ML051400292

Draft - Section C Operating (Folder 2)

ML051400292
Person / Time
Site:	Millstone
Issue date:	01/26/2005
From:	Wilson M Dominion Nuclear Connecticut
To:	D'Antonio J Operations Branch I
Conte R
References
Download: ML051400292 (91)

Text

A m Millstone Station c.

P-.

t Unit 2 Operator Training SIMULATOR EXERCISE GUIDE I.

I itle:

LOIT Simulator E\\aluation # I ID Number:

ES04LI 1 Revision:

0

11.

Initiated :

Deyeloper Date I\\!.

Approved:

Reviewer Date Operator Trainin&upervisor Date 1

I itle:

Simulator Evaluation

11) Number:

ES04LI 1 Re\\ ision:

0

.~

~

TABLE 01-CONTENTS SECTIONS LISTED IN ORDER:

I.

Co\\w Page 3

Table of Contents Exercise Overview

4.

Instructor Guide / Summary

-7 Scenario lnitial Conditions

?

Attachments 0

Validation Checklist 0

Training Turno\\~er Sheet EXERCISE OVERVIEW 1.

Purpose:

I. Evaluate the licensees' ability. as a team and individually, to safel). and responsibly operate the plant during normal plant operations, abnormal operating conditions and emergency operating conditions.

b.

Evaluate licensees in the follotving areas. as applicable:

1)

2) 3 )

Ability of the crew to perform crewdependent (and time-critical) tasks.

Ability of indi\\iduals to perform critical tasks.

Ability of the crew to:

a)

Understandhterpret alarms/annunciators b) c)

Understand plant/systeins response d) e)

f, Perform control board operations Ability of each individual to:

Diagnose e\\.ents/condi tions based on signals/readings Comply \\vith/use procedures and Technical Specifications Properly conimunicate informatiordproper crew interactions

4)

Iitlc:

Simulator Evaluation

11) Niumbe~-: ESO-CI-11 Revision :

0 a) b)

Correctly diagnose e) ents c) d)

e) f)

g )

Demonstrate a responsible attitude

11)

Respond and correctl! interpret annunciators Properl). interpret integrated system response Comply with and use Technical Specifications Comply with and use procedures Properly perform control board operations Properlj. communicate information and interact \\\\ it17 the rest of the crew 3

Exercise Brief I.

The simulator \\\\ill be prepared for the e\\aluation and the licensees \\+ill be briefed on the conduct ofthe evaluation and the areas in ohich they nil1 be evaluated.

The sj~nulator \\\\ill be initialized in Mode I. NOP/NOT, EOL. Equilibrium Xe, 35 ppm boron, 2 2 protected and 24E tied to 24D.

Four hours prior to taking the shift. an minor earth quake < 0.09g ZIA \\+as felt and \\verified by the USGS Earthquake Information Center.

All actions for the AOP 2562, Earth Quake have been performed. A CTh4T entry is being discussed b!.

management. The decision has not been made.

Unit 3 declared an UE/DI. The event is 110\\v terminated.

SP-265413 Forcing Sprays is scheduled for the beginning of shift.

No equipment out of service.

7

-7.

Scenario Suminarq :

Shortl!. after taking the shift, the creik u ill experience the following:

Force sprays per chemistrys recommendation to equalize boron in the pressurizer.

Loss of C SW Pp. requiring the B SW Pp. be started on 22.

Failure of 6A Heater High Level Dump valve requiring the iral\\ e placed in manual and controlled from the Foxboro screen.

The Pzr Safety RC-200 ~ 4 1 1 de\\.elop a leak. This will puts the cren into TSAS 3.4.6.2.d RCS Leakage. The US ma!. have engineering evaluate the operability of the Safety to determine if TSAS 3.4.2 Safeties Valves, needs to be entered.

3

I itlc:

Sirnulator Evaluation Ill Numhcr:

ESO4LIl The crew commences a Rapid Iloivnpo\\ver per AOP 2575 and AOI 2565 RCS Leakage.

During the Rapid Donnpoiber. the SAFETY degrades forcing the crest7 to trip.

EOP 2525 will be folloned b! EOP 2532 LOCA.

The crem will start the cooldonin in EOP 2532.

Nhile in EOP 2532, the,4 CAR Fan n i l 1 experience high \\librations requiring it to be tripped.

During the cooldoLvn in EOP 2532. a SGTR occurs in # I S/G. forcing the crew into EOP 2540.

The creiv will select success path CI-1 and transition to EOP 2540E.

I he scenario can be terminated when the A CAR is secured and the crew has successfully isolated the # I S/G.

4.

IlantlSiniulator differences that maj. affect the scenario are:

None LI u rat ion :

2.O hours

. \\ I I Control Room Conduct, Operations and Communications shall be in accordance with Master il lanual I4 (MP-14). Review the Simulator Operating Limits (design limits of plant) and Simulator hiodeling 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

Sl-_C?ION 4 ID N ~ ~ i i b ~ : r ES04L1 1 Re\\.isioii: 0 Task IDA/blalf 1 n s tr uc tor In forma ti o n / Act i 1.i t y i\\ ss i gn Expected Actions s t anclurd

~..

11111e I

equivalent Utilizing an open room, 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 ppm boron / Blend ratio - 165 PMW/l BA SG Blowdown - -25 gpni 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 = 6.85, SGBD = 25/25, EB Purge I

liang the 22 Protected Sign Shift the Xties for RBCCW, SW and HPSI

- Close SI-41 1 & 655, Open SI 412 & 653 (C-

- Close RB 2 1 1 C. Open RB 2 1 1 D iC-06)

01)

IN S-r INST INST INST 5

SEC IION 4 ID Number ESO4L11 Rc\\kion:

Task Time IDAh~l~il1 Instructor Iiiformation :lcti\\ it!

Assign Ex pec t ed i\\C t I on s s t and mi PPO T1 Annunciator PZR PRESS DEVIATION Illforins the LJS this is an expected EDR 14 (RO)

EDR1.5 (RI)

SWR22 (22F)

CVRll (22F)

RC-27

- Close SW 97A. Open SW 97B (C-06)

BKR 24E from 24C (A30.5)

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 RCOjE Ensure BKR A408 24E to 24D is closed.

Reset the RCS Leak Rate.

If the crew is delaying forcing sprays, call as Jim Kunze and prompt the crew to start.

us PPO PPO US directs the PPO to coininence forcing sprays.

Crew inay have a short briefing SP 2654B is approId for imp 1 c iii entat i oil.

Backup Heaters are placed to CLOSE PIC-1OOY setpoint is lowered

- 50% output

- HIC-I IOE/F controller start to rise.

PA-Press ad.justed to - 2250 psia SP-2654B ARP 259OB (C06iD3 7) 6

SECll0N -I IT1 Number ESO4LI 1 Rei.ision: 0 Task Time I DA/P\\/Idf Instructor Inhl-niation lZcti\\ it!

Ass i gn Expect c cl Act i oiis s ti\\ndard T2 sw-01C Trip of C SW Pump After crew completes 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 S W Pp.

Wait for the US to direct his actions per AOP-2565 Loss of SW.

While one attempt to restart the C SW Pp. is allowed by GDL 600, the IJS should not direct a restart for the following reasons:

Annunciator (C-06.BA4) indicates a faulted SPO alarm for Forcing Sprays.

The ARP does not have to opened or implemented.

Reports the C SW Pp tripped and Annunciator. S W PUMP C OVERLOAD/TRIP (C-06. B.44)

Uith US direction. reset the C SW Pp and attempt one restart.

01 With US permission, starts the B SW Pp and aligns it to the B S W HDR.

AE-1 TM-1 G DL-600 GDL-200 AKI 7

SECTION 4 ID Number ES04T.I I Revision: 0 Task S tandnrd Instructor Information / Activity Assign Expected Actions Tiiiic IDA/h4alf pump motor.

The "B" SW Pp. is available to replace the "C" 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 implementation.

sw Pp.

I Response to Annunciator C-06 BA-4, "SW PUMP C OVERLOADITRIP".

Entry into AOP 2565 "Loss of SW" IJS SPO 1

~

Enters the ARP, o r 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, with 0 amps.

Low flow on coinponents served by header.

If alarm is valid. Go To AOP 2565.

"Loss of SW" Refer to OP 2326A, "SW System" and perform actions to place "B" SW pump in scrvice on Fac. 2.

=106/BA4 4OP-2565 4RP 259OE 4RP 259OE 4RP 2590E

US should not direct an attempt to restart the 'C' sw Pp I US enters Section 6.0 of AOP 2565.

I lJ S us lis SPO IJ S/SPO IJS SPO Determines that Annunciator (C-O6/BA4)

"SW PUMP C OVERLOAD/TRIP" is lit.

If lit, do not restart the "C" SW Pp.

Directs the SPO to start the 'B' S W Pp.

Directs tlie SPO froin Section 6 of AOP 2565.

Place the "C"' SW Pp. in "PTL" Ensure S W-O7A, "Discharge Xtie" Closed Ensure SW-9713 "Discharge Xtie" Open.

Start tlie 'B' SW Pp.

Check Ann. (C06/A19A) "SW Pp. 'B' SIAS/LNP Start Manually Blocked" lit.

Direct a PEO to place tlie "SIAS/LNP Actuation Signal I IS 0484A" in N( >RhlAL..

Directs a I'EO to Stop Sodium H>rpochloritc to the "C" SW Pp.

Monitors

'B' SW Header Flo\\i Pump Pressure Motor Amps AOP 2565 AOP 2565 AOP 2565

SECTTOK 4 ID Nuinbcr !304L.I 1 Kci ision: 0 1 ask X s s i g n E s pc c te cl Actions Standard I'inic IDAlh4all' Instructor In fil rm a ti o n / Act i \\, i t 4 4s PEO, I I nit j litin then re1m.i 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 satisfactory.

Strainer D/P cell is vented and satisfactor!,.

sw Pp.

A s Electricul Maintenance nnd PEO ii'iiit 10 niin

[hen report Breaker A407 IS tripped and has one dropped flag.

Looks like the breaker opened on O i w Current.

l f uskcd, report it will tirke hoiti.) to deternzirze if und ivhere the fuiili is LJ S knds. or directs Work Control to send a

'EO to check the 'C' SW Pp. brealter A407 to check the 'C' SW Pp.

Directs Work Control to contact maintenance to assist in determining the condition of the 'C' S W Pp.

1,o.g~ into LCO 3.7.4.1 "SW SYSTEM" anc

\\OP 2565 AOP 2565 10

SECTION 4

11) N ~iiiibcr ESO-ILI 1 Re\\ ision: 11 I a 5 k Timc IDA/MalJ Iii st ruct or In fomiat i 011 I Ac ti1.i ty Ass ig i i Expected :\\ctions s tanclard B SW Pp wont 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 System.

ARP-2590E (C06/7, AA 19)

Wait 5 min. and insert the remote. SIAS/LNP Actuation Signal HS 6484A in NORMAL.

Call the CR and report switch in NORMAL.

Section 7 evaluates key plant parameters to ensure there are no other pi-oblems.

The LJS may direct the PPO or SPO to cniiiplete Section 7 and ad\\-ise for any parameters not in the normal range.

us INST Inst.

ITS IRM 7.1.2 1 APPEN R SW SYSTEM Directs a PEO to place thc SIAS ILNP Start Signal HS 6484.A to NORMAL Logs out of LCO 3.7.4.1 and IRM 7.1.2 1 11

Instructor Information Actil it\\'

Assign E s pe c t ed Actio 11s Standard 1 h e

IDA/h lalf I

I I

T3 Heater 6A Level Hi iinnunciator FW 38B @0%

Fail FW Heater 6A level transmitter (LT5043A)

Inst.

AE-2 180 sec ramp fails downscale.

TM-2 Actual level in the heater rises to - 20 inches due to the "averaged" level lowering.

If necessary, modify the FW 38B to ensure level does not reach 34 inches. Use the PPC to monitor the actual heater level.

Inst Heater 6A level stabilized at -- 20" during the validation with no ad.justmcnt to the mal fuiic ti on.

US can direct the SPO to iinplement the ARP or direct the steps himself.

US Responds to alarm C05. BA-20, "HEATER 6A LEVEL HI" ARP 2590D. BA-

20.

"HEATER 6A LEVEI.

111" SPO Displays "Heaters 4Ai5AlbA" screen on ARP 259OD IJS Directs a PEO to check

[IRP 25C)OD the Foxboro displaq.

local l e ~ e l gauge.

Valve lineup Controller malfunction and air connection.

12

SE(ITI0N 1

11) Nulml~el-ESO4Lll Rc\\.ision: 12

'I-. 1.

J S \\

Time 1 D AIh'Lall' Instructor In timiat i o n 1 Activity

Issign Expcctecl,,IC tions Sta11dard The actual heater level should stabilize at - 20 ".

no reason to trip the plant.

A s PEO Iixiit 3 minutes rind report.

All air lines are intact.

Heater 6A siteglass reads. - 20 inches Display the Feedwater heater level on the PPC.

and report the level of the good transmitter.

The crew may opt to place the High and Norinal Level Dump \\dyes into manual before bypassing L?' 5043A to preclude another Feedwater heater transient caused by suddenly bypassing the faulted transmitter.

This is supported by GDL 600 step 2.2 "Manual Operation of Controllers".

If the crew follows the ARP and does not go to manual first. the resultant transient will not trip the ITS Inst SPO SPO If Foxboro indications roaches 34 inches or local level gage exceeds 34 inches Trip the Rx. Trip turbine, Close both MSIVS.

Stop all condensate pumps and perform EO P2 5 2 5.

If one transmitter does not agree with the other transmitter and sight glass, Bypass the faulty transmitter on the Foxboro display.

SPO selects and bypasses "LT SOJ3A".

If the SPO does not placc the \\ al\\.cs in in anu a 1.

614 Heater and 5.4 Heater Hi and Low level annunciators will alarm 011 C-05.

The heater levels will stabilize within minutes.

ARP 3590D ARP 2590D 13

RCOSA @

1.O% (300 sec)

RCOSA (De 1 ete)

~~

~~

KC-200 Pzr Safety Leakage RC-200 leakage Pzr Press will lower to - 2240 psia and stabilize.

Note: The Acoustic Vlv Monitor (AVMS) for RC-200 is inop, as indicated on the turnover sheet.

Annunciator C02/3 A-1 1, AVMS Alarm The US may refer to this ARP knowing it will not energize.

would be required if the AVMS were operating properly.

Delete RCOSA when both annunciators C-03 A42

& C42 alarm Pzr Safety Valve RC200 Dis Temp Hi and Pzr Relief Valve Dis Temp Hi.

Insert RCOjA periodically to simulate an intermittently 1 i ft i ng relief va1x.e.

The goal is to get the crew to start a down power without getting any Quench Tank Annunciators (CO3, A36/B36/C36). These annunciators direct the operators to trip the plant which would bypass h of this guide and eliminate actions that the operators must be evaluated on.

AE-3 TM-3 15

SE('TI0N 4 ID Number ES04Ll1 Rc\\ ision: I!

Tad, Time ILIA/Malf Instructor Iiiforniation / i-lcti\\.itj.

\\.ssi gn Expectcd /2clicms Srnlldnrd If the crew calls the OMOC or Kunze, direct the crew to start a plant shutdown at a rapid controlled rate.

I After 15 minutes, the PPC leak rate should be -

1 Igpm.

PPO Report Annunciator "Pzr Safety Valve ARP 2590B CO2/3, A42 Disch Temp Hi.

PPO Monitor for ARP 25WB RC200 Dis Temp Hi" is alarniing.

Quench Tank Pressure, Temp. and Level.

Safety Tail Pipe Temp. TI-1 07.

Report Tail pipe temp rising.

US Monitor RCS Leak Rate ARP 2590B Leak rate should be rising.

ARP 259OB The US many not enter the TS 3.4.2. It is not clear that the RC-200 is inop. It niay still lift at 2500#.

US may call for an engineering evaluation.

The PPO should monitor the AVMS and determine they do not indicate RC-402. 404 (PORVs) or RC-201 (Safety) are leaking.

US Refer to 13 3.4.2 "Safety Valves" PPO I -

By the process of elimination, the oiily relief' 1

16 If leaking PORV is possible. c>de each Block Valve and monitor AVMS and Tail Pipe temperatures.

ARP 259OB

SECI ON 4 ID Numbcr ES04LI 1 Kci-isinn: Q Tad<

Time 1 D A/ b l al f Instructor Information 1,.\\cti\\ it)

.A s si g n k x p e c IC d Actio 11 s standard that could cause rising Quench fank pararncters and Tail Pipe temperatures is RC-200.

Response to Annunciators C-03, A36 QT Hi/Lo 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.

NOTE 2: If the crew inipleinents the above ARPs.

there is guidance to trip the plant.

If the crew orders the reactor tripped, insert T-5 (RCO5A @, 20%, 300 sec)

OP 2301A PDT and QT Operation NOTE 1 : The crew may usc OP 330 1 A to reduce 01 Level, Pressure and Temperature. This is not required if they are in AOP-2568 RCS Leak.

No need to cycle Block Valves.

us/

CREW 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 car1-j out EOP 17

xc-r ION 4 lime IDA/Malf Instructor Inforiliatioil,' i\\cti\\ it)

is s i gn Expected 1 1 c t i o 11 s s tan d ;u.d LL) Nuniber E,S041,I 1 Re\\ 151on: 0 I ask NOTE 2: If the crew uses OP 2301A. they may use one or both of the following sections:

4.1 Recirc and Cooling the QT and PDT 4.5 Emptying QT The US will direct the PPO to implement OP 2301A.

Enter AOP-2568 "RCS Leak" 1

I PPO PPO Verify closed LRR-64.1/54.1, Open LRR-57.1/62.1 "QT "PDT/QT Recirc-Cool" vlvs Recire/C Ig" ~ l v s Verify open RB-340..'QT/PDT Hx RBCCW Out" vlvs.

Open RC-401 "QT Drain" If PDT pressure is higher than QT pressure:

Verify closed, GR-1 1.1 and GR-1 1.2 "PDT Disch Isolations".

01~11 LRR-47.1 "PDT Vent" OPEN RC-400.'Q~l' Velit" OP-230 1 A step 4. I OP-230 I A step 4.5 18

SECTION 4 ID Number kSO4LI 1 Kei,i.sion: 0 I ask Time IDA/hlalf Instructor Inforination / ActiL it!

Ass i gn Expected Actions Standard 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.O within the required range with the possible exception of:

Pzr Level Pzr Pressure l h e PPO/SPO may need to report lo\\\\, Pzr Level and ensure niax charging and min. 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 US will iinpleinent Section 4.0.

us US/PPO US/PPO Directs entry into AOP 2568 and performs P 1 ant Assessment.

If Pzr Lvl is not 35 to 70%

Manually operate Charging and If Pzr Press not 2225 to 2300#

Ensure Spray Vlvs closed.

Letdown.

Place all BU Heaters to "ON".

AOP 2568.

Sec. 3.0 AOP 2568 Step. 3.2 AOP 2568 Step. 3.3 AOP 2568.

Sect. 4.0 19

SEC-rIoN 4

11) Number ES04LII ReLrision: Q Task Iimc ILlA/h~lalf Instructor Information /

it!

Ass i g ii E s pe c ted Actions Standard The US may have previously done an RCS Leak Kate.

If leakage is :225 gpin.

SM must classify Unusual Event / DI per BU2 Identified Leakage 25 gpm.

~~

The US may personally implement, or handoff, Section 5.0.

If requested. report no activity in RBCCU and no leakage in Aux. Rldg. After a niininiuni of 20 minutes for a \\risual inspection. (Time may be adjusted if multiple personnel are assigned to the inspection)

Enter AOP 2575 Rapid Downpower US/PPO us I Crew Shl US/SPO If RCS leakage exceeds aidable charging capability. TRIP the Rx. and Go To EOP 2525.

The leak rate is not charging capacity.

No need to trip at this time.

Initiates Leak Rate Determination.

lJS should determine leak rate 2 10 gpm identified leakage.

Classify per FAP06 Log into LCO 3.4.6.2 Refer to AOP 2575 and start a Rapid Downpower UE/Dl per BU2 if leakage 125 gpni.

Implenient Section 5 to ensure no other leaks.

Crew attempts to idcntifj. leak location by performing applicable steps of AOP 2568.

May direct chemistry sample RRCCU Sj stem or have PEO obscrve CVCS piping in Aus. Bldg.

AOP 2 5 6 8, Step 4.1 AOP 2568, Step 4.4 FA P 06 AOP 2568 Section 5 20

SECTIOhi 4 I D Nm117er ESO4L.I 1 Re\\.ision: 0 l-asl;

'1. i in e I DAlhiIal f Instructor Information 1 ActiiitJ-Ass i g n E s pc c t e d i 1 c t i c) II s Slandarcl Due to the low pressure condition. the B/U Heaters should already be on and the spray vlvs shut.

SM us SM SM IJS IJSIPPO 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.

Make the following notifications CONVEX and IS0 Health Physica OMOC Unit 3 IF parameters associated lvitli automatic reactor or turbine trips are challenged, manually TRIP reactor and Go 'To EOP 2525. "Standard Post Trip Actions."

Trip criteria should not be challenged.

Initiate forcing sprq's.

- This step ha\\ e dread!. been completed..

AOP 2568.

AOP 2575 AOP 2575 Step 3.4-7 AOP 2575 Step 3.8 21

C c

I/;

3 e

c) a a

c 0

c I

I

SECTION 4 IT) Number l~,SO41.11 Re\\-ision: 0 Task Time LL)i\\/r\\Ialf Instructor 1 11 for ni a t i on ' Act i 11 it 1-Assign Eslxcted Actions s t nndasd T5 RCOSA @ 20%

(300 sec)

The PPO must determine the neutral blend ratio and add the gpm. of Boric Acid that corresponds to the YO power reduction, as specified on Table-2.

The neutral blend should be listed on the turnover sheet.

When thc crew has established a controlled downpower, to approximately 95%, or if they trip, increase the Safety leak forcing them to trip.

RC 200 Leaking Pzr Safety Rx Trip EOP-2525 PPO US/PPO WST Borates to charging pump suction:

ADJUST setpoint of"BOK1C ACID FLOW" controller, "FC-2 1 OY," to flowrate determined in step 3.14.

OPEN "RWST TO CMG SUCT, CH-504."

PLACE "MAKEUP MODE SEI,"

switch in "MANUAL."

START a boric acid pump. and CIIECK boric acid pump discharge pressure greater than 98 psig.

OPEN "VCT MAKE1 Jl' BYPASS, CIH-196.

IF required, "VCT Lvl" dropping, Refer To "Heavy Blend to Maintain VCT Level," to make-up to the VCT.

AOP 2575 Step 5.12 MA-1 TM-4 23

SECTION 4 ID Numbci-ESO4I.I 1 Re\\ ision: 0 Task s t Inclarcl Time ID A/bl a1 f Instructor Information,2cti\\ritj Ass i gn 1: spec t c il IC t i o 11 s Note: US will pose questions regarding these aspects of each safety function. PPO and SPO responses critical to proper diagnosis and key actions are Bold in the following sections.

Crew US Ideiitifjr rapidly rising RCS leakage.

May initiate a manual trip if quick enough. Respond to trip TAW EOP 2525.

Query PPO and SPO on the status of Safety Functions as delineated in EOP 2525:

Reactivity Control (PPO)

Reactor Maintenance of Vital Auxiliaries (SPO)

Turbine Electrical buscs SW&RBCCW RCS Inventory Control (PPO)

Pzr le\\.el & Subcooled margin (SCRI).

value & trend If Pzr Lvl is not 20 to 80%, the PPO should

- manually operate charging and letdown to compensate for Pzr Lvl.

EOI 2535 24

SECTION 4 ID Number ES04LIl Rc\\.ision: 0 I'ask Timc IDA/hlal f Instruct or I n f b rnia t i o 11 / Act ivi t 1-Ass i g 11 Ex 1x2 c te d Act i o 11 s s t 311 da rcl US/PPO should initiate SIAS. CIAS & EBFAS at approximately 1800 psia.

CT-1 Trip 2 RCPs (LOCA-13)

CT-2 Sccure all RCP within 5 min. of loss of NPSH. (2260 3.1.1)

RCS Pressure Control (PPO)

If Pzr. Press < 1714 psia

- ensure SIAS, CIAS, EBFAS &

- secure one RCP per loop

- secure all RCPs if < NPSH

- ensure PORVs closed, if open, CKAC close the Block Vlv.

Core Heat Removal (PPO)

RCP status Loop delta-T Th SCM RCS Heat Removal (SPO)

SG pressures 880-920#

RCS Tc 530-535 O F SG levels, value & trend RCSSCPvl Containinelit (CTMT) Isolation (PPO)

Radinoiiitors inside CTMT in alarm and rising. (R7891 Refuel Floor) outside CTMT, steam plant, not in alarm or rising.

CTMT pressure >1# and rising.

If CTMT Press 2 4.42 psig.

(1 1'- 2 2 6 0 CT-1 CT-2 25

IJ S SPO PPO

~~

- Initiate SIAS, CIAS, EBFS, CR4C Sr MSI CUvlT Temperature & Pressure Control (PPO)

CTMT temperature > 120" F CTMT pressure >I# and rising.

- Ensure at least 2 CARS with RBCCW If CTMT Press > 9.48 pig,

- Ensure CSAS actuated.

- All CS Pps. > 1300 gprn.

CTMT Combustible Gas Control (PPO)

CTMT temperature > 120' F CTMT pressure >1# 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 EOP 2525 EOP 2525 EOP 2525

SECTION 4 I D Number I-:SO4L.I 1 l<e\\.ision: 0 Task Time ID NMal f Instructor Information I Activity Assign Expected Actions s tan diu-d Verify that the STA has indcpendently diagnosed the event h I Enter EOP 2532 LOCA Classification will be done as an Admin JPM later.

NOTE 1 : The BOOTH INSTRUCTOR must remove the following IO Lvlien 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.

LJS STA us SM STA LTerified when accomplished.

Query board operators re: safety function status, perform diagnostic flowchart, and diagnose sinal1 break LOCA, transition to EOP 2532.

E\\raluate and concur.

Directs SFSCs for EOP 2532 be initiated.

Classifies event as either an Alert, C-1 based on KCB2, 3 or 4.

Verify that the STA has independently classified the event EOP 2525 EU-1 MP-26-EPI-FAP06 27

ID NI Reports annunciator for "C'TMT AIR RECIRC FAN 'A' VIBRATION HI

energized.

SECTION 4 mber ESO41,Il Re\\ ision: Q Task I DAIblal f Instructor Iiiforination / Acti\\itj.

Assign Expected Actions s tall d n r d EM-I TM-5 Ti ni e Stop "A" CAR fan per OP-2323A.

Monitor CTMT for increasing pressure.

temp and moisture.

Submit TR to maintenance.

T6 T7 IO "C-0 1 A4" (ON)

IO "C-01 A4" (Delete)

SG02A @ 30%

(60 sec.)

IO "ON" Annunciator C-0 1 '44, "CTMT AIR KECIRC FAN 'A' VIBRATION HI" When directcd by Chemistry to sample SGs, after

--3O inin delay report both SGs < MDA.

NOTE: Givc the PPO time to identify the High CAR Vibration before inserting the following malfunction. We don't want to mask the HI VIBRATION annunciator.

1. 1 SiG Tube Rupture - 750 gpm.

If the MSIVs are open, the SJAE should show a rise indicating a SGTR in #1 SIG.

If MSIVs are closed, the SJAE \\\\on't rise but the SGBD RM will rise and the # 1 SI(; Level will eventually show an unusual risc indicating a SGTK in # 1 SIC;.

PP 0 USiPPO Inst. I SPO Direct Chemistry to sample SG(s).

EOP 2532 28

SEC'TION 4 ID Niiiiiher ES04LI 1 1 - h ision: 0 Task Time 1l)~IiMalf In t ruc t or Inform B t i on i Act i \\ V i t!

A s si g n Expected Act10115 SLandard CT-2 Secure all RCP within 5 min. of loss of NPSH. (2260 3.1.1)

PPO PPO Pro PPO IJ S/PPO/

SPO Verify SIAS. CIAS, EBFAS, and CIWC on E-01x 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 condcnser Isolate the LOCA Ensure valves are closed for isolating LOCA Check not RBCC W Radmonitor.

Check RBCCW Surge Tk not rising Check LOCA NOT Outside CTMT Check Radmonitors outside C IMT on PPC' Place Hydrogen Analyzers in Service EOP 2541 Appendix 19.

oP 2532

tep 5 ZOP 2532 step A ZT-2 ZOP 2532 Step 7 EOP 2532 Step 8 EOP 2532 Step 9 MA-2 TM-6 29

SECl'ION 4 I<wision: 0 ID Number ES04LIl Task Time IDA/IvIalf Instructor Inforination / Activity Assign Expected Actions s tandartl When the crew determines they have a SGTR in #1 S/G, move forward in this guide to EOP 2540.

PPO CT-3 Perform a plant cooldown. (LOCA-11)

The operators will commence a rapid cooldown within the Tech Spec limits.

CT-4 Establish RCS Pressure Control.

(LOCA-1)

SIAS flow iiiust be capable of recoveriiig/inaintailling RCS pressure.

The crew should establish and maintain the RCS press. vs temp. within the PT Curve.

PPO SPO SPO SPO PPO

,f CTMT pressure is >4.42 psig or CTMT Radmonitors are in alarm

. Ensure SIAS, CIAS, EBFAS, MSI &

CRAC.

Start all available CAR Fans with RBCCW Flow.

If CTMT Press.

9.48 psig.

Ensure CS Pps. running Ensure CS Flow > 1300 gpm.

If MSIVs are closed, open AR-17 "Vacuum Breaker" If MSIVs are open Align Condenser Air Removal to Unit 2 stack Initiate a controlled cooldown If MSIVs Open, use SD/BP Vlvs If MSIVs Closed. use ADVs.

Initiate a controlled depressurization of the RCS to SDC conditions.

If no RCPs use Aux Spray If RCPs running use Main Spraq ZOP 2532 Step 10 EOP 2532 Step 11 EOP 2532 Step 12 EOP 2532 Step 15 EOP 2532 Step 17 CT-3 EOP 2532 Step 18 CT-1 30

ID Number ES04LI 1 I

I I

SECTION 4 Task IL)i\\/Malf 111s t ruc t o r I n fo rni a t i on / Act i\\i t 5 Ass i g i Expected Actions S taiidaril rime Major change in plant conditions (tube rupture) requiring transition to Functional Recovery (2540)

EOP 2540 Functional Recovery The SM should classify the event as AlerbCl per RCB4 Note: Classification will be accomplished in JPM-A4SRO.

1JS SM us lJS/SPC When crew recognizes they have a LOCA with a S/G Tube Rupture.

Iiiiplenient the Diagnostic Flow Chart (2541 Appendix 1)

Confirms 2 events requiring Functional Recovery (EOP 2540)

Cren. transitions to EOP 2540 Functional Recovery..

Classify the Event Enter time in Safety Function Tracking Page Ensure Master Silence in Off

~~

Saniple both SIGs Open the Sample V11.s. MS-191AIR Direct Chem to sample both S/Gs fol activity and boron.

When samples are reported, close MS-I 191AIB OP 2260 Step 1.19.2 EC-1 EU-2 PAP06 EOP 2540 Step 1 EOP 3 4 0 Step 2 EOP 3530 Step 4

Hydrogen Analyzers may already be in service.

1 us/spo 1 Place Hydrogen Analyzers in service.

EOP 2540 Maintenance of Vital AC Power MVA-AC-1 RSST US Directs the STA to verify the Safety Function are satisfied for the cliosen EO I 2 5 40 Step 8 1

Re\\.ision: 0

?iLSl<

-\\ssign lhpected Actions Stanclard Time TDAiMal f Instructor Information / 4ctiL.i t j I us 1 Identify the Success Paths using RATS.

EOP 2540 Safety Function 1

Success Path I Operating I CEA Insertion Y

I Y

Reactivity Control I RC-1 Battery Chargers/Station Batteries I MVA-DC-I Maintenance of Vital DC Power Y

Y Y

_ _ _ _ _ _ _ _ _ _ ~

~

~~

RCS Inventory Control I IC-2 Y

Y 1 Safety Injection RCS Pressure Control I PC-2 I Saturated Y

Y Y

Y I HR-2 RCS and Core Heat Removal SI operating

~ontaininent Isolation 1 CI-I 1 Automatic/Manual N

N Containment Temperature and Pressure Control Y

Y CARS (Emerg)

CTPC-2 Containment Combustible Gas Control Y

Y Hydrogen Recombiners CCGC-1 32

SECTION 4 111 Nuniber ES04L11 Rei ision: 0 Tash Time IDA/blalf Iiistructor Inlbrmation Activitj.

Assign Expected Actions Srand ard The 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 radmonitor SJAE radmonitors Maximum controllable rate is characterized by a rate that does not further degrade the conditions of the plant.

Efforts should be made to preserve NPSH, Subcooling and Pzr/lead Levels. while trying to h i t S/G level by isolating the S/G as soon as possible.

17s us UYPPO us/

CREW USiSPO

~~

~

success paths.

Perform operator actions for chosen success paths based on priority assigned.

Transitions to EOP 2540E Containment Is0 lation If CTMT Press. > 3.32 psig or CTMT Radmonitors rising or in alarm.

US directs the PYO to ensure STAS, CIAS, EBFAS AND MSI OII C-01 and c-0 1 x.

If a SGTR is indicated, identify and isolate the most affected S/G.

US references EOP 254 1 Appendix I2 Coiiimence an KCS cooldo~vii at maximum controllable rate to 3 15 Tli in both Si&

If the condenser is available SIJBP Vllls will be used.

IF the condenser is not a\\.ailable, both ADVs will be used.

E 0 I 2 5 4 0 Step 9 EU-3 EC-2 EOP 2540 Step 0 EOP 25401, Step I EOP 2540E Step 2 EOP 254 I Append 12 Step 1 33

The IJS should give the PPO a pressure range the does not violate any of the listed limits.

If HPSI throttleistop criteria is met, the PPO should limit injection flow to stabilize Pzr. Levcl and promote depressurization.

~~

~

Isolate the faulted S/G within 60 minutes of evidence of a tube rupture. (OP 2260 3.3.1)

The scenario can be terminated when the crew has successfully isolated the #l S/G.

IJS/PPO US/PPO Depressurize the RCS using main or aux.

spray while maintaining the follcxving limits:

Within the P/T Curve NPSH if RCPs are operating Within 50 psig of the #1 S/G.

If HPSI throttldstop criteria are met:

Control charging and Ietdwt 11 Throttlc or stop HPSI flm.

EOP 254 1 Append 12 Stcp 2 EOP 2541 Appclld 12 Stcp 2 CT-5

Section 4

SUMMARY

.I'itle: Simulator Evaluation ID Number:

ES04LIl Revision :

0 C' R I TI C' AL TASKS CT-1:

Trip 2 RCPs (LOCA-13)

(2'1-2:

C'T-3:

Perform a plant cooldown C'T-4:

Establish RCS Pressure Control.

CT-5:

Secure all RCP within 5 min. of loss of NPSH.

Isolate the most effected S/G.

35

Section 5 SCENARIO INITIAL CONDITIONS

Title:

Simulator Evaluation ID Number:

ES04LI1 Ke1.i si on :

0 Initial Conditions 22 is protected 100% power. NOPNOT, EOL, Equilibrium Xenon 3 5 ppm boron / Blend ratio - 165 PMW i I RA SG Rlowdown - -25 gpm each 24E aligned to bus 24D Out of Service Equipment None Crew Instructions Four hours prior to taking the shift, a minor earth quake < 0.09g ZPA uas felt and verified by the USGS Earthquake Information Center.

1-111 actions for the AOP 2562. Earth Quake have been performed.

A CTMT entry is being discussed by management, no decision has been made.

Unit 3 declared an UE/D1. The event is now terminated.

SP-2654B Forcing Sprays is scheduled for the beginning of shift.

No equipment out of service.

36

ATTACH I\\.I EN T VAL.IDAT'ION CHECKLIST

Title:

Simulator Evaluation ID Number:

ES04LI1 Rc\\,ision:

0 Remote fiinctions:

All remote functions contained in the guide are certified.

MalfLinctions:

All malfunctions contained in the guide arc certified Initial Conditions:

'I'he initial condition(s) contained in the guide are certified or ha\\^ been developed from certified ICs.

Simulator Operating Limits:

The simulator guide has been evaluated for operating I iniits and/or anomalous response.

Tcs t Run:

The scenario contained in the guide has been test run on the simulator. Simulator response is reasonable and as expected.

Date Verified By:

37

SHIFT TURNOVER REPORT PREPARED BY Unit Supervisor /NIGHT Shift DATE-TIME Todav 0515 SHIFT 18100 - 06100 Date Time LCO Action Action Requirement PLAiST STA TUS:

.LtOL)E: 1 RX POWER: 100 10 Equipment Reason

,\\l1iGA4 11:4 T7S. Thermal: 2699 MWTH Electric: m M W e RCS Identified: U g p m LE-lK-IGE: Unidentified: U g p m Date/Time:Todav 001 5 Action Requirement Infinite action: Establish hourly fire watch.

Infinite action: Attachment I of OP 2301A PZR PRESS: 2250 psia RCS T-A VE: =degrees F

PROTECTED: TrainIFacilit).

LCO Action Equipment Reason TSAS 3.3.3.8 ai3 RC-200 Failed SP 24 I OA TRMAS 3.7. I O I

See AIL See Active Impairment List.

22 (YELLOW)

EVOLUTIONS IN PROGRESS 8 z NOTES Reference /Date Continuous TS LCO and TRM ACTION Statements in effect (if more than one ACTION requirement per LCO. list each sel,aratel\\~

REACTOR COOLANT Time 0625 Parameter Reading Parameter Reading Po\\ver 100 Yo Flouride 0.81 ppb TLlVt?

572 deg I:

Chloride 3.75 ppb Boron 35 PPm Oxygen 4 ppb OD COhlPENSATORY ACTIONS / Temp LOGS (Bold: Tech Specs. Italics: TRM)

ON-LINE STATUS REPORT Unit 2 Chemistry I Blend Ratio:

1) 165: I I

Attachment Guide No.: ESOQLIl SCENARIO ATTRIBUTES CHECKLIST Scenario

Title:

LOIT Simulator Evaluation Number:

ES041,I 1

'l'echnical Reviewer:

D. A. Pantalone Date:

12/03/2004 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.

Y

1.

Y

2. The scenario consists mostly of related events Y

3.

Each event description consists of:

the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the expected Emergency Plan classification the event termination point (if applicable)

Y

4.

No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

Y

5.

The events are valid with regard to physics and thermodynamics Y

6.

Sequencinghiming of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

N/A 7.

If time compression techniques are used, scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.

Y

8.

The simulator modeling is not altered.

Y

9.

The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure that functional fidelity is maintained while running the scenario.

39

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 bolded in the evaluation guide.

1.

Total Malfunctions (TM) - Include EMS - (5 - 8) 6

1. Trip of C SW Pump

2. Fail FW Heater 6A leire1 transmitter downscale.

3. RC-200 Pzr Safety Leakage

3. RC 200 Pzr Safety Leakage > Charging

5. CTMT AIR RECIRC FAN A VIBRATION HI

6. # I S/G Tube Rupture - 750 gpni.

2.

MaIfs after EOP entry (EMS) - (1 - 2)

1. CTMT AIR RECIRC FAN A VIBRhITION HI

3.

Abnormal Events (AE) - (2 - 4) 1. Trip of C SW Pump

2. Fail FW Heater 6A level traiisinitter downscale.

3. RC-200 Pzr Safetl, Leakage

4. Major Transients (MA) - (1 - 2)

1. RC 200 Pzr Safety Leakage Charging

2. # I S/G Tube Rupture - 750 gpm.

5.

EOPs entered requiring substantive actions (EU) - (1 - 2) 1. EOP 2532 Loss of Coolant Accident.

2. EOP 2540 Functional Recovery

3. EOP 2540E Functional Recovery of Containment Isolation.

3

6.

EOP Contingencies requiring substantive actions (EC) - (0-2) 2

1. 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) 40

Attachment Guide No.: ES04LIl SCENARIO ATTRIBUTES CHECKLIST

7.

('ritical Tasks (CT)- (2 - 3)

I. rrip 2 RCPs (LOCA-13)

2. Secure all RCP within 5 min. of loss ofNPSH.

3. Perform a plant cooldown

4. Establish RCS Pressure Control.

5. Isolate the most affected SiG.

8.

\\pproxiinate Scenario Run Time: 60 to 90 inin.

9.

Technical Specifications exercised during the scenario.

41

~ Event Malf.

Event Event No.

No.

Type*

Description 1

NIA N (BOP)

Raise power to 4%.

R IATC)

Appendix D Scenario Out line Form ES-D-1 I 7

~

ED16B I C (ALL)

I Loss of Vital Instrument Bus. VA 20.

I

~

MP2 Scenario No.: ES04L12 Op-TestNo.: 2

~

Examiners:

Operators:

Initial Conditions: 1 % Power, EOL, RCS Boron is 466 ppm, Equilibrium Xenon, Bus 24E is aliqned to Bus 24C. SG blowdown is 40 qpm on each SG. Group 7 CEAs are at 120 steps, Facility 2 is protected. No equipment is out of service.

Turnover:

1% Power. Facilitv 2 is protected. RCS Boron is 466 ppm, Blend ratio is 11.8:l.

SGBD @

40 gpm per SG, 24E aligned to 24C. A snow storm is in progress with sustained winds of 20-25 mph. Need to raise power to 4%, using PMW, to commence warming the main turbine. Reactor Enqineering would like to leave Group 7 CEAs at 120 steps up to 5%

power to allow for better AS1 control when raisinq power above 5%. OP 2203, Plant Startup is complete UD through step 4.5.10.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor I

Appendix D, Page 38 of 39

Mills tone Station Unit 2 Operator Training SIMULATOR EXERCISE GUIDE I.

Title:

LOIT Simulator Evaluation #2 ID Number:

ES04LI2 Revision:

0

11.

Initiated:

De\\,eloper Reviewer 1 V.

Approved:

Operator Trayfing Supervisor 1/12/05 Date Date Date 1

Iitlc: Simulator E\\duation

11) Number:

ES04L12 Revi si o n :

0 TABLE OF CONTENTS SECT IONS IJSlED IN ORDER:

1.

Cover Page 7

Table of Contents

-3.

Exercise O\\,erview

4.

Instructor Guide / Summary Scenario Initial Conditions

It t achments Validation Checklist 0

Training Turnover Sheet EXERCISE. OVERVIEW

1.

Purpose :

a.

Evaluate the licensees ability, as a team and individually, to saiely and responsibly operate the plant during normal plant operations. abnormal operating conditions and emergency operating conditions.

Evaluate licensees in the following areas. as applicable:

I )

2)

-3)

b.

Ability of the crew to perform crewdependent (and time-critical) tasks.

Ability of individuals to perform critical tasks.

Ability of the crew to:

a)

Understandhnterpret 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) i)

g)

Demonstrate a responsible attitude h)

Diagnose events/conditions based on signalsheadings Comply witlduse 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

Titlc: Simulator Eiduation ID Number:

ES04LI2 Ke1.i si on :

0

2.

I.%ercise Brief Thc simulator \\vi11 be prepared for the e\\ aluation and the licensees \\\\ill be briefed on the conduct ofthe e\\duation and the areas in nhich they \\vi11 be evaluated.

The simulator will be initialized to IC-91 or equivalent, critical at 1 YO poner, EOL. Equilibrium Xe. 366 ppm boron. There are no sur~eillances in progress and no equipment out of service. A snou storm has been predicted for the area uith accumulation of 3-5 inches. Winds are presentljr from the West-Southwest at 20-25 mph. Snow has already started to fall. The ere\\\\ mill be instructed to raise power to 4% and stabilize in preparation for Turbine warm up in accordance

\\iith OP 2203. Plant Startup.

During the power ascension, the dilution valve will fail to close resulting in adding more PMW than desired. The crew will stop the power ascension and take action to stop the dilution. After the ere\\\\ stabilizes power. the "D" Circulating Water Screen D/P n i l 1 rise to the point that the "D" Circulating Water Pump trips. The crew will enter AOP 25 17, Circulating Water hlalfiinctions, and perform steps associated nith the loss of a Circulating Water Pump. While the cren is performing steps of AOP 25 17. the Control Room Air Conditioning System will mtoniatically transfer to the Recirc mode due a failure of Control Room Radiation Monitor. RM-0799A. The crew will perform the actions of A W 2590A-159. The US will enter TRM Action Statement 3.3.3.1.lb. When the crew contacts the I&C Department concerning the Rad Monitor failure. annunciator C-8 on C-05, Main Steam Is01 Valve Air Press Lo. will alarm. The cren \\\\ill respond to the annunciator b) referencing the appropriate Annunciator Response Procedure.

Shortl! after the annunciator alarms, the #2 MSIV will close. This nil1 result in an Excess Steam Demand in the Enclosure Building. The crew should manually trip the reactor. During the performance of EOP 2536, Excess Steam Demand, VA-20 will suddenly deenergize. The loss of VA-20 \\\\ill result in the opening ofthe #2 Aux Feed Regulating Valve. The crew must take action to stop feed to #2 S/G.

The scenario map be terminated when the S/G has been isolated and actions have been taken to prel ent exceeding PTS limits.

-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 /> All Control Room Conduct, Operations and Communications shall be in accordance with Master h,lanual 14 (MP-I 4). Review the Simulator Operating Limits (design limits of plant) and Simulator hlodeling Limitations and Anomalous Response List prior to performing this training scenario. The instructor should be aware if any of these limitations may be exceeded.

3

SLCTION 4 ID Number LS04LI2 Kmision Q Task T i m IDMMalf Instructor Information /,4cti\\ity Assign Expected Actions Standard Tlnitial

~~

IC-91 or equivalent CHR06 (22.8)

CHR07 (223.4)

CHR08 (23.6)

CHR09 (224.1)

CHRlO (23.1)

CHRl 1 (222.9)

Simulator Setup and Initial Conditions:

1 % Power, EOL, Equilibrium Xenon, RCS Boron 466 ppm.

Insert a remote function for wind direction from the West-Southwest at 23 mph.

Set blowdown to 40 gpni on both S/Gs.

0 0

0 0

0 0

0 0

0 0

0 0

0 Provide the crew with the following turnover info:

1 % power, EOL. Equilibrium Xenon Gp 7 CEAs @ 120 steps 466 ppm boron Blend ratio - 1 1.8: 1 SG Blowdown - 40 gpm each Condensate 011 short recycle A Main Feed Pump in operation Vacuum being inaintained with the Hoggers 24E aligned to bus 24C Forcing Pressurizer Sprays 2 Charging Pumps running Snow storm in progress (20-25 mph winds)

No surveillances due.

4

SECTION 4 ID Number ES04I-I2 lie\\ ision: 0 Task

' h i e IDA/Malf Instructor Information / Activity Assign Expectcd Actions Standard

~

~~

Provide the following documents:

0 OP 2203, Plant Startup, signed off up through step 4.5.10.

0 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 up. Reactor Engineering would prefer to use dilution to raise power. Dilution should be done in 100 gallon increments. Rods will be used above 5% power for AS1 control.

Shortly after the crew has assumed the shift and they have started to dilute to raise power to 4%.

insert a malfunction to prevent the Dilution Valve, CH-2 1 OX, from closing.

When requested as I&C, inform the crew that you will obtain the appropriate paperwork and trouble shoot the problem.

PPO US PPO When the PMW counter reaches '0'.

observe continuous flow of PMW to the RCS. Inform the US of the condition.

~~

Direct the PPO to place the Makeup Selector Switch in a position to prevent dilution or close VCT Makeup Bypass, CH-196. Inform the I&C Dcpt.

Place the Makeup Mode Selector Switch to the Manual or Borate position or close VCT Makeup Bypass. CH-196 and observe

'0' PMW flow to the RCS. Inform the US that PMW flow is secured.

MI'- 14 TM 1 AE 1 ARP 2590c' ARP X90C CT 1 5

CW02D

( IOO%)

Ranip=36O sec.

NOTE: The US may provide a specific value, as long the plant does NOT enter MODE 1 (25%

power).

CT 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.)

When the plant has stabilized. insert a malfunction to cause the "L)" Circ Water Scrccn DIP to increase.

After a 5-10 minute delay, report as the PEO that all requested actions are completc. Also report that the "D" traveling screen is NOT rotating. It appears that a pin has sheared.

us SPO USISM IJS Direct the PPO to monitor plant parameters and ensure reactor power does NOT exceed 5%. If power approaches 5%,

direct the PPO to either insert group 7 CEAs or borate to maintain power 4%.

Observe rise in "D Circ Water Screen DIP or ackno\\vledge Annunciatoi-D- I O on C-

05. Tralveling Screen AP.

Enter AOP 25 17. Circulating Water Mal functions, and per ftmi In i ti al Act ions.

Direct a PEO to:

0 Check all screens rotating Monitor tra\\.eling screen DIP 0

Start both screen wash pumps.

Place all traveling screens in fast.

Check screen wash pump strainer DIPS less than 4 psid.

Placc screen wash trash hasket in senrice Not i 5 Env i ro nnien t a1 S en-i ces-N uc 1 ear When DIP approaches 30". direct SPO to perform actions of AOP 22 17. Section 5.

MP-14 MP-14 TM 2 AE 2

.\\KP 2 5 9 0 E - 0 5 6 OP 2.327 AOP 2517 6

SECIION 4

11) Number ES04L13 Re\\ ision: 0 1 ask Time IDA/Malf Instructor Information / ActiIity Assign Expected Actions s tanda1-d Check condenser backpressurc is (4.5 in.

lig.

The LJS may may NOT direct cross tying D Water Box with C Water Box. Steps in italics are optional.

i\\OP 21 17

~

SPO SPO If required, update PPC Condenser Performance Report to indicate actual Circ Water valve positions.

Notify Enviroiiiiieiital Services-Nuclear of Circ Pump trip.

IJ S AOP 25 17 AOP 25 1 7 SPO Inform maintenance of the 1) Screen failure aiid direct them to troubleshoot and repair.

IJSiSM MI-14 us Trip the D Circ Water Pump.

Close CW-1 1 E, D Water Box Inlet C ros.~

tic 14 uler hoxcs 9

9 Ensure CW-11 D. D Circ Mflitei. Bos Outler, i t open 9

I l p n CIV-12C, Condensw 1 B Inlet Cro TS-Tic Place D Circ Wuterpump in Pull-To-Lock AOP 25 17 Inform Unit 3 that water boxes are cross tied.

AOP 2517 7

SECTION 4

11) Numbcr ESO4LT2 Rwision: 0

'I ';1s 1;

'l'inie IDiI/Ivlalf Instructor Inforiiiation 1.Acti\\.it!.

Is s i gn Ex pc c t cd :\\ c t i ( ) n s Standard I RMO 10 (1 OOYO) I When the crew has cross tied n-ater boxes. insert a failure of Control Room Radiation Monitor, RM-9799A. (The annunciator will alarm at 22%

Ranip=25O sec.

I I severity.)

When inforincd of thc failure of' Rhl 9799'4.

report that I&C will obtain the appropriate paperwork and coininence troublesliooting.

TS 3.3.3.1 is NOT applicable lvith RM-9799B OPERABLE.

PPO T JS PPO I

J S / S h4 I IS Observe the C.R.A.C.S. in Auto Recirc Mode annunciator on C-01. C-40 Direct the PPO to observe RM-9799A and to perform ARP actions for the annunciator.

Obseri e RM-9799A is pegged high.

Placc both Rccirc IIand Snitches in RECIRC.

Verify proper damper aligiinieiit Ensure Control Room Filter Fan. F-32A is operating Ensure Fac. 1 Control Room Supply and Exhaust Fans arc running.

Detcrmine that the swap to recirc was caused by a failure of' Rh4-9799A Obtain run hours for Filter Fan. F-32A and F-.32R and log in Shl log.

Infcmi the l&C Dept. of the failure of Rhd-9799A.

Refer to TS 3.3.:. 1. Action 16.

Enter TRM 3.3.3.1 - 1 b MP-13 TM 3 AE 3 MP-14 Tech Specs

?'RIVl 8

11) NLIlmber ESO41.12 Re\\.ision: 12 linic I DAiMal I Instructor Information il,.cti\\.ity Assign Expected. -ctions s t~u1dal-d I/O ON aiiiiuiiciator C -8 on C-05 Observe annunciator C-8. Main Steam Is01 Valve 2 Air Pres Lo on C-05.

MP-14 TM 1 When the crew has completed the actions of ARP 259OA-159, insert a malfunction to cause an alarm on C-05, Main Steam Is01 Valve 2 Air Pres Lo, C-

8.

SPO T;

When dispatched as a PEO, repeat back any direction, but do NOT provide any further report.

IJS/SM Direct a PEO to:

Observe local Instrument Air header prcssure.

Check both channel solenoid vents are NOT venting.

Insect for Instrument Air line leaks.

o 0

0 If possible. reconnect any broken air lines.

us Direct crew to perform EOP 2525 if the MSIV closes.

ARP 259OD-03 1 I J SIS h4 Direct Maintenance to trouble shoot and/or repair.

When directed as Maintenance. report that you will send someone out to iinxxtigate.

Approxiniatel\\~ 5 minutes after thc 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.

T4 MS06B

(:re\\\\

Obscrvc closure of if2 hlSlV h 11-1 4 TI11 5 TM 6 ILIA2 MS02B (7%)

Ranip=400 sec After the MSIV has closed. obser~

e lolvering S/G pressures. lonering RCS temperatures. and lo~zering RCS pressure.

M P 16 Direct a manual Reactor trip and performance of EOP 2525.

Place Master Alarm Silence in SILENCE.

Announce Unit 2 trip on the plant paging system. Direct performance of EOP 2525.

us LJS/SM OP 2260

SECTION 4 Rc\\.ision: 0 ID Number ES04IB Task Ti 111 c lDA/Malf Instructor Information / Activity Assign Ex pe c t ed A c ti on s Standml The PPO may also manually initiate MSI on low SG pressure.

l J S PPO Juery board operators regarding the statu\\

)f safety functions.

Ioniplete and report SPTA:

. Ensures Reactivity safety function is being met:

o Reactor is tripped o All CEAs are inserted.

o Poiver is going donn.

3 SUR is ncgatiie.

- Verifies RCS Tin entor! safetj function is being met:

o Reports Letdoicii is isolated and 111 available Charging Pumps are running.

- Verifies RCS Pressure safety function is being met:

o Reports heaters are off due to low level o Reports spray \\ d i e s are closed o Reports PORVs and Safeties are closed.

o When Pressurizer pressure falls to less than 1800 psia. manually initiates SIAS, or \\ erifies autoinatic SIAS \\\\hen pressure lalls bcloix 17 14 psia.

o Reports SIAS, CIAS, EBFAS, (and MSI) initiated nith Facility 1 C.R.A.C.S. in recirc.

)P 3260 10

ID If KCS pressure lowers to NPSIi setpoint. secure all RCPs.

CT 2 Isolate Auxiliary Feedwater to the #2 S/G from the Control Room within 10 minutes of the initiation of the ESD.

This action will be performed when #2 S/G is empty as indicated by a rise in RCS temperature SPO SPO

- Verifies Core Heat Remo\\al establishcd.

o Two RCPs are operating (one in each

- Reports value and trcnd of KCS subcooling.

- Verifies Containment Integrity safety function is being met by \\wifying CTMT pressure. temperature. and rad monitor readings.

o Obsen es all rad monitors are normal.

loop).

Complete and report SPTA:

I rip turbine. stop \\tal\\ es closed. MWc indicate 0, and 8T&W opcn All electrical buses are energized Both SW and RBCCW facilities running Verifies status of Core Heat Removal o MSIVs closed due to low SG pressure. #2 lower than # 1.

(I ADVs and safet). val\\-es arc closed o Feed flou is NOT excessix e o Place both Auxiliary Fecd Override/Man/Start/Keset hand switches in Pull-To-Lock Feeding # 1 SG o with Auxiliary Feed to restore level to 40-70%.

o Adjust #1 ADV to stabilize RCS temperature.

FOP 2525 EC 2 CT 2 EOP 2525 11

SECTIOIU 4 1D Nuinber l<S041212 Kci.isioii:

TaSk Iimc Il)r-2/Ivlalf Instructor Information Acti\\i t!.

Ass i g n E spec t e d Actions Stand 3 rd Event is classified as an Alert, Charlie-One (BA2), based on an unisolable steam line break outside Containment.

us USISM USIST.4

~~

Per forms subsequent act i on s :

Ensures Vacuum Breaker, AR-17, is open Opens subcooling valve, HD-106 Stops both Heater Drains Pumps Isolated both Main Feed Pumps Ensures only one Condensate Pump is running Verities Instrument lZir pressure is >90 PSifi When queried, report completion and verification of subsequent actions.

Refers to Diagnostic Flow Chart and determines that EOP 2536, Excess Steam Demand is the appropriate procedure.

~~

Direct the performance of Safety Function Status Checks for EOP 2536 Direct Chemistr). to obtain samples of #1 SG and analyze for Boron and activity.

Direct SPO to close S/G sample valves when samples have been taken.

~~

~

Ensure event is classified.

UP 2260

~~

EOP 2525 EU 1 EOP 2536 EOP 25.36 EOP 2536 12

SLi:C'I'I(.>N 4 ID Number ES041,12 Re\\,ision: 0

'l'asl.1 Time IDA/hlal f Instructor Information / Actiiit!.

'4 s s i g n E x pec t cd :\\ c ti o ns s tan d ard II S US PP 0 IJS SPO Open place keeper and enter EOP entry time Return Master Silence switch to Normal Direct PPO to:

Check SIAS Actuation Optimize Safety Injection Ensure:

At least one train of SI,4S. CIAS. and EBFAS have actuated by checking blue lights on C-OlX Safetj, Injection flow is adequate using Appendix 2, Figures.

All available Charging Pumps are running.

Vital Switchgear Cooling is in operation on C-80 Direct SPO to ensure MSI has properly actuated and to verify open thc vacuum breaker, AR-1 7.

Observe conditions on C-01 X to ellsure proper actuation of MSI or observe indications on C-05 and C-06/7.

EOP 25-36 EOP 2536 EOP 2536 EOP 2536 EOP 2536

PPO ED I6B While the SPO is isolating #2 S/G, insert a malfunction to trip the supply breaker to Vital Instrument Bus, VA-20.

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 stabilize the plant prior to referencing an approved procedure provided the appropriate procedure is used after taking those actions.

us SPO Crew us 1JS Verify 2 RCPs in each loop are stopped with the respectiLre spray valve closed.

If Pressurizer 1~re.s.rmrc 1owt.r.r to less Ihm minimum NPSH, then.stop 1-enmining RCPs.

Determine that #2 S/G is the most affected.

Commence actions to isolate the #2 S/G.

Observe loss of power 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 Dcniand. is still the appropriate procedurc and direct the SPO to stop Ausiliar!. Feed to fi2 S/G.

EOP 2536 EOP 2536 EOP 2536 TM 7 EM 1 MA 2 OP 2260 EC 3 EOP 2525 14

FWR60 (Man)

FWR64 (0)

MSR13 (RI)

CT 3: 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-Tie Valve Stop the running Aux. Feed Pump(s)

Dispatch a PEO to manually close #2 Aux Feed Regulating Valve. FW-43B.

Complete actions to isolate #2 S/G bj.

ens ur i 11 g :

e e

e e

e e

e e

e e

0

1. 2 MSIV is closed

1. 2 MSIV Bypass is closcd.

ADV Quick Open Periiiissi\\.e in Off.

1. 2 Main Feed Block V a l ~ x. FW-42B.

is closed

1. 2 Main Feed Air Assist Check V a h c FW-5B, is closed

1. 2 S/G steam Supply to Terry Turbine, MS-202. is closed

1. 2 S/G Blo\\vdo\\v;n Isolation. blS-220B.

is closed Both Auxiliar!. Feed O\\~erride/h~lnniStart.'Kcset hand sivitches are in P~ill-'l'o-Lock

1. 2 A u s Feed Regulating Val\\.e. FU'-

43B. is closed

$2 Main Steam Lo\\\\- Point Drain, hlS-266B. is closed

1. 2 Main Steam Safety Valves are closed h'lP It)

CT 3 EOP 2536 15

SFCTION 4 ID Number ES04LI2 Rei.ision: 0 Task

'Pilnc IDA/IvIalf Instructor Iiilbrmation / ActivitJ-r\\ssigii Expected Actions s trund arc\\

~

~

The SPO will stabilize RCS temperature with #1 ADV when the #2 S/G indicates cinpty. The PPO will lower or maintain RCS pressure to prevent exceeding 200°F subcooling. This step may need to be pulled forward to prevent exceeding the PTS 1 imi t.

CT-4 Limit Tc subcooling (CET subcooling if all RCPs are secured) to 5200'F.

Lower RCS pressure using Main (or Auxiliary) Spray Valve.

0 Establish RCS temperature control using the #1 ADV when #2 S/G indicates empty.

0 I! S SPO I PPO PPO Veri 1)' iiiost affcctcd Si(; has been isolated:

Lowest steani prcssurc 0

Lonest le\\.el Lowest cold leg temperature Stabilize RCS tempcrature.

Open uiiaffectcd ADV to stabilize RCS temperature.

Maintain KCS within the RCS P/T limit:

0 Manually control Pressurizer heaters and spray.

If HPSI throttle stop criteria are met:

o Control Charging and Letdown o Throttle or stop HPSL Pumps.

?'hrottle/Stop HPSI Pumps when the following conditions are met:

0 Pressurizer level >20%

0 RCS subcooling is above niininiuni operating limits of the PIT Curve At least one Si(; available to remove heat at 40-70% or being restored Reactor Vessel level 2 43%

EOP 2536 EOP 2536 CT 4 EOP 2541 16

c 3

'l.itle: Simulator Evaluation 1 1) Number-:

ES041.I 1 I<c\\.ision:

0 C'RI'IICAI, TASKS Establish reactivity control. Stop the dilution to prei.ent exceeding 5% power unplanned entry into MODE 1). (If required, horation or CEIlR.1 insertion may he used.)

Isolate Auxiliary Feedwater to the #2 S/G from the Control Room within 10 minutes of the initiation of the ESD.

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.

Limit Tc subcooling (CET subcooling if all RCPs are secured) to 5200°F.

Ihtablish RCS temperature control using the #I ADV when #2 S/G indicates empty.

Lower RCS pressure using Main (or Ausiliary) Spray Valve.

18

SEC1'ION 5 S C EN i\\ RI 0 IN 1 T I AL CON DI T I ON S I irlc: Simulator ELduation

11) NLlmt7cr:

ESO4LII Re

\\ T i si on :

0 I nit ial Conditions 1 "10 poiver. EOL, Equilibrium Xenon Gp 7 C'EAs @ 120 steps 466 ppni boron Blend ratio - 1 1.8: 1 SG Blondown - 40 gpni each Condensate on short recycle "A" Main Feed Pump in operation Vacuum being maintained with the I joggers 24E aligned to bus 24C Forcing Pressurizer Spra) s 2 Charging Pumps running Snow storm in progress Expect 3-5" (20-25 mph winds)

N o sur\\.eillances due.

Out of Service Equipment None C'reiv Instructions Ixaise poiver to approximately 4% using dilution to begin Main Turbine warn1 up. Reactor 1:ngineering would prefer to use dilution to raise power. Dilution should be done in 100 gallon increments. Rods will be used above 5% power for AS1 control.

19

ATTACHMENT VALlDATION CHECKLIST

Title:

Simulator Evaluation ID Number:

ES04L12 Revision:

0 Remote functions:

All remote functions contained in the guide are certified.

Malfunctions :

All malfunctions contained in the guide are certified Initial Conditions:

The initial condition(s) contained in the guide are certified or have been developed from certified ICs.

Simulator Operating Limits:

The simulator guide has been evaluated for operating limits and/or anomalous response.

Test Run:

The scenario contained in the guide has been test run on the simulator. Simulator response is reasonable and as expected.

Verified BY 20

Date Time LCO Action Action Requirement Equip in en t Reason O D CORIPENSATORY ACTIONS / T e m p LOGS (Bold: Tech Specs. Italics: TRM) rocia!

Action Requirement Infinite action: Establish howl! fire watch.

LCO Action Equipment Reason TRMAS 3.7, 10 I

See AIL Set. Active Impairment List.

Unit 2 Chemistry ON-LINE STATUS REPORT EVOLUTIONS IN PROGRESS & NOTES I'lirnt startup. Raise power to 4% using dilution for wxrining the blain Turbine. Commence dra\\\\.ing a

\\iicuuin till. starting a Min Feed Pump.

Forcing I+ssurizer sprays. Two Charging Pumps operating.

"11" h,lain Feed Pump in opereation

('ontlensate 011 short recycle.

Snow storm in progress. Expect 3-5". Winds at 20-25 mph.

REACTOR COOLANT Time 06:25 Pa rii ni et er Reading 11 Parameter Reading PO\\\\ el.

1 O

t 11 Fluoride 0 8 1 nnh Reference /Dute O P 2203 Toda}.

OP2203 Today OP 2203 T o d q OP2203 Today CONVEX Today

-1 a\\ e 532 degF I( Chloride 1.75 ppb t h l Oil 466 ppin 11 Oxygen

- 5 pp b 21

Attachment SCENARIO ATTRIBUTES CHECKLIST Scenario

Title:

LOIT Simulator Evaluation Number:

ES04I,I2 Iechnical fhiewer:

R. J. Ashey Date:

1/12/05 01 1, \\L i-ri 1.r I v~ ATTRIBUTES Y

1.

The initial conditions are realistic, in that some equipment andlor instrumentation may be out of service, but it does not cue the crew into expected events.

Y

2.

The scenario consists mostly of related events.

Y

3. Each event description consists of:

the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the expected Emergency Plan classification the event termination point (if applicable)

Y

4.

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.

Sequencingkming 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.

22

..\\ ttachnien t Guide No.: ESOJLI2 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 )

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 Is01 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. The supply breaker to Vital Instrument Bus, VA-20, trips Malfs after EOP entry (EMS) - (1 - 2) 1 Abnormal Events (AE) - (2 - 4) 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 Major Transients (MA) - (1 - 2)

1. Steam line break upstream of #2 MSlV in the Enclosure Building

2. The supply breaker to Vital Instrument Bus, VA-20, trips EOPs entered requiring substantive actions (EU) - (1 - 2) 1 EOP Contingencies requiring substantive actions (EC) - (0-2) 1

2.

3 Critical Tasks (CT)- (2 - 3)

1.

2 3

4 The supply breaker to Vital Instrument Bus, VA-20. trips EOP 2536, Excess Steam Demand Verify RCS Pressure safety function is being met Place both Auxiliary Feed Override/Man/Start/Reset hand switches in Pull-To-Lock Recognize a significant change in plant conditions and refer to the Diagnostic Flow Chart.

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.)

Isolate Auxiliary Feedwater to the #2 S/G from the Control Room within 10 minutes of initiation of the ESD.

Isolate Auxiliary Feedwater to the #2 S/G from the Control Room within 10 minutes of

1. 2 Auxiliary Feed Regulating Valve opening.

Limit Tc subcooling (CET subcooling if all RCPs are secured) to <2OO0F.

Restore Letdown (if required)

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) 7 1

3 3

A Approximate Scenario Run Time: 60 to 90 min.

Total 75 Technical Specifications exercised during the scenario.

(YIN)

Y 23

IC-91 ES04L12 A

AS1 Upper 4.75 AS1 Lower 4.81 Nuclear Power 4.92 AT Power 1.70 Tcold Cal.

4.80 B

4.65 4.67 5.00 2.50 4.79 C

4.78 4.79 4.94 1.50 4.80 D

4.71 4.76 4.87 3.90 4.72

Millstone Station Unit 2 Operator Training

0.

I C ' "

SIMULATOR EXERCISE GUIDE I.

Title:

LOIT Simulator Evaluation #3 ID Number:

ES04LI3

11. Initiated:

111. Reviewed:

IV. Approved:

&(&

R. J. Ashe Developer Operator Tra' ing Supervisor J;

Revision:

0 1/13/05 Date Date

Title:

Simulator Evaluation ID Number:

ES04LI3 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 Attachments Validation Checklist 0

Training Turnover Sheet EXERCISE OVERVIEW I.

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.

ELduate licensees in the following areas, as applicable:

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)

Understand/interpret alarms/annunciators b) c)

Understand planb'systems response d) e) 9 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 signalsheadings Comply withhse procedures and Technical Specifications Properly communicate inforniatiodproper crew interactions Respond and correctly interpret annunciators Properly interpret integrated system response Comply with and use Technical Specifications Comply with and use procedures Properly perforiii control board operations Properly communicate information and interact with the rest of the crew 2

Title:

Simulator Evaluation ID Number:

ES04LI3 Revision:

0

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 to IC 90 or equivalent; 100% power, BOL, Equilibrium Xe, 120 1 ppm boron. There are no surveillances in progress. The Turbine Driven Auxiliary 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 service for filter replacement. Containment pressure is now reading 2 1 inches of water. Containment must be depressurized after the crew 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. While the crew is discussing the down power, Channel C Pressurizer Pressure will fail low resulting in several annunciators. The crew will review the annunciators and select the appropriate Annunciator Response Procedure. The PPO will bypass the appropriate channels of RPS, ESAS, and Automatic Auxiliary Feed. After the crew has bypassed the appropriate channels and has logged into the appropriate Tech Spec Action Statements, condenser vacuum will begin to degrade. The crew will enter AOP 2574, Loss of Condenser Vacuum, and take the appropriate actions to include continuing the down power (started earlier) to slow the loss of vacuum. 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 energize their respective buses. This will result in a loss of all Condensate Pumps. Additionally, the B Auxiliary Feed Pump is severely degraded, resulting in minimal flow fiom that pump. The crew will perform 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 All 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 ID Number:

ES04LI3 Revision:

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 /> All 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 ES04LI3 Revision: 0 Task Time IDA/Malf Instructor Information / Activity Assign Expected Actions Standard Tliiitial IC 90 or equivalent Using IDT, set CHMDRY to 1.284e05 E5 Under CH, I/O OFF G for HS8137 (2)

ED02 1 BT9 1 ES03J FWR22 (Local)

FW20C (Trip)

FW30B (100%)

Ranip=300 sec.

BT3 7 MSR 13 (RI)

MSRl2 (RO)

MSR I3 (RO)

Simulator Setup and Initial Conditions:

100% power, BOL, Equilibrium Xe, 120 1 ppm boron.

I Raise Containment pressure to read 22 inches of water.

I/O off both green lights for F-16 Loss of the RSST on the plant trip Failure of C HPSI Pump to automatically start on SIAS (failure of AM-614).

Disable the Terry Turbine and place a yellow tag on the Terry Turbine Steam Admission Valve, SV-4188.

I I

Gradual degradation of the B Aux Feed Pump.

Rack in breaker for MS-202.

Close Steam Supplies To Terry Turbine, MS-20 1 and MS-202, and insert remotes to rack out the associated breakers.

Place yellow tags on valve hand switches TM 5 TM 8 EM 2 TM 6 MA 2 5

SECTION 4 ID Number ES04LI3 Revision: 0 Task Time TDA/Malf Instructor Information / Activity Assign Expected Actions Standard

~

~~~

~__________

Provide the crew with the following turnover info, allow the crew to walk-down the boards, and perform briefing. The crew should indicate that they have taken the watch.

100 % power, BOL, Equilibrium Xenon 1201 ppm boron Blend ratio - 3.4:l 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.

Provide crew with OP 23 14B, section 4.13.

Steps 4.13.1 through 4.13.8 are signed off as complete.

Ensure the surrogate directs the PPO to depressurize Containment. If the crew does NOT initiate actions to depressurize Containment, as Chemistry, call the SM and ask when they started the Containment depressurization.

US/PPO PPO Brief the crew on the depressurization of Containment.

Place EBFAS in operation as follows:

Monitor for proper operation.

Align Condenser Air Removal to Unit 2 Stack.

Start either A or B EBFAS Fan MP-14 OP 23 14G 6

SECTION 4 ID Number ES04L13 Revision: 0 Task Stand arc1 Tiiiie ID A/Mal f Instructor Information / Activity Assign Expected Actions After a short delay, as the PEO, report that the Hydrogen Purge Flow Limiting Butterfly Valve in the 3 86 East Penetration Room is open.

PPO Open either Facility 1 or Facility 2 Hydrogen Purge Valves on C-01 and direct a PEO to open the associated Hydrogen Purge Flow Limiting Butterfly Valve in the 386 East Penetration Room.

OP 23 14B us Record start time in SM log.

I OP 2314B As Chemistry, acknowledge the time Containment venting was started.

us Notify Chemistry that Containment venting is in progress.

OP 23 14B PCO 1 Once the crew has initiated Containment depressurization, insert a malfunction to cause a loss of the PPC.

Crew

~~

~

While observing the PPC, note a failure of the PPC to update any parameter.

MP-14 TM 1 AE 1 Observe Computer Inop alarm on C-08 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.

Enter AOP 25 18, Loss of the PPC.

Direct a PEO to complete Attachment 1 of AOP 25 18.

MP-14 USISM us Log into TSAS 3.1.3.3d. All pulse counter channels are inoperable.

AOP 25 18 Examinee will need to contact the Booth Instructor to place the PWR RATIO HI/LO switch in the OPER position PPO Place PWR RATIO HI/LO, B 12B switch to OPER (Inside RC-22, Front, Rack #9) and observe Annunciator BB 12 on C-04.

AOP 25 18 us Log into TSAS 3.2.1 a. AS1 is outside the power dependent limits on the Power Ratio Recorder. AS1 must be restored to within the limits within one hour.

AOP 25 18 7

SECTlON 4 ID Number ES04LI3 Revision: 0 Task IDA/Malf Instructor Information / Activity Assign Expected Actions Standard I ime 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.

us US/SM PPO SPO US PPO SPO/PPO Brief the crew on entry into AOP 2575, Rapid Downpower, and the use of Attachments 1, 5, and 6.

Inform HP, CONVEX, IS0 New England, Unit 3 and other personnel required by MP-01 -SM-GDL1.01 Brief crew on plant trip criteria.

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. (Attachment 5)

MP-14 AOP 2518 AOP 2575 AOP 2575 AOP 2575 AOP 2575 AOP 2575 AOP 2575 8

SECTION 4 ID Number ES04LI3 Revision: 0 Task IDA/Malf Instructor Information / Activity Assign Expected Actions Standard Time RPlOC (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.

Compare Channel C Pressurizer Pressure and TM-LP set point to the other safety chaiinels.

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) 0 Channel C High Pressurizer Pressure Trip (RPS)

Sensor Cabinet C Pressurizer Pressure Bistable (ESAS)

Channel C ATWS (C-1 00) 0 MP-14 TM 2 MP-14 ARP 259OC-023 Tech Specs ARP 259OC-023 9

SECTION 4 ID Number ES04LI3 Revision: 0 Task Tiiiic IDNMalf Instructor Information / Activity Assign Expected Actions Standard FW33 (4%)

Ramp=900 sec.

FW33 (Delete)

When the crew has completed the actions of ARP 259OC-023, insert a malfunction to cause condenser vacuum to degrade. Do NOT allow vacuum to degrade to the manual trip setDoint.

~~

~

US should inform the crew that a plant trip will be initiated whedif condenser vacuum lowers to between 6 and 7 inches Hg abs.

Adiust 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 alarm.

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 Removal 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 psig.

Check Condensate Surge Tank level is

> 15% and NOT lowering Check Exhaust Hood Temperature is less than 175°F.

Ensure 2-AR-17, Vacuum Breaker. is closed.

MP-14 TM 3 AE 2 AOP 2574

~

AOP 2574 10

SECTION 4 ID N unib er E S 04 L I3 Rei.ision: 0

.r3Sk

-1 i me IDA/Malf Instructor Information / Activity Assign Expected Actions Standard T4 FW33 (100%)

When dispatched as a PEO, repeat back the direction, wait a few minutes and report that the directed actions are complete.

With the exception of adiusting the loss of vacuum malfunction, do NOT insert any other remote functions or malfunctions at this time.

When the US has determined that vacuum is NOT stabilizing, insert a malfunction to cause a rapid degradation of condenser vacuum.

USISM us Crew us US/SM US

~

~

~

Direct a PEO to:

0 Open Mechanical Vacuum Pump individual and combined suction valves.

Place a second set of SJAE in service.

Check for proper operation of the Atmospheric Drain Collecting Tank level control system.

Check for water seal in Vacuum Breaker.

Check condenser expansion joint loop seal is filled.

Inspect for leakage.

Determines vacuum is NOT stabilizing and directs the crew to continue the down power per AOP 2575.

Observe rapidly lowering condenser vacuum and loss of main generator output.

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.

AOP 2574 AOP 2574 AOP 2575 MP-14 TM 4 MA 1 MP-J 4 OP 2260 OP 2260 11

i SECTION 4 ID Number ES04LI3 Revision: 0 Task Time IDAiMalf Instructor Information / Activity Assign Expected Actions Standard PPO Complete and report SPTA:

Ensures Reactivity safety function is being met:

?k Reactor is tripped rt All CEAs are inserted.

• Power is going down.

& SUR is negative.

Verifies RCS Inventory safety function is being met

-kt Pressurizer level is between 35 and 70%

Verifies RCS Pressure safety function is being met:

nh Pressurizer pressure is between 2225 Verifies Core Heat Removal established.

• Two RCPs are operating.

• Reports loop delta T less than 10°F.

1$ Reports value and trend of RCS Verifies Containment Integrity safety function is being met by verifying CTMT pressure, temperature, and radiation monitor readings are normal.

and 2300 psia.

subcooling.

EOP 2525 12

SECTION 4 ID N~iiiiher ES04LI3 Revision: 0 Task Instructor Information / Activity Assign Expected Actions Standard Time IDA/Malf May report that B Auxiliary Feed Pump discharge pressure is lowering; pump is degraded.

SPO Complete and report SPTA:

Trip turbine, stop valves closed, MWe indicate 0, and 8T&9T open Electrical alignment is as follows:

$r 25A and 25B are deenergized

$hr 24A and 24B are deenergized T% 24C and 24D are energized by their respective Diesel Generators ssk. 20 1 A and 20 1 B are energized

+Y VAlO and VA20 are energized Both SW and RBCCW facilities running Verifies status of Core Heat Removal a$ Reports value and trend of both S/G pressures (880 to 902 psig).

db Reports RCS Tc value and trend.

(530 to 535°F).

+r Reports value and trend of both S/G levels between 40 and 70 or being restored to this band.

ssk. Reports both motor driven Auxiliary Feed Pumps operating.

A Concurs with US report of subcooling value.

0 0

EOP 2525

SECTION 4 ID Number ES04LI3 Revision: 0

'Task Time IDAiMalf Instructor Information / Activity Assign Expected Actions Stand al-d IAR10 (Open)

When dispatched as the PEO, after 5-10 minutes, report that Station Air has been cross tied with Unit 3.

T& Dispatches a PEO to align Station with Unit 3 and cross ties Station Air with Instrument Air.

When queried, report completion and verification of subsequent actions.

SPO OP 2260 PPO /

SPO Refers to Diagnostic Flow Chart and determines that EOP 2528, Loss of Off Site Power/Loss of Forced Circulation is the appropriate procedure.

us EOP 2525 USISTA Announces and opens Vacuum Breaker, AR-1 7 Opens subcooling valve, HD-106 Stops both Heater Drains Pumps Isolated both Main Feed Pumps Ensures only one Condensate Pump is running Verifies Instrument Air pressure is >90 Psig Performs subsequent actions:

1 EOP2525 0

a Directs the performance of Safety Function Status Checks for EOP 2528 EOP 2528 ETJ 1 14

SECTION 4 ID Number ES04LI3 Revision: 0 Task Time IDA/Malf Instructor Information / Activity Assign Expected Actions Standarcl

~

T4 EDO5C Event is classified as an Unusual Event, Delta-One, based on PU 1, Loss of Off Site Power for greater than 15 minutes.

While the SPO is verifying MSIV closure, insert a malfunction to cause an overload trip of Bus 24C.

USISM us us SPO Crew SPO us Ensure event is classified.

Open place keeper and enter EOP entry time Return Master Silence switch to Normal Direct SPO to:

0 Close both MSIVs 0

Ensure both MSIV bypass valves are closed.

Open AR-17, Condenser Vacuum Breaker Verifies:

Both MSIVs are closed.

0 Both MSIV Bypass Valves are closed.

AR-17, Vacuum Breaker is open.

Observe indications for the loss of Bus 24C.

Observes A DG running with NO cooling water and emergency trips A DG.

Inform the crew that a significant change in plant conditions requires the Diagnostic Flow Chart to be performed again.

EOP 252s EOP 2528 EOP 2528 EOP 2528 TM 7, EM 1, MA 2 MP-16 OP 2260 EOP 2525 OP 2260 15

SECTTON 4 1D Number ES04LI3 Revision: 0 Task Standard Time IDA/Malf Instructor Information / Activitir Assign Expected Actions SPO Crew us USISTA 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 be stopped.

HIC-4165, Tavg Controller placed in Manual and closed.

Both Pressurizer Spray Valves, RC-1 OOE and RC-1 OOF in Manual and closed.

Secures all RCPs.

Places NIC-4165, Tavg Controller, in Manual and closed.

Places both Pressurizer Spray Valves, KC-1 OOE and RC-1 OOF in Manual and closed.

MP 14 OP 2260 EU 2 OP 2260 EOP 2537 EOP 2537 EOP 2537 16

SECTION 4 ID Number ES04L13 Revision: 0 Task Time ID A/Mal f Instructor Information / Activity Assign 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 > 5 O F rise in Tc.

CT-2 C HPSI Pump must be started prior to opening the PORVs.

PORV Block Valve, RC-403, is deenergized (has NO open indication). but will remain open when deenergized.

us SPO

~

Directs the PPO to initiate Once-Thru-Cooling Initiates Once-Thru-Cooling by the following:

Turns off both Proportional Heaters.

Places all Backup Heaters in Pull-To-Lock.

Opens both Atmospheric Dump Valves Manually actuates SIAS.

Ensures HPSI Pumps have started.

o Recognizes C HPSI Pump did NOT start and manually 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.

Informs US when complete.

EOP2537 EC 1 EOP 2537 CT-1 CT-2 17

m 3

SECTION 4

Title:

Simulator Evaluation ID Number:

ES04LI3 Revision:

0 CRITICAL TASKS CT-1 Once-Thru-Cooling must be initiated prior to reaching 70 inches in the lowest Steam Generator or when a >S°F uncontrolled rise in Tc is observed.

CT-2 C HPSI Pump must be started prior to opening the PORVs.

19

SECTION 5 SCENARIO INITIAL CONDITIONS

Title:

Simulator Evaluation TD Number:

ES04LI3 Revision:

0 Initial Conditions 0

0 0

0 0

0 0

0 0

0 100 % power, BOL, Equilibrium Xenon 120 1 ppm boron Blend ratio - 3.4: 1 SG Blowdown - 40 gpni 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 iiiont lis.

Containment pressure is 2 1. Conditions have been verified as acceptable to depressurize Containment.

A work control staff is available to perform tasks outside of the Control Room.

Out of Service Equipment 0

0 The Turbine Driven Auxiliary Feed Pump is out of service for a bearing replacement.

Radwaste Fan, F-16 is out of service for filter replacement.

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.

20

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 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.

1 Test Run:

The scenario contained in the guide has been test run on the simulator. Simulator response is reasonable and as expected.

21

MI? SIMULATOR TRAINING SHIFT TURNOVER REPORT DATE-TIME Today 0515 PREPARED BY SHIFT Unit Supervisor /NIGHT Shift 18:OO - 06:OO PLAET STA TUS:

MODE: 1 RXPOUER:

I %

separately)

Date

~roday fodiiy I-otla!

Today kEGA ltrA 7-73.. Thermal: m M W T H PZR PRESS: 2250 psia Electric: U M W e RCS T-A IE:

=degrees F

RCS LL4kGE:

Identified: u p i n PROTECTED:

Train/Facility Unidentified: M g p m Date/Time:Today 00 15 21 (RED)

Time LCO Action Action Requirement Equipment Reason 0430 3.7. I.2

a.

With one Auxiliary Feed Pump inoperable, Terry Turbine Terry Turbine tagged restore the required Auxiliary Feed Pumps to OPERABLE 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 HOI 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 IiOT SHUTDOWN within the follo\\eiiig 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Actions h. 1. h.2 for tire areas R-l and R-13.

location. perform actions b. I and h. 1 for tire areas R-3, R-l I. R-16, and R-17.

pcrforin actions b. 1 and b. I for fire areas R-

1. R-2, and R-13.

for bearing replacement 0430

7. I.15. item A

b. I and With valw inoperable froin C-10, perform SV-4188. AFW Terry Turbine tagged 0430

7. I, 15, item B b.1 and With Pump/l~urliine inoperable. from either P-4 and 1-1-2 I AFW Terry Turbine tagged b.2 b.2 Steam Supply Valve for bearin2 replacement I%inip and Turbine for bearing replaccment Governor Control Steam Supply Valve from SG 2, MO\\

0430 7.1.15. item C

b. I and With the valve closed or disconnect closed, 2-MS-202. AFW Ierry Turbine tagged b.2 for hearing replacement Action Rea uirement LCO I Action I Eauinment I Reason Infinite action: Establish hourly fire watch.

I TRMAS 3.7.10 I I

I See AIL I

See Active Impairment List.

Infinite action: Attachment I of OP 2301A I TSAS 3.3.3.8 I d3 I

RC-200 I

Failed SP 24 1 OA EVOLUTIONS IN PROGRESS & NOTES The I O 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 nionths. Chemical use has been prohibited in the Enclosure Building for the past week.

OD COMPENSATORY ACTIONS/ Temp LOGS (Bold: Tech Specs, Italics: TRM)

I Reference /Dote OP 23 14B Today Power 100 Yo lave 572 deg F Unit 2 Chemistry ON-LINE STATUS REPORT Flouride 0.81 ppb Chloride 1.75 ppb REACTOR COOLANT Time 06:25 Parameter Reading

]I Parameter Reading I Boron 1201 ppm 11 Oxygen

<5 pp b I

I ~ ~ c n t ~

I M o :

/I 3.4 : I I

22

Attachment SCENARIO ATTRIBUTES CHECKLIST Scenario

Title:

LOIT Simulator Evaluation Number:

ES04L13 Technical Re\\:iewer:

R. J. Ashey Date:

12/6/04 QUALITATIVE ATTRIBUTES Y

1.

Y

2.

Y

3.

Y

4.

Y

5.

Y

6.

N/A 7.

Y

8.

Y

9.

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 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)

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.

Sequencingltiming 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.

23

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.

2.

3.

4.

5.

6.

7.

8 9

Total Malfunctions (TM) - Include EMS - (5 - 8)

1. Loss of the PPC

2. Fail Channel C Pressurizer pressure transmitter low

3. Degrading Condenser vacuum

4. Loss of Condenser vacuum

5. Loss of RSST

6. Degradation of 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) 7. 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)

I.

Transition from EOP 2525 to EOP 2528

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) 8 2

2 2

2 1

2

1. Initiate Once-Thru-Cooling prior to reaching 70 inches in the lowest Steam Generator or when a >5F uncontrolled rise in Tc is observed.

2. Start C HPSl Pump prior to RCS pressure rising above 1200 psia after the PORVs are opened.

Approximate Scenario Run Time: 60 to 90 min.

Total 75 Technical Specifications exercised during the scenario.

(Y/N)

Y 24

IC-90 ES04L13 Load Limit Pot Setting = 5.85 A

B C

D AS1 Upper 4.68 4.65 4.66 4.63 AS1 Lower 4.85 4.72 4.76 4.74 Nuclear Power 4.66 4.988 4.80 4.85 AT Power 3.90 4.10 3.92 4.07 Tcold Cal.

4.80 4.80 4.80 4.90