a short briefing
- SP 2654B is approved for implementation.
PPO - Backup Heaters are placed to CLOSE PPO - PIC-100Y setpoint is lowered
- 50% output
- HIC-1 lOEiF controller start to rise.
- Pzr Press adjusted to - 2250 nsia 6
SEC TION -I ID Number ES04L11 Kc\ ision: C, lask Time IDA/Malf Iiistr uct or I nihrnia t ioii / Act i 1.it y Ass i g i i E spect ed i\c t i o 11s s tandard Annunciator PZK PRESS DEVIATION PPO - liifornis the US this is an expected alarm for Forcing Sprays.
- The ARP does not have to opened or implemented.
Trip of C SW Pump AE-1 TM-1 T2 sw-01c After crew coinpletes Forcing Sprays. trip the C SW Pp.
The SPO has several options to mitigate this event. He may:
- Start the B SW Pp. and align it to the B SW HDR, Per GDL-200, Skill of Trade.
- Uses the ARP to start the B SW Pp .
- Wait for the US to direct his actions per AOP-2565 Loss of S W.
SPO Reports the C SW Pp tripped and Annunciator. SW PIJMP C OVERLOADITRIP (C-06, BA4)
GDI,-6OO
- With US direction, rcset the C S W While one attempt to restart the C SW Pp. is Pp and attempt one restart.
7
SEC I'ION 4 ID Number ES04LI 1 Re! ision: 0 Task Ti me I D A /Ma1f Tn s t 1-uct or Info rill at i on / Ac t i1.it j Assign E spcc t c d Actions Stanclitsd
~~ ~
allowed by GDL 600, the IJS should not direct a or restart for the following reasons: - With IIS permission. starts the "B" Su' GDL-200
- Annunciator (C-06.BA4) indicates a hulted Pp and aligns it to the "3" SW I IDR. ARP pump motor. C06/BA4
- The "B" SW Pp. is available to replace the "C" AOP-2565
~-
sw Pp. ~
The US may first enter AOP-2565 or the ARP, the sequence is not critical. It is important that both procedures are eventually checked for complete iinplemeiitatioii.
~ ~~
Response to Annunciator C-06 BA-4. "SW ARP 2590E PUMP C OVERLOAD/TRIP".
us Enters the ARP, or directs the SPO to enter ARP 2590E the ARP.
SPO Checks the following to determine if alarm ARP 2590E is valid (C-06)
- Pump red light is not lit and amber light is lit. Ivith 0 amps.
- Lon. flow on components s e n 4 bj.
- Ifalarm is valid. Go To AOP 2565.
"Loss of SW" Refer to OP 2326A, "SW System" and Derform actions to nlace "B" SW uumn in 8
service on Fac. 2.
h t r y into AOP 2565 Loss of SW JS should not direct an attempt to restart the C us Determines that Aiiiiunciator (C-061BA4) AOP 2565
- w Pp SW PUMP C OVERLOAD/TRIP is lit.
- If lit, do not restart the C SW Pp.
LJ S Directs the SPO to start the B SW Pp. AOP 2565
.JS enters Section 6.0 of AOP 2565.
US Directs the SPO from Section 6 of AOP AOP 2565 SPO 2565.
Place the C SW Pp. in PTL Ensure SW-97A. Discharge Xtie Closed Ensure SW-97B Discharge Xtie Open.
Start the B SW Pp.
Check Ami. (CO6/,4 19.4) SW Pp. B SIASiLNP Start Maiiually Blocked lit.
USiSPO Direct a PEO to place the SIAS/LNP Actuation Signal HS 6484A in NORMAL.
~
LJS Directs a PEO to Stop Sodium OP 2328A Hypochlorite to the C S W Pp.
SPO Monitors
TI) Number ES04Lll - Re\isioii: 0 1ask Ti 111e I DA/Mal f Instructor I n formati on ,' \i c t i \ v i tl. Assign 1: xpe c tecl Actio 11s st,?nda1-d
- Piimp Pressure
- Motor Amps us Sends, or directs Work Control to send a AOP 2565 PEO
- to check the 'C' SW Pp. breaker A407
- to check the 'C' S W Pp
- Directs Work Control to contact maintenance to assist in determining the condition of the 'C' SW Pp.
As PEO. vruit j inin. then report
- Sodium Hypochlorite is secured to the "C" sw Pp.
- The 'C' SW Pp looks normal.
- 'B' SW Pp. Packing Leakoff, Lube Water Flow, Noise and Vibration and Discharge Press are satisfactor).
. Strainer DIP cell is vented and satisfactory.
4s Electricul Muintenance und PEO Muil I O min hen reporl.
Breaker A407 is tripped and has one dropped flag.
Looks like the breaker opened 011 Over Current.
10
SECTION 4 ID N~iiiiber ESO4LI 1 Re\.ision: 0 Task rime TDiZ/Malf' Instructor Information / Actii8itjr ,4ss i gn Expected Actions Standard If asked, report it ivill lukc ho1rr.r to determine if lrnd Mqhere the jmdt is.
US Logs into LCO 3.7.4.1 "SW SYSTEM" and 4 0 P 2565 TRM 7.1.2 1 "APPEN R SW SYSTEM" "B" SW Pp won't auto start on a SIAS until HS-6484A "SIAS /LNP Start Signal" is placed in the NORMAL.
- LCO 3.7.4.1 applies until HS 6484 is placed in the normal position.
This guidance is not in AOP 2565. but is in the following:
- OP-2326A "SW Systel11".
- ARP-2590E (C06/7, AA19) us Directs a PEO to place the "SIAS /LNP OP 2326A Start Signal HS 6484A" to NORMAL step 4.5.20 SWR 31 Wait 5 min. and insert the remote. "SIASILNP INST (NORM ) Actuation Signal HS 648.111" in NORhl.4L.
Call the CR and report switch in NORMAL.
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SE~f1ON4 ID Number F,SO41_11 Re\ isimi: 0 Tnsl, Time IDA/Malf Instructor Information ,' Acti\ ity Assign Lxpccted ilctions s la I1d aril
- ection 7 evaluates key plant parameters to Inst.
m u r e there are no other problems.
The US may direct the PPO or SPO to complete Section 7 and advise for any parameters not in the normal range.
~
US Logs out of LCO 3.7.4.1 and TRM 7.1.21
~ ~~
Heater 6A Level Hi Annunciator FW 38B @O% Fail FW Heater 6A level transmitter (LTS043A) Inst. AE-2 180 sec ramp fails downscale. TM-2
- Actual level in the heater rises to - 20 inches due to the "averaged" level lowering.
[f necessary, modify the FW 38B to ensure level Inst does not reach 34 inches. Use the PPC to monitor the actual heater level.
Heater 6A level stabilized at 20" during the validation with 110 adjustment to the nialfttnc tion.
~
US can direct the SPO to implement the ARP or us Responds to alarm CO5. BA-20. ARP direct the steps himself. "HEATER 6A LEVEL HI" 259OD. RA-20, "HEATER 6A LEVEL HI
SPO Displays "Heaters 4A/5A/bA" screen on ARP 259OD the Foxboro display.
12
SECTION 4 ID Number ES04LI1 Re] ision: 0 Task Time IDrllMalf Instructor Information / ActiIvitJ. Assign Espectcd Actions Standard IJS Directs a PEO to check
- local level gauge.
- Valve lineup
- Controller malfunction and air connection.
The actual heater level should stabilize at - 20 . 17s If Foxboro indications reaches 34 inches or ARP 2590D no reason to trip the plant. local level gage exceeds -34 inches
- Trip the Rx, Trip turbine.
- Close both MSIVs.
- Stop all condensate punlps and perform EOP2525.
4s PEO wuit 3 minutes and report: Inst
. All air lines are intact.
. Heater GA siteglass reads. - 20 inches Display the Feedwater heater level on the PPC, and report the level of the good transmitter.
[f one transmitter does not agree with the I R P 2590D ither transmitter and sight glass. Bypass the faulty transmitter on the Foxboro display.
The crew may opt to place the High and Normal SPO SPO selects and bypasses .LT 5043A.
Level Dump valves into manual before bypassing - If the SPO does not place the valves i n LT 5043A to preclude another Feedwater heater
'ZI E l I i
SECTION 4 I D Nuinber ES041,ll Re\.ision: 9
.risi, Timc 1I)A/I~lalf Instructor Information i ActivitJ. ;Issign E specL ed A c ti on s stantlard RC-402 PORV Leakage
-r4 RC06A @ RC-402 leakage AE-3 1 .j?4 Pzr Press will lower to - 2240 psia and stabilize. TM-3 Note: The leak is too small for the Acoustic Vlv Monitor (AVMS) for RC-402 to detect.
- Annunciator C02/3 A-11, AVMS Alarm will not energize.
- The US may refer to this ARP knowing it would be required if the AVMS were operating properly.
If the crew calls the OMOC or Kunze, direct the I I crew to start a plant shutdown at a rapid controlled rate.
PPO Report Annunciator Pzr Relief Va1i.e Dis c\RP 2590B
( 0 2 3. C42 Disc11 Temp Ni.
PPO Monitor for A R 1 25 90H 1 quench tank. Refcr to P 230 1 A. PD.1 I 15
SECTION 1 ID N ~ i i i i b ES041A1
~ Revision. 12 Task Time IL)A/Malf Instructor Infimnation I Acti! it\ Ass i gii Expect cd Ac ti 011s st andard and Q7Operation.
us Refer to LCO 3.4.3 Relief Valves and ARP 259013 LCO 3.4.6.2 RCS Leakage US can direct the PPO or SPO to determine the us Access the PPC Leak Rate.
RCS Leak Rate.
I The US may direct that the leak rate be restarted to get an accurate leak rate.
The PPO should monitor the AVMS and Determine Leaking POKV determine they do not indicate RC-402. 404
- Monitor AVMS (PORVs) or RC-201 (Safety) are leaking.
If the PPO closes RC-405 first, the DIS TEMP US/PPO If unable to determine leaking PORV ARP 2590B will not decrease. The procedure directs RC-405
- Close RC-403 or RC-405 to be opened and RC-403 closed.
- Monitor PORV DIS TEMP T I - 106
- When RC-403 is closed. the DIS TEMP will decrease indicating the correct PORV is isolated.
I Response to Annunciators C-03, A36 QT Hi/L,o and C-03, B36 QT Press Hi NOTE 1 : The crew may not respond to the above annunciators because they are in AOP -2568 RCS Leak.
16
rasi\
Iinic ID ill bcl a 1f Instructor Information / Acti\.itj Assi gt i Expected : k t i o n s s land ard NOTE 2: If tlie crew implenients the above ARPs.
there is guidance to trip tlie plant.
If the crew orders the reactor tripped, insert T-6 (RC04 @, 70%)
us/ If high pressure is due to relief or safety ARP CREW valve blowdown and cannot be isolated. 2590B-206 Go to EOP 2525 Standard Post Trip step 5 Actions and perform required actions.
C-03. B36
- Trip the plant and carry o u t EOP 2525.
OP 2301A PDT and QT Operation NOTE 1 : The crew may use OP 230 1 A to reduce QT Level, Pressure and Temperature. This is not required if they are in AOP-2568 RCS Leak.
NOTE 2: If the crew uses OP 230 1 A, they may use one or both of the following sections:
4.1 Recirc and Cooling the QT and PDT 4.5 Emptying 01 The US will direct tlie PPO to implement OP PPO - Verify closed LRR-64.1/54.1. OP-230 1 A 2301A. PDIlQT Recirc-Cool v1i.s step 4.1
- Open LRR-57.1/62.1 QT RecirelCIg vlvs
- Verify open RR-240, QTIPDT Hx RBCCW Out vlvs.
17
s m x m ;1 ID Number ESO4I.I 1 ision: 0 I dS1, Time IDA/Ivlalf Instructor Information Xctivit) Ass i gn Espectcd '4ctlons Standard PPO - Open RC-401 "QT Drain"
- If PDT pressure is higher than QT pressure:
- Verify closed, GR-11.1 and GR-I 1.2 "PDT Discli Isolations".
- Ope11 LRR-47.1 "PDT VC11t"
- OPEN RC-400 ,'QT Vetlt" Rising RCS Leakage T5 RC-04 (35.0% RCS Head Vent Leak - .35 gpm.
Enter AOP-2568 "RCS Leak" The US may hand off Section 3.0 of AOP-2568 to us Directs entry into AOP 2568 and performs AOP 2568.
the PPO or SPO, requiring the SPO to report any Plant Assessment. Sec. 3.0 parameters out to the normal range.
The US or PPO/SPO should find all the parameters necessary to complete Section 3.0 within the required range with the possible exception of:
- Pzr Level
- Pzr Pressure 18
SECTION 4 ID Number ES04LI1 Kci ision: 0 I ask Tiiiie IDA/klal f Instructor Intorination / ActiL it! Assign Expected Actions s talld nrcl The PPO/SPO map need to report low Pzr Lei,el If Pzr 1,vl is not 3 5 to 70Y0 .4OP 2508 and ensure max charging and inin. letdown. Step. 3.2
- Manually operate Charging and I xtdown.
The PPO/SPO may need to report low Pzr USiPPO If Pzr Press not 2225 to 2300# AOP 2568 Pressure - Place all BU Heaters to ON. Step. j.3
- BU Heaters should already be ON. - Ensure Spray Vlvs closed.
If the US handed off Section 3.0 to the SPO, the AOP 2568.
lis will implement Section 4.0. Sect. 4.0 US/PPO If RCS leakage exceeds available charging AOP 2568.
capability, TRIP the Rx. and Go To EOP Step 4.1 2525.
- The leak rate is not > charging capacity.
- No need to trip at this time.
US/PPO Direct RCS Leak Kate AOP 2568.
/SPO - Step 4.3 The operator access the PPC and reports present leak rate.
19
I The US may have previouslj. done an KCS Leak IJS I I n i ti ate s Ixali Rat c Ile t e r m i iiat io n . A O P 2568.
Rate. Crew Step 4.4 US should determine leak rate I O gpm identified leakage.
If leakage is >25 gpm. SM Classify per FAP06 FAPO6
- SM must classify Unusual Event / D1 per - IJE/Dl per BU2 if leakage >25 gpm.
BU2 Identified Leakage > 25 gpm.
Log into LCO 3.4.6.2 Refer to AOP 2575 and start a Kapid Downporter The US may personally implement. o r handoff. US/SPO Implement Section 5 to ensure 110 other \OP 2568 Section 5.0. leaks. Section 5 Ifrequested, report 110 activity in RBCCW and no Crew attempts to identify leak location by AOP 2568 leakage in Aux. Bldg. After a minimum of 20 performing applicable steps of AOP 2568.
minutes for a visual inspection. (Time may be May direct chemistry sample RBCC W adjusted if multiple personnel are assigned to the System or have PEO observe CVCS piping inspection) in Aux. Bldg.
Enter AOP 2575 Rapid Downpower Crew determines that identified RCS leak AOP 2568.
rate exceeds T/S 3.4.6.2 limit and begins to AOP 2575 initiate a plant shutdown per AOP 2575.
20
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i SECTION 4 in Number ESO4LI 1 Re\rision: -
0 1 ask I'ime IDA/Malf Inslr uc t or I n f'orinat i o t i / '4 c t i i s i t I Assign Lx pe c t ed A c ti ons Standard USiPPO Insert Group 7 five to ten steps. AOP 2575 Step 3.12 PPO START additional charging piinips as AOP 2575 required. Step 3.13
- A controlled downpower of >20%/hr. is PPO Based on plant conditions, SELECT the AOP 2575 reasonable, unless RCS pressure is challenged. appropriate boron addition rate from the Step 3.14
- If RCS pressure is challenged. <:20%/hr. tables.
should be directed.
PPO Borates to charging pump suction: AOP 2575 Step 3.15 ADJUST setpoint of "BORIC' ACID FLOW" controller. "FC-2 1OY to flowrate
.I' determined in step 3.14.
- OPEN "RWST TO CHG SUCT, CH-504."
- PLACE "MAKEUP MODE SEL" switch in "MANUAL."
- START a boric acid pump. and CHECK boric acid pump discharge pressure greater than 98 psig.
- OPEN "VCT MAKEUP BYPASS.
CH- 196.
22
c ci N
I SECTION 4 ID Number ES04LIl Rei ision: 0 ~
Task Time IDA/Malf Instructor In form at i on / Act i vi t y Assign Expected Actions Standard
- Turbine
- Electrical buses
- SW&RBCCW RCS Inventory Control (PPO)
- Pzr level & Subcooled margin (SCM),
value &: trend If Pzr Lvl is not 20 to 80%, the PPO should
- manually operate charging and letdown to compensate for Pzr Lvl.
RCS Pressure Control (PPO)
US/PPO should initiate SIAS, CIAS & EBFAS at If Pzr. Press < 1714 p i a OP-2260 approximately 1800 psia. - ensure SIAS, CIAS, EBFAS &
CT-1 Trip 2 RCPs (LOCA-13) CRAC
- secure one RCP per loop CT-1 CT-2 Secure all RCP within 5 min. of loss of - secure all RCPs if < NPSH CT-2 NPSH. (2260 3.1.1) - ensure PORVs closed, if open, close the Block Vlv.
Core Heat Removal (PPO)
- RCP status
- LOOPdelta-T
- Th SCM RCS Heat Removal (SPO) 24
- SG pressures 880-920#
- RCS Tc 530-535 O F
- SG levels, value & trend
- RCSSCM Containment (CTMT) Isolation (PPO)
- Radrnoiiitors inside CTMT in alarm and rising. (R7891 Refuel Floor)
- outside CTMT, steam plant. not in alarin or rising.
- CTMT pressure > I # and rising.
If CTMT Press 2 4.42 psig.
- Initiate SIAS, CIAS, EBFS, CRAC
& MSI CTMT Temperature & Pressure Control (PPO)
- CTMT temperature > 120" F
- CTMT pressure >I# and rising.
- Ensure at least 2 CARS with KBCCW If CTMT Press > 9.48 psig,
- Ensure CSAS actuated.
- All CS Pps. > 1300 gpm.
SEC flOh 4 111 I \ j ~ i i i i L ~ES04LlI
~ Kcj ision: 12 Task Tiiiie TDA/M\/Ialf Instructor information / it\, Assign kxpccted Actions Standard CTMT Combustible Gas Control (PPO)
- CTMT teiiiperature > 120 F
- CTMT pressure > I # and rising.
- Place CTMT Aux Fans in Slow
- Start all PIR Fans us Query PPO & SPO regarding the status of EOP 2525 EOP 2525 subsequent actions SPO Report subsequent actions complete and EOP 2525 verified when accomplished.
PPO Report subsequent actions complete and EOP 2525 verified when accomplished.
Verify that the STA has iiidependently diagnosed us Query board operators re: safety function EOP 2525 the event .
status per form di agn o st i c fl o w c hart, and EU-1 diagnose small break 1,OCA. transition to EOP 2532.
STA Evaluate and concur.
Enter EOP 2532 LOCA LJ S Directs SFSCs for EOP 2532 bc initiated.
26
St;.('TION 4 ID Number ES04LI 1 Kelision: 12
.l'asli Time IDAIMalf Instructor Information i Activity Ass i g n Expected Xc t i o 11s Standard Classification will be done as an ildrnin JPM later. SM Classifies e\.ent as either an Alert. C-1 based on RCB2. 3 or 4. I MP-26-EPI-FAPO6 STA Verify that the STA has independently classified the event NOTE 1: The BOOTH INSTRUCTOR must remove the following IO when the
- CAR Fan is stopped
- and the reset button "CAR FAN VIB RESET
is pressed.
NOTE 2: 1 minute after the US returns the "Annunciator Silence Switch" to NORMAL.
insert the following IO.
T7 IO "ON" Annunciator C-01 A4. "CTMT AIR PPO Reports annunciator for "CI'MT AIR EM-1 RECIRC FAN 'A' VIBRATION HI" RECIRC FAN 'A' VIBRATION HI" TM-5 energized.
IO -'C-O1 A4" LJSIPPO Implements the ARP for '2-01 .,44. 2590A-0 13 (Delete) - Stop ",4"CAR fan per OP-2323iZ.
- Monitor CThl'I for increasing pressure.
temp and moisture.
- Submit TR to maintenance.
M'hen directed by Chemistry to sample SGs. after Inst. i Direct Chemistry to sample S W s ) . EOP 2532
-30 inin delay report both SCrs MDA.
J. SPO 27
SEC'I'ION 4 ID N LLIIILX~ ES04LI 1 Iicvision: 12
'l'asl<
' 1. i me IDAiMalf Instruct or 1n form at i on / Act i 1.it y Ass i gn Expected Actions Stand r1rd NOTE: Give the PPO time to identify the High CAR Vibration before inserting the follcn-ing malfunction. We don't want to mask the HI VIBRATION annunciator.
SG02A @ 60% #1 S/G Tube Rupture - 750 gpm.
If MSIVs are closed, the SJAE won't rise but the SGBD RM will rise and the # 1 SiG Le\.el will e\witually show an unusual rise indicating a SGTR in # I S/G.
PPO Vcl-if?.SIAS. CIAS. EBFAS. and ('RACon EOP 2532 c-01x Step 5
- Check SI Flow adequate
- Ensure all available Chg. Pp. operating.
- Ensure vital switch gear cooling
~
CT-2 Secure all RCP within 5 min. of loss of PPO If RCS Press NPSH EOP 2532 NPSH. (2260 3.1.1) Step 6
- Trip all RCPs
- CT-2 close steam dumps to condenser
- spray valves 28
I SECTION 4 lL) Number ES04L.I 1 Ke\.ision: 0 I'as I<
Time IDAiMalf Instructor Information / Activity Assign Lkpected Actions s tan d arci PPO Isolate the LOCA EOP 2532
- Step 7 Ensure valves are closed for isolating LOCA
- Check not RBCCW Radmonitor.
- Check RBCCW Surge Tk not rising PPO Check LOCA NOT Outsidc CTbIT
- Check Kadmonitors outside CTMT on PPC IJ S/PPO/ Place Hldrogen Analyzers in Service EOP 35-32 SPO - EOP 2541 t\ppendix 19.
Step 9 MA-2 TM-6
~
When the crew determines they have a SGTR in # 1 PPO If CTMT pressure is '4.42 psiig or CTMT EOP 2532 S/G, move forward in this guide to EOP 2540. Radmonitors are in alarm Step 10
- Ensure SIAS, CIAS, EBFAS, MSI &
CRAC.
- Start all available CAR Fans \vith RBCCW I-low.
PPO If CTMT Press. 9.48 psig. EOP 2532
- Ensure CS Pps. running Step 1 1
- Ensure CS Flo\v ;' 1300 gpm.
SPO If MSIVs are closed, open AK- 1 7 EOP 2532 "Vacuuni Breaker" Step 12
SECTION -I ID Nuiiiber ES04LI1 I<e\.ision: 0 lasli Time TL)A/MalI Instructor 1nfi)rmation / Acti\.ity Assign Expected ilctions s t and ard__
SPO If MSIVs are open EOP 2532
- Step 15 Align Condenser Air KeniokA to Unit 2 stack
- The operators will coinmence a rapid cooldown SPO Initiate a controlled cooldown EOP 2532 within the Tech Spec limits. - If MSIVs Open, use SD/RP Vlvs Step 17
- If MSIVS Closed. usc ADVS.
- SIAS flow must be capable of PPO Initiate a controlled depressurization of the EOP 2532 recoverin~/maintaiiiingRCS pressure. RCS to SDC conditions. Step 18
- The crew should establish and maintain the - If no RCPs use Aux Spray RCS press. vs temp. within the PT Curve. - If RCPs running use Main Spray Major change in plant conditions (tube rupture) When crew recognizes they have a LOCA OP 2260 requiring transition to Functional Recovery (2540) with a S/G Tube Rupture. Step 1.19.2
- Implement the Diagnostic Flow Chart EC-1 (2541 Appendix 1)
- Confirms 2 events requiring Functional Recovery (EOP 2540)
EOP 2540 Functional Recovery IJ S Crew transitions to EOP 2540 Functional ELI-2 RecoLxry.
SE('T1ON 4 1L) N~itiiber ES04LI 1 Rci.ision: 0
'Task
.I' i me ID A/MaI 1' Instructor Inforination / .\cti\ it) r\ ssi gn Espectcd (ktions Standard The SM should classifj. the e\'ent as sM Classify the Event FAPO6 EOP 25.10
- AlertiC1 per RCB4 Step 1 Note: Classification will be accomplished in JPM-A4SRO.
IJS - Enter time in Safety Function Tracking 254*
Page Ensure Master Silence i n Off
-1 SteQ2 IJSISPO Sample both SiGs EOI' 2 5 40 Step 4 I
I Hydrogen Analyzers may already be in service. USiSPO Place Hydrogen Analyzers in service. EOP 2540 Step 5 us Identify the Success Paths using RATS. EOP 2540 Stel-, 6 Safety Function Success Path Priority Operating Reactivity Control RC- 1 CEA Insertion Y Y 31
SFC I I O N -I ID Numbcr kSO-IL,TI Re\ ision: 9 1as],
Time IDA/hlalf Instructor Information / Acti\.ity Assign Espectcd Actions s tandard Maintenance of Vital MVA-DC- 1 Battery Chargers/Station Batteries Y Y DC Power Maintenance of Vital MVA-AC-1 RSST Y Y AC Power RCS Inventory Control IC-2 Safety Iiijecti on Y Y RCS Pressure Control PC-2 Saturated Y Y RCS and Core Heat HR-2 SI operating Y Y Removal I
Containment Isolation CI-1 Automatic/Manual N N Containment CTPC-2 CARS (Emerg) Y Y Temperature and Pressure Control Containment CCGC- 1 Hydrogen Recombiners Y Y Combustible Gas Control 1 US Directs the STA to verify the Safety EOP 2540 Function are satisfied for the chosen Step 8 success paths.
32
SECPION 4 ID Nuinber ESO4LI 1 Re\.ision: 0
.lask Time I DA/Malf Instruct or Ill formation 1 Act i vi t 1, Assign Expectcd Actions Standard 1 he U S should transition to EOP 2540E. us Perform operator actions for chosen EOP 2540 success paths based 011 priority assigned. Step 9 E17-3 EC-2 Transition to EOP 2540E us Transitions to EOP 2540E Containment EOP 2540 Isolation Step 9 US/PPO If CTMT Press. 4.42 psig or CTMT EOP 2540E Radmonitors rising or in alarm. Step I
- IJS directs the PPO to eiisurc SIAS, CIAS, EBFAS AND MSI on C-01 and c - 0 1 x.
The crew will identify the #1 S/G as faulted by us/ If a SGTR is indicated. identify and isolate EOP 2540E one or all of the following. the most affected S/G. Step 2 CREW
- Feed Flow/Steam Flow mismatch - US references EOP 2541 Appendix 12
- SGBD radinonitor
- SJAE radmoiiitors CT-3 Cooldown to 5 515 Th. CT-3 Maxiilium controllable rate is characterized b \ r a I JS/SPO Coininence an RCS cooldown at maximum rm 254 I rate that does not further degrade the conditions of controllable rate to <5 15 Th in both S/C;s. Append 12 the plant. Step 1
- If the condenser is available SDiRP kfforts should be made to presene NPSH, Vlvs \vi11 be used.
Subcooling and Pzr/Head Levels. while trying t o - IF the condenser is not available. both limit S/G level by isolating the Si(; as soon as ADVs will be used.
possible.
The US should give the PPO a pressure range the UWPO Depressurix the RCS using main or aux.
does not violate any of the listed limits. spraj. while maintaining the following Append 12 limits: Step 2 If HPSI throttleistop criteria is mct, the PPO US/PPO If HPSI throttle/stop criteria are met: EOP 2541 should limit injection flow to stabilize Pzr. Le\ el Append 12
- Control charging and letdown Step 2 and pro 111o te depres sur i zati on.
CT-4 Isolate the faulted SIC within 60 minutes CT-4 of evidence of a tube rupture. (OP 2260 3.3.1)
US/SPO Directs the SPO to isolate # 1 S/G per EOP 2541 Appendix 12 Append 12 Step 6
SPO Isolates # 1 Si(; bj.:
1 . # 1 ADV in AT JTO @ 920 psia and closed.
- 2. Close MSIV
- 3. Close MSTV Bypass
- 4. Close FW-4 1.A (FRV)
- 5. Close FW-42A (FRV Block Vlv)
- 6. Close FW-SA (MF Isolation Check)
- 7. Ensure closed MS-220 (Blowdown v 111)
- 8. Pull-to-Lock both AFW Override handswi tches
- 9. Close FW-43A (Aux FRV)
- 10. Close FW-12A (AUXFW Check VIV) 1 1. Close MS-201 (TDAFP Steam Supplj,)
- 12. Close bIS-265 (MS Lolv Pt. Drain)
- 13. Check all safetj- ~ - 1closed
~s The scenario can be terminated when the crew has successfully isolated the #1 WG.
35
Section 4
SUMMARY
'Title: Simulator Evaluation
[D Number: ES04LI1 Rev i sion : 0 C K1TIC A L '1-ASKS CT-I : Trip 2 RCPs (LOCA-13)
CT-2: Secure all RCP within 5 min. of loss of NPSH.
cr-3 Cooldown to 5 515" Th.
cw: Isolate the most effected S K .
36
Section 5 SCENARIO INITIAL CONDITIONS
Title:
Simulator Evaluation ID Number: ES04LI1 Revision: 0 Initial Conditions
- 100% power, NOP/NOT, EOL, Equilibrium Xenon
- 35 ppm boron / Blend ratio - 165 PMW / 1 BA
- %2 is protected
- SG Blowdown - -25 gpm each
- 24E aligned to bus 24D Out of Service Equipment RC-200 AVMS Crew Instructions The simulator will be prepared for the evaluation and the licensees will be briefed on the conduct of the evaluation and the areas in which they will be evaluated.
The simulator will be initialized in Mode I. NOPNOT, EOL, Equilibrium Xe. 35 ppm boron, 22 protected and 24E tied to 24D.
Four hours prior to taking the shift, an minor earth quake < 0.09g ZPA was felt and verified by the USGS Earthquake Information Center.
All actions for the AOP 2562, Earth Quake have been performed.
Due to a slow rise in CTMT Sump, AOP 2568 RCS Leak was implemented.
A CTMT entry was made per AOP 2568. step 5.2.d, and there is a small flange leak on 2-CH-442 Letdown Is0 Vlv.
Leakage is categorized as Identified Leakage - 5.0 gpm.
The crew is periodically pumping the CTMT Sump to ensure RCS leak does not degrade.
Management has determined that the next crew will shutdown the plant. This will provide time for engineering to develop a repair plan, notify the necessary people and brief the next crew.
Unit 3 declared an UE/DI. The event is now terminated.
SP-2654B Forcing Sprays is scheduled for the beginning of shift.
RC-200 AVMS (Pzr Safety Vlv) is Out of Service 37
ATTACHMENT VALIDATION CHECKLIST
Title:
Simulator Evaluation ID Number: ES04LI 1 Revision: 0 Verified By:
Remote functions:
All remote functions contained in the guide are certified.
Malfunctions:
A11 malfunctions contained in the guide are certified Initial Conditions:
The initial condition(s) contained in the guide are certified or have been developed from certified ICs.
Simulator Operating Limits:
'The simulator guide has been evaluated for operating limits and/or anomalous response.
Test Run:
The scenario contained in the guide has been test run on the simulator. Simulator response is reasonable and as expected.
Date 38
Mf'2 Slh/tl iLiZ-rOR 7TRAINING SHIFT TURNOVER REPORT DATE-TIME PREPARED BY SHIFT Todav 0515 Unit Supervisor /"NIGHT" Shift 18:OO - 06100
~
\/ODE 1 R Y POIVER 100 Yo
.\If<(;. Ill'. 1 TTS Thermal: 2699 MWTFI PZR PRESS 2250 psia Electric: U M W e RCS T-A P'E m d c g r e e s F KC'S Identified: 3.5gpiii PROTECTED: TrainiFacility L E4 h:-lGE Unidentified : 0.33 gpm Date/Time:Todav 001 5 22 (YELLOW)
Date Time LCO Action Act ion Requirement Equipment Reason Continuous T S LCO a n d TRM ACTION Statements in cffect (if more than one ACTION requirement per LCO, list each semratelvl Action Requirement LCO Action Equipment Reason Intinite action: Establish hourly fire watch. I TRMAS 3.7.10 1 See AIL See Active Impairment List.
I Infinite action: Attacliment I o f O P 2301A I TSAS 3.j.3.S 1 a13 I RC-200 I Failed SP 24 1 OA J OD COMPENSATORY ACTIONS / T e m p LOGS (Bold: Tech Specs, Italics: TRM)
EVOLUTIONS IN P R O G R E S S & N O T E S Refererice /Date 10 1 gpm leak 011 CH442 Today CThl J Sump I S being pumped periodically to inonitor KC'S Leakage SF-lOi4B "Forcing Pzr Sprays for Boroii Equalization" IS approked for completion on this \\atch Unit 2 Chemistry ON-LINE STATUS REPORT REACTOR COOLANT Time 0 6 2 5 1% ra 111et er Reading- 1 Parameter Reading Poner 100 Yo 1; I uori de 0.81 ppb Ta\;e 572 delrF Chloride 1.75 m b I Boroii 35 PPm (1 Oxygen <5 PPb I I Blcnd Ratio: 1 165: 1 I
Attachment Guide No.: ES04LI1 SCENARIO ATTRIBUTES CHECKLIST Scenario
Title:
1- 0 1T S i in 111ato r Ev ai uat i on Number: ESO41,I I Technical Reviaver: D. A. fantalone Date: 12/03i2004 QUALITATIVE ATTRIBUTES Y 1 The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.
Y 2. The scenario consists mostly of related events Y 3 Each event description consists of:
the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the expected Emergency Plan classification the event termination point (if applicable) 4 No more than one non-mechanistic failure (e.g., pipe ,reak) is incorporated into the scenario without a credible preceding incident such as a seismic event.
Y 5. The events are valid with regard to physics and thermodynamics.
Y 6. Sequencinghiming of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.
N/A 7 If time compression techniques are used, scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.
Y 8. The simulator modeling is not altered.
Y 9. The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure that functional fidelity is maintained while running the scenario.
40
Attachment Guide No.: ES04LIl SCENARIO ATTRIBUTES CHECKLIST Note: Following criteria list scenario traits that are numerical (quantitative) in nature. Credited malfunctions tasks and procedures should be boided in the evaluation guide.
-l
, Total Malfunctions (TM) - Include EMS - (5 - 8) 6
- 1. Trip of C SW Pump
- 2. Fail FW Heater 6 A level transmitter do\vnscale.
- 3. RC-302 P0RVlxnkage
- 4. ftCS Leakage > Charging 5 . CTMT AIR REClRC FAN A VIBRATION HI
- 6. # 1 S/G Tube Rupture - 750 gpm.
- 2. Malfs after EOP entry (EMS) - (1 - 2)
- 1. CTMT AIR RECIRC FAN A VIBRATION H I
- 3. Abnormal Events (AE) - (2 - 4) 1 . Trip of C SW Pump
- 2. Fail FW Heater 6A level transmitter downscale.
- 3. RC-403 PORV Leakage 7
- 4. Major Transients (MA) - (1 - 2) 1 . RCS Leakage Charging
- 2. # I S / G lube Rupture - 750 gpm.
- 5. IOPs entered requiring substanti\re actions (EU) - ( I - 2) 3 1 . EOP 2532 Loss of Coolant Accident
- 2. EOP 2540 Functional Recovery
- 3. EOP 2540E Functional Recovery of Containment Isolation
- 6. EOP Contingencies requiring substantive actions (EC) - (0-2) 2 I . Major change in plant conditions (tube rupture) requiring transition to Functional Recovery (EOP 2540)
- 2. Evaluation of Success PatWSafety Functions requiring transition to Functional Recovery of Containment Integrity (EOP 2540E)
Attachment Guide No.: ES04LIl SCENARIO ATTRIBUTES CHECKLIST
- 2. Secure all RCP within 5 min. of loss ofNPSH.
-3. Perform a plant cooldo~vn5 5 15. Th
- 4. Isolate the most affected S/G.
- 8. Approximate Scenario Run Time: 60 to 90 min. Total 120
- 0. Technical Specifications exercised during the scenario. (Y/N)_ 1 -
42
Attachment Guide No.: ES04LIl SCENARIO ATTRIBUTES CHECKLIST IC-92ES04LIl Load Limit Pot Setting = 6.80 A B C -D AS1 Upper 4.70 4.72 4.73 4.67 AS1 Lower 4.73 4.68 4.75 4.67 Nuclear Power 4.56 4.82 4.68 4.67 A T Power 3.91 4.10 3.92 4.07 Tcold Cal. 4.80 4.80 4.80 4.85 43
Millstone Station Unit 2 Operator Training SIMULATOR EXERCISE GUIDE I.
Title:
LOIT Simulator Evaluation #2 ID Number: ES04LI2 Revision: 0
- 11. Initiated:
1112/05 Developer Date Reviewer Date IV. Approved:
~~
Operator Trayfing Supervisor Date 1
Title:
Simulator Evaluation ID Number: ES04LI2 Revision: 0 TABLE OF CONTENTS SECTIONS LISTED IN ORDER:
- 1. Cover Page 3 Table of Contents
-> . Exercise Overiiew
- 4. Instructor Guide / Summary
$ . Scenario Initial Conditions Attachments Validation Checklist Iraining Turnover Sheet EXEKCISE OVERVIEW
- 1. Iiirpnse:
- a. E\duate the licensees abilit!. as a team and individually, to safel) and responsibly operate the plant during normal plant operations. abnormal operating conditions and emergency operating conditions.
- b. E\.aluate licensees in the follou ing areas. as applicable:
I) Ability of the cren to perform creu-dependent (and time-critical) tasks.
- 3) Ability of indiLi1uals to perform critical tasks.
- 3) Ability of the crew to:
a) Understandhterpret a1artns:annunciators b) Diagnose eventsiconditions based on signals/readings c) Understand plant/s! rtems response d) Comply witWuse procedures and Technical Specifications e) Properly communicate informatiodproper crew interactions 0 Perform control board operations
- 4) Ability of each individual to:
a) Respond and correctly interpret annunciators b) Correctly diagnose e\ ents c) Properly interpret integrated system response d) Comply uith and use Technical Specifications e) Comply with and use procedures f) Properly perform control board operations g) Demonstrate a responsible attitude h) Properly communicate information and interact with the rest of the crew 2
.I itle: Simulator E\duation I l l Number: ES04LI2 Re\'i si on : 0 3 Exercise Brief:
The simulator will be prepared for the evaluation and the licensees will be briefed on the conduct nt'the evaluation and the areas in which they will be evaluated.
The simulator will be initialized to IC-91 or equivalent. critical at 1 YOpower, BOL, positive MTC, 1650 ppm Boron. There are no surveillances in progress. A snow storm has been predicted for the area with accumulation of 3-5 inches. Winds are presently from the West-Southn-est at 20-25 mph. Snow has already started to fall. The crew \vi11 be instructed to raise pmver to 4% and stabilize in preparation for Turbine warm up in accordance with OP 2203, Plant Startup.
During the power ascension. the dilution valve will fail to close resulting in adding more PMW than desired. The crew will stop the power ascension and take action to stop the dilution. After the crew stabilizes power. the "D" Circulating Water Screen DIP will rise to the point that the "D" Circulating Water Pump trips. The crew will enter AOP 25 1 7, Circulating Water Malfunctions. and perform steps associated with the loss of a Circulating Water Pump. While the crew is performing steps of AOP 251 7, Channel Y Pressurizer Pressure transmitter will fail high resulting in the opening of the spray \dves. The US will direct the PPO to either take manual control of Channel Y pressurizer pressure or swap to Channel X. When the crew contacts the I&C Department concerning the failed pressure transmitter, annunciator C'-8 on C-05. Main Steam Is01 Va11.e Air Press Lo. will alarm. The crew will respond to the annunciator by referencing the appropriate Annunciator Response Procedure. Shortly after the annunciator alarms. the #2 M S I V will close. This will result in an Excess Steam Demand in the Enclosure Building. The crew should manually trip the reactor. During the perfbrmance of EOP 2536, Excess Steam Demand, VA-20 will suddenly deenergize. The loss of VA-20 will result in the opening of the #2 Aux Feed Regulating Valve. The crew must take action to stop feed to #2 SiG.
The scenario may be terminated when the S/G has been isolated and actions have been taken to prevent exceeding PTS limits.
-3. PlantiSimulator differences that may affect the scenario are:
None
- 4. Duration: 1.5 hours
- Ill Control Room Conduct, Operations and Conimunications shall be in accordance with Master hlanual 14 (MP-14). Review the Simulator Operating Limits (design limits of plant) and Simulator 4 lodeling Limitations and Anomalous Response List prior to performing this training scenario. l h e instructor should be aware if ani\,of these limitations may be exceeded.
3
SECTION 4 ID Number ES04I,I2 Kmision: 0 Task
!init: IDAIbIalf Instructor In formati on /i \i c t i t y
\ T i A ssi gn Expected ,Zctioiis stnndard IC-91 or Simulator Setup and Initial Conditions:
equivalent 1 % Power, BOL, RCS Boron 1680 ppni.
CHR06 (22.8) Insert a remote function for wind direction from CHR07 (223.4) the West-Southwest at 23 mph.
CHR08 (23.6)
CHR09 (224.1)
CHRlO (23.1)
CHRl1 (222.9)
RP04A Insert malfunctions to prevent all four Reactor TM 7 RP04B trip buttons from tripping the reactor.
RP04C RP04D RP27.4 Insert a inalfunction to prevent an automatic Reactor trip.
Ensure all 4 Circ Water Pumps are operating.
Set blowdown to 40 gpm on both S/Gs.
Ensure the following FRV Bypass Valve positions:
- 1 - 33.2%
- 2 - 33.7%
Ensure conditions are stable prior to the crew taking the shift.
4
Task Tim 1DNhl al 1' I 11st ruc t o r I n for i n nt i on / ;\ c ti 1.it > Ass i gn E spec t ed 11c ti ( n s
) St:1nclmi Provide the crew with the following information:
0 I YOpower, BOL, positilre MTC 0 Groupp 7 CEAs @ 135 steps 0 1680 ppm boron 0 Blend ratio - 2.5: 1 0 SG Blowdown - 40 gpm each 0 Condensate on short recycle 0 "A" Main Feed Pump in operation 0 Vacuum being maintained n i t h the Hoggers 0 24E aligned to Bus 24C 0 Forcing Pressurizer Sprays 0 2 Charging Punips running 0 Snow storm in progress (20-25 mph winds) 0 No surveillances due.
Provide the following documents:
OP 2203, Plant Startup, signed off up through step 4.5.10.
Attachments 1 and 2 of OP 2203 on the SPO and PPO desks.
Reactivity Plan Direct the crew to raise power to approximately 4% using dilution to begin Main Turbine warm
~ p Reactor
. Engineering would prefer to use
- lilution to raise power. Dilution should be done n 25 gallon increments. Rods will be used above 5% power for AS1 control.
5
SECIION 4 1L) Nuniber ES04LI2 Rc\.ision: 0 Task Tiiiic IDt-\/l~Idf Instructor Information / Activity il ss i gn Expect c d X c t i ons Standard CVBA (7) When the crew begins the third dilution of 25 PPO When the PMW counter reaches 0. MP-I4 gallons to raise power to 4%, insert a inalfinction observc continuous flow of PMW to the TM 1 to prevent the Dilution Valve, CH-2 1OX, from RCS. Inform the US of the condition. AE 1 closing.
When requested as I&C, inform the crew that you 1.JS Direct the PPO to close VCT Makeup ARP 2590c will obtain the appropriate paperlvork and trouble Bypass, CM- 196 or placc the Makeup shoot the problem. Selector Switch in a position to prevent dilution. Inforin RE and the I&C Dept.
~ ~ ~
PPO Close VCT Makeup Bypass, CH- 196 or ARP 2590C place the Makeup Mode Selector Switch to CT I the Manual or Borate position. Observe 0 PMW flow to the RCS. Inforin the IJS that PMW flow is secured.
NOTE: The US may provide a specific value, as us Direct the PPO to monitor plant parameters MP-I 4 long the plant does NOT enter MODE 1 (>5%
power).
CT 1 Establish reactivity control. Stop the dilution within 5 . (Dilution must be stopped to prevent an unplanned entry into MODE 1).
6
SECTION 4 ID N~iiibci- ES041.12 Rcl ision: 0 I 'ask Timc I DA/Mal I' Instructor Inform at i o n Act i1.i t i 1 !Issign Expected Actions s Land asci
'l- I CW02D (100%) When the plant has stabilized, insert a SPO Observe rise in "D" Circ Water Screen D/P MP- 14 Ramp=460 sec. malfunction to cause the '*D'*Circ Water Screen or acknowledge Ailnunciator D- 10 on C-TM 2 DIP to increase. 05, Traveling Screen AP.
AE 2 After a 5-1 0 minute delay. report as the PEO that USISM Enter AOP 25 17, Circulating Water ARP all requested actions are complete. Also report Malfunctions, and perform Initial Actions. 259OE-056 that the "D' traveling screen is NOT rotating. It Direct a PEO to:
appears that a pin has sheared. All other traveling 0 Start both screen wash pumps.
screens are operating properly. 0 Place all traveling screens in fast.
0 Chcck screen wash pump strainer D/Ps less than 4 psid.
0 Check all screens rotating Monitor traveling screen DIP Place screen wash trash basket in OP 2327 service Notify Environmental Services-Nuclear IJS When D/P approaches 30", direct SPO to AOP 25 17 perform actions of AOP 25 17. Section 5 .
7
SFC I ION J It) Number ESO4LI2 Re\.ision: 0 I-a 5k Time IDA/Malf Instructor Infbrination .Acti\.it! Assign Expected Actions Standard The US may may NOT direct cross tying D SPO Trip the D Circ Water Pump. AOP 2517 Water Box with C Water Box. Steps in itulics Close C W- 11E, D Water Box Inlet are optional.
Cross tie wciter boxes:
Place D Circ Water piimp in Pull-T(1-Loc.k E m ~n-e( W-I I D, D (irr Wcittv. Box C)irtlef, is open rn Opcn (W- 12C , Condtwsei-I B Inlet Cross -Tie Check condenser backpressure is 54.5 in. AOP 25 17 Hg.
Optional. Only required if water boxes are cross AOP 25 I7 tied.
Optional. Only required if water boxes are cross SPO Upucte PPC Condenser Perfor-mume AOP 25 17 tied. Report to indicate uctuul ('ire Wutci. i*c~Ive positions.
USISM Notif!. En\ironinental Ser\+xs-Nuclex of AOP 2517 Circ Pump trip.
us Inform iiiaiiiteiiance of the DScreen MP-14 failure and direct them to troubleshoot and repair.
8
SEC IION 4 ID Number ESO4LI2 Re\,ision: Q Task Time IDA/Mnlf Inst 111c tor I n forin at i on / Act i v i t >, Assign E xpr ct ed Actions Stand arc\
Rxo I R ( I 00%) When the crew has cross tied water boxes, insert a PPO Observe the Channel Y pressurizer MP- 14 Rnmp=250 sec. malfunction to fail Channel Y Pressurizer pressure rising and Channel X Pressurizer TM 3 Pressure transmitter high. pressure lowering. Observe PZR Pressure Selected Channel Deviation Hi/Lo AE 3 annunciator and Pressurizer CH Y Pres Hi/Lo annuciators.
IJS Direct the PPO to perform ARP actions for MP-14 the annunciator.
PPO With lJS concurrence (or dircction) I\KP perform one of the following: 2530B-2 12 Shift Pressurizer pressure control to or 220 channel X.
Manually close the spraq valves.
Place channel Y Pressurizcr pressure control in Manual.
When informed of the Pressurizer pressure UWSM Inform the I&C Dept. of the failure of ARP transmitter failure, report that I&C will obtain the Channel Y Pressurizer prcssure. 25903-2 12 appropriate paperwork and commence o r 230 troubleshooting.
9
0 a
m c
L
SEC I-loh4 ID Numher ES04L12 Keiision. 0 Task riine IDAiMalf Instructor Information 1 Actii itj. A s si g n Expected Actions stnnclard
~ ~ ~~ ~
T4 MS06R Approximately 5 minutes after the low pressure Crew Observe closure of #2 MSIV. MP-14 alarm is annunciated, insert a malfunction to fail TM 5 MS02B (7%) After the MSIV has closed, obser1.t.
close the #2 MSIV and cause a steam line break TM 6 Rainp=400 sec. lowering SIG pressures, lowering RCS upstream of the valve in the Enclosure Building. MA2 temperatures, and lowering RCS pressure.
us Direct a niaiiual Reactor trip and MP 16 performance of EOP 2525.
CT 2: Establish reactivity control. Open PPO Presses manual Reactor trip push buttons CT 2 CEDM MG set breakers to trip the reactor and observes a failure of the Reactor to within 2 minutes of pressing the manual trip trip.
pus buttons or automatic Reactor trip signal.
Opens the CEDM MG set output breakers and observes a Reactor trip.
Place Master Alarm Silence in SILENCE. OP 2260 Announce Unit 2 trip on the plant paging system.
I us Query board operators regarding the status of safety functions.
OP 2260 11
SECTION 4 ID N~tiiiber ES041,12 Rex-ision: 0 Task Ti me IIIA/h/lalf Instructor Information / Activit\,
Assign Expected Actions Standard PPO Complete and report SPTA: EOP 2525
- Ensures Reactivity safety fiinction is being met:
o Reactor is tripped. (Performed contingency action to trip the CEDM MG output breakers.)
o All CEAs are inserted.
o Power is going down.
o SUR is negative.
- Verifies RCS Inventory safety function is being met:
o Reports Letdown is isolated and all available Charging Pumps are running.
- Verifies RCS Pressure safety function is being mct:
o Reports heaters are off due to low level o Reports spray valves are closed o Reports PORVs and Safeties are EC 1 closed.
o When Pressurizer pressurc fails to less than I800 p i a . manuallq initiates SIAS, or verifies automatic The PPO may also manually initiate MSI on laic SIAS when pressure falls below SG pressurc. 17 14 p i a .
o Reports SIAS. CIAS, ERFAS. und A4X 12
SECTION 4 ID Number ES04L12 Task Re \.i si o n : -
0 Time IIIA/Malf' Instructor Intorination / PIctivitJ Ass i g11 Espccted Actions standartl
~~~
- Verifies Core Heat R e m o \ ~ destablished If KCS pressure lowers to NPSH setpoint. secure o Two KCPs are operating (one in each all KCPs. 1oop) .
- Reports value and trend of RCS subcooling.
- Verifies Coiitainment Integrity safety function is being met bl.7 lrerifying CTMT pressure, temperature. and rad monitor readings.
o O b s e n u all rad monitors are normal.
SPO c' 0Ill}' 1et e and report s P 1'A :
Frip turbine. stop \ . a l \ ~ xclosed. R we indicate 0.and 8T&9T opcn A11 electrical buses are energized Both SW and RBCCW facilities running Verifies status o f Core Heat Removal o MSIVs closed duc to Ion SG pressure. #2 loner than # 1.
o ADVs and safet) \.al\w are closed o Feed flow is NOT excessive o Place both Auxiliar!. Feed ?C 2 c'?' 3: Isolate Auxiliary Feedwater to the #2 O\ erride/Man/Start/Reset hand 5/G from the Control Room within 10 minutes snitches in Pull-'I'o-Lock
)f the initiation of the ESD. 3 Feeding # 1 SG onl\ \vith Auxiliar~ 3T 3 Feed to restore level to 40-70%.
13
S E ( 7 ION 1 1D Xumber ES04L12 Ke\ision: Q Task Time IDA/Malf Instructor Information I' Acti1.i ty Assign Espectcd Actions Standard
~
This action will be performed when #2 SIC; is SPO Adjust # 1 ADV to stabilize RCS EOP 2525 enipty as indicated by a rise in RCS teniperature temperature.
SPO Performs subsequent actions: EOP 2525 Ensures Vacuum Breaker, AR- 1 7, is open Opens subcooling valve, HD-106 Stops both Heater Drains Punips Isolated both Main Feed Punips Ensures only one Condensate Pump is running Verifies Instrument Air pressure is >90 Psi&
I PPO 1 When queried, report completion and OP 2260 SPO verification of subsequent actions.
us Refers to Diagnostic Flow Chart and EOP 2525 determines that EOP 2536, Excess Steani EU 1 Deniand is the appropriate procedure.
IJSIST.4 Direct the performance of Safetj. Function EOP 2536 Status Checks for EOP 2536 LJ S Direct Chemistry to obtain saiiiples of ## 1 EOP 2536 SG and analyze for Boron and activit".
Direct SPO to close S/Ci sample vali es when saniples have bcen taken.
14
SEC IlON 4 ID N u n i t m ESO4L12 Rei ision: 12 Time lDA/lvl al f Instructor Info rni at i o n / .\c t i 1.it) .Assign E spec t e d Act io11s s landard Event is classified as an Alert, Charlie-One USISM Ensure event is classified. EOP 2536 (BA2), based on an unisolable steam line break outside Containment.
us Open place keeper and enter EOP entry EOP 2536 time Return Master Silence switch to Normal us Direct PPO to: EOP 2336 Check SIAS Actuation Optimize Safety In-jcction
~
PPO Ensure: EOP 2536 At least one train of SIAS. CIAS, and EBFAS have actuated by checking blue lights on C-01 X Safetg Injection flow is adequate using Appendix 2. Figures.
0 All available Charging Pumps are run n i 11 g ,
Vital Switchgear Cooling is in operation on C-80 us Direct SPO to ensure MSI has properl!, NIP 2536 actuated and to Irerif). open the vacuum breaker, AR- 17.
SPO Observe conditions on c-0 1 X to ensure LOP 2536 proper actuation of MST o r obser1.e indications on C-05 and c-0617.
SECTION 4 ID Number ES04LI2 Ice\ isioii: Q Task Time I DA/Malf Instructor Information Activit).
/ :\ssign Expected Actions s t a11d arc1 Verify 2 RCPs in each loop are stopped EOI' 2536 with the respective spray l d v c closed.
I pressiirc loicws I O less ~ l m i IfPr*es.vi.irizc~
m in in1urn .VPLSH>I her? s l o p re nict in ing R CPs.
Determine that #2 SIC; is the 'most EO 1' 2 5 30 affected' .
While the SPO is isolating #2 SIC;, insert a nialfunction to trip the supply breaker to Vital Instrurncnt Bus, VA-20. r cren Coiiiinence actions to isolate the #2 SIG.
Observe loss of po\\.er to components powered by VA-20.
Recognize a significant change in plant conditions and refer to the Diagnostic Flow TM 8 EM I MA 2 OP 2260 EC 3 Chart.
The US may direct the SPO to stop Auxiliary Feed US Using the Diagnostic Flow Chart, EOP 2525 to the #2 S/G prior to referencing the Diagnostic determine that EOP 2536. Excess Steam Flow Chart. It is acceptable (desired) per OP Demand. is still the appropriate procedure 2260, EOP User Guide, to take actions to s t a b i l k and direct the SPO to stop Auxiliary Feed the plant prior to referencing an a p p r o \ d to #2 SIG.
procedure provided the appropriate procedure is used after taking those actions.
16
SEC I ION 4
- 11) Nu1nhi.r ES04LI2 Re\ ision. 0 Task Time I DA/Malf Instructor Information 1 Actii i t j $1s sigii h p e c t e d i\ctions Standard CT 4: Isolate Auxiliary Feedwater to the #2 SPO Close 2-FW-44. Aux Feed X-Tic Val\fe g~ MP 16 S/G from the Control Room within 10 minutes Stop the running Aux. Feed Pump(s) E of the initiation of when #2 Auxiliary Feed CT 4 Regulating Valve opened. Dispatch a PEO to manually close #2 Aux Feed Regulating Valve, FW-43B.
FWRGO (Man) If requested, as the PEO, close #2 Aux Feed Reg FWR64 (0) Valve, FW-43B.
SPO Complete actions to isolate #2 SIG by EOP 2536 ensuring:
I #2 MSIV is closed I #2 MSIV Bypass is closed.
I ADV Quick Open Permissive i n Off.
0 #2 Main Feed Block Valve. FW-42B.
is closed 0 #2 Main Feed Air Assist Check Valve.
FW-SB, is closed When directed, as the PEO, close the disconnect I #2 SIG steam Supply to Terry Turbine.
MSR13 (RI) for MS-202. MS-202, is closed 0 #2 SIG Blowdown Isolation. MS-220B.
is closed I Both .4uxiliarj Feed O\rerride/Man/Start/Reset hand snitches are in Pull-To-Lock e #2 Aux Feed Regulating Valve, 1.W-43H. is closed 0 #2. Main Steam Low Point Drain. MS-266B, is closed a #2 Main Steam Safety Valves are closed 17
SEC-I'ION 4 ID Number ES04L12 Rc\ ision:
I'ask
-1 inie IDA/lvIalf Instructor Information / ActiL it! A ssi p Expected Actioiis Standard us Verify most affected S/G has been isolated: EOP 2536 0 Lowest steam pressure 0 Lowest level 0 Lowest cold leg temperature The SPO will stabilize RCS temperature with #1 SPO I Stabilize RCS tempcrature. EOP 2536 ADV when the #2 S/G indicates empty. The PPO PPO 0 Open unaffected ADV to stabilize RCS will lower or maintain RCS pressure to prevent tenipe raturc.
Exceeding 200°F subcooling. This step iiiay need Maintain RCS within the RCS P/?'limit:
to be pulled forward to pre\Vent exceeding the PTS Manuall) control Pressurizer heaters limit. and sprq..
CT-5: Limit Tc subcooling (CET subcooling if If HPSI throttle stop criteria are met: CT 5 all RCPs are secured) to 5200OF. o Control Charging and Letdo\\ n o Throttle or stop HPSl Punips.
Lower RCS pressure using Main (or Auxiliary) Spray Valve.
Establish RCS temperature control using the # I ADV when #2 S/G indicates empty.
~ -
PPO Throttle/Stop HPSI Puiiips \vhe11 the follon ing conditions are met:
RCS subcooling is abo1.e niiniiiium operating limits of the P/l Cur\ e 0 Pressurizer le\ el -.20%
At least oiic SiG available to remo\c lieat at 40-70'% or being restored 0 Rcactor Vessel ler.el> 43%
+
.(
e U
c c
SECTION 4
SUMMARY
'l.itlc: Simulator Evaluation
- 11) NLimber: ES04Lll Ke\.ision: 0 C I< I'1'1C A I_ '1.ASKS C'T I : Establish reactivity control. Stop the dilution within 5 minutes (Dilution must be stopped to prevent a n unplanned entry into MODE 1).
C'T 2: Establish reactivity control. Open CEDM MG set breakers to trip the reactor within 2 minutes of pressing the manual trip pus buttons o r automatic Reactor trip signal.
CT 3: Isolate Auxiliary Feedwater to the #2 S/G from the Control Room within 10 minutes of the initiation of the ESD.
C,'T 4: Isolate Auxiliary Feedwater to the #2 S/G from the Control Room within 10 minutes of the initiation of when #2 Auxiliary Feed Regulating Valve opened.
CT-5: Limit Tc subcooling (CET subcooling if all RCPs are secured) to (20OOF.
Establish RCS temperature control using the #I ADV when #2 S / G indicates empty.
Lower RCS pressure using Main (or Auxiliary) Spray Valve.
20
SECTION 5 S C EN 11l i I 0 I N I TI AL CON 111I-I ON S
'I itle: Simulator Evaluation ID Wumber: ES04LI1 lie\i sion: 0
~~ ~ ~
Initial Conditions 0 1 % power, B01,. positilre M'PC' 0 Gp 7 CEAs 135 steps 0 1680 ppm boron 0 Blend ratio - 2.5: 1 0 SG Bloudown - 40 gpm each 0 Condensate on short rec!.cle 0 "A" Main Feed Pump in operation 0 Vacuum being maintained with the Hoe& 0 rers 0 24E aligned to Bus 24C 0 arcing Pressurizer SprajTs 0 2 Charging Pumps running 0 Snow storm in progress Expect 3-5" (20-25 niph u inds) 0 N o surveillances due.
Out of Service Equipment None Crew Instructions liaise power to approximatel! 4% using dilution to begin hlain I urbine warm up. Reactor Engineering would prefer to use dilution to raise pouer. Dilution should be done in 25 gallon increments. Rods will be used above 5% power for AS1 control. OP 2203. Plant Startup, is signed off up through step 4.5.10.
21
IITIACHMENT VAI_IDATION CHECKLIST I; tle: Simulator Evaluation ID Number: ES04L12 Revision: 0 Verified BY:
Ikmote functions:
- Ill remote functions contained in the guide are certified.
h la1 f~inctions:
- \I1 inalfiinctions contained in the guide are certified Initial Conditions
The initial condition(s) contained in the guide are certified or ha\.e been developed from certified ICs.
Simiilator Operating Limits:
Ilie simulator guide has been evaluated fi,r operating Iimi ts and/or anomalous response.
Pest l i i i n :
The scenario contained in the guide has been test run on the simulator. Simulator response is reasonable and as expected.
7 22
k/ir-2 S I M I~I...ITOR TRAINING SHIFT TURNOVER REPORT D ATE-TIME PREPARED BY SHIFT
-Today 0515 Unit Supervisor !NIGHT Shift 18100- 06:OO PLANT STA TUS:
,\IODE: 2 RX POWER: L/O
.tlE( L-1 WA TTS; Thermal: B M W T H PZR PRESS: 2250 psia Electric: OMWe RCS T-AVE: =degrees F KC*S Identified: 0.073 gpm PROTECTED: Trai n / F x i 1it!
LE,IKAC;E: Unidentified: 0.032 gpni Date/Time: Today 00 1 5 22 (YELLOW)
TS LCO i1nd TRM ACTION Statements Coming Due (if inore than one ACTION requirement per LCO, list each sena ra telvl Date Time LCO Action Action Requirement Equipment Reason Action Requirement LCO Action Equipment Reason Infinite action: Establish hourly fire watch. TRhlAS 3.7. I O I See AIL See Actice Impaimient List.
O D COR,IPENSATORY ACTIONS / Temp LOGS (Bold: Tech Specs. Italics: T K M )
7 odn!
EVOLLJTIONS IN PROGRESS & NOTES Reference /Date Plant startup. Raise power to 4%, using dilution onl!.. for warming the Main Turbine. OP 2203 Today Forcing Pressurizer sprays. Two Charging Pumps operating. OP2203 Today
.A* Maiii Feed Pump in operation. OP 2203 Today Condensate on short recycle. OP 2203 Toda!
Silo\\ storm i n progress. Expect 3-5. Winds at 20-25 mph. CONVEX Today Unit 2 Chemistry ON-LINE STATUS REPORT Pa ram et er Reading Parameter Reading Po lvc r 1 Yo Fluoride 0.81 nnb T~\Y 532 d e g F C11 1oride 1.75 ppb I 13o ro 11 1680 ppni Oxygen 4 ppb I Blend Ratio: 1 2.5 : 1 I 23
Attachment SCENARIO ATTRIBUTES CHECKLIST Scenario 1.itle: LOIT Simulator Evaluation Number: ESO4L12 Technical Re\.ieiver: R. .I.Ashey Date: 1/12/05 (1IJ A 1- Il- ATlV E ATTRIBUTES Y 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.
Y 2. The scenario consists mostly of related events.
Y 3. Each event description consists of:
- the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event
- the symptoms/cues that will be visible to the crew
- the expected operator actions (by shift position) the expected Emergency Plan classification the event termination point (if applicable)
Y 4 No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
Y 5 The events are valid with regard to physics and thermodynamics.
Y 6 Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.
N/A 7 . If time compression techniques are used, scenario summary clearly so indicates.
Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.
Y 8. The simulator modeling is not altered.
Y 9. The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure that functional fidelity is maintained while running the scenario.
24
Attach men t Guide No.: ES04LI2 SCENARIO ATTRIBUTES CHECKLIST Note: Following criteria list scenario traits that are numerical (quantitative) in nature. Credited malfunctions tasks and procedures should be bolded in the evaluation guide.
- 1. Total Malfunctions (TM) - Include EMS - (5 - 8) 8
- 1. Failure of dilution controller (PMW flow continues)
- 2. D Circ Water Screen D/P increases causing D Circ Water Pump trip
- 3. Control Room Radiation Monitor, RM-9799A, fails high
- 4. Main Steam lsol Valve 2 Air Pres Lo, Annunciator C-8 on C-05 alarms
- 5. #2 MSlV fails closed
- 6. Steam line break upstream of #2 MSlV in the Enclosure Building
- 7. Failure of trip push buttons and automatic trip failure
- 8. The supply breaker to Vital Instrument Bus, VA-20, trips
- 2. MaIfs after EOP entry (EMS) --.(I - 2) I 1 . The supply breaker to Vital Instrument Bus, VA-20, trips
- 3. Abnormal Events (AE) - (2 - 4) 3 I . Failure of dilution controller (PMW flow continues)
- 2. D Circ Water Screen D/P increases causing ID Circ Water Pump trip
- 3. Control Room Radiation Monitor, RM-9799A, fails high
- 4. Major Transients (MA) - (1 - 2 ) 2
- 1. Steam line break upstream of #2 MSlV in the Enclosure Building
- 2. The supply breaker to Vital Instrument Bus, VA-20, trips
- 5. EOPs entered requiring substantive actions (EU) - (1 - 2 ) I
- 1. EOP 2536, Excess Steam Demand
- 6. EOP Contingencies requiring substantive actions (EC) - (0-2) 3
- 1. Verify RCS Pressure safety function is being met
- 2. Place both Auxiliary Feed Override/Man/Start/Reset hand switches in PuIl-TO-Lock
- 3. Recognize a significant change in plant conditions and refer to the Diagnostic Flow Chart.
25
- 7. Critical Tasks (CT)- (2 - 3) 5
- 1. Establish reactivity control. Stop the dilution to prevent exceeding 5% power unplanned entry into MODE 1). (If required, boration or CEDM insertion may be used.)
- 2. Establish reactivity control. Open CEDM MG set breakers to trip the reactor within 2 minutes of pressing the manual trip pus buttons or automatic Reactor trip signal.
- 3. Isolate Auxiliary Feedwater to the #2 S/G from the Control Room within 10 minutes of initiation of the ESD.
- 4. Isolate Auxiliary Feedwater to the #2 S/G from the Control Room within 10 minutes of #2 Auxiliary Feed Regulating Valve opening.
- 5. Limit Tc subcooling (CET subcooling if all RCPs are secured) to ~ 2 0 0 ° F Establish RCS temperature control using the #I ADV when
- 2 S/G indicates empty.
Throttle/stop HPSl Pumps when the appropriate conditions are met (if required).
Restore Letdown (if required).
- 8. Approximate Scenario Run Time: 60 to 90 min.
- 9. Technical Specifications exercised during the scenario.
26
IC-91 ES04L12
-A -B -
C -D AS1 Upper 4.85 4.82 4.85 4.82 AS1 Lower 4.85 4.82 4.87 4.82 Nuclear Power 4.69 4.68 4.68 4.68 AT Power 1.32 2.19 1.29 1.07 Tcold Cal. 4.89 4.91 4.82 4.96
Millstone Station Unit 2 Operator Training SIMULATOR EXERCISE GUIDE I.
Title:
LOIT Simulator Evaluation #3 ID Number: ES04LI3 Revision: 0
- 11. Initiated:
1/13/05 Developer Date 111. Reviewed:
Date IV. Approved:
m Operator Tra ing Supervisor Date
~
Title:
Simulator Evaluation ID Number: ES04L13 Revision: 0 TABLE OF CONTENTS SECTIONS LISTED IN ORDER:
- 1. Cover Page 2.
-) .
Table of Contents Exercise Overview
- 4. Instructor Guide / Summary
- 5. Scenario Initial Conditions Attachments 0 Validation Checklist Training Turnover Sheet EXERCISE OVERVIEW 1.
Purpose:
- a. Evaluate the licensees ability. as a team and individually, to safely and responsibly operate the plant during normal plant operations, abnormal operating conditions and emergency operating conditions.
- b. Evaluate licensees in the following areas. as applicable:
- 1) Ability of the crew to perform crew-dependent (and time-critical) tasks.
- 2) Ability of individuals to perform critical tasks.
- 3) Ability of the crew to:
a) Understandhterpret alarms/annunciators b) Diagnose events/conditions based on signalsh-eadings c) Understand plant/systems response d) Comply witNuse procedures and Technical Specifications e) Properly communicate informatiodproper crew interactions f) Perform control board operations
- 4) Ability of each individual to:
a) Respond and correctly interpret annunciators b) Correctly diagnose events c) Properly interpret integrated system response d) Comply with and use Technical Specifications e) Comply with and use procedures f) Properly perform control board operations g) Demonstrate a responsible attitude
- 11) Properly communicate information and interact with the rest of the crew 2
Title:
Simulator Evaluation 1D Number: ES04LI3 R e\ri sion : 0 3
I . Exercise Brief:
The simulator will be prepared for the evaluation and the licensees \\ill be briefed on the conduct of the e\duation and the areas in which they will be evaluated.
The simulator will be initialized to IC 90 or equiwlent; 100% power, BOL. Equilibrium Xe, 120 I ppm boron. There are no surveillances in progress. The Turbine Dri\ en Auxiliar!? Feed Pump is tagged out for a pump bearing replacement and is scheduled for return on the next shift.
Radwaste Ventilation Fan. F-16, is out of senrice for filter replacement. Containment pressure is non reading 2 I inches of water. Containment must be depressurized after the c r m assumes the shift.
After the crew has initiated depressurizing Containment, the PPC will be lost requiring entry into Tech Specs and a down power. The crew will enter AOP 25 18. Loss of the PPC, and perform the applicable steps. When the crew has reduced power by a feu percent. Channel C Pressurizer Pressure will fail low resulting in several annunciators. lhe c r m \\ill re\ iew the annunciators and select the appropriate Annunciator Response Procedure. 1he PPO will bypass the appropriate channels of RPS. ESAS, and Automatic Auxiliary Feed. After the crew has bqpassed the appropriate channels and has logged into the appropriate Tech Spec Action Statements, condenser vacuum nil1 begin to degrade. The crew will enter AOP 2574, Loss of Condenser Vacuum, and take the appropriate actions to include continuing the down pomer (started earlier) to slow the loss o f \ acuum. When the crew has taken the appropriate actions and has determined that a continuation of the down power is warranted. condenser vacuum will degrade more rapidly resulting in a (manual or automatic) plant trip. On the trip. the RSST will fail to automatically transfer and both Emergency Diesels will energbe their respective buses.
This \ \ i l l result in a loss of all Condensate Pumps. Additionally. the 3 Auxiliar) Feed Pump is se\ erely degraded, resulting in minimal flo\v from that pump. The creu mill perforni the actions of EOP 2525. Standard Post Trip Actions and transfer to EOP 2528, Loss of Off Site Power/Loss of Forced Circulation. While performing EOP 2528. the A Diesel Generator will trip.
ultimately resulting in a loss of all feedwater (B Auxiliary Feed Pump will NOT be sufficient to restore S/G levels). The crew will rediagnose the event and will transfer to EOP 2537, Loss of A11 Feedwater, which will require initiation of Once-Thru-Cooling. During the initiation of OTC, the C HPSI Pump will NOT automatically start, requiring it to be manually started.
The scenario may be terminated when the crew has determined that they must transfer to EOP 2540. Functional Procedure.
3
Title:
Simulator Evaluation 1D Number: ES04LI3 Rev i s i on : 0
-3. Plant/Simulator differences that may affect the scenario are:
None
- 4. Duration: 1.5 hours
,411 Control Room Conduct, Operations and Communications shall be in accordance nit11 Master Manual 14 (MP- 14). Review the Simulator Operating Limits (design limits of plant) and Simulator blwleling Limitations and Anomalous Response List prior to performing this training scenario. The instructor should be aware if any of these limitations may be exceeded.
4
SECTION 4 ID Number ES04LI3 Revision: Q Task Time IDAiMalf Instructor Information / Acti\.ity Assign Expected Actions Standard IC 90 or Simulator S e t w and Initial Conditions:
equivalent 100% power, BOL, Equilibrium Xe, 1201 ppm.
1Jsing IDT, set Raise Containment pressure to read 22 inches of CMMDRY to water.
1.284e05 E5 1Jnder CH, I/O 110 off both green lights for F- 16 OFF G for HS8137 ( 2 )
ED02 on BT9 1 Loss of the RSST on the plant trip I TMS ES03.I Failure of C HPSI Pump to automatically start TM 8 on SIAS (failure of AM-6 14). EM 2
-~
FWR22 (Local) Disable the Terry Turbine and place a yellow tag FW20C (Trip) on the Terry Turbine Steam Admission Valve, SV-4188.
FW30B (1 00%) Gradual degradation of the B Aux Feed Pump. TM 6 Ramp=300 sec. MA 2 BT37 MSR13 (RI) Rack in breaker for MS-202.
Close Steam Supplies To Terry Turbine. MS-20 1 and MS-202, and insert remotes to rack out the associated breakers.
Place yellow tags on valve hand switches RC-27 Ensure RC200 AVMS does NOT cause the annunciator on C-02 or indicate on RCOjE Ensure blowdown is set to 40 gpm each S/G.
5
SECTION 4 ID Number E SO4LI3 Revision: Q 1'as.I.<
Time TDA/Malf Instructor Information / ActiLrit! Assign Expected Actions S taiidard 0 Terry Turbine out for bearing replacenlent 0 F-16 out for filter replacement 0 RC-200. AVMS is out of service.
0 Enclosure Building Purge using Main Exhaust has been in continuous operation for several months.
0 Provide crew with OP 23 14B, section 4.13.
Steps 4.13.1 through 4.13.7 are signed off as complete.
I TO Ensure the surrogate directs the PPO to US/PPO Brief the crew on the depressurization of MP- 14 depressurize Containment. If the crew does NOT Containment.
initiate actions to depressurize Containment, as Chemistry, call the S M and ask when they started the c' on t ainm ent depressuri za t i o 11.
6
SECTION 4 ID N~uiibcr ES04LI3 Rei.ision: Q Task Time IDAiMalf Instructor Infomation i Acti\ it) Assign Expccted Actions Stand x d Ensure the H2 Purge Valves associated with the PPO Place EBFAS in operation as follo\vs: OP 33 14B same facility EBFS Fan are opened. Align Condenser Air Removal to Unit OP 23 14G 2 Stack.
o Open EB-57, Cond Air Removal to Unit 2 Stack (C-06) o Close EB-56, Cond Air Removal to Millstone Stack (C-06) o Close EB-55. Cond Air Removal to Millstone Stack (C-06)
Start A EBFAS Fan (C-0 I )
o Open EB-50, EBFS Suction Damper o Open EB-5 1, Header A Isolation o Start F-25, A EBFS Fan o Check EB-52, Fan A Discharge Damper, opens Monitor for proper operation.
After a short delay, as the PEO, report that the PPO Open Facility 1 Hydrogen Purge Valves. OP 23 14B Hydrogen Purge Flow Limiting Butterfly Valve in EB- 100 and EB-99, on C-0 1. and direct a the 386 East Penetration Room is open. PEO to open the associated Hydrogen Purge Flow Limiting Buttertly Val\ e. EB-194, in the 386 East Penetration Room.
~
us Record start time in SM Log. OP 23 14B As Chemistry, acknowledge the time Containment us Notify Chemistry that Containment venting OP 23 14B venting was started. is in progress.
7
Sk:(TI( IN 4 ID Number ES04L13 Re\.ision: 0 Tash Tinie IDA/Malf Instrirctor Information / Activit! Ass i &I1 E spec t ed Actions Standard TI PCO 1 Once the crew has initiated Contailinlent Crew While observing the PPC. note a failure of MP- 14 depressurization, insert a malfunction to causc a the PPC to update ally parameter.
TM 1 loss of the PPC.
Observe Computer hop alarm on C-08 AE 1 After a 5-10 minute delay, report as Computer US/SM Enter AOP 25 18, Loss of the PPC. MP- 14 Services that the PPC has a significant Direct a PEO to complete Attachment 1 of malfunction and that troubleshooting has begun. AOP 25 18.
An update will be provided when more information is available.
US Log into TSAS 3.1.3.3d. All pulse counter AOP 25 I8 channels are inoperable.
RPR3 5 Examinee will need to contact the Booth PPO Place PWR RATIO HI/LO, B 12B switch to AOP 25 18 (NORM) Instructor to place the PWR RATIO HI/LO switch OPER (Inside RC-22, Front, Rack #9) in the OPER position. and observe Annunciator BB12 on C-04.
US Log into TSAS 3.2. la. AS1 is outside the AOP 25 18 power dependent limits on the Power Ratio Tech Specs Recorder. AS1 must be restored to within the limits kvithin one hour.
US Brief the crew on entry into AOP 2575. MP- 14 Rapid Downpower, and the use of Attachments 1. 5, and 6.
US/SM Inform HP, CONVEX, IS0 New AOP 25 18 England. IJnit 3 and other persoiinel AOP 2575 required by MP-0 1-SM-GDT, 1 .O 1 0 Brief crew on plant trip criteria.
8
SEC~I-ION4 ID Number ES04LI3 Ke\.ision: I!
-rasi\:
Ti iiie 1DAiMalf Instruct or I n fo rill at i on / Act i \ri t j, Assign Expected Actions Standard PPO Initiate forcing sprays. AOP2575 1
~-
~
I SPO Maintain S/G levels 55 to 70% during the AOP 2575 down power.
The crew should Borate from the RWST as the us Determine that a 5 to 10% down power is preferred method. required to restore the power dependent limits on the Power Ratio Recorder.
Select the desired method of Boration for the down power.
From the RWST (preferred)
From the on service BAST If the crew initiates the down power using CEA PPO Commence Boration from the RWST to one AOP 2575 I insertion, then ensure they use Step 4.1 1 of OP charging pump to commence lowering I 2302A. power.
If asked, report as the PEO that baseline data has been recorded.
SPO Using Load Limit Pot, adjust Turbine load to AOP 2575
/PPO follow Reactor power and maintain Tavg on program. (At tachmen t 5 )
SECTION 4 111 N~inibcr ES04I,I3 Revision: 0 Task Time IDA/Malf Instructor Information / Activity Assign Expccted Actions Standard
~ ~~
i I
RP 1OC (0) When the crew has reduced power by PPO Observe the TM-LP TRIP CH C annunciator MP-14 approximately 3-5%, insert a malfunction to fail (DA-3 on C-04).
TM 2 1 Channel C Pressurizer Pressure transmitter low.
us Direct the PPO to perform ARP actions for MP-14 ~
the annunciator.
PPO Coinpare Channel C Pressurizer Pressure ARP and TM-LP set point to the other safety 259OC-023 channels.
us Enter TS 3.3.1.1. Action 2. Tech Specs Enter TS 3.3.2.1, Action 2
~
PPO Obtain the necessary keys and bypass the AKP following: 259OC-023 i 1 Channel C TM-LP Trip (RPS)
Channel C High Pressurizer Pressure Trip (RPS)
Sensor Cabinet C Pressurizer Pressure Bistable (ESAS)
Channel C ATWS (C-1 00) 10
SECTION 4 ID Number ES04LI3 Kexrision:
Task Time IDAiMalf Instructor Information / Activity Assign Expected Actions Standard
~~
T3 FW33 (3%) When the crew has coinpleted the actions of ARP Crew Observe and report lowering vacuum, MI-14 Ramp=35O sec. 259OC-023, insert a malfunction to cause lowering electrical output, or Low Vacuum TM 3 condenser vacuum to degrade to 5-5.5 inches Hg a1arm.
abs. Do NOT allow vacuum to degrade to the AE 2 manual trip setpoint.
US should inform the crew that a plant trip will be us Brief crew on entry into AOP 2574, Loss AOP 2574 initiated whedif condenser vacuum lowers to of Condenser Vacuum, plant trip criteria, between 6 and 7 inches Hg abs. and the need to reduce power if vacuum continues to degrade.
FW33 (1%) Adjust the loss of vacuum malfunction to allow SPO Start A and B Mechanical Vacuum AOP 2574 vacuum to continue to degrade. but maintain it Pumps.
below the manual trip setpoint. Ensure Condenser Air Rcmoval is aligned to the Millstone Stack through A Condenser Air Removal Fan.
Ensure proper operation of the Circulating Water System.
Check steam seal pressure between 2 and 6 p i g .
Check Condcnsate Surge Tank level is
> I 5% and NOT lowering Check Exhaust Hood Temperature is less than 175°F.
Ensure 2-AR-17, Vacuum Breaker, is closed.
11
SEC'l'ION 4 TU Number ES041,E Re\rision: Q Task l'ime IL)A/Malf Instructor Information i Acti\,itJ. Assign Expectcd Action s Standard FWRl9(0pen) When dispatched as a PEO, open the Mechanical USISM Direct a PEO to: AOP 2574 FWWO(0pen) Vacuum Pump suction valves. Open Mechanical Vacuum Pump FW33 (Val-.) Vacuum should improve slightly then stabilize. individual and combined suction Set the loss of vacuum malfunction as required to valves.
maintain approximately 5-5.5 inches Hg absolute. Place a second set of SJAE in service.
After 5- 10 minutes. report that the Mechanical Check for proper operation of the Vacuum Pump suction valves are open and that a A tinospheric Drain Collecting Tank second set of Air E.jectors has been placed in level control system.
service. Check for watcr seal in Vacuum Breaker.
Report that there is NO obvious indication of a vacuum leak. Check condenser expansion joint loop seal is filled.
Inspect for leakage.
us Determines vacuum is NOT stabilizing and AOP 2574 directs the crew to continue the down AOP 2575 power per AOP 2575.
T4 FW33 (100%) When the US has determined that vacuum is NOT Crew Observe rapidly lowering condenser MP-I 4 stabilizing, insest a nialfunction to cause a rapid \ acuum anti loss of main generator output. TM 4 degradation of condenser yacuuin. MA 1 1JS Direct a manual plant. MP- 14 IJS/SM Place Master Alarm Silence in SILENCE. OP 2260 Announce "Unit 2 trip" on the plant paging system. Direct performance of EOP 2525.
us Query board operators regarding the status OP 2360 of safety functions.
12
SEC I'ION 4 ID Number ES04L1-3 ReIrision: 0
-rasii Time IDA/Malf Instructor Information / Activity As sign Expected Actions Standard PPO Complete and report SPTA: EOP 2525 0 Ensures Reactivity safety function is being met:
-I Reactor is tripped
- All CEAs are inserted.
- Power is going down.
i SUR is negative.
0 Verifies RCS Inventory safety function is being met Pressurizer level is betwcen 35 and 70%
0 Verifies RCS Pressure safety function is being met:
A Pressurizer pressure is between 2225 and 2300 psia.
0 Verifies Core Heat Removal established.
.9$ NO RCPs are operating and placed Tavg controller, HIC-4265 in inanual and closed.
qJk Reports loop delta T less than 10°F.
i Reports value and trend of RCS subcooling.
0 Veri ti e s Containment Integrity safety function is being met by verifying CTMT pressure, temperature. and radiation monitor readings are normal.
SECTION 4 ID Number ES04LI3 Task I'ime IDAlMalf ,'
Instructor Information Activity Assign Expected Actions Standard SPO Complete and report SPTA: EOP 2525 Trip turbine. stop valves closed. M We indicate 0, and 8T&9T open Electrical alignment is as follows:
& 25A and 25B are deenergized A- 24A and 24B arc deenergized m$ 24C and 24D are energized by their respective Diesel Generators
& 20 1 A and 20 1 B are energized
%k VAlO and VA20 are energized Both SW and RBCCW facilities running Verifies status of Core Heat Removal
- Reports value and trend of both S/G pressures (880 to 902 psig).
& Reports RCS Tc value and trend.
(530 to 535°F).
- Reports value and trend of both S/G le\rels betlveen 40 and 70 or being restored to this band.
May rep rt that "B" Auxiliary Feed Pump lischarge pressure is lowering: pump is degraded. i Reports both motor driien Auxiliary Feed Puinps operating.
i Concurs ivith US report of s ubco o 1 i ng \ a I ut'.
14
SECTION 4 ID Number ES04LI3 Reirision: 0
'Task Ti iiie TDAiMalf Instructor Infcmiation Activity Assign Expected Actions Standard I SPO Performs subsequent actions:
Announces and opens Vacuum Breaker, AR- 1 7 EOP 2525 Opens subcooling valve, HD-106 Stops both Heater Drains Pumps Isolated both Main Feed Punips Ensures only one Condensate Pump is running Verifies Instrument Air pressure is >90 psig IAR10 (Open) When dispatched as the PEO, after 5-10 minutes, Q Dispatches a PEO to align Station report that Station Air has been cross tied with with Unit 3 and cross ties Station Air Unit 3. with Instrument Air.
PPO I When queried, report completion and OP 2260 SPO verification of subsequent actions.
LJS Refers to Diagnostic Floiv Chart and EOP 2525 determines that EOP 2528. Loss of Off E1T 1 Site Power/Loss of Forced Circulation is the appropriate procedure.
~
US is 1-A Directs the perforniaiice of Safety Function EOP 2528 Status Checks for EOP 2528
SEC IION 4 ID Number ES04LI-3 Re\zision: 12 Ill&
Tinic IDA/Malf Instructor Information / Activity A ssi gn Expected Actions Standard Even[ is clirssijied us [in Unusutil Event, Deltu- SM En.su1.e event is clitssifified. EOP 2528 One, based on P l J l , Loss of 0ffLYiteP o ~ w for r
greater i h m 15 minutes.
IJS Open place keeper aid enter EOP entry EOP 2528 time Return Master Silence switch to Normal US Direct SPO to: EOP 2528 Close both MSIVs Ensure both MSIV bypass valves arc closed.
Open AR-17, Condenser Vacuum Breaker T4 EDOSC While the SPO is vcrifying MSIV closure, insert a SPO Verifies: EOP 2528 malfunction to cause an overload trip of Bus 24C. Both MSIVs are closed. TM 7 ,
0 Both MSIV Bypass Valves are closed. EM 1, 0 AR- 17, Vacuum Breaker is open. MA 2 Crew Obser\,e indications for the loss o f Bus MP- 16 24c.
SPO Observes A DG running with NO OP 2260 cooling water and emergency trips A EOP 2525 DG.
US Inform thc crew that a significant changc OP 2260 in plant conditions requires the Diagnostic Flow Chart to be performed again.
16
SECTION 4 ID Number ESO4LI3 .- . Relision: 0 1 ask Tiiiie IDA/blalf Instructor Information 1 Activity 12 ssi gn Expected Actions Stnndard SPO Observes lowering discharge pressure on M P 14 B Aux Feed Pump.
Determines that a loss of all feedwater has-Crew OP 2260 occurred and that EOP 2537, Loss of All Feedwater, must be entered.
EU 2 US Briefs crew on entry into EOP 2537. OP 2260 US/STA Directs the performance of Safety Function EOP 2537 Status Checks for EOP 2537.
us Directs: EOP 2537 All RCPs to bc stopped.
HIC-4165, Tavg Controller placed in Manual and closed.
Pressurizer Spraj. Valves, RC- 1 OOE and RC- 1OOF, to be placed in Manual and closed.
PPO Ensures all RCPs are secured. EOP 2537 Places MIC-4 165, l a y Controller. in Manual and closed.
Places Pressurizer Spray Valves, RC-1OOE and RC- 1 OOF in Manual and closed.
17
SECIION 4 ID fiuniber ESO4LIj Reivision: )!
lask rime I DA/Malf Instructor Infimnation / Acti\.itj. /Issign Expected Actions Standard The Note prior to this step states that OTC should lis Directs the PPO to initiate Once-Thru-be initiated prior to SG level reaching 70 if two Cooling trains of HPSI, PORVs and ADVs are NOT available.
CT-1 Once-Thru-Cooling must be initiated SPO Initiates Once-Thru-Cooling by the EOP 2537 prior to reaching 70 inches in the lowest following:
CT- 1 Steam Generator or for a >5OF rise in Turns off both Proportional Heaters.
Tc. (OTC will be initiated early due to Places a11 Backup Heaters in Pull-To-loss of one facility.) Lock.
Opens both Atmospheric Dump Val\.es Manually actuates SIAS.
Ensures HPSI Pumps have started.
o Recognizes C HPSI Pump did CT-2 CT-2 C HPSI Pump must be started prior to NOT start and inanually starts it.
opening the PORVs. Ensures all HPSI Injection Valves are open.
Ensures all available Charging Pumps are running.
POKV Block Valve. RC-403. is deenergized (has Ensures both PORV Block Valves are NO open indication), but \vi11 remain open \\;hen open.
deenergized. When C HPSI Pump has started.
opens both PORVs.
Informs US when complete.
18
-1 h
r G
.C
.-z i
2 A
.a .
!3 L
t
..c C
/
1 c
.-C c
'+
C E
c c
+
c
-c J
c c
s-
\
4 a
3 0
c r:
t=
SECTION 4
SUMMARY
Title:
Simulator Evaluation
- 11) Number: ES04LI3 Revision: 0 CKITICAL TASKS CT-1 Once-Thru-Cooling must be initiated prior to reaching 70 inches in the lowest Steam Generator or when a >S°F uncontrollecl rise in Tc is observed. (OTC will be initiated early due to loss of one facility.)
CT-2 C HPSI Pump must be started prior to opening the PORVs.
20
SECTION 5 SCENARlO INITIAL CONDITlONS
Title:
Simulator Evaluation ID Number: ES04L13 Rei4 si on : 0 Initial Conditions 0 100 % power, BOL. Equilibrium Xenon 0 1201 ppm boron 0 Blend ratio - 3.4: 1 0 SG Blowdown - 40 gpm each 0 24E aligned to bus 24C 0 Terry Turbine out for bearing replacement 0 F- 16 out for filter replacement 0 Enclosure Building Purge using Main Exhaust has been in continuous operation for several months.
0 Containment pressure is 2 1". Conditions have been verified as acceptable to depressurize Con t ai nni ent .
0 A work control staff is available to perform tasks outside of the Control Room.
Out of Service Equipment 0 The Turbine Driven Auxiliary Feed Pump is out ofservice for a bearing replacement.
0 Radwaste Fan, F-16 is out of service for filter replacement.
0 RC-200. AVMS is out of service.
Crew Instructions Depressurize Containment per OP 23 14B, Containment and Enclosure Building Purge. Steps 4.13.1 through 4.13.7 are complete. The 10 minute averages for the Containment Rad Monitors have been compared to the latest Chemistry grab sample and are acceptable for depressurization.
Containment Rad Monitor readings have been logged into the SM log. Enclosure Building Purge has been in continuous operation for the past 3 months. Chemical use has been prohibited in the Enclosure Building for the past week.
21
ATTACHMENT VALIDATION CHECKLIST
Title:
Simulator Evaluation ID Number: ES02LI3 Revision: 0 Remote functions:
All remote functions contained in the guide are certified.
vp:
Malfunctions:
All malfunctions contained in the guide are certified Initial Conditions:
The initial condition(s) contained in the guide are certified or have been developed from certified ICs.
Simulator Operating Limits:
The simulator guide has been evaluated for operating limits and/or anomalous response.
Test Run:
The scenario contained in the guide has been test run on the simulator. Simulator response is reasonable and as expected.
21
hl1'2 SIP\?I!I,A TOR TRAINING SHIFT TURNOVER REPORT DATE-TIME PREPARED BY SHIFT Today 05 15 Unit Supervisor /"NIGHT" Shift 18:OO - 06100 PLANT STA TUS:
AlODE: 1 RX POWER: I 00Yo
.LlEC;,41/1:1TTS: Thermal: a M W T H PZR PRESS: '250 psia Electric: U M W e RCS T-A VE: =degrees F KC'S f.E,-lk'.4GE: Identified: U g p m PROTECTED: Train! Fac i I i t\.
Unidentified: 0.0jgpm Date/Tirne:Todav 001 5 Z1 (RED)
[ TS L C O a n d T R M A C T l O N Statements Coming Due (if more than one ACTION requirement p e r LCO, list each Action Action Requirement Equipment Reason 1 With one Auiiliary Feed Pump inoperable. 'I'err! Turbine 'rem?. Turhine tagged restore the required Auxiliary Feed Pumps fir bearing replacement to OPER,\ULE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in I IOT SHUTDOWN within the hllnwiiig 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.1 and \t/ith 1 :iI\,e iiiopcixhle from C- IO. perform SV-4 188. AFW 'l'crr>*Tui-bine tagged b.2 clctioiis b. I. 1x2 Ibr lire m a s K-I and R-13. Stem Siippl\ \"al\e for hearing replacement b.1 and With 1'ump:'Turbinc inoperable. liom either f'-4 and 11-2 1 A l W l'eir? 'I'urbine tiigged b.2 location. perform actinns b. 1 and b. I for fire Primp and rurbine for hearing replaceinen\
areas K--3. R-l I. K-16.and K-17. (io\ crnor Control
--.: I--- --I---
I'oda) 0-130 I
- 7. I . 15. item C b. 1 and With the d y e closed or disconnect closed, b.2 1 . K-2. and R-13, 2-MS-202. AFW l'err? Turbine tagged perform actions b. I and b. I for fire areas R- Stcain Supply \'nlve for bearing replacement iroin SG 2. h4OV Action Requirement LCO Action Equipment Reason Infinite action: Establish hourly fire watch. TRMAS 3.7.10 1 See AIL See Active Iinpaiiment List.
Infinite action: Attachment I ofOP 2301A TSAS 3 . j 2 . 8 a,'? RC-200 Failed S P 2410A OD COMPENSATORY ACTIONS / Temp LOGS (Bold: Tech Specs, Italics: TRM)
I EVOLUTIONS IN PROGRESS & NOTES Reference mate Thc I O minute aiwages for the Containment Rad hlonitors ha\x been compared to the latest Chemistr!. grab OP 23 14B Today sample and iire xccptable for depressurization. Contninment Rad Monitor readings have been logged into the Shl log. Enclosure I3uilding Purge has been in continuous operation tbr the past 3 months. Chemical use has been prohibited in the I-nclosure Ruilcling for the past week.
23
Unit 2 Chemistry ON-LINE STATUS REPORT Parameter Reading Parameter Reading Po\! er 100 Yo Flouride 0.81 m b
?'a\.e 572 deg F Chloride 1.75 ppb Boron 1201 ppm Oxygen <5 ppb 24
Attachment SCENARIO ATTRIBUTES CHECKLIST Sccnario 'Title: LOIT Simulator Evaluation Number: ES04LI 3 Technical Reviewer: R. J. Ashey Date: 12/6/04 QUALITATIVE ATTRIBUTES Y 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.
Y 2. The scenario consists mostly of related events.
Y 3. Each event description consists of:
the point in the scenario when it is to be initiated
- the malfunction(s) that are entered to initiate the event
- the symptomskues that will be visible to the crew
- the expected operator actions (by shift position)
- the expected Emergency Plan classification the event termination point (if applicable)
Y 4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
Y 5. The events are valid with regard to physics and thermodynamics.
Y 6. SequencingAiming of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.
NA 7 . If time compression techniques are used, scenario summary clearly so indicates.
Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.
Y 8. The simulator modeling is not altered.
Y 9. The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure that functional fidelity is maintained while running the scenario.
25
Attachment Guide No.: ES04LI3 SCENARIO ATTRIBUTES CHECKLIST Note: Following criteria list scenario traits that are numerical (quantitative) in nature. Credited malfunctions tasks and procedures should be bolded in the evaluation guide.
- 1. Total Malfunctions (TM) - Include EMS - (5 - 8) 8
- 1. Loss of the PPC
- 2. Fail Channel C Pressurizer pressure transmitter low
- 3. Degrading Condenser vacuum
- 4. Loss of Condenser vacuum 5 . Loss of RSST
- 6. Degradation of BAux Feed Pump
- 7. Loss of Bus 24C
- 8. Failure of C HPSl Pump to automatically start
- 2. Malfs after EOP entry (EMS)- (1 - 2)
- 1. Loss of Bus 24C after entry into EOP 2528
- 2. Failure of C HPSl Pump to start after SlAS initiation
- 3. Abnormal Events (AE) - (2 - 4)
- 1. Loss of the PPC
- 2. Degrading Condenser vacuum
- 4. Major Transients (MA) - (1 - 2) 2
- 1. Loss of Condenser vacuum resulting in plant trip
- 2. Loss of Bus 24C resulting in Loss of All Feedwater
- 5. EOPs entered requiring substantive actions (EU) - (1 - 2) 2
- 6. EOP Contingencies requiring substantive actions (EC) - (0-2) 1
- 1. Initiate Once-Thru-Cooling
- 7. Critical Tasks (CT)- (2 - 3) 2 1, Once-Thru-Cooling must be initiated prior to reaching 7 0 inches in the lowest Steam Generator or when a >5F uncontrolled rise in Tc is observed. (OTC will be initiated early due to loss of one facility.)
- 8. Approximate Scenario Run Time: 60 to 90 min. Total 75
- 9. Technical Specifications exercised during the scenario. (Y/N) Y 26
IC-90 ES04L13 Load Limit Pot Setting = 5.85 A
- -B -
C -
D AS1 Upper 4.68 4.65 4.66 4.63 AS1 Lower 4.85 4.72 4.76 4.74 Nuclear Power 4.66 4.988 4.80 4.85 A T Power 3.90 4.10 3.92 4.07 Tcold Cal. 4.80 4.80 4.80 4.90
MILLSTONE POWER STATION SIMULATOR EXAM GUIDE APPROVAL SHEET Lesson
Title:
LOIT Simulator Evaluation #4 (Spare)
Revision: 0 ID Number: ES04LI4 (Spare)
This document is the property of the Millstone Power Station which controls its distribution. Further transfer, copying, or modification of this document is strictly prohibited without the written consent of the Millstone Power Station.
Approved by: I I /I+$-
Assistant Manager, Unit 2 Operations (Optional) Date I
Approved by: 3/9/6 Date
SIMULATOR EXAM GUIDE SUhlh,I,4RY OF CHANGES
- 1. None in Revision 0, Change 0.
Page 2 of 30
SIMULATOR EXAM GUIDE TABLE 01.'CONTENTS SECTIONS LISTED IN ORDER
- 1. Exam Overviem
- 2. Scenario Initial Conditions Sheet 7
-7 . Exam Guide
- 4. Exam Guide Summary
- 5. STA Follow-up Questions
-_ Attachments
- 1. Validation Checklists
- 2. Shift Turnover Sheet Scenario Attribute Check 1ist
?
-3 .
Page 3 of 30
EXAM OVERVIEW
Title:
LOIT Simulator E\.aluation #4 (Spare)
ID Number: ES04L14 (Spare) Revision: 3 1.
Purpose:
- a. E\ aluate the licensees' abilitl. as a team and individually, to safelq and responsiblj.
operate the plant during nomial plant operations, abnormal operating conditions and emergency operating conditions.
- b. Evaluate licensees in the following areas, as applicable:
- 1) Ability of the crew to perform crew-dependent (and time-critical) tasks.
- 2) Ability of individuals to perform critical tasks.
- 3) Ability of the crew to:
a) Understandhterpret alarms/annunciators b) Diagnose events/conditions based on signals/readings c) Understand plant/systems response d) Comply withhse procedures and Technical Specifications e) Properly communicate informat iodproper cren int t'mc t i ons t) Perform control board operations
- 4) Ability of each indi\.idual to:
a) Respond and correctly interpret annunciators b) Correctly diagnose events c) Properly interpret integrated system response d) Comply with and use Technical Specifications e) Comply with and use procedures t) Properly perform control board operations g) Demonstrate a responsible attitude h) Properly communicate infonnation and interact mith the rest of'the c r w Page 4 of 30
I'he simulator will be prepared for the elduation and the licensees \ \ i l l he briefed on the conduct of the evaluation and the areas in which they m i l l be e\.aluated.
Thc simulator will be initialized to IC-89 (or equivalent) at 100% power. BOI,, f31Xe. 1201 ppin boron. The "C" Charging Pump is out of service for seal replacement. '*R" Charging Pump is aligned to Facility 2.
The site experienced a minor seismic event (0.08g ZPA) 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> earlier, ,4OP 2562.
Earthquake. was entered. and a UE/D-1 declared by Unit 3. All seismic instruments hale been or are being evaluated and accessible plant piping systems have been full! inspected including
- i tour of containment. (limited b) accessibility at power). No indications of damage o r leakage were noted. Management is discussing options for a plant shutdo\\n to conduct full accessibility inspections of systems inside containment.
Shortly after the crew takes the shift, the "A" RBCCW Pump will trip. The crew will restore Facility 1 RBCCW by starting the "B" RBCCW Pump. The US will enter and exit TSAS 3.7.3.1 due to the loss and restoration of RBCCW to Facility 1 . When the crew enters section 7.0 oCAOP 2564. Loss of RBCCW, Charging header flow will begin to lokxer. The crew should diagnose this as a degraded "A" Charging Pump. The PPO u ill start "B" Charging Pump and secure "A" Charging Pump. The US will enter TSAS 3.5.2 and 1RMAS 3.1.2.4 and TRM 7.1.1. Table 7.1.1-1, Item A. actions b. 1 and b.2. When the US has addressed the appropriate administrative requirements for the "A" Charging Pump. Channel B cold leg temperature transmitter. TE I 12CB. will become 'noisy' causing the following annunciators to alarm intermittently: RX POWER AT CH DEVIATION, RPS PRE TRIP. TM-LP TRIP CH 8,PRESSURIZER CH B TM-LP SETPOINT HI/LO, and Computer Alarin. LOOP 1 B Cold Leg Temp 1,o. The crew should reference the appropriate ARP and bypass RPS Channel B f Ii Power, TM-L-P. and LPD trips. Additionall). they should request IBiC to isolate and remo\ e Channel B cold leg temperature transmitter. TEI 12CB.
When the crew has completed actions associated with Channel B cold leg temperature transmitter. TE 1 12CB, a S/C Tube Leak of - 5 gpm will occur in #2 W t i . The US should reference T.S.A.S.3.4.6.2.b and AOP 2569, Steam Generator Tube Leak. A d o u n poner should be commenced in accordance with AOP 2575, Rapid Downponer.
At - 95% (or at the discretion of the examiners). the S/G Tube Leak will increase in size such that pressurizer level cannot be maintained. requiring that the Unit be tripped. The IJS \$ill direct that the unit be manually tripped and that EOP 2525 be carried out.
Upon completion of EOP 2525. the US should enter EOP 2534 and direct that SFSCs be tahen a er!. I5 minutes.
When SJAS is actuated, AM-523 will fail to actuate components to their SIAS positioiiicoiidition. (A &B RBCCW -1 0' A. SW Header to TBCCW. C'H-501. C1-515. and 8 1 & #2 SIT Outlet Isolations). Additionally, when SlAS is initiated. the "A" f1PSI Pump \I i l l sin\\ !I degrade.
LfIien RCS pressure lowers to 1450 p i a . the "C" HPSI punip u i l l be lost. M'ith the ".4" HPSI I'LIIII~ degraded, the US should elect to start the "B" IIPSI pump. hich is aligned to Facilit\
1.
When $2 SG has been isolated, an unisolable steam leak will de\.elop on +2 SI<; i n the Enclosure Building. This steam leak develops from a cracked butt \\ell on the hlain Steam line side of2-MS-3B, which is unisolable. With 2 events occurring. the ITS should direct entry into EOP 2540.
The scenario may be terminated when EOP 2540 has been entered. success paths selected, feed has been isolated to #2 S/G and RCS pressure is being reduced to minimize the differential. and actions to address challenged success paths are being carried out by the crew.
- 3. Plant/Siniulator differences that may affect the scenario are:
'The simulator does not model the Loose Part Monitor Panel. Operators will be provided the information for their annunciator response from the simulator instructor.
- 4. Duration of Exam: 1.5 hours.
All Control Room Conduct, Operations and Communications shall be in accordance with Master iLlanual 14 (MP-14). Review the Simulator Operating Limits (design limits of plant) and Simulator Modeling Limitations and Anomalous Response List prior to performing this training scenario. The instructor should be aware if any of these limitations may be exceeded.
Page 6 o f 30
_ _ _ _ ~ ~
SIh11JIA T O R EXt\M GUIDE SCENARIO INITIAL CONDITIONS
Title:
LOIT Simulator Evaluation #4 (Spare)
ID Number: ES04LI4 (Spare) Re\.ision: 0 Out of Service Equipment "C" Charging Pump out for seal replacement. "B" Charging Pump is aligned to Facility 2.
Crew Instructions The plant has been at 100% power fbr 30 days following a Refueling Outage.
There are no surveillances due.
It is day shift, normal weekday.
Facility 1 is protected.
The site experienced a minor seismic elrent. (0.08g ZPA). 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> earlier. AOP 2562.
Earthquake, was entered and a UE/D-I declared by Unit 3. All seismic instruments have been or are being evaluated and accessible plant piping systems are being fully inspected. A tour of containment (limited by accessibility at power) has been perfomied. No indications of damage or leakage have been noted by operators. hlanagement is discussing options for a plant shutdown to conduct full accessibili 11, inspections of sj'stems inside containment.
Page 7 of 30
All Control Room Conduct. Operations and Communications shall be in accordance applicable Unit Procedures.
"Review the Simulator Operating Limits (design limits of plant) and the Simulator Modeling Limitations and Anomalous Response List prior to performing this exam scenario on the simulator. The evaluators should be aware if any of these limitations may be exceeded."
(NSEM 6.02)
Page 8 of 30
E-MTB 6-ML 3 E0S3 68-31
Simulator --ram Guide Tttlc: mT Simulator EI aluatioii $4 (Spnrc) ID N ~ t i i l ~ ESO4LI4 r (Spare) K r \ i\ion (1 Task Assign 1.inic Expected Actions Stanclard 1 CVKIO ( R O ) Rack out the C Charging Pump breaker and place a yellow tag on the hand switch.
CVRl 1 (22F) Ensure B Charging Pump is on Facility 2 (22F).
Ensure lamacoid for Facility 2 is displayed on C-02 Perfomi the actions of the Simulator Examination Crew Walk down control boards. MP 14 Briefing Sheet and provide the SM with a turnover.
Provide the following information:
0 The plant has been at 100% power for 30 days following a Refueling Outage. It is day shift, normal weekday. There are no surveillances due.
0 Charging Pump C is out for a seal replacement.
Charging Pump B is on Facility 2.
0 The site experienced a minor seismic event, (0.08g ZPA) approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> earlier. AOP 2562, Eartahquake. was entered and a IJEiD- 1 declared by lJnit 3. All seismic instruments have been or are being clxluated and accessible plant piping slrstems are being fully inspected including a tour of containment. (limited by accessibility at pon.er). No indications of daniagc or leakage have been noted by operators. Management is discussing options for a plant shutdown to conduct full accessibility inspections of systems inside containment.
Page 1 0 o f 3 0
Task Assign Instructor Inforiiintion / Activitj, Expected Actions s t alldard TI Insert a inalfunction to trip the A. RBCCW Pump. Crew Observe the loss of the A hlP- I4 RBCCW Pump us Direct SPO to ensure B AOP 2564 RBCCW Pump is aligned to TM 1 Facility 1 and Start B RBCCW AE 1 Pump.
When dispatched as the PEO (maintenance), report that SPO Performs the follow i ng : A O P 2564 there are NO obvious problems. You will continue to Ensures Pump B Dischargc troubleshoot .
Crosstie Valve to A Header, RBA-25 1 A. is open.
Starts B RBCCW Pump Place A RBCCW Pump hand switch i n Pull-To-Lock.
Observes and acknowledges the RBCCW PlJMP B SIASILNP MANUALI-Y BLOCKED annunciator on C-06.
Dispatches n PEO (maintenance) to look for any problems ivitli the breaker o r the pump. --
Page 1 1 of3O
Simulator ram Guide f'itlc: LO1 1' Simulator Ei~duation#-I (Spare) 1 Task IDA/Mal f Instructor Information / Activity Assign us 7, Plant Assessment.
PPO Report: AOP 2564 Adequate Shutdown Margin exists: all CEA are fully withdrawn.
Pressurizcr level is 65% and stable Pressurizer is 2250 psia (nominal) and stable.
Three CAR Fans are operating in slow speed.
SPO Reports: AOP 2504
- JS Notifies hlaintennnce.
Enters and exits TSAS .3.7,-3.1 Enters TRh.1 7.1.20. Iteiii I I .
0 Determines NO reportabilit!.
Page 12 of30
Sirnulatot! -am Guide
Title:
LOI'I' Simulator Evaluation #4 (Spare)
Task Tim I DA/Malf Instructor Info rni H t i on / Act i vi t v Assign Expected Actions CY22 ( 1 00%) While the crew is discussiiigibriefiiig the loss of PPO Observe and report loweriiig Charging Ramp=200 sec. "A" RBCCW Pump, insert a malfunction to cause a flow, Pressurizer level, or LOW degradation of the "A" Charging Pump. CHARGING FLOW annunciator.
If dispatched as a PEO or maintenance, report that us Direct the PPO to determine the cause MP- 14 the "A" Charging Pump is making a loud banging of the lower Charging flow and to noisc. reference the appropriatc ARP.
PPO Check Charging Ilo\v. Ensure a i d report the Charging Meadcr Isolation Valves, CH-5 18, CH-5 19, and C'H-429.
are open.
---1 PPO Determines and reports Pressurizer i\RP level is lowering slowly. 259OB-057 us Directs the PPO to start "B" Charging Pump and place "A" Charging Pump in Pull-To-Lock.
PPO Starts "B" Charging Pump and places "A" Charging Pump in Pu~I-To-LocI~.
us Logs into TSAS 3 3 . 2 , TRM -3.1 2 . 4 and TRM 7.1 . l , Table 7.1.1-1. Item A.
actions b.1 and b.2.
AKI' 2590B-057 Tech Specs 1
I TRbl I Page 13 o f 3 0
Sirnulato! -yarn Guide
Title:
LOIT Simulator Evaluation 84 (Spare) ID Number ES04LI4 (Sparel Reiisioii -
0 Task IDAiMalf Instructor Information / Activity Assign Expected Actions Standard RPO 1F ( 100%) While the crew is discussing/briefing the loss of the PPO Observe and report the following MP- 14 Ramp=250 sec. A Charging Pump, insert a malfunction to cause annunciator as they alarm:
TM 3 Loop 1B Cold Leg Transmitter, TE-l12CB, to RX POWER AT CH DEVIATION AE 3 become noisy.
RPSPRETRIP TM-LP TRIP CH B PRESSURIZER CH B mwr SETPOINT HULO Computer Alarm, LOOP 1B Cold Leg Temp Lo Report as I&C. Inform the crew that you will us Directs the PPO to reference the MP-14 troubleshoot the problem. appropriate ARP. Informs I&C.
PPO Observe Channel B pressurizer ARP-pressure indication and compare to 259OC-022 other channels. Report observations.
PPO Observe Th and Tc instruments. ARP-Report Channel B Tc is noisy. 259OC-022 PPO With concurrence of the US, bypasses ARP Channel B WS TMLP, High Power, 2590B-022 and LPD trips.
Delete RPOlF As I&C report that the transmitter Weidmuller pin us Enter TSAS 3.3.1.1. Action 2. ARP was a little corroded. Pin has been fixed. 2590B-022 Request I&C to isolate and repair Tech Specs transmitter.
Page 14 of 30
Simulator 'am Guide
Title:
LOI'I' Simulator Evaluation +4(Spare) ID Number ES04LI;I (Spare) K c i ision 0 Task Time IDA/Malf Instructor Information / Activity Assign Expected Actions Stanctard
~ _ _ _
T., SGOl B(5O) Insert a malfunction which will cause a SIG Tube Crew Identify the loss of' RCS inventory and TM-4 Ramp=200 sec. -
Leak of 5 gpm. determine that the leakage is Si(; tube AE-1 leakage within the capacity of the t
available Charging Pumps.
SPO Observe N-6 and SJAE radiation monitors for increasing counts. Note rising counts on #2 S/G N-16 rad monitor.
~-
us Determine that the leakage is S/G tube leakage within the capacity of the available Charging Pumps.
IJS Direct entry into AOP 2569, Steam AOP 2569 Generator Tube Leak.
Direct Chemistry to sample both S/Gs for boron and activity.
Refer to Tech Spec 3.4.6.2~and Tech Specs identify that the Unit must come off line.
SM Refer to RAC 14 and classify this event KAC 14 as an Echo due to a S/D required by TS's. (UE/D-1 if leakage determined to be 2 10 gpm.)
Make required notifications of the downpower.
~
Page 15 of 30
Sirnulatoy xim Guide -
I'itle: LO1 I' Simulator Evaluation d4 ( S l i m ) ID Number ES04LI4 (Spare) i<e\.ision 0 I---
~
h Task Instructor I n forinat i o n i Act i v i tv Assieii Expected Actions IIie down power rate should be 50°/o per hour or
?.
us Brief the PPO and SPO of the required greater. 1he Boration source should be the on down power, the rate, and the method service BAST. of reactivity addition. Should include caution regarding reduced MIU capability.
PPO Commence boration to the suction of the Charging Pumps.
If necessary. insert CEAs to maintain ASI.
SPO As Rx power is reduced, lower turbine 1 load.
Page 16 o f 3 0
Simulator -am Guide
Title:
I,OIT Simulator E\ nluation #4 (Spare)
SCi0213( 15) After the downpower is initiated, increase the Crew After the Main Steam Line Radiation I severity of thc S/G Tube Leak to 450 gpm. Monitor alarm identify that the S/G TIM-6 MA-1 Tube Leakage has increased.
us Direct that the reactor be tripped and AOP 2569 EOP 2525 be commenced when:
MSL RM alarms and is confirmed OR Primary to secondary leakage exceeds the Chg Pp capacity.
PPO SPO Report:
Reactor tripped All CEAs fully inserted Power going down Report:
7 EOP 2525 i
Turbine tripped All steam admission valves are closed Generator Megawatts are zero 1 8T and 9T are opened 1
I I JS 2ommence query of both control board lperators to identify the status of the
)lant Page 17 of 30
Simulator 'am Guide Ti tlc: LOIT Simulator Evaluation d-l (Spare) ID Niiniber ES041-I4 (Spare) Re1 ision 0 Task Time ID A/Mal: Instructor Information / Activity Assign Expected Actions 5: tandard PPO Report:
Pressurizer level < 20% and going down Pressurizer pressure < 1900 psia
~ -~
PPO will norinally manually initiate SIAS at I800 US Direct the PPO to manually actuate psia. Manual initiation of SIAS is NOT required. SIAS at some RCS pressure > 1714 psia.
SPO Report: At least 1 S/G level being returned to 40-70% 011 Main Feed PPO Report:
CTMT conditions normal Rad Monitors NORMAL with the following exceptions:
- SJAE
- S/G BloMido\+rn
- #2 S/G MS Rad Monitor
- #2N-16 us Query the control operators to identify the status of performance and verification of the subsequent actions of EOP 2525.
Page 18 of 30
Simulator -yam Guide
Title:
LOIT Simulator Evaluation #4 (Spare) ID Number ES04LI4 (Sparc) Re 1-isio 11 -0 I
Tasl< I IDA/Malf Instructor Information / Activity Assign Expected Actions Standard
~~
The C HPSI will trip when RCS Pressure <1450 us Direct the PPO to place C HPSI in psia. The timing of the pump trip depends on the PTL, enable and start B HPSI, action of the crew and, therefore, may happen assuming the B HPSI was NOT before or after this point. started to replace the loss of the A HPSI.
If the A HPSI is still running, it is NOT required that the B HPSI Pump be started. It is only required if the A HPSI is already degraded.
As the Turbine Building PEO. report that the C us Direct the Turbine Building PEO to HPSI pump breaker has tripped, but it is NOT check o u t IC HPSI pump breaker, evident \vhy the trip occurred. A403.
As electrical Maintenance, report that you will Request Maintenance to check the C investigate the problem with the C HPSI pump HPSI breaker (and possibly the A breaker. (If requested, CANNOT determine the HPSJ Pump).
problem with the A HPSI Pump).
PPO Report SIAS has been inanually OP 2260 actuated, some components failed to actuate.
Aand C(or B and D) RC,Ps are secured.
Page 19 of 30
Simulator -Yam Guide
Title:
LOIT Siniiilator E\.aluntion #4 (Spare) ID Number ES04LI4 (Spare) Revision
~-__
Task IDA/klalf Instructor Inforination / Activity Ass i ~n Expected Actions st a11dard us Uses the diagnostic flow chart to EOP 2525 update the shift as to the status of the plant.
A SGTR has occurred, directs entry into EOP 2534.
~
Concurs with cntiy into EOP 2534. EOP 2525 Classifies the cvent os un A l e i d ~ ' 1 EOP 2534 us Enters EOP 2534 and directs that EOP EU-1 2534 SFSCs be completed every 15 min S/G isolation may be successfully completed when Refers to EOP 2534 and directs that the RCS has been cooled down to < 5 15°F per EOP Chemistry sample both S/Gs for boron 2534. and activity.
SGTR-7: Perform a plant cooldown to a Th of -= Directs the SPO to cooldown the RCS CT-1 515OF. at the maximum controllable rate using either the SD & BP Valves or the ADVs at a rate which allobvs the continued use of the RCPs.
SGTR-9: Secure RCPs within 5 minutes of Crew Monitor RCP NPSH and secure RCPs EOP 2534 exceeding NPSH limit. if inadequate. CT-2 Page 20 o f 3 0
Simulator --ram Guide Titlc: ILOIT Simulator E \ d u a t i n n #-I (S1m-e) ID Number ES04LI4 (Spare) Re\isinn 0
~- ------I -- I I ask I .
I Tim Instructor Information / ActiLSity Assigii Expected Actions Standard ,
I SP0 Commence cooling down the RCS I using BOTH S/Gs at a MAXIMUM and CONTROLLABLE rate dumping steam to the condenser.
This inalfunction may be observed earlier. Crew Identify the degraded AHPSI pump when flow degrades to 0 gpm.
us Direct the PPO to place A HPSI in PTL, enable and start B I-IPSI, assuming the B HPSI was not started to replace the loss of the C HPSI.
As Aux Building PEO: Nothing apparent. us Direct the Aux Building PEO to check out A HPSI pump.
SGTR-6: Start the B HPSI Pump within 15 us minutes of NOT satisfying the SI Flow Curve (OPTIONAL).
This critical task is critical Jno if the B HPSI is started as a result of NOT satisfying the SI flow curve. The SI flow curve is applicable when RCS pressure is less than 1250 p i a (HPSI shutoff head).
L SPO Notify the US when RCS TH 5 15°F.
Page 21 of.30
Simulator -yam Guide Pitle: LO1 I Simulator Evaluation 4(Spare)
Task Time IDA/Malf Instructor Information / Activity Assign Expected Actions Standard SGTR-5: Isolate the affected S/G is isolated in us Direct the SPO to isolate the #2 S/G CT-4 accordance with EOP 2534 within 60 minutes of per EOP 2534.
the Reactor trip.
MS02B (2%) Actuate an Excess Steam Demand in the Enclosure Crew Identify the abnormal SG and RCS TM-6 Ramp=20 sec. Building after the #2 SG has been isolated. response. MA-2 EM-4 us Directs entry into EOP 2540 since 3 events (a SGTR and an ESD) are occurring.
Directs Chemistry to sample both S/Gs for boron and activity.
SM Concurs with the entry into EOP 2540.
Selects EOP 2540 on SPDS and EOP 25-34 directs that EOP 2540 SFSCs be EU-2 completed every 1 5 minutes.
Enters EOP 2540 and proceeds to identify the SUCCCSS paths which are currently in use and to identify ~vliicli Safety Functions are in jeopardy.
SA4 Concurs with entry into EOP 2.740 C1ussijie.s the event us un SA E/(?
Page 22 of 30
T c z 2
I T r J
E
+ c v 0 w rl, w j 0
c c; r,
Simulatq -yam Guide T'itle: LOIT Simulator E\.aluation ft3 (Spare) ID Number ES04LI.C (Spare) Rei.ision 0 Task Time ID A/Mal f Instructor Information I Activity Assign Expected Actions us Enters EOP 2540D to verify recoI.er!. EC-2 of RCS Heat Removal.
May already be accomplished in previous EOP. us Direct the SPO to isolate #2 S/G per EOP EOP 2540D 2540D When Unlock, Close and Lock the disconnect for 2-MS- US Direct Maintenance or Aux Building directed 202. Set MSR13 to rack in (RT) and report that the PEO to close and lock the disconnect disconnect for 2 MS-202 is closed and locked. for 2-MS-202, to isolate the Terry Turbine from #2 SIG.
HR-3: Establish RCS heat removal by us stabilizing RCS temperature using #I ADV temperature by using # 1 S/G ADV per when #2 S/G is almost blown dry (CETs begin to EOP 2540D when the RCS cooldown rise). begins to slow down.
The session may be terminated when feed and steam to #2 S/G are secured and RCS pressure is being reduced to minimize the differential. RCS cooldown will be controlled by the blowdown of #2 SIG.
Page 24 of 30
EXAM wrx;
SUMMARY
Title:
LOIT Simulator E\ nluation #.(Spare)
I ID Number: ES04L14 (Spare) Revision: I>
- 1. Critical Tasks CT-1 SGTR-7: Perform a plant cooldown to a T h of < SIS°F.
CT-2 SGTR-9: Secure RCPs within 5 minutes of exceeding NPSH limit.
CT-3 SGTR-3: Start the B HPSI within 15 minutes of NOT satisfying the SI Flow Curve. (OPTIONAL)
CT-4 SGTR-5: Isolate the affected S/G is isolated in accordance with EOP 2534 within 60 minutes of the Reactor trip.
CT-5 HR-3: Establish RCS heat removal by stabilizing RCS temperature using #1 ADV when #2 S/G is almost blown dry (CETs begin to rise).
Page 25 o f 3 0
SIhlllLATOK EXAM GUIDE V A1,IDATION CHECKLIST l i t 1e : LOIT Simulator Evaluation #4 (Spare)
ID Number: ES04LI4 (Spare) Revision: 4 Initial Conditions:
The initial condition(s) contained in the guide are certified or have been developed from certified ICs.
Test Run:
'The scenario contained in the guide has been test run on the simulator. Simulator response is reasonable and as expected.
Simulator Operating Limits:
The siniulator guide has been evaluated for operating limits and/or anomalous response.
For Examination Scenario:
The Scenario Attributes Checklist is complete and attached. This is not rcquired for Progress Review Exams 4-Page 26 o f 30
hlI2 S l P ~ l l ~ l IOR, . l TRAINING SHIFT TURNOVER REPORT DATE-TIM E P R E P A R E D BY SHIFT I l-oda\, 05 I 5 1 Unit Supervisor /NIGHT Shifi I 1S:OO - 06:OO Date Time LCO Action Action Requirement Equipment Reason Toda? 0600 TRM 7.1.1, a With P18C inoperable from C-10, ensure C Charging Seal replacement.
Table 7.1.1-1, P18B is operable from C- 10 or perform Pump Itern C Actions b. 1, b.2 for Fire Areas R- 1 R-13.
With P 18C inoperable from CR, perform Actions b. I , b.2 for Fire Area R-4.
C o n t i u u o o s TS LCO a n d T R M A C T I O N Statements in effect (if more t h a n one A C T I O N r e q u i r e m e n t p e r LCO, list each sena ra telv)
Action Requirement LCO Action Equipment Reason Infinite action: Establish hourly fire watch. TRMAS 3.7.10 1 See AIL See Active Impairment List.
OD C O M P E N S A T O R Y A C T I O N S / T e m p LOGS (Bold: Tech Specs, Italics: TRM) 1 i Inspection of plant systems for leakage due to seismic event. Today Unit 2 Chemistry ON-LINE STATUS REPORT REACTOR COOLANT Time 0 6 2 5 Parameter Reading Parameter Reading Po\\ et- 100 Yo Fluoride 0.81 ppb Pn\.c 572 d e g F Chloride 1.75 ppb Oxygen <5 PPb Blciid Ratio: 3.4 : 1
Attachment SCENARIO ATTRIBUTES CHECKLIST Sc e liar i o Tit le : LOIT Simulator Evaluation Number: ES04L14 Technical Reviewer: R.J . Ashey Date: 2/28/05 QUAI .IT24TIVEATTRIBUTES Y 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.
Y 2. The scenario consists mostly of related events.
Y 3. Each event description consists of:
- the point in the scenario when it is to be initiated
- the malfunction(s) that are entered to initiate the event
- the symptomskues that will be visible to the crew
- the expected operator actions (by shift position)
- the expected Emergency Plan classification
- the event termination point (if applicable)
Y 4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
Y 5. The events are valid with regard to physics and thermodynamics.
Y 6. SequencingAiming of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.
Y 7. If time compression techniques are used, scenario summary clearly so indicates.
Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.
Y 8. The simulator modeling is not altered.
Y 9. The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure that functional fidelity is maintained while running the scenario .
Attachment Guide No.: ES04L12 SCENARIO ATTRIBUTES CHECKLIST Note: Following criteria list scenario traits that are numerical (quantitative) in nature. Credited malfunctions tasks and procedures should be bolded in the evaluation guide.
Total Malfunctions (TM) - Include EMS - (5 - 8) 9 I . Trip of t h e A RBCCW Pump
- 2. Degradation of the A Charging Pump
- 3. Loop 1B Cold Leg Transmitter, TE-112CB noisy
- 4. Tube leak in #2 Steam Generator 5 . Tube rupture in #2 Steam Generator
- 6. Excess steam demand in the Enclosure Building 7 . Actuation Module AM523 fails to actuate
- 8. A HPSl Slowly degrades
- 9. Loss of C HPSl Pump Malfs after EOP entry (EMS)- (1 - 2) 4
- 1. Actuation Module AM523 fails to actuate
- 2. A HPSl slowly degrades
- 3. Loss of C HPSI Pump
- 4. Excess steam demand in the Enclosure Building Abnormal Events (AE) - (2 - 4) 4
- 1. Trip of the A RBCCW Pump
- 2. Degradation of the A Charging Pump
- 3. Loop 1B Cold Leg Transmitter, TE-112CB noisy
- 4. Tube leak in #2 Steam Generator Major Transients (MA) - (1 - 2)
- 1. Tube rupture in #2 Steam Generator
- 2. Excess steam demand in the Enclosure Building EOPs entered requiring substantive actions (EU) - (1 - 2)
- 1. EOP 2534, Steam Generator Tube Rupture
- 2. EOP 2540, Functional Recovery Procedure
Attach men t Guide No.: ES04L12 SCENARIO ATTRIBUTES CHECKLIST
- 6. EOP Contingencies requiring substantive actions (EC) - (0-2)
- 1. Enter EOP 2540E, Containment Integrity
- 7. Critical Tasks (CT)- (2 - 3)
- 1. SGTR-7: Perform a plant cooldown to a Th of < 515°F.
- 3. SGTR-3: Start the B HPSl Pump within 15 minutes of not satisfying the SI Flow Curve.
- 4. SGTR-5: Isolate the affected S/G is isolated within 60 minutes of the Reactor trip, in accordance with EOP 2534.
- 5. HR-3: Establish RCS heat removal by stabilizing RCS temperature, using #I ADV when #2 S/G is almost blown dry (CETs begin to rise).
- 8. Approximate Scenario Run Time: 60 to 90 min. Total 80 Technical Specifications exercised during the scenario. (Y/N) Y
IC-89 ES04L14 A -B -C -D AS1 Upper 4.67 4.64 4.67 4.67 AS1 Lower 4.86 4.75 4.83 4.82 Nuclear Power 4.65 4.78 4.68 4.66 AT Power 3.92 4.10 3.92 4.03 Tcold Cat. 4.71 4.70 4.870 4.72