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 Revision:
0 ID Number:
ES041,I 1
- 11.
Initiated:
Developer 111.
Reviewed:
Reviewer 0 1/24/2005 Date Date Date 1V.
Approved:
Title:
Simulator Evaluation ID Number:
ES04LI 1 Revision:
0 TABLE OF CONTENTS SECTIONS LISTED IN ORDER:
- 1.
Cover Page
- 2.
Table of Contents
- 3.
Exercise Overview
- 4.
Instructor Guide / Summary
- 5.
Scenario Initial Conditions 9
At taclmen ts 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) c)
Understand plant/systems response d) e)
f)
Perform control board operations Ability of each individual to:
Diagnose eventdconditions based on signalsheadings Comply w i t h h e procedures and Technical Specifications Properly communicate informatiodproper crew interactions 2
Title:
Simulator Evaluation ID Number:
ES04LIl Revision :
0 a) b)
Correctly diagnose events c) d)
e) f)
g)
Demonstrate a responsible attitude h)
Respond and correctly interpret annunciators Properly interpret integrated system response Comply with and use Technical Specifications Comply with and use procedures Properly perform control board operations 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. 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 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:
3
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.
crew will enter AOP-2575 "Rapid Downpower" Leakage".
After the block valve is closed per the ARP. the leak on CH-442 nil1 increase and the The crew commences a Rapid Downpower per "AOP 2575" and AOP 2568 "RCS 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 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />
,,Ill Control 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.
4
SECTION 4 ID Number ES041,Il Revision:
Task Instructor Inforinntion / Actii it!
Assign Expected Actions Standard Time 1LINMalf Utilizing an open rooin. brief the crew on the conduct of the evaluation and the areas in which they will be evaluated.
For Turnover Brief:
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:
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-
- CloseRB211C,OpenRF3211D(C-06)
- 01)
INST INST INST 5
i SECTION 4 TD Number LSO-IL 1 Re\\,ision: 0 Task Time IL)A/hlalf Instruct or Info rniat i on / Act i1.i t y Assign Expected Actions s tandard EDRl4 (RO)
EDRl5 (RI)
SWR22 (22F)
CVRl 1 (22F)
RC-27
~
RC-04 @ 0.5%
RUN
- Close SW 97A. Open SW 97B (C-06)
BKR 24E from 24C (A305)
BKR 24E from 24D (A408)
B SW Pp. Strainer power supply.
B SW Pp. Charging Pp. kirk key supply 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.
RCS Head Vent Leak - 3.5 gpm.
Go to RUN If the crew is delaying forcing sprays. call as Jim Kunze and prompt the cren to start.
LJS PPO PPO US directs the PPO to coiiinience forcing sprajs.
Crew iiiay ha\\^ a short briefing SP 2654B is approved for implementation.
Backup Heaters are placed to CLOSE PIC-100Y setpoint is lowered
- 50% output
- HIC-1 lOEiF controller start to rise.
Pzr Press adjusted to - 2250 nsia SP-3654B 6
SEC TION -I Kc\\ ision: C, ID Number ES04L11 lask Time IDA/Malf Iiis tr uct or I nihrnia t ioii / Act i 1.i t y Ass i g i i E spe c t e d i\\c t i o 11 s s tandard T2 sw-01c Trip of C SW Pump 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.
While one attempt to restart the C SW Pp. is PPO SPO Annunciator PZK PRESS DEVIATION liifornis the US this is an expected alarm for Forcing Sprays.
The ARP does not have to opened or implemented.
Reports the C SW Pp tripped and Annunciator. SW PIJMP C OVERLOADITRIP (C-06, BA4)
With US direction, rcset the C SW Pp and attempt one restart.
AE-1 TM-1 GDI,-6OO 7
SEC I'ION 4 ID Number ES04LI 1 Re! ision: 0 Task Assign Ti me I D A /M a1 f Tn s t 1-uc t or Info rill at i on / Ac t i1.i t j E s pcc t c d Actions S tanclitsd allowed by GDL 600, the I JS should not direct a restart for the following reasons:
Annunciator (C-06.BA4) indicates a hulted pump motor.
The "B" SW Pp. is available to replace the "C" 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 PUMP C OVERLOAD/TRIP".
us SPO
~~
~
or With IIS permission. starts the "B" Su' Pp and aligns it to the "3" SW I IDR.
Enters the ARP, or directs the SPO to enter the ARP.
Checks the following to determine if alarm 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 GDL-200 ARP C06/BA4 AOP-2565 ARP 2590E ARP 2590E ARP 2590E 8
htry into AOP 2565 Loss of SW JS should not direct an attempt to restart the C
- w Pp
.JS enters Section 6.0 of AOP 2565.
us LJ S US SPO USiSPO LJ S SPO service on Fac. 2.
Determines that Aiiiiunciator (C-061BA4)
SW PUMP C OVERLOAD/TRIP is lit.
If lit, do not restart the C SW Pp.
Directs the SPO to start the B SW Pp.
Directs the SPO from Section 6 of AOP 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.
Direct a PEO to place the SIAS/LNP Actuation Signal HS 6484A in NORMAL.
~
Directs a PEO to Stop Sodium Hypochlorite to the C S W Pp.
Monitors AOP 2565 AOP 2565 AOP 2565 OP 2328A
TI) Number ES04Lll Re\\isioii: 0 1 ask Assign 1: x pe c tecl Actio 11s s t,?nda1-d Ti 111 e I DA/Mal f Instructor In format i on,' i\\ c t i \\ v i tl.
As PEO. vruit j inin. then report Sodium Hypochlorite is secured to the "C" 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.
sw Pp.
10 us
'B' SW Header Flow Piimp Pressure Motor Amps Sends, or directs Work Control to send a 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.
AOP 2565
SECTION 4 ID N~iiiiber ESO4LI 1 Re\\.ision: 0 Task rime TDiZ/Malf' Instructor Information / Actii8itjr
,4ss i g n Expected Actions Standard Directs a PEO to place the "SIAS /LNP Start Signal HS 6484A" to NORMAL SWR 31 (NORM )
OP 2326A step 4.5.20 If asked, report it ivill lukc ho1rr.r to determine if lrnd Mqhere the jmdt is.
"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)
Wait 5 min. and insert the remote. "SIASILNP Actuation Signal HS 648.111" in NORhl.4L.
Call the CR and report switch in NORMAL.
US us INST Logs into LCO 3.7.4.1 "SW SYSTEM" and TRM 7.1.2 1 "APPEN R SW SYSTEM" 40P 2565 1 1
SE~f1ON 4 ID Number F,SO41_11 Re\\ isimi: 0
- Tnsl, Time IDA/Malf Instructor Information,' Acti\\ ity Assign Lxpccted ilctions s la I1 d aril FW 38B @O%
180 sec ramp
- ection 7 evaluates key plant parameters to mure 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.
~
~~
Heater 6A Level Hi Annunciator Fail FW Heater 6A level transmitter (LTS043A) fails downscale.
Actual level in the heater rises to - 20 inches due to the "averaged" level lowering.
[f necessary, modify the FW 38B to ensure level 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 direct the steps himself.
Inst.
US Inst.
Inst us SPO
~
Logs out of LCO 3.7.4.1 and TRM 7.1.21
~
Responds to alarm CO5. BA-20.
"HEATER 6A LEVEL HI" Displays "Heaters 4A/5A/bA" screen on the Foxboro display.
AE-2 TM-2 ARP 259OD. RA-20, "HEATER 6A LEVEL HI
ARP 259OD 12
SECTION 4 ID Number ES04LI1 Re] ision: 0 Task Time IDrllMalf Instructor Information / ActiIvitJ.
Assign Espectcd Actions Standard The crew may opt to place the High and Normal Level Dump valves into manual before bypassing LT 5043A to preclude another Feedwater heater SPO The actual heater level should stabilize at - 20.
no reason to trip the plant.
SPO selects and bypasses.LT 5043A.
If the SPO does not place the valves in 4s PEO wuit 3 minutes and report:
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.
IJS 17s Inst Directs a PEO to check local level gauge.
Valve lineup Controller malfunction and air connection.
If Foxboro indications reaches 34 inches or local level gage exceeds -34 inches Trip the Rx, Trip turbine.
Close both MSIVs.
Stop all condensate punlps and perform EOP2525.
[f one transmitter does not agree with the ither transmitter and sight glass. Bypass the faulty transmitter on the Foxboro display.
'Z I i
E l
I
SECTION 4 Re\\.ision: 9 ID Nuinber ES041,ll
.risi, Timc 1I)A/I~lal f Instructor Information i ActivitJ.
- Issign E spec L ed A c ti on s s tantlard I
I
-r 4 PPO RC06A @
1.j?4 Report Annunciator Pzr Relief Va1i.e Dis RC-402 PORV Leakage RC-402 leakage Monitor for Pzr Press will lower to - 2240 psia and stabilize.
Ni.
A R 1 25 90H Note: The leak is too small for the Acoustic Vlv Monitor (AVMS) for RC-402 to detect.
Annunciator C02/3 A-11, AVMS Alarm The US may refer to this ARP knowing it will not energize.
would be required if the AVMS were operating properly.
If the crew calls the OMOC or Kunze, direct the crew to start a plant shutdown at a rapid controlled rate.
PPO AE-3 TM-3 c\\RP 2590B (02 3. C42 Disc11 Temp 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 s t andard US can direct the PPO or SPO to determine the RCS Leak Rate.
The US may direct that the leak rate be restarted to get an accurate leak rate.
The PPO should monitor the AVMS and determine they do not indicate RC-402. 404 (PORVs) or RC-201 (Safety) are leaking.
If the PPO closes RC-405 first, the DIS TEMP will not decrease. The procedure directs RC-405 to be opened and RC-403 closed.
When RC-403 is closed. the DIS TEMP will decrease indicating the correct PORV is isolated.
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.
us us US/PPO and Q7 Operation.
Refer to LCO 3.4.3 Relief Valves and LCO 3.4.6.2 RCS Leakage ARP 259013 Access the PPC Leak Rate.
I Determine Leaking POKV Monitor AVMS If unable to determine leaking PORV Close RC-403 or RC-405 Monitor PORV DIS TEMP TI-106 ARP 2590B I
16
rasi\\
Assi g t i Expected : k t i o n s s land ard Iinic ID ill bcl a 1 f Instructor Information / Acti\\.itj 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%)
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 2301A.
17 us/
CREW PPO If high pressure is due to relief or safety valve blowdown and cannot be isolated.
Go to EOP 2525 Standard Post Trip Actions and perform required actions.
Trip the plant and carry out EOP 2525.
Verify closed LRR-64.1/54.1.
Open LRR-57.1/62.1 QT PDIlQT Recirc-Cool v1i.s RecirelCIg vlvs Verify open RR-240, QTIPDT Hx RBCCW Out vlvs.
ARP step 5 2590B-206 C-03. B36 OP-230 1 A step 4.1
s m x m ;1 Time IDA/Ivlal f Instructor Information Xctivit)
Ass i g n Espectcd '4ctlons Standard ID Number ESO4I.I 1 ision: 0 I dS1, T5 RC-04 (3 5.0%
Rising RCS Leakage RCS Head Vent Leak -.35 gpm.
Enter AOP-2568 "RCS Leak" The US may hand off Section 3.0 of AOP-2568 to the PPO or SPO, requiring the SPO to report any 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 PPO us 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" Directs entry into AOP 2568 and performs Plant Assessment.
AOP 2568.
Sec. 3.0 18
SECTION 4 ID Number ES04LI1 Kci ision: 0 I ask Tiiiie IDA/klal f Instructor Intorination / ActiL it!
Assign Expected Actions s tall d n rcl The PPO/SPO map need to report low Pzr Lei,el and ensure max charging and inin. letdown.
The PPO/SPO may need to report low Pzr Pressure BU Heaters should already be ON.
If the US handed off Section 3.0 to the SPO, the lis will implement Section 4.0.
USiPPO US/PPO US/PPO
/SPO If Pzr 1,vl is not 35 to 70Y0 Manually operate Charging and I xtdown.
If Pzr Press not 2225 to 2300#
Ensure Spray Vlvs closed.
Place all BU Heaters to ON.
If RCS leakage exceeds available charging capability, TRIP the Rx. and Go To EOP 2525.
The leak rate is not > charging capacity.
No need to trip at this time.
Direct RCS Leak Kate The operator access the PPC and reports present leak rate.
.4OP 2508 Step. 3.2 AOP 2568 Step. j.3 AOP 2568.
Sect. 4.0 AOP 2568.
Step 4.1 AOP 2568.
Step 4.3 19
I The US may have previouslj. done an KCS Leak Rate.
If leakage is >25 gpm.
SM must classify Unusual Event / D1 per BU2 Identified Leakage > 25 gpm.
The US may personally implement. or handoff.
Section 5.0.
Ifrequested, report 110 activity in RBCCW and no leakage in Aux. Bldg. After a minimum of 20 minutes for a visual inspection. (Time may be adjusted if multiple personnel are assigned to the inspection)
Enter AOP 2575 Rapid Downpower IJS I Crew SM US/SPO I n i ti at e s Ixali Rat c Ile t e rm i iia t io n.
US should determine leak rate identified leakage.
Classify per FAP06 Log into LCO 3.4.6.2 Refer to AOP 2575 and start a Kapid Downporter I O gpm IJE/Dl per BU2 if leakage >25 gpm.
Implement Section 5 to ensure 110 other leaks.
Crew attempts to identify leak location by performing applicable steps of AOP 2568.
May direct chemistry sample RBCC W System or have PEO observe CVCS piping in Aux. Bldg.
Crew determines that identified RCS leak rate exceeds T/S 3.4.6.2 limit and begins to initiate a plant shutdown per AOP 2575.
AOP 2568.
Step 4.4 FAPO6
\\OP 2568 Section 5 AOP 2568 AOP 2568.
AOP 2575 20
/.
E c
i 6 E
c r
r I
I 2 g 2 ;
m m
c N
i SECTION 4 Re\\rision: 0 in Number ESO4LI 1 1 ask Assign Lx pe c t ed A c ti ons Standard IDA/Malf Inslr uc t or In f'orin at i o t i / '4 c t i i s i t I I'ime A controlled downpower of >20%/hr. is reasonable, unless RCS pressure is challenged.
If RCS pressure is challenged. <:20%/hr.
should be directed.
USiPPO PPO PPO PPO Insert Group 7 five to ten steps.
START additional charging piinips as required.
Based on plant conditions, SELECT the appropriate boron addition rate from the tables.
Borates to charging pump suction:
ADJUST setpoint of "BORIC' ACID FLOW" controller. "FC-2 1 OY.I' to flowrate determined in step 3.14.
OPEN "RWST TO CHG SUCT, CH-504."
switch in "MANUAL."
START a boric acid pump. and CHECK boric acid pump discharge pressure greater than 98 psig.
OPEN "VCT MAKEUP BYPASS.
PLACE "MAKEUP MODE SEL" CH-196.
AOP 2575 Step 3.12 AOP 2575 Step 3.13 AOP 2575 Step 3.14 AOP 2575 Step 3.15 22
c ci N
I SECTION 4
~
Rei ision: 0 ID Number ES04LIl Task IDA/Malf Instructor In form at i on / Act i vi t y Assign Expected Actions Standard Time US/PPO should initiate SIAS, CIAS & EBFAS at approximately 1800 psia.
CT-1 Trip 2 RCPs (LOCA-13)
CT-2 Secure all RCP within 5 min. of loss of NPSH. (2260 3.1.1) 24 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)
If Pzr. Press < 1714 p i a
- ensure SIAS, CIAS, EBFAS &
- secure one RCP per loop
- ensure PORVs closed, if open, CRAC close the Block Vlv.
Core Heat Removal (PPO)
RCP status LOOP delta-T Th SCM RCS Heat Removal (SPO)
OP-2260 CT-1 CT-2
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 Kcj ision: 12 111 I \\ j ~ i i i i L ~ ~
ES04LlI Task TDA/M\\/Ialf Instructor information /
it\\,
Assign kxpccted Actions Standard Tiiiie Verify that the STA has iiidependently diagnosed the event Enter EOP 2532 LOCA us SPO PPO us STA LJ S CTMT Combustible Gas Control (PPO)
CTMT teiiiperature > 120 F CTMT pressure > I # and rising.
- Place CTMT Aux Fans in Slow
- Start all PIR Fans Query PPO & SPO regarding the status of EOP 2525 subsequent actions Report subsequent actions complete and verified when accomplished.
Report subsequent actions complete and verified when accomplished.
Query board operators re: safety function status. per form d i ag n o s t i c fl o w c hart, and diagnose small break 1,OCA. transition to EOP 2532.
Evaluate and concur.
Directs SFSCs for EOP 2532 bc initiated.
EOP 2525 EOP 2525 EOP 2525 EOP 2525 EU-1 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 11 s Standard Reports annunciator for "CI'MT AIR RECIRC FAN 'A' VIBRATION HI" energized.
T7 EM-1 TM-5 IO -'C-O1 A4" (Delete)
Direct Chemistry to sample S W s ).
Classification will be done as an ildrnin JPM later.
EOP 2532 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.
IO "ON" Annunciator C-01 A4. "CTMT AIR RECIRC FAN 'A' VIBRATION HI" M'hen directed by Chemistry to sample SGs. after
-30 inin delay report both SCrs J. MDA.
SM STA PPO LJSIPPO Inst. i SPO Classifies e\\.ent as either an Alert. C-1 MP-26-EPI-based on RCB2. 3 or 4.
I FAPO6 Verify that the STA has independently classified the event Implements the ARP for '2-01.,44.
Stop ",4" CAR fan per OP-2323iZ.
Monitor CThl'I for increasing pressure.
temp and moisture.
Submit TR to maintenance.
2590A-0 13 27
SEC'I'ION 4 Iicvision: 12 ID N LLIIILX~ ES04LI 1
'l'asl<
Ass i gn Expected Actions Stand r1rd
' 1. i me IDAiMalf Instruct or 1 n form at i on / Act i 1.i t y
~
CT-2 Secure all RCP within 5 min. of loss of NPSH. (2260 3.1.1)
SG02A @ 60%
- 60 sec.)
PPO 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.
- 1 S/G Tube Rupture - 750 gpm.
If the MSIVs are open, the SJAE should show a rise indicating a SGTR in #1 S/G.
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 ('RAC on c-0 1 x Check SI Flow adequate Ensure all available Chg. Pp. operating.
Ensure vital switch gear cooling If RCS Press NPSH Trip all RCPs spray valves close steam dumps to condenser EOP 2532 Step 5 EOP 2532 Step 6 CT-2 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 ar ci When the crew determines they have a SGTR in # 1 S/G, move forward in this guide to EOP 2540.
PPO PPO IJ S/PP O/
SPO
~
PPO PPO SPO Isolate the LOCA Ensure valves are closed for isolating LOCA Check not RBCCW Radmonitor.
Check LOCA NOT Outsidc CTbIT Check RBCCW Surge Tk not rising Check Kadmonitors outside CTMT on PPC Place Hldrogen Analyzers in Service EOP 2541 t\\ppendix 19.
If CTMT pressure is '4.42 psiig or CTMT Radmonitors are in alarm Ensure SIAS, CIAS, EBFAS, MSI &
CRAC.
Start all available CAR Fans \\vith RBCCW I-low.
If CTMT Press.
9.48 psig.
Ensure CS Pps. running Ensure CS Flo\\v ;' 1300 gpm.
If MSIVs are closed, open AK-1 7 "Vacuuni Breaker" EOP 2532 Step 7 EOP 35-32 Step 9 MA-2 TM-6 EOP 2532 Step 10 EOP 2532 Step 1 1 EOP 2532 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 The operators will coinmence a rapid cooldown within the Tech Spec limits.
SIAS flow must be capable of recoverin~/maintaiiiing RCS pressure.
The crew should establish and maintain the RCS press. vs temp. within the PT Curve.
Major change in plant conditions (tube rupture) requiring transition to Functional Recovery (2540)
EOP 2540 Functional Recovery SPO SPO PPO IJ S If MSIVs are open Align Condenser Air KeniokA to Unit 2 stack Initiate a controlled cooldown If MSIVs Open, use SD/RP Vlvs If MSIVS Closed. usc ADVS.
Initiate a controlled depressurization of the RCS to SDC conditions.
If no RCPs use Aux Spray If RCPs running use Main Spray When crew recognizes they have a LOCA with a S/G Tube Rupture.
Implement the Diagnostic Flow Chart (2541 Appendix 1)
Confirms 2 events requiring Functional Recovery (EOP 2540)
Crew transitions to EOP 2540 Functional RecoLxry.
EOP 2532 Step 15 EOP 2532 Step 17 EOP 2532 Step 18 OP 2260 Step 1.19.2 EC-1 ELI-2
SE('T1ON 4 1L) N~itiiber ES04LI 1 Rci.ision: 0
'Task
. I
' i me I D A/MaI 1' Instructor Inforination /.\\cti\\ it) r\\ ssi gn Espectcd (ktions Standard Enter time in Safety Function Tracking The SM should classifj. the e\\'ent as AlertiC1 per RCB4 Note: Classification will be accomplished in JPM-A4SRO.
254*
I I
s M Ensure Master Silence in Off Sample both SiGs IJS EOI' 2 5 40 Step 4 IJSISPO Hydrogen Analyzers may already be in service.
USiSPO us Place Hydrogen Analyzers in service.
Identify the Success Paths using RATS.
Classify the Event EOP 2540 Step 5 EOP 2540 Stel-, 6 FAPO6 EOP 25.10 Step 1 Safety Function Success Path Page Reactivity Control RC-1 CEA Insertion SteQ 2 1
Operating Y
Y Priority 31
SFC I ION -I ID Numbcr kSO-IL,TI Re\\ ision: 9 1 as],
Assign Espectcd Actions s tandard Time IDA/hlalf Instructor Information / Acti\\.ity Maintenance of Vital DC Power Maintenance of Vital AC Power MVA-DC-1 Battery Chargers/Station Batteries Y
Y MVA-AC-1 RSST Y
Y RCS Inventory Control RCS Pressure Control Y
IC-2 Safety Iiij ec ti on Y
Y PC-2 Saturated Y
Y RCS and Core Heat Removal Containment Isolation Containment Temperature and Pressure Control Y
HR-2 SI operating CI-1 Automatic/Manual N
N CTPC-2 CARS (Emerg)
Y Y
I Containment CCGC-1 Hydrogen Recombiners Combustible Gas Control 32 Y
Y 1
US Directs the STA to verify the Safety Function are satisfied for the chosen success paths.
EOP 2540 Step 8
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 US should transition to EOP 2540E.
Transition to EOP 2540E The crew will identify the #1 S/G as faulted by one or all of the following.
Feed Flow/Steam Flow mismatch SGBD radinonitor SJAE radmoiiitors CT-3 Cooldown to 5 515 Th.
Maxiilium controllable rate is characterized b \\ r a rate that does not further degrade the conditions of the plant.
kfforts should be made to presene NPSH, Subcooling and Pzr/Head Levels. while trying to limit S/G level by isolating the Si(; as soon as possible.
us us US/PPO us/
CREW I JS/SPO Perform operator actions for chosen success paths based 011 priority assigned.
Transitions to EOP 2540E Containment Isolation If CTMT Press.
Radmonitors rising or in alarm.
4.42 psig or CTMT IJS directs the PPO to eiisurc SIAS, CIAS, EBFAS AND MSI on C-01 and c-0 1 x.
If a SGTR is indicated. identify and isolate the most affected S/G.
US references EOP 2541 Appendix 12 Coininence an RCS cooldown at maximum controllable rate to <5 15 Th in both S/C;s.
If the condenser is available SDiRP Vlvs \\vi11 be used.
IF the condenser is not available. both ADVs will be used.
EOP 2540 E17-3 EC-2 Step 9 EOP 2540 Step 9 EOP 2540E Step I EOP 2540E Step 2 CT-3 rm 254 I Append 12 Step 1
The US should give the PPO a pressure range the does not violate any of the listed limits.
U W P O Depressurix the RCS using main or aux.
spraj. while maintaining the following limits:
Step 2 Append 12 CT-4 Isolate the faulted SIC within 60 minutes of evidence of a tube rupture. (OP 2260 3.3.1)
If HPSI throttleistop criteria is mct, the PPO should limit injection flow to stabilize Pzr. Le\\ el and pro 111 o te de pres sur i zat i on.
CT-4 EOP 2541 Append 12 Step 2 US/PPO If HPSI throttle/stop criteria are met:
Control charging and letdown US/SPO Directs the SPO to isolate # 1 S/G per Appendix 12 EOP 2541 Append 12 Step 6
The scenario can be terminated when the crew has successfully isolated the #1 WG.
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
- 8. Pull-to-Lock both AFW Override v 111) handswi tches
- 9. Close FW-43A (Aux FRV)
- 12. Close bIS-265 (MS Lolv Pt. Drain)
- 13. Check all safetj- ~ - 1 ~ s closed 35
Section 4
SUMMARY
'Title: Simulator Evaluation
[D Number:
ES04LI1 Rev i si on :
0 C K 1 TIC A L '1-A S KS CT-I :
Trip 2 RCPs (LOCA-13)
CT-2:
c r - 3 c w :
Secure all RCP within 5 min. of loss of NPSH.
Cooldown to 5 515" Th.
Isolate the most effected S K.
36
Section 5 SCENARIO INITIAL CONDITIONS
Title:
Simulator Evaluation ID Number:
ES04LI1 Revision:
0 Initial Conditions
%2 is protected 100% power, NOP/NOT, EOL, Equilibrium Xenon 35 ppm boron / Blend ratio - 165 PMW / 1 BA 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 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 Verified By:
38
Mf'2 Slh/tl iLiZ-rOR 7TRAINING SHIFT TURNOVER REPORT DATE-TIME Todav 0515 PREPARED BY SHIFT Unit Supervisor /"NIGHT" Shift 18:OO - 06100
~
.\\If<(;. Ill'. 1 TTS Thermal: 2699 MWTFI PZR PRESS 2250 psia
\\/ODE 1 RY POIVER 100 Yo 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 Unidentified : 0.3 3 gpm Date/Time:Todav 001 5 22 (YELLOW)
L E4 h:-l GE Date Time LCO Action Act ion Requirement Equipment Reason Continuous TS LCO and TRM ACTION Statements in cffect (if more than one ACTION requirement per LCO, list each semratelvl Action Requirement LCO Action Equipment Reason I Infinite action: Attacliment I ofOP 2301A I TSAS 3.j.3.S 1 a13 I
RC-200 I
Failed SP 24 1 OA J
Intinite action: Establish hourly fire watch. I TRMAS 3.7.10 OD COMPENSATORY ACTIONS / Temp LOGS (Bold: Tech Specs, Italics: TRM) 1 See AIL See Active Impairment List.
EVOLUTIONS IN PROGRESS & NOTES CThl J Sump IS being pumped periodically to inonitor KC'S Leakage SF-lOi4B "Forcing Pzr Sprays for Boroii Equalization" IS approked for completion on this \\\\atch 10 1 gpm leak 011 C H 4 4 2 Unit 2 Chemistry ON-LINE STATUS REPORT Refererice /Date Today REACTOR COOLANT Time 0625 1% ra 111 et er 11 Parameter Reading Reading-Poner 100 Yo Ta\\;e 572 delrF 1; I uori de 0.81 ppb Chloride 1.75 m b I Boroii 35 PPm (1 Oxygen
<5 PPb I
I Blcnd Ratio:
11 165: 1 I
Y 1
Y
- 2.
Y 3
4 Y
5.
Y
- 6.
N/A 7 Y
- 8.
Y 9.
Attachment Guide No.: ES04LI1 SCENARIO ATTRIBUTES CHECKLIST Scenario
Title:
Technical Reviaver:
D. A. fantalone Date:
12/03i2004 1- 0 1 T S i in 11 1 at o r Ev ai uat i on Number:
ESO41,I I QUALITATIVE ATTRIBUTES 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.
The scenario consists mostly of related events 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)
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.
The events are valid with regard to physics and thermodynamics.
Sequencinghiming of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.
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.
The simulator modeling is not altered.
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)
- 1. Trip of C SW Pump
- 2. Fail FW Heater 6A 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
- 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)
- 1. EOP 2532 Loss of Coolant Accident
- 2. EOP 2540 Functional Recovery
- 3. EOP 2540E Functional Recovery of Containment Isolation 6
7 3
- 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)
Total 120 (Y/N) 1 Attachment Guide No.: ES04LIl SCENARIO ATTRIBUTES CHECKLIST
- 7.
Critical Tasks (CT)- (2 - 3) 1. Trip 2 RCPs (LOCA-I 3)
- 2. Secure all RCP within 5 min. of loss ofNPSH.
-3. Perform a plant cooldo~vn 5 5 15. Th
- 4. Isolate the most affected S/G.
- 8. Approximate Scenario Run Time: 60 to 90 min.
- 0.
Technical Specifications exercised during the scenario.
5 42
Attachment Guide No.: ES04LIl SCENARIO ATTRIBUTES CHECKLIST IC-92ES04LIl Load Limit Pot Setting = 6.80 B
A AS1 Upper 4.70 4.72 AS1 Lower 4.73 4.68 Nuclear Power 4.56 4.82 A T Power 3.91 4.10 Tcold Cal.
4.80 4.80 C
4.73 4.75 4.68 3.92 4.80 D
4.67 4.67 4.67 4.07 4.85 43
Millstone Station Unit 2 Operator Training SIMULATOR EXERCISE GUIDE I.
Title:
LOIT Simulator Evaluation #2 ID Number:
ES04LI2
- 11.
Initiated:
Developer Reviewer IV.
Approved:
Operator Trayfing Supervisor Revision:
0 1 11 2/05 Date Date
~~
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.
E\\.aluate licensees in the follou ing areas. as applicable:
I )
- 3) 3 )
- b.
Ability of the cren to perform creu-dependent (and time-critical) tasks.
Ability of indiLi1uals to perform critical tasks.
Ability of the crew to:
a)
Understandhterpret a1artns:annunciators b) c)
Understand plant/s! rtems response d) e) 0 Perform control board operations Ability of each individual to:
a) b)
Correctly diagnose e\\ ents c) d)
e) f)
g)
Demonstrate a responsible attitude h)
Diagnose eventsiconditions based on signals/readings Comply witWuse procedures and Technical Specifications Properly communicate informatiodproper crew interactions
- 4)
Respond and correctly interpret annunciators Properly interpret integrated system response Comply uith and use Technical Specifications Comply with and use procedures Properly perform control board operations 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 YO power, 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 Start up.
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 MSIV 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 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />
- 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 format i on /i i\\ c t i \\ T i t y A ssi gn Expected,Zctioiis s tnndard IC-91 or equivalent CHR06 (22.8)
CHR07 (223.4)
CHR08 (23.6)
CHR09 (224.1)
CHRlO (23.1)
CHRl1 (222.9)
RP04A RP04B RP04C RP04D RP27.4 Simulator Setup and Initial Conditions:
1 % Power, BOL, RCS Boron 1680 ppni.
Insert a remote function for wind direction from the West-Southwest at 23 mph.
Insert malfunctions to prevent all four Reactor trip buttons from tripping the reactor.
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.
TM 7 4
Task 1 DNhl al 1' I 11s t ruc t o r I n for inn t i on / ;\\ c ti 1. it >
Ass i g n E spec t ed 11 c ti ( ) n s St:1nclmi T i m 0
0 0
0 0
0 0
0 0
0 0
0 0
Provide the crew with the following information:
I YO power, BOL, positilre MTC Groupp 7 CEAs @ 135 steps 1680 ppm boron Blend ratio - 2.5: 1 SG Blowdown - 40 gpm each Condensate on short recycle "A" Main Feed Pump in operation Vacuum being maintained nith the Hoggers 24E aligned to Bus 24C Forcing Pressurizer Sprays 2 Charging Punips running Snow storm in progress (20-25 mph winds)
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 s s i gn Expect c d X c t i ons Standard When the PMW counter reaches 0.
observc continuous flow of PMW to the RCS. Inform the US of the condition.
Direct the PPO to close VCT Makeup Bypass, CM-196 or placc the Makeup Selector Switch in a position to prevent dilution. Inforin RE and the I&C Dept.
C V B A (7)
MP-I4 TM 1 AE 1 ARP 2590c When the crew begins the third dilution of 25 gallons to raise power to 4%, insert a inalfinction to prevent the Dilution Valve, CH-2 1 OX, from closing.
~
~
~
Close VCT Makeup Bypass, CH-196 or place the Makeup Mode Selector Switch to the Manual or Borate position. Observe 0 PMW flow to the RCS. Inforin the IJS that PMW flow is secured.
Direct the PPO to monitor plant parameters When requested as I&C, inform the crew that you will obtain the appropriate paperlvork and trouble shoot the problem.
ARP 2590C CT I MP-I 4 NOTE: The US may provide a specific value, as 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).
PPO 1.J S PPO us 6
SECTION 4 ID N~iiibci-ES041.12 Rcl ision: 0 I 'ask Expected Actions s Land asci Timc I DA/Mal I' Instructor Inform at i o n 1 Act i1.i ti
!Issign
'l-I CW02D (100%)
Ramp=460 sec.
When the plant has stabilized, insert a malfunction to cause the '*D'* Circ Water Screen DIP to increase.
After a 5-1 0 minute delay. report as the PEO that all requested actions are complete. Also report that the "D' traveling screen is NOT rotating. It appears that a pin has sheared. All other traveling screens are operating properly.
SPO USISM IJS Observe rise in "D" Circ Water Screen D/P or acknowledge Ailnunciator D-10 on C-05, Traveling Screen AP.
Enter AOP 25 17, Circulating Water Malfunctions, and perform Initial Actions.
Direct a PEO to:
0 0
0 0
Check all screens rotating Monitor traveling screen DIP Notify Environmental Services-Nuclear Start both screen wash pumps.
Place all traveling screens in fast.
Chcck screen wash pump strainer D/Ps less than 4 psid.
Place screen wash trash basket in service When D/P approaches 30", direct SPO to perform actions of AOP 25 17. Section 5.
MP-14 TM 2 AE 2 ARP 259OE-056 OP 2327 AOP 25 17 7
SFC I ION J It) Number ESO4LI2 Re\\.ision: 0 I-a 5 k Time IDA/Malf Instructor Infbrination.Acti\\.it!
Assign Expected Actions Standard The US may may NOT direct cross tying D Water Box with C Water Box. Steps in itulics are optional.
SPO Optional. Only required if water boxes are cross tied.
Check condenser backpressure is 54.5 in.
Hg.
AOP 25 17 us Optional. Only required if water boxes are cross tied.
Trip the D Circ Water Pump.
Close C W-1 1 E, D Water Box Inlet Cross tie wciter boxes:
Place D Circ Water piimp in Pull-E m ~n-e ( W-I I D, D (irr Wcittv. Box C)irtlef, is open Opcn (W-12C, Condtwsei-I B Inlet Cross -Tie T(1-Loc.k rn SPO USISM AOP 2517 AOP 25 I7 Upucte PPC Condenser Perfor-mume Report to indicate uctuul ('ire Wutci. i*c~Ive positions.
AOP 25 17 Notif!. En\\ironinental Ser\\+xs-Nuclex of Circ Pump trip.
AOP 2517 Inform iiiaiiiteiiance of the D Screen failure and direct them to troubleshoot and repair.
MP-14 8
SEC IION 4 ID Number ESO4LI2 Re\\,ision: Q Task Assign E x pr c t ed Act ions Stand arc\\
Time IDA/Mnlf Ins t 111 c tor I n forin at i on / Act i v i t >,
Rxo I R ( I 00%)
Rnmp=250 sec.
When the crew has cross tied water boxes, insert a malfunction to fail Channel Y Pressurizer Pressure transmitter high.
When informed of the Pressurizer pressure transmitter failure, report that I&C will obtain the appropriate paperwork and commence troubleshooting.
PPO IJS PPO UWSM Observe the Channel Y pressurizer pressure rising and Channel X Pressurizer pressure lowering. Observe PZR Pressure Selected Channel Deviation Hi/Lo annunciator and Pressurizer CH Y Pres Hi/Lo annuciators.
Direct the PPO to perform ARP actions for the annunciator.
With lJS concurrence (or dircction) perform one of the following:
Shift Pressurizer pressure control to channel X.
Manually close the spraq valves.
Place channel Y Pressurizcr pressure control in Manual.
Inform the I&C Dept. of the failure of Channel Y Pressurizer prcssure.
MP-14 TM 3 AE 3 MP-14 I\\KP 2530B-2 12 or 220 ARP 25903-2 12 or 230 9
0 a
m c
L
SEC I-loh 4 ID Numher ES04L12 Keiision. 0 Task riine IDAiMalf Instructor Information 1 Actii itj.
A s s i g n Expected Actions s tnnclard T4 MS06R MS02B (7%)
Rainp=400 sec.
Approximately 5 minutes after the low pressure alarm is annunciated, insert a malfunction to fail close the #2 MSIV and cause a steam line break upstream of the valve in the Enclosure Building.
Crew us I
us CT 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.
~
~
~~
~
Observe closure of #2 MSIV.
After the MSIV has closed, obser1.t.
lowering SIG pressures, lowering RCS temperatures, and lowering RCS pressure.
PPO Direct a niaiiual Reactor trip and performance of EOP 2525.
Presses manual Reactor trip push buttons and observes a failure of the Reactor to trip.
Opens the CEDM MG set output breakers and observes a Reactor trip.
Place Master Alarm Silence in SILENCE.
Announce Unit 2 trip on the plant paging system.
Query board operators regarding the status of safety functions.
MP-14 TM 5 TM 6 MA2 MP 16 CT 2 OP 2260 OP 2260 11
SECTION 4 Rex-ision: 0 ID N~tiiiber ES041,12 Task Assign Expected Actions Standard Ti me IIIA/h/lalf Instructor Information / Activit\\,
PPO The PPO may also manually initiate MSI on laic SG pressurc.
Complete and report SPTA:
- 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.
is being met:
o
- Verifies RCS Inventory safety function 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 closed.
o When Pressurizer pressurc fails to less than I800 pia. manuallq initiates SIAS, or verifies automatic SIAS when pressure falls below 17 14 pia.
o Reports SIAS. CIAS, ERFAS. und A4X EOP 2525 EC 1 12
SECTION 4 Re \\.i s i o n : 0 ID Number ES04L12 Task s tandartl IIIA/Malf' Instructor Intorination / PIctivitJ Ass i g 11 Espccted Actions Time If KCS pressure lowers to NPSH setpoint. secure all KCPs.
c'?' 3: Isolate Auxiliary Feedwater to the #2 5/G from the Control Room within 10 minutes
)f the initiation of the ESD.
SPO
~~~
- Verifies Core Heat Remo\\~d established o Two KCPs are operating (one in each
- 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 1 oop).
normal.
c' 0 Ill}' 1 et e and report s P 1 'A :
Frip turbine. stop \\.al\\~x closed. R indicate 0. and 8T&9T opcn A11 electrical buses are energized Both SW and RBCCW facilities running we Verifies status of 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 O\\ erride/Man/S tart/Reset hand snitches in Pull-'I'o-Lock Feeding # 1 SG onl\\ \\vith Auxiliar~
Feed to restore level to 40-70%.
3
?C 2 3T 3 13
SE(7 ION 1 1D Xumber ES04L12 Ke\\ision: Q Task Time IDA/Malf Instructor Information I' Acti1.i ty Assign Espectcd Actions Standard Refers to Diagnostic Flow Chart and determines that EOP 2536, Excess Steani Deniand is the appropriate procedure.
Direct the performance of Safetj. Function Status Checks for EOP 2536 This action will be performed when #2 SIC; is enipty as indicated by a rise in RCS teniperature EOP 2525 EU 1 EOP 2536 I
SPO SPO PPO 1 SPO us IJSIST.4 LJ S
~
Adjust # 1 ADV to stabilize RCS temperature.
Performs subsequent actions:
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&
When queried, report completion and verification of subsequent actions.
EOP 2525 EOP 2525 OP 2260 Direct Chemistry to obtain saiiiples of ## 1 SG and analyze for Boron and activit".
Direct SPO to close S/Ci sample vali es when saniples have bcen taken.
EOP 2536 14
SEC IlON 4 Rei ision: 12 ID N u n i t m ESO4L12 E s pec t e d Act io 11 s s landard lDA/lvl al f Instructor Info rni at i o n /.\\c t i 1.i t)
.Assign Time Direct SPO to ensure MSI has properl!,
actuated and to Irerif). open the vacuum breaker, AR-17.
Observe conditions on c-0 1 X to ensure proper actuation of MST or obser1.e indications on C-05 and c-0617.
Event is classified as an Alert, Charlie-One (BA2), based on an unisolable steam line break outside Containment.
NIP 2536 LOP 2536 USISM us us PPO us SPO Ensure event is classified.
Open place keeper and enter EOP entry time Return Master Silence switch to Normal Direct PPO to:
Check SIAS Actuation Optimize Safety In-jcction
~
Ensure:
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.
All available Charging Pumps are run n i 11 g,
Vital Switchgear Cooling is in operation on C-80 0
EOP 2536 EOP 2536 EOP 2336 EOP 2536
SECTION 4 Ice\\ isioii: Q ID Number ES04LI2 Task Time I DA/Malf Instructor Information / Activit).
- \\ssign Expected Actions s t a11 d arc1 I
The US may direct the SPO to stop Auxiliary Feed to the #2 S/G prior to referencing the Diagnostic Flow Chart. It is acceptable (desired) per OP 2260, EOP User Guide, to take actions to stabilk the plant prior to referencing an appro\\d procedure provided the appropriate procedure is used after taking those actions.
c ren r While the SPO is isolating #2 SIC;, insert a nialfunction to trip the supply breaker to Vital Instrurncnt Bus, VA-20.
US Verify 2 RCPs in each loop are stopped with the respective spray l d v c closed.
IfPr*es.vi.irizc~
pressiirc loicws IO less ~ l m i m in in1 urn.VPLSH>
I her? s l o p re nict in ing R CPs.
Determine that #2 SIC; is the 'most affected'.
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 Chart.
Using the Diagnostic Flow Chart, determine that EOP 2536. Excess Steam Demand. is still the appropriate procedure and direct the SPO to stop Auxiliary Feed to #2 SIG.
EOI' 2536 EO 1' 2 5 3 0 TM 8 EM I MA 2 OP 2260 EC 3 EOP 2525 16
SEC I ION 4
- 11) Nu1nhi.r ES04LI2 Re\\ ision. 0 Task Standard Time I DA/Malf Instructor Information 1 Actii itj
$1 s si gii hpected i\\ctions FWRGO (Man)
FWR64 (0)
MSR13 (RI)
CT 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.
If requested, as the PEO, close #2 Aux Feed Reg Valve, FW-43B.
When directed, as the PEO, close the disconnect for MS-202.
SPO SPO Close 2-FW-44. Aux Feed X-Tic Val\\fe g~
Stop the running Aux. Feed Pump(s) E Dispatch a PEO to manually close #2 Aux Feed Regulating Valve, FW-43B.
Complete actions to isolate #2 SIG by I
I I
0 0
I 0
I e
0 a
ensuring:
- 2 MSIV is closed
- 2 MSIV Bypass is closed.
ADV Quick Open Permissive in Off.
- 2 Main Feed Block Valve. FW-42B.
is closed
- 2 Main Feed Air Assist Check Valve.
FW-SB, is closed
- 2 SIG steam Supply to Terry Turbine.
MS-202, is closed
- 2 SIG Blowdown Isolation. MS-220B.
is closed Both.4uxiliarj Feed O\\rerride/Man/S tart/Reset hand snitches are in Pull-To-Lock
- 2 Aux Feed Regulating Valve, 1.W-43H. is closed
- 2. Main Steam Low Point Drain. MS-266B, is closed
- 2 Main Steam Safety Valves are closed MP 16 CT 4 EOP 2536 17
SEC-I'ION 4 ID Number ES04L12 Rc\\ ision:
I'ask A ssi p Expected Actioiis Standard
-1 inie IDA/lvIalf Instructor Information / ActiL it!
The SPO will stabilize RCS temperature with #1 ADV when the #2 S/G indicates empty. The PPO will lower or maintain RCS pressure to prevent Exceeding 200°F subcooling. This step iiiay need to be pulled forward to pre\\Vent exceeding the PTS limit.
CT-5: Limit Tc subcooling (CET subcooling if all RCPs are secured) to 5200OF.
Lower RCS pressure using Main (or Auxiliary) Spray Valve.
Establish RCS temperature control using the #I ADV when #2 S/G indicates empty.
us SPO I PPO PPO Verify most affected S/G has been isolated:
0 Lowest steam pressure 0
Lowest level 0
Lowest cold leg temperature Stabilize RCS tempcrature.
0 Open unaffected ADV to stabilize RCS tenipe raturc.
Maintain RCS within the RCS P/?' limit:
Manuall) control Pressurizer heaters and sprq..
If HPSI throttle stop criteria are met:
o Control Charging and Letdo\\\\ n o Throttle or stop HPSl Punips.
~
Throttle/Stop HPSI Puiiips \\vhe11 the follon ing conditions are met:
0 Pressurizer le\\ el -.20%
0 Rcactor Vessel ler.el> 43%
RCS subcooling is abo1.e niiniiiium operating limits of the P/l Cur\\ e At least oiic SiG available to remo\\c lieat at 40-70'% or being restored EOP 2536 EOP 2536 CT 5
+
(.
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.A SKS C'T I :
Establish reactivity control. Stop the dilution within 5 minutes (Dilution must be stopped to prevent an 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 or 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 11 liI 0 I N I TI AL CON 111 I-I ON S
'I itle: Simulator Evaluation ID Wumber:
ES04LI1 lie\\i sion:
0
~~
~
~
Initial Conditions 0
0 0
0 0
0 0
0 0
0 0
0 0
1 % power, B01,. positilre M'PC' Gp 7 CEAs 135 steps 1680 ppm boron Blend ratio - 2.5: 1 SG Bloudown - 40 gpm each Condensate on short rec!.cle "A" Main Feed Pump in operation Vacuum being maintained with the Hoe&
0 rers 24E aligned to Bus 24C arcing Pressurizer SprajTs 2 Charging Pumps running Snow storm in progress Expect 3-5" (20-25 niph u inds)
No 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
IITIAC HMENT VAI_IDATION CHECKLIST I; tle: Simulator Evaluation ID Number:
ES04L12 Revision:
0 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 Verified BY:
22
k/ir-2 SIMI ~I...ITOR TRAINING SHIFT TURNOVER REPORT D ATE-TIME
-Today 0515 PREPARED BY SHIFT Unit Supervisor !NIGHT Shift 18100 - 06:OO PLANT STA TUS:
.tlE( L-1 WA TTS; Thermal: B M W T H PZR PRESS: 2250 psia
,\\IODE:
2 RX POWER: L/O Electric: OMWe RCS T-AVE: =degrees F
KC*S Identified: 0.073 gpm PROTECTED: Trai n/Fx i 1 it!
Date 22 (YELLOW)
LE,IKAC;E: Unidentified: 0.032 gpni Date/Time: Today 00 1 5 Time LCO Action Action Requirement Equipment Reason TS LCO i1nd TRM ACTION Statements Coming Due (if inore than one ACTION requirement per LCO, list each sena ra telvl Action Requirement Infinite action: Establish hourly fire watch.
LCO Action Equipment Reason TRhlAS 3.7. I O I
See AIL See Actice Impaimient List.
EVOLLJTIONS IN PROGRESS & NOTES Plant startup. Raise power to 4%, using dilution onl!.. for warming the Main Turbine.
Forcing Pressurizer sprays. Two Charging Pumps operating.
.A* Maiii Feed Pump in operation.
Condensate on short recycle.
Silo\\\\ storm in progress. Expect 3-5. Winds at 20-25 mph.
OD COR,IPENSATORY ACTIONS / Temp LOGS (Bold: Tech Specs. Italics: TKM) 7 odn!
Reference /Date OP 2203 Today OP2203 Today OP 2203 Today OP 2203 Toda!
CONVEX Today Pa ram et er Reading Po lvc r 1
Yo Unit 2 Chemistry ON-LINE STATUS REPORT Parameter Reading Fluoride 0.81 nnb T ~ \\ Y 532 degF C 11 1 o ride 1.75 ppb I
13 o ro 11 1680 ppni Oxygen 4 ppb I Blend Ratio:
11 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 (1 IJ 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 symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the malfunction(s) that are entered to initiate the event the expected Emergency Plan classification the event termination point (if applicable)
Y 4
Y 5
Y 6
N/A 7.
Y
- 8.
Y
- 9.
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.
The events are valid with regard to physics and thermodynamics.
Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.
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.
The simulator modeling is not altered.
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)
- 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 8
- 2.
MaIfs after EOP entry (EMS) --.(I - 2)
- 1. The supply breaker to Vital Instrument Bus, VA-20, trips Abnormal Events (AE) - (2 - 4)
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
- 3.
I 3
- 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
- 3. Recognize a significant change in plant conditions and refer to the Diagnostic Flow Chart.
P u Il-TO-Lock 25
- 7.
Critical Tasks (CT)- (2 - 3)
- 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 ~200°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).
5
- 8.
Approximate Scenario Run Time: 60 to 90 min.
- 9.
Technical Specifications exercised during the scenario.
26
IC-91 ES04L12 A
AS1 Upper 4.85 AS1 Lower 4.85 Nuclear Power 4.69 AT Power 1.32 Tcold Cal.
4.89 B
4.82 4.82 4.68 2.19 4.91 C
4.85 4.87 4.68 1.29 4.82 D
4.82 4.82 4.68 1.07 4.96
Millstone Station Unit 2 Operator Training SIMULATOR EXERCISE GUIDE I.
Title:
LOIT Simulator Evaluation #3 ID Number:
ES04LI3
- 11. Initiated:
111. Reviewed:
IV. Approved:
Developer m
Operator Tra ing Supervisor Revision:
0 1/13/05 Date Date
~
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.
Evaluate licensees in the following areas. as applicable:
- 1)
- 2) 3 )
- b.
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 alarms/annunciators b) c)
Understand plant/systems response d) e)
f )
Perform control board operations Ability of each individual to:
a) b)
Correctly diagnose events c) d)
e) f )
g)
Demonstrate a responsible attitude
- 11)
Diagnose events/conditions based on signalsh-eadings Comply witNuse procedures and Technical Specifications Properly communicate informatiodproper crew interactions
- 4)
Respond and correctly interpret annunciators Properly interpret integrated system response Comply with and use Technical Specifications Comply with and use procedures Properly perform control board operations Properly communicate information and interact with the rest of the crew 2
Title:
Simulator Evaluation 1D Number:
ES04LI3 R e\\ri sion :
0 I.
3 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. 1 he 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 \\\\ill 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 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />
,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 equivalent Simulator Setw and Initial Conditions:
100% power, BOL, Equilibrium Xe, 1201 ppm.
1Jsing IDT, set CMMDRY to 1.284e05 E5 Raise Containment pressure to read 22 inches of water.
ED02 on BT9 1 Loss of the RSST on the plant trip 1Jnder CH, I/O OFF G for HS8137 (2)
I T M S 110 off both green lights for F-16 ES03.I Failure of C HPSI Pump to automatically start on SIAS (failure of AM-6 14).
TM 8 EM 2 FWR22 (Local)
FW20C (Trip)
FW30B (1 00%)
Ramp=300 sec.
Close Steam Supplies To Terry Turbine. MS-20 1 and MS-202, and insert remotes to rack out the
-~
Disable the Terry Turbine and place a yellow tag on the Terry Turbine Steam Admission Valve, Gradual degradation of the B Aux Feed Pump.
SV-4188.
TM 6 MA 2 BT37 MSR13 (RI) 5 Rack in breaker for MS-202.
RC-27 associated breakers.
Place yellow tags on valve hand switches 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.
SECTION 4 ID Number E SO4 LI3 Revision: Q 1'.I.
as <
S taiidard Time TDA/Malf Instructor Information / ActiLrit!
Assign Expected Actions TO 0
0 0
0 Terry Turbine out for bearing replacenlent F-16 out for filter replacement RC-200. AVMS is out of service.
Enclosure Building Purge using Main Exhaust has been in continuous operation for several months.
Provide crew with OP 23 14B, section 4.13.
Steps 4.13.1 through 4.13.7 are signed off as complete.
0 I
Ensure the surrogate directs the PPO to depressurize Containment. If the crew does NOT initiate actions to depressurize Containment, as Chemistry, call the S M and ask when they started the c' on t ainm en t depres sur i za t i o 11.
US/PPO Brief the crew on the depressurization of MP-14 Containment.
6
SECTION 4 ID N~uiibcr ES04LI3 Rei.ision: Q Task Assign Expccted Actions Stand x d Time IDAiMalf Instructor Infomation i Acti\\ it)
Ensure the H2 Purge Valves associated with the same facility EBFS Fan are opened.
After a short delay, as the PEO, report that the Hydrogen Purge Flow Limiting Butterfly Valve in the 386 East Penetration Room is open.
~
As Chemistry, acknowledge the time Containment venting was started.
PPO PPO us us Place EBFAS in operation as follo\\vs:
Align Condenser Air Removal to Unit 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 o
o o
Damper Open EB-5 1, Header A Isolation Start F-25, A EBFS Fan Check EB-52, Fan A Discharge Damper, opens Monitor for proper operation.
Open Facility 1 Hydrogen Purge Valves.
EB-100 and EB-99, on C-0 1. and direct a PEO to open the associated Hydrogen Purge Flow Limiting Buttertly Val\\ e. EB-194, in the 386 East Penetration Room.
Record start time in SM Log.
Notify Chemistry that Containment venting is in progress.
OP 33 14B OP 23 14G OP 23 14B OP 23 14B OP 23 14B 7
Sk:(TI( IN 4 ID Number ES04L13 Re\\.ision: 0 Tash Tinie IDA/Malf Instrirctor Information / Activit!
Ass i &I1 E s pec t ed Actions Standard TI PCO 1 Once the crew has initiated Contailinlent depressurization, insert a malfunction to causc a loss of the PPC.
After a 5-10 minute delay, report as Computer Services that the PPC has a significant malfunction and that troubleshooting has begun.
An update will be provided when more information is available.
Crew While observing the PPC. note a failure of the PPC to update ally parameter.
Observe Computer hop alarm on C-08 Enter AOP 25 18, Loss of the PPC.
Direct a PEO to complete Attachment 1 of AOP 25 18.
US/SM US Log into TSAS 3.1.3.3d. All pulse counter channels are inoperable.
Place PWR RATIO HI/LO, B 12B switch to OPER (Inside RC-22, Front, Rack #9) and observe Annunciator BB12 on C-04.
Log into TSAS 3.2. la. AS1 is outside the power dependent limits on the Power Ratio Recorder. AS1 must be restored to within the limits kvithin one hour.
Brief the crew on entry into AOP 2575.
Rapid Downpower, and the use of Attachments 1. 5, and 6.
RPR3 5 (NORM)
Examinee will need to contact the Booth Instructor to place the PWR RATIO HI/LO switch in the OPER position.
PPO US US US/SM Inform HP, CONVEX, IS0 New England. IJnit 3 and other persoiinel required by MP-0 1 -SM-GDT, 1.O 1 Brief crew on plant trip criteria.
0 MP-14 TM 1 AE 1 MP-14 AOP 25 I8 AOP 25 18 AOP 25 18 Tech Specs MP-14 AOP 25 18 AOP 2575 8
SEC~I-ION 4 ID Number ES04LI3 Ke\\.ision: I!
-rasi\\:
Standard Ti iiie 1DAiMalf Instruct or I n fo rill at i on / Act i \\ r i t j, Assign Expected Actions The crew should Borate from the RWST as the preferred method.
If the crew initiates the down power using CEA insertion, then ensure they use Step 4.1 1 of OP 2302A.
If asked, report as the PEO that baseline data has been recorded.
PPO SPO us PPO SPO
/PPO Initiate forcing sprays.
~
~-
Maintain S/G levels 55 to 70% during the down power.
Determine that a 5 to 10% down power is 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 Commence Boration from the RWST to one charging pump to commence lowering power.
Using Load Limit Pot, adjust Turbine load to follow Reactor power and maintain Tavg on program. (At tachmen t 5 )
AOP2575 1
AOP 2575 I
AOP 2575 I
I AOP 2575
SECTION 4 111 N~inibcr ES04I,I3 Revision: 0 Task Time IDA/Malf Instructor Information / Activity Assign Expccted Actions Standard RP 1 OC (0)
~
~~
When the crew has reduced power by approximately 3-5%, insert a malfunction to fail Channel C Pressurizer Pressure transmitter low.
PPO us PPO us PPO Observe the TM-LP TRIP CH C annunciator (DA-3 on C-04).
Direct the PPO to perform ARP actions for the annunciator.
Coinpare Channel C Pressurizer Pressure and TM-LP set point to the other safety channels.
Enter TS 3.3.1.1. Action 2.
Enter TS 3.3.2.1, Action 2 Obtain the necessary keys and bypass the following:
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)
I MP-14 i
TM 2 1
~
~
AKP 259OC-023 i 1
10
SECTION 4 ID Number ES04LI3 Kexrision:
Task Time IDAiMalf Instructor Information / Activity Assign Expected Actions Standard T3 FW33 (3%)
Ramp=35O sec.
FW33 (1%)
When the crew has coinpleted the actions of ARP 259OC-023, insert a malfunction to cause condenser vacuum to degrade to 5-5.5 inches Hg abs. Do NOT allow vacuum to degrade to the manual trip setpoint.
US should inform the crew that a plant trip will be initiated whedif condenser vacuum lowers to between 6 and 7 inches Hg abs.
Adjust the loss of vacuum malfunction to allow vacuum to continue to degrade. but maintain it below the manual trip setpoint.
~~
Crew us SPO Observe and report lowering vacuum, lowering electrical output, or Low Vacuum a1 arm.
Brief crew on entry into AOP 2574, Loss of Condenser Vacuum, plant trip criteria, and the need to reduce power if vacuum continues to degrade.
Start A and B Mechanical Vacuum Pumps.
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.
MI-14 TM 3 AE 2 AOP 2574 AOP 2574 11
SEC'l'ION 4 Re\\rision: Q TU Number ES041,E Task l'ime IL)A/Malf Instructor Information i Acti\\,itJ.
Assign Expect cd Action s Standard Determines vacuum is NOT stabilizing and directs the crew to continue the down power per AOP 2575.
\\ acuum anti loss of main generator output.
Observe rapidly lowering condenser Direct a manual plant.
Place Master Alarm Silence in SILENCE.
Announce "Unit 2 trip" on the plant paging system. Direct performance of EOP 2525.
Query board operators regarding the status of safety functions.
T4 AOP 2574 AOP 2575 MP-I 4 TM 4 MA 1 MP-14 OP 2260 OP 2360 FWRl9(0pen)
FWWO(0pen)
FW33 (Val-.)
FW33 (100%)
When dispatched as a PEO, open the Mechanical Vacuum Pump suction valves.
Vacuum should improve slightly then stabilize.
Set the loss of vacuum malfunction as required to maintain approximately 5-5.5 inches Hg absolute.
After 5-10 minutes. report that the Mechanical Vacuum Pump suction valves are open and that a second set of Air E.jectors has been placed in service.
Report that there is NO obvious indication of a vacuum leak.
When the US has determined that vacuum is NOT stabilizing, insest a nialfunction to cause a rapid degradation of condenser yacuuin.
USISM us Crew 1 JS IJS/SM us Direct a PEO to:
Open Mechanical Vacuum Pump individual and combined suction valves.
Place a second set of SJAE in service.
Check for proper operation of the A tinospheric Drain Collecting Tank level control system.
Check for watcr seal in Vacuum Breaker.
Check condenser expansion joint loop seal is filled.
Inspect for leakage.
AOP 2574 12
SEC I'ION 4 ID Number ES04L1-3 ReIrision: 0
-rasii As sign Expected Actions Standard Time IDA/Malf Instructor Information / Activity PPO Complete and report SPTA:
0 0
0 0
0 Ensures Reactivity safety function is being met:
-I&
Reactor is tripped
- All CEAs are inserted.
- Power is going down.
i SUR is negative.
Verifies RCS Inventory safety function is being met Pressurizer level is betwcen 35 and 70%
Verifies RCS Pressure safety function is being met:
A Pressurizer pressure is between 2225 Verifies Core Heat Removal established.
.9$ NO RCPs are operating and placed and 2300 psia.
Tavg controller, HIC-4265 in inanual and closed.
qJk Reports loop delta T less than 10°F.
i Reports value and trend of RCS Veri ti e s Containment Integrity safety function is being met by verifying CTMT pressure, temperature. and subcooling.
radiation monitor readings are normal.
EOP 2525
ID Number ES04LI3 SECTION 4 Task I'ime IDAlMalf Instructor Information,' Activity Assign Expected Actions Standard SPO May rep rt that "B" Auxiliary Feed Pump lischarge pressure is lowering: pump is degraded.
Complete and report SPTA:
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.
i Reports both motor driien Auxiliary Feed Puinps operating.
i Concurs ivith US report of s ubco o 1 i ng \\ a I ut'.
EOP 2525 14
SECTION 4 ID Number ES04LI3 Reirision: 0
'Task Ti iiie TDAiMalf Instructor Infcmiation Activity Assign Expected Actions Standard Performs subsequent actions:
Announces and opens Vacuum 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 Q Dispatches a PEO to align Station with Unit 3 and cross ties Station Air with Instrument Air.
Breaker, AR-1 7 When queried, report completion and verification of subsequent actions.
Refers to Diagnostic Floiv Chart and determines that EOP 2528. Loss of Off Site Power/Loss of Forced Circulation is the appropriate procedure.
I EOP 2525 OP 2260 EOP 2525 E1T 1 IAR10 (Open)
SPO PPO I SPO When dispatched as the PEO, after 5-10 minutes, report that Station Air has been cross tied with Unit 3.
LJS Directs the perforniaiice of Safety Function Status Checks for EOP 2528 US is 1-A
~
EOP 2528
SEC IION 4 ID Number ES04LI-3 Re\\zision: 12 Ill&
Expected Actions Standard Tinic ID A/Malf Instructor Information / Activity A ss i g n Even[ is clirssijied us [in Unusutil Event, Deltu-SM En.su1.e event is clitssifified.
EOP 2528 One, based on PlJl, Loss of 0ffLYite P o ~ w r for 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.
Breaker Open AR-17, Condenser Vacuum EOP 2528 TM 7,
Both MSIVs are closed.
0 Both MSIV Bypass Valves are closed.
EM 1, 0
AR-17, Vacuum Breaker is open.
MA 2 T4 EDOSC While the SPO is vcrifying MSIV closure, insert a SPO Verifies:
malfunction to cause an overload trip of Bus 24C.
Crew Obser\\,e indications for the loss of Bus MP-16 24c.
SPO Observes A DG running with NO OP 2260 cooling water and emergency trips A DG.
EOP 2525 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 Tiiiie IDA/blalf Instructor Informat 1 ask 12 ss i gn Expected Actions S tnndard ion 1 Activity SPO Crew US US/STA us PPO Observes lowering discharge pressure on B Aux Feed Pump.
Determines that a loss of all feedwater has -
occurred and that EOP 2537, Loss of All Feedwater, must be entered.
Briefs crew on entry into EOP 2537.
Directs the performance of Safety Function Status Checks for EOP 2537.
Directs:
All RCPs to bc stopped.
HIC-4165, Tavg Controller placed in Manual and closed.
Pressurizer Spraj. Valves, RC-1 OOE and RC-1 OOF, to be placed in Manual and closed.
Ensures all RCPs are secured.
Places MIC-4 165, l a y Controller. in Manual and closed.
Places Pressurizer Spray Valves, RC-1 OOE and RC-1 OOF in Manual and closed.
MP 14 OP 2260 EU 2 OP 2260 EOP 2537 EOP 2537 EOP 2537 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 be initiated prior to SG level reaching 70 if two trains of HPSI, PORVs and ADVs are NOT available.
CT-1 Once-Thru-Cooling must be initiated prior to reaching 70 inches in the lowest Steam Generator or for a >5OF rise in Tc. (OTC will be initiated early due to loss of one facility.)
CT-2 C HPSI Pump must be started prior to opening the PORVs.
POKV Block Valve. RC-403. is deenergized (has NO open indication), but \\vi11 remain open \\\\;hen deenergized.
lis SPO Directs the PPO to initiate Once-Thru-Cooling Initiates Once-Thru-Cooling by the following:
Turns off both Proportional Heaters.
Places a11 Backup Heaters in Pull-To-Lock.
Opens both Atmospheric Dump Val\\.es Ensures HPSI Pumps have started.
o Recognizes C HPSI Pump did NOT start and inanually starts it.
Ensures all HPSI Injection Valves are open.
Ensures all available Charging Pumps are running.
Ensures both PORV Block Valves are open.
When C HPSI Pump has started.
opens both PORVs.
Manually actuates SIAS.
Informs US when complete.
EOP 2537 CT-1 CT-2 18
h
-1 r
G i
.C z
2 t
A
.a.
!3 L
c C /
1 c
C c :
C
'+
E c
c -
+ c -
c J c c
\\ s 4
a 3
0 r:
c 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
0 1201 ppm boron 0
0 0
0 0
0 0
0 100 % power, BOL. Equilibrium Xenon Blend ratio - 3.4: 1 SG Blowdown - 40 gpm each 24E aligned to bus 24C Terry Turbine out for bearing replacement F-16 out for filter replacement Enclosure Building Purge using Main Exhaust has been in continuous operation for several months.
Containment pressure is 2 1". Conditions have been verified as acceptable to depressurize Con t ai nni en t.
A work control staff is available to perform tasks outside of the Control Room.
Out of Service Equipment 0
0 0
The Turbine Driven Auxiliary Feed Pump is out ofservice for a bearing replacement.
Radwaste Fan, F-16 is out of service for filter replacement.
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.
Malfunctions:
All malfunctions contained in the guide are certified vp:
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 Today 05 15 PREPARED BY SHIFT Unit Supervisor /"NIGHT" Shift 18:OO - 06100 PLANT STA TUS:
AlODE: 1 RX POWER:
I 00Yo
.LlEC;,41/1:1 TTS:
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 LCO and T R M ACTlON Statements Coming Due (if more than one ACTION requirement per LCO, list each Action Requirement With one Auiiliary Feed Pump inoperable.
restore the required Auxiliary Feed Pumps 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 />.
\\t/ith 1 :iI\\,e iiiopcixhle from C-IO. perform clctioiis b. I. 1x2 Ibr lire m a s K-I and R-13.
With 1'ump:'Turbinc inoperable. liom either location. perform actinns b. 1 and b. I for fire areas K--3. R-l I. K-16. and K-17.
With the d y e closed or disconnect closed, perform actions b. I and b. I for fire areas R-1. K-2. and R-13, I'oda)
--.: I---
Equipment
'I'err! Turbine SV-4 188. AFW Stem Siippl\\ \\"al\\e f'-4 and 11-2 1 A l W Primp and rurbine (io\\ crnor Control 2-MS-202. AFW Stcain Supply \\'nlve iroin SG 2. h4OV 0-130
- 7. I. 15. item C
--I---
Action Requirement Infinite action: Establish hourly fire watch.
Infinite action: Attachment I ofOP 2301A I
LCO Action Equipment Reason TSAS 3.j2.8 a,'?
RC-200 Failed SP 2410A TRMAS 3.7.10 1
See AIL See Active Iinpaiiment List.
Action EVOLUTIONS IN PROGRESS & NOTES Thc IO minute aiwages for the Containment Rad hlonitors ha\\x been compared to the latest Chemistr!. grab 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.
1 Reference mate OP 23 14B Today b.1 and b.2 b.1 and b.2
- b. 1 and b.2 Reason
'rem?. Turhine tagged fir bearing replacement
'l'crr>* Tui-bine tagged for hearing replacement l'eir? 'I'urbine tiigged for hearing replaceinen\\
l'err? Turbine tagged for bearing replacement OD COMPENSATORY ACTIONS / Temp LOGS (Bold: Tech Specs, Italics: TRM)
I 23
Unit 2 Chemistry ON-LINE STATUS REPORT Parameter Reading Po\\! er 100 Yo Parameter Reading Flouride 0.81 m b
?'a\\.e 572 deg F Boron 1201 ppm 24 1.75 ppb Oxygen
<5 ppb Chloride
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)
- 1. Loss of the PPC
- 2. Fail Channel C Pressurizer pressure transmitter low
- 3. Degrading Condenser vacuum
- 5. Loss of RSST
- 6. Degradation of B Aux Feed Pump
- 7. Loss of Bus 24C
- 8. Failure of C HPSl Pump to automatically start 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 Abnormal Events (AE) - (2 - 4)
- 1. Loss of the PPC
- 2. Degrading Condenser vacuum Major Transients (MA) - (1 - 2)
- 1. Loss of Condenser vacuum resulting in plant trip
- 2. Loss of Bus 24C resulting in Loss of All Feedwater EOPs entered requiring substantive actions (EU) - (1 - 2)
- 2. Transition from EOP 2528 to EOP 2537 EOP Contingencies requiring substantive actions (EC) - (0-2)
- 1. Initiate Once-Thru-Cooling Critical Tasks (CT)- (2 - 3) 1, Once-Thru-Cooling must be initiated prior to reaching
- 2.
- 3.
- 4.
- 5.
- 6.
7.
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.)
Approximate Scenario Run Time: 60 to 90 min.
- 8.
- 9.
Technical Specifications exercised during the scenario.
8 2
2 1
2 Total 75 (Y/N)
Y 26
IC-90 ES04L13 Load Limit Pot Setting = 5.85 A
B C
AS1 Upper 4.68 4.65 4.66 AS1 Lower 4.85 4.72 4.76 Nuclear Power 4.66 4.988 4.80 AT Power 3.90 4.10 3.92 Tcold Cal.
4.80 4.80 4.80 D
4.63 4.74 4.85 4.07 4.90
MILLSTONE POWER STATION Approved by:
SIMULATOR EXAM GUIDE APPROVAL SHEET Assistant Manager, Unit 2 Operations (Optional)
Date I
3 / 9 / 6 Date Lesson
Title:
Revision:
0 ID Number:
ES04LI4 (Spare)
LOIT Simulator Evaluation #4 (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+$-
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.
- 2.
7
-7.
- 4.
- 5.
- 1.
- 2.
?
-3.
Exam Overviem Scenario Initial Conditions Sheet Exam Guide Exam Guide Summary STA Follow-up Questions Attachments Validation Checklists Shift Turnover Sheet Scenario Attribute Check 1 is t Page 3 of 30
EXAM OVERVIEW
Title:
ID Number:
ES04L14 (Spare)
Revision: 3 LOIT Simulator E\\.aluation #4 (Spare) 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.
Evaluate licensees in the following areas, as applicable:
1 )
- 2) 3 )
- b.
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 alarms/annunciators b) c)
Understand plant/systems response d) e)
t)
Perform control board operations Ability of each indi\\.idual to:
a) b)
Correctly diagnose events c) d)
e) t)
g)
Demonstrate a responsible attitude h)
Diagnose events/conditions based on signals/readings Comply withhse procedures and Technical Specifications Properly communicate informat iodproper cren int t'mc t i ons
- 4)
Respond and correctly interpret annunciators Properly interpret integrated system response Comply with and use Technical Specifications Comply with and use procedures Properly perform control board operations 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 mill be e\\.aluated.
Thc simulator will be initialized to IC-89 (or equivalent) at 100% power. BOI,, f31 Xe. 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 1 RMAS 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 Wti. The US should reference T.S.A.S. 3.4.6.2.b and AOP 2569, Steam Generator Tube Leak. A doun 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. C1-5 15. 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 pia. 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.
1.
hich is aligned to Facilit\\
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 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
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 of 30
_ _ _ _ ~ ~
SIh11JI A T O R EXt\\M GUIDE SCENARIO INITIAL CONDITIONS
Title:
ID Number:
ES04LI4 (Spare)
Re\\.ision:
0 LOIT Simulator Evaluation #4 (Spare)
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 E 0 S 3 68-31
Simulator --ram Guide Tttlc:
mT Simulator EI aluatioii $4 (Spnrc)
ID N ~ t i i l ~ r ESO4LI4 (Spare)
K r \\ i\\ion (1 Crew 1.i nic Walk down control boards.
CVKIO (RO)
CVRl 1 (22F)
Rack out the C Charging Pump breaker and place a yellow tag on the hand switch.
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 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.
Task Assign Expected Actions Page 10 of30 Stanclard 1
MP 14
TI Instructor Inforiiintion / Activitj, Insert a inalfunction to trip the A. RBCCW Pump.
When dispatched as the PEO (maintenance), report that there are NO obvious problems. You will continue to troubleshoot.
Task Assign Crew us SPO Expected Actions Observe the loss of the A RBCCW Pump Direct SPO to ensure B RBCCW Pump is aligned to Facility 1 and Start B RBCCW Pump.
Performs the follow i ng :
Ensures Pump B Dischargc Crosstie Valve to A Header, RBA-25 1 A. is open.
Starts B RBCCW Pump Place A RBCCW Pump hand switch in Pull-To-Lock.
acknowledges the RBCCW PlJMP B SIASILNP MANUALI-Y BLOCKED annunciator on C-06.
(maintenance) to look for any problems ivitli the breaker o r the pump.
Observes and Dispatches n PEO s t alldard hlP-I4 AOP 2564 TM 1 AE 1 AOP 2564 Page 1 1 of3O
Simulator ram Guide Notifies hlaintennnce.
Enters and exits TSAS.3.7,-3.1 0
Determines NO reportabilit!.
Enters TRh.1 7.1.20. Iteiii I I.
f'itlc:
LO1 1' Simulator Ei~duation #-I (Spare) 7, Plant Assessment.
Report:
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.
Reports:
Task Instructor Information / Activity Assign us PPO SPO
- JS Page 12 of30
Sirnulatot!
-am Guide
Title:
LOI'I' Simulator Evaluation #4 (Spare)
Task Assign PPO T i m I DA/Malf Instructor Info rni H t i on / Act i vi t v Expected Actions Observe and report loweriiig Charging flow, Pressurizer level, or LOW CHARGING FLOW annunciator.
CY22 ( 1 00%)
Ramp=200 sec.
While the crew is discussiiigibriefiiig the loss of "A" RBCCW Pump, insert a malfunction to cause a degradation of the "A" Charging Pump.
If dispatched as a PEO or maintenance, report that the "A" Charging Pump is making a loud banging noisc.
Direct the PPO to determine the cause of the lower Charging flow and to reference the appropriatc ARP.
us PPO PPO MP-14 Check Charging Ilo\\v. Ensure aid report the Charging Meadcr Isolation Valves, CH-5 18, CH-5 19, and C'H-429.
are open.
---1 i\\RP 259OB-057 Determines and reports Pressurizer level is lowering slowly.
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' I
2590B-057 1 Tech Specs TRbl I
Page 13 of30
Sirnulato! -yarn Guide Reiisioii
Title:
LOIT Simulator Evaluation 84 (Spare)
ID Number ES04LI4 (Sparel Instructor Information / Activity IDAiMalf Task Assign RPO 1 F ( 100%)
Ramp=250 sec.
While the crew is discussing/briefing the loss of the A Charging Pump, insert a malfunction to cause Loop 1B Cold Leg Transmitter, TE-l12CB, to become noisy.
Delete RPOlF PPO Report as I&C. Inform the crew that you will troubleshoot the problem.
As I&C report that the transmitter Weidmuller pin was a little corroded. Pin has been fixed.
us PPO PPO PPO us Expected Actions Observe and report the following annunciator as they alarm:
RX POWER AT CH DEVIATION RPSPRETRIP TM-LP TRIP CH B PRESSURIZER CH B mwr SETPOINT HULO Computer Alarm, LOOP 1B Cold Leg Temp Lo Directs the PPO to reference the appropriate ARP. Informs I&C.
Observe Channel B pressurizer pressure indication and compare to other channels. Report observations.
Observe Th and Tc instruments.
Report Channel B Tc is noisy.
With concurrence of the US, bypasses Channel B WS TMLP, High Power, and LPD trips.
Enter TSAS 3.3.1.1. Action 2.
Request I&C to isolate and repair transmitter.
0 -
Standard MP-14 TM 3 AE 3 MP-14 ARP-259OC-022 ARP-259OC-022 ARP 2590B-022 ARP Tech Specs 2590B-022 Page 14 of 30
Simulator
'am Guide Time T.,
Title:
LOI'I' Simulator Evaluation +4 (Spare)
IDA/Malf SGOl B(5O)
Ramp=200 sec.
t Instructor Information / Activity Insert a malfunction which will cause a SIG Tube Leak of - 5 gpm.
ID Number ES04LI;I (Spare)
K c i ision Task Assign Crew SPO us IJS SM Expected Actions Identify the loss of' RCS inventory and determine that the leakage is Si(; tube leakage within the capacity of the available Charging Pumps.
Observe N-6 and SJAE radiation monitors for increasing counts. Note rising counts on #2 S/G N-16 rad monitor.
Determine that the leakage is S/G tube leakage within the capacity of the available Charging Pumps.
Direct entry into AOP 2569, Steam Generator Tube Leak.
Direct Chemistry to sample both S/Gs for boron and activity.
Refer to Tech Spec 3.4.6.2~ and identify that the Unit must come off line.
Refer to RAC 14 and classify this event 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.
0 -
Stanctard
~
TM-4 AE-1
~-
AOP 2569 Tech Specs KAC 14
~
Page 15 of 30
Sirnulatoy - xim Guide Task Assieii us PPO i<e\\.ision 0 I'itle:
LO1 I' Simulator Evaluation d4 (Slim)
ID Number ES04LI4 (Spare)
Expected Actions Brief the PPO and SPO of the required down power, the rate, and the method of reactivity addition. Should include caution regarding reduced MIU capability.
Commence boration to the suction of the Charging Pumps.
I---
~
SPO 1
If necessary. insert CEAs to maintain ASI.
As Rx power is reduced, lower turbine load.
Instructor In for inat i o n i Act i v i tv IIie down power rate should be 50°/o per hour or greater. 1 he Boration source should be the on service BAST.
?.
h Page 16 of30
Simulator
-am Guide
Title:
I,OIT Simulator E\\ nluation #4 (Spare)
SCi0213( 15)
After the downpower is initiated, increase the severity of thc S/G Tube Leak to - 450 gpm.
1 I
I Crew us PPO SPO JS After the Main Steam Line Radiation Monitor alarm identify that the S/G Tube Leakage has increased.
Direct that the reactor be tripped and EOP 2525 be commenced when:
MSL RM alarms and is confirmed OR Primary to secondary leakage exceeds the Chg Pp capacity.
Report:
Reactor tripped All CEAs fully inserted Power going down Report:
Turbine tripped All steam admission valves are closed Generator Megawatts are zero 8T and 9T are opened 1
2ommence query of both control board lperators to identify the status of the
)lant TIM-6 I
MA-1 AOP 2569 EOP 2525 7i Page 17 of 30
Time Instructor Information / Activity Simulator
'am Guide Ti tlc:
LOIT Simulator Evaluation d-l (Spare)
ID Niiniber ES041-I4 (Spare)
Re1 ision Task Assign PPO ID A/Mal:
PPO will norinally manually initiate SIAS at I800 psia. Manual initiation of SIAS is NOT required.
US SPO PPO us Expected Actions Report:
Pressurizer level < 20% and going down Pressurizer pressure < 1900 psia
~
-~
Direct the PPO to manually actuate SIAS at some RCS pressure > 1714 psia.
Report: At least 1 S/G level being returned to 40-70% 011 Main Feed Report:
CTMT conditions normal Rad Monitors NORMAL with the following exceptions:
- SJAE
- S/G BloMido\\+rn
- 2 S/G MS Rad Monitor
- 2N-16 Query the control operators to identify the status of performance and verification of the subsequent actions of EOP 2525.
0 5: tandard Page 18 of 30
Simulator -yam Guide
Title:
LOIT Simulator Evaluation #4 (Spare)
ID Number ES04LI4 (Sparc)
Re 1-i si o 11 IDA/Malf Instructor Information / Activity The C HPSI will trip when RCS Pressure <1450 psia. The timing of the pump trip depends on the action of the crew and, therefore, may happen before or after this point.
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 HPSI pump breaker has tripped, but it is NOT evident \\vhy the trip occurred.
As electrical Maintenance, report that you will investigate the problem with the C HPSI pump breaker. (If requested, CANNOT determine the problem with the A HPSI Pump).
Tasl<
Assign us us PPO Expected Actions Direct the PPO to place C HPSI in PTL, enable and start B HPSI, assuming the B HPSI was NOT started to replace the loss of the A HPSI.
Direct the Turbine Building PEO to check out IC HPSI pump breaker, A403.
Request Maintenance to check the C HPSI breaker (and possibly the A HPSJ Pump).
Report SIAS has been inanually actuated, some components failed to actuate.
A and C (or B and D) RC,Ps are secured.
0 -
I I
Standard
~~
OP 2260 Page 19 of 30
Simulator -Yam Guide
Title:
LOIT Siniiilator E\\.aluntion #4 (Spare)
IDA/klalf Instructor Inforination / Activity S/G isolation may be successfully completed when the RCS has been cooled down to < 5 15°F per EOP 2534.
SGTR-7: Perform a plant cooldown to a Th of -=
515OF.
SGTR-9: Secure RCPs within 5 minutes of exceeding NPSH limit.
ID Number ES04LI4 (Spare)
Revision Task Ass i ~n us us Crew
~ - _ _
Expected Actions Uses the diagnostic flow chart to 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.
Classifies the cvent os un A l e i d ~ ' 1 Enters EOP 2534 and directs that EOP 2534 SFSCs be completed every 15 min Refers to EOP 2534 and directs that Chemistry sample both S/Gs for boron and activity.
Directs the SPO to cooldown the RCS 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.
Monitor RCP NPSH and secure RCPs if inadequate.
s t a11 dar d EOP 2525 EOP 2525 EOP 2534 EU-1 CT-1 EOP 2534 CT-2 Page 20 of30
Simulator --ram Guide I.
I ask Assigii SP 0 Crew us us
~-
T i m
I I
I Expected Actions Standard I
I Commence cooling down the RCS using BOTH S/Gs at a MAXIMUM and CONTROLLABLE rate dumping steam to the condenser.
Identify the degraded A HPSI pump when flow degrades to 0 gpm.
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.
Direct the Aux Building PEO to check out A HPSI pump.
L Titlc:
ILOIT Simulator E\\duatinn #-I (S1m-e)
Instructor Information / ActiLSity This inalfunction may be observed earlier.
As Aux Building PEO: Nothing apparent.
SGTR-6: Start the B HPSI Pump within 15 minutes of NOT satisfying the SI Flow Curve (OPTIONAL).
This critical task is critical onJ 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).
ID Number ES04LI4 (Spare)
Re\\isinn 0 us Notify the US when RCS TH 5 15°F.
SPO Page 21 of.30
Simulator -yam Guide Time Pitle:
LO1 I Simulator Evaluation 4 (Spare)
IDA/Malf MS02B (2%)
Ramp=20 sec.
Instructor Information / Activity SGTR-5: Isolate the affected S/G is isolated in accordance with EOP 2534 within 60 minutes of the Reactor trip.
Actuate an Excess Steam Demand in the Enclosure Building after the #2 SG has been isolated.
Task Assign us Crew us SM SA4 Expected Actions Direct the SPO to isolate the #2 S/G per EOP 2534.
Identify the abnormal SG and RCS response.
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.
Concurs with the entry into EOP 2540.
Selects EOP 2540 on SPDS and directs that EOP 2540 SFSCs be 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.
Concurs with entry into EOP 2.740 C1ussijie.s the event us un SA E/(?
Standard CT-4 TM-6 MA-2 EM-4 EOP 25-34 EU-2 Page 22 of 30
T c T E
v
+
2 z rJ c 0
w rl, I
w j
0 c c;
- r,
Simulatq -yam Guide Instructor Information I Activity Time Task Assign us When directed Enters EOP 2540D to verify recoI.er!.
of RCS Heat Removal.
Direct the SPO to isolate #2 S/G per EOP 2540D Direct Maintenance or Aux Building PEO to close and lock the disconnect for 2-MS-202, to isolate the Terry Turbine from #2 SIG.
T'itle:
LOIT Simulator E\\.aluation ft3 (Spare)
ID Number ES04LI.C (Spare)
Rei.ision 0 EC-2 EOP 2540D ID A/Mal f May already be accomplished in previous EOP.
Unlock, Close and Lock the disconnect for 2-MS-202. Set MSR13 to rack in (RT) and report that the disconnect for 2 MS-202 is closed and locked.
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).
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.
us US us temperature by using # 1 S/G ADV per EOP 2540D when the RCS cooldown begins to slow down.
Expected Actions Page 24 of 30
EXAM wrx;
SUMMARY
Title:
LOIT Simulator E\\ nluation #.I (Spare)
ID Number:
ES04L14 (Spare)
Revision:
I>
- 1.
Critical Tasks CT-1 SGTR-7: Perform a plant cooldown to a Th 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 of30
SIhlllLATOK EXAM GUIDE V A1,IDATION CHECKLIST l i t 1 e :
ID Number:
ES04LI4 (Spare)
Revision:
4 LOIT Simulator Evaluation #4 (Spare)
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 SlP~ll~l,.l IOR TRAINING DATE-TIM E SHIFT TURNOVER REPORT PREPARED BY SHIFT Date Toda?
I l-oda\\, 05 I 5 Time LCO Action Action Requirement Equipment Reason 0600 TRM 7.1.1, a
With P18C inoperable from C-10, ensure C Charging Seal replacement.
Table 7.1.1-1, Itern C P18B is operable from C-10 or perform 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.
Pump 1
Unit Supervisor /NIGHT Shifi I
Action Requirement Infinite action: Establish hourly fire watch.
1S:OO - 06:OO LCO Action Equipment Reason TRMAS 3.7.10 1
See AIL See Active Impairment List.
Inspection of plant systems for leakage due to seismic event.
Contiuuoos TS LCO and T R M ACTION Statements in effect (if more than one ACTION requirement per LCO, list each sena ra telv)
Today OD COMPENSATORY ACTIONS / T e m p LOGS (Bold: Tech Specs, Italics: TRM) 1 i
Unit 2 Chemistry ON-LINE STATUS REPORT REACTOR COOLANT Parameter Reading Po\\\\ et-100 Yo Pn\\.c 572 degF Time 0625 Parameter Reading Fluoride 0.81 ppb 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.IT24TIVE ATTRIBUTES Y
Y
- 2.
The scenario consists mostly of related events.
Y
- 3.
Each event description consists of:
- 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.
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.
Y
- 5.
Y
- 6.
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.
The events are valid with regard to physics and thermodynamics.
SequencingAiming of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.
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.
Y
- 7.
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)
I. Trip of the A RBCCW Pump
- 2. Degradation of the A Charging Pump
- 3. Loop 1 B 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)
- 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)
- 1. Trip of the A RBCCW Pump
- 2. Degradation of the A Charging Pump
- 3. Loop 1 B 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 9
4 4
Attach men t Guide No.: ES04L12 SCENARIO ATTRIBUTES CHECKLIST
- 6.
EOP Contingencies requiring substantive actions (EC) - (0-2)
- 1. Enter EOP 2540E, Containment Integrity
- 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.
- 7.
- 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
AS1 Upper 4.67 AS1 Lower 4.86 Nuclear Power 4.65 AT Power 3.92 Tcold Cat.
4.71 B
4.64 4.75 4.78 4.10 4.70 D
C 4.67 4.67 4.83 4.82 4.68 4.66 3.92 4.03 4.870 4.72