ML022140041

From kanterella
Jump to navigation Jump to search
Final As-Administered Scenarios for the LaSalle Initial Examination - April 2002
ML022140041
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 04/08/2002
From: Bielby M
NRC/RGN-III/DRS/OLB
To:
References
ER-02-301
Download: ML022140041 (56)
v • d • e


Text

FINAL AS-ADMINISTERED SCENARIOS FOR THE LASALLE INITIAL EXAMINATION - APRIL 2002

LaSalle County Station Operations Scenario #1 Exam Date: April 8, 2002 Developed By: Raymond Keith Walton Date 3/24/2002

ScCnario #1 NARRATIVE

SUMMARY

The unit is at 80% power and 1091, FCL. Perform IIPCS surveillance test p-: LOS-HP-Q I, followed by a failure of the CRD FCV failing closed. A high suction strainc: -:,fferential pressure condition results in operators tripping the 'A' RBCCW pump and starting tl,- -:andby RBCCW pump. An operator in the field reports a steam leak from the 'B' high pressut.-: eedwater heater room. This requires isolating the feedwater heater and dropping power usin,- -oth CRAM rods and recirculation flow. This is followed by a feedwater line break inside the steu::: tunnel. Bus 143 experiences an overload condition rendering HPCS unavailable.

Scenario segments

  • Perform HPCS Surveillance Test IAW LOS -HP-Q I
  • 1A RBCCW pump Suction Strainer high d/p
  • Steam leak from 'B' HP Feedwater heater room requires isolating the 3' HP heater
  • Loss of FW heating requires reduction in power from CRAM rods and :ecirc flow
  • Bus 143 over current condition - HPCS unavailable Needed to Accomplish this Scenario:
  • Partially completed copy of LOS-HP-Q 1, Attachment 1A up to Step A. 10. (Crew starts at Step A. 10).

PALasalle EXaUII\SCcIaU ioi I .uo,.2 2

S Ce111 i*( # 1I a

Facility: LaSalle County Station Scenario No.: 1 Op-Test No.: 2002301 Examiners: Operators:

Initial Conditions: Reactor power nat.80% and 109% FCL Turnover: Perform I- PCS Survs-e lance Test, LOS-HPQ1 Event Malf. Event Event No. No. Type* Description 1 N Pe-form HPCS Surveillance Test, LOS-HP-Q1 (BOP) 2 C C2 D FCV Fails Closed (produces a CRD High Temp alarm)

(RO) 3 C 1 . RBCCW Pump Suction Strainer High D/P (with slowly (BOP) dereasing discharge pressure to alarm setpoint, 53 psig) 4 C Ca I from field of steam leak in HP FW heater bay, operator (BOP) c':ses ES001B, HP FW htr B inlet vlv.

5 R RO Inserts CRAM Rods and/or CRAM rods lAW LOP-HD-05 (RO) 6 C Csqtrol Rod has Collet failure, rod drifts out of core. RO (RO) r-.st hold rod in button until rod is scrammed locally 7 M F,'! Line Break in Steam Tunnel, Failure to Auto Scram 8 C B-s 143 Overcurrent, Results in Loss of HPCS I I I

  • (N)ormal, (R)eactivity, (I)nst,.!ment, (C)omponent, (M)ajor LGA-001, RPV Control LGA-002, Secondary Containment control LGA-004, RPV Blowdown P:\Lasallc Exani\Sccnario I r l.doc 3

I'mtrio 41 SHIFT TURNOVER INFORMATION

-, Day of week and shift

  • Today, Day Shift

- Weather conditions'

  • Warm
  • Windy (Plant power levels)
  • Unit I - 80/(YPoer. 109% FCL + Unit 2- 100 §/ Power. 0.5 5 FCIL

+ 2960 MWt + 3489 MWt

  • 945 MWe + I189 MWe
  • 74 Mlbm/hr CORE FLOW + 93 Mlbm/hr CORE FLOW Thermal Limit Problems/Power Evolutions
  • None + None Existing LCOs, date of next surveillance
  • fHPCS Inoperable for Testing + None LOSs in progress or major maintenance
  • Start LOS-HP-Q1. HPCS Test at Attachment + None I A step A. 10

= Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment

+ None Comments, evolutions, problems, etc.

+ Online Risk is Yellow S" UOnline Safety is Green

?: Lasalle Exan\Scenari o Ir I.doc 4

SceCnaro I th I SIMULIATOR SETUP A. CARDS/TAGS TO BE HUNG:

B. MISCELLANEOUS:

Timeclock Board

1. HPCS/R 3.5.1 condition E. Make TC Board and turnover sheets reflect HPCS made inoperable to perform surveillance test.

C. TURNOVER INSTRUCTIONS:

  • Gather the crew in an appropriate classroom setting and turnover sheet to provide a shift turnover. Stress the following items:
1. Unit assist NSO will start HPCS pump lAW LOS-HP-QI, Attachment I A. Step A.10
2. Complete Briefs for LOS-HP-Q 1 prior to taking watch.
3. HPCS is inoperable due to testing
4. Reactor power 80%, on the 109% FCL
5. Unit 2 at Full Power PA:Lasallc ExanA\ScCrwio I r I 5tw 5

sc~lmilo #I Event 1-1 Initiation: Following Shift turnover on the \i 2al of lead cxaZm1inaer Time/Notes Expected Crew Response

__HPCS Pump Quarterly_ Surveillance Test (LOS-HP-Q1)

Reactor Operator Response:

Monitors panel 603 fori abnorrnal/unusmlal conditions and alarms.

BOP Operator Response:

Per LOS-HP-Q 1. Attachment IA. Step A. 10:

"* START HPCS pump from H 1P601.

"* VERIFY E22-F012, HPCS MIn Flow vale opens.

"* Throttle open E22-F023, FIPCS Test to SP valve, establish 6300 gpm flow rate as indicated on E22-R603.

"* Verify E22-FO 12, HPCS Min flow valve closes.

"* Local Operation to prevent overpressurization of HPCI water leg pump

"* Verify lB DG Cooling water pump ON

"* Verify HPCS Diesel Gen. Cooling water ptump hand switch in NORMAL AFTER START.

"* NLO to VERIFY HPCS cubicle cooler fan is on

"* Using E22-F023, HPCS TEST TO SP VL\V. set flow 6300 to 6400 GPM as indicated on E22-R603 and record flow.

Unit Supervisor Response:

  • Directs HPCS testing TERMINUS: Crew gets HPCS running at rated flow.

P:Ja'salle Exam\Sccririo I r I .doc 6

'*cna C11 #I Event 1-2 Initiation: After crew gets HPCS runn in and cue from lead examiner.

Time/Notes Expected Crew Response Key Event: CRD FCV Fails Closed (CRD 10-47)

P603-A403, CRD Hi Temp Reactor'Operator Response:

P:- P603-A403:

NOTIFY Unit Supervisor.

N

  • .: Control Room Panel I H 13-P603. VERIFY CRD Cooling Water

-,v is in normal range. (no, no flow)

ST.-tnsfers to LOA-RD-101, Step B.2, (FCV Failure):

CHECK DRIFT lights - OFF (ves)

CHECK the following:

"* CRD flow < 63 gpm. (no)

"* Cooling header dp <30 psid.

"* TI-IROTTLE OPEN Drive Water PCV ICI 1-F003.

Maintain CRD Flow <63 gpm.

Maintain Cooling header dp<30 psid.

"* T:insfer C 1l-R600 to MANUAL

.- :just 1C1 I-R600 controller output to about 60 gpm.

"* DISPATCH NLO.

BOP Operator Response:

  • \,Vonitors panels for unusual/abnormal alarms/conditions

" A.- Control Room Panel IH22-P007. on CRD/RX Vessel Temperature Recorder, DETERMINEs CRD 10-47 initiated high temp. alarm.

Unit Supervisor Response:

SP,?sitions himself as command authority on the unit.

Acknowledges immediate operator actions and directs subsequent A

-,,Jtions.

  • Requests an additional NSO to the control room for manual FW control.
  • Enforces Ops expectations and standards.

.ithorizes A performing LOA-RD-101.

TERMINUS: Redaces CRD flow and pressure to normal bands.

tP\t.asallc Fxam\Scermriolrr..

I 7

'1

s. ce -ll-* I Time/Notes inEvent 1-3 ....Initiation: After events Expected Crew Response I-I & 1-2 completed, on signal from lead e xanilner IA RBCCW Pump Trouble 1PM 10J-A 102, RBCCW Pump Suction Strainer D/P High IPM 1OJ-A201, RBCCW Pmp Discharge Pressure Low BOP Operator Response:

Responds to annunciator PM 10J-A 102 & PM IOJ-A20 i:

  • CHECK RBCCW pump discharge pressure is equal to or less than setpoint.
  • START standby RBCCW pump per LOP-WR-02.
  • Dispatch an operator to check on proper operations.

Per LOP-WR-02, E.2. "Startup and Operation of RBCCW System:"

  • Observe 'B' RBCCW pump amperes increase to 145 - 172 amps on 11 WRO05 on PM1OJ panel.
  • Observe 'B' RBCCW pump discharge header pressure increase to 52 80 psig on PI-WR008 on PMIOJ panel.
  • STOP the WA' RBCCW pump after the system pressure stabilizes.
  • Observes that RBCCW discharge header pressure returns to normal.

Reactor Operator Response:

  • Monitors panels for abnormal/unusual conditions/alarms.

Unit Supervisor Response:

0 Acknowledges alarm.

o Refers to LOA-WR-101.

Terminus: Starts standby RBCCW pump.

CUE: Lead Examiner cue simulator operator to call in steam leak on HP FW htr room midway during Key Event 1-3.

P:\ýISýIlC F:.X'nM1\.SCCnTi[ I I IrI .doc 8

Sccu-i 10o# 1 Event 1-4 & 1-5 Initiation: After E\ cn t 1-3 completed, after cueIrom leadcxam:

I Time/Notes Expected Crew Response Steam Leak in High Pressure Feedwater Heater Room Decrease Reactor Power using CRAM Rods and RR Flow Reactor Operator Response:

"* Dispatch Field Supv to investigate.

"* RedLIces power IAW LGP-3-1 using either RR and/or CRAM ds.

"* Lowers RR flow to 49 Mlbm/hr JAW LOA-HD- 101, Step B.5

1. Decrease core flow to 60 Mlbm/hr per LOP-RR-107:

"* At a rate up to 300 MWe/hour or at a higher rate specified . QNE

"* Verify manual light on recirculation loop flow controller V \

station A/B is ON.

"* Change floýv evenly in both loops by pressing LOWER bu:K.n and observing flow indication to flow controller M/A station.

Inserts 4 CRAN I rods IAW LOA-HD- 101. Fig 1.

MONITORS FW Temp. decrease after isolating HP FW htr.

M

  • Runs OD-20 and /or OD-3 core monitoring codes.

BOP Operator Response:

Pet LOP-HD-05. E.2 and/or LOA-HD-101, B. 12:

"* OPEN ES003, 16A/B High Pressure Extraction Steam Spill \.

"* CLOSE ESO01B. High Pressure Heater 16B Extraction Stea. :ilet vlv.

Unit Supervisor Response:

"* After Field Supv calls back, directs isolating steam to FW he:.r 16B lAW LOP-HD-05, Step E.2. "Isolating HP FW Heaters Durinn Normal Power Operation."

"* Directs lowering reactor power using RR flow and/or CRAM -,Is as specified by QNE.

"* Calls RP to restrict access to area.

"* Contact QNE to adjust MCPR TERMINUS: Crew isolates HP FW heater and decreases power.

P:\[lasalle Exar\"\Scenntrio Ir 1.doc 9

Scenario -I Event 1-6 Initiation: A ftcr Evcnt\ -- ,s 5 completed, al tet cue from lead examiner Tline/Notes - \ pected Crew Response Control Rod Experience-s Collet Failure P603-A504: Cont-ý. Rod Drive Drift Alarm (CRD 22-47)

P603-A406: RBN.J E:iInop P603-A308: Rod C;-:, Block

  • 1 -

Reactor Operator Resporne:

Per P603-A504:

  • Enter LOA-RD- 101. -t trol Rod Drive Abnormal Procedure" Per LOA-RD- 101, S. it B. 1:
  • SELECT drifting roc' -RD 22-47)

"* CHECK insert Block 1._:it OFF at rod select matrix (no)

"* Remove Insert Block - either Bypassing RWM or Disable blocks to 100% (if above LPSP

"* INSERT rod to posit. "0 (full in) 0 Continuously DEW -SS either Notch In PB or Continuous In PB.

"* CHECK drifted cont: --,)d remains at 00 (no)

"* INSERT and HOLD .i ccd control rod at 00 until rod is locally scrammed from HC --. placing both scram test switches in TEST JAW Attachment A , D(A-RD-101.

i BOP Operator Response:

"* Monitors panel for ai: :mal/unusual conditions.

"* RESET rod drift per... .edure to monitor for other rod drifts.

Unit Supervisor Respon't:

0 Orders Scramming o: ctor if more than one rod drifts.

"* Orders locally scram---i., drifted CRD.

"* REFERS to Tech Sp, 3. 1.3

"* Contacts QNE, EvaluL--ý core thermal limits.

TERMINUS: FRO inserts drifted control J-,d. SRO reviews Tech Specs.

P:I, ýilskI l !'IxHm\ScenarioI r I .doc 10

1____

Event 1-7 Initiation: Plantl %criasor afIter cue fromn lead e \an iner Tinle/Notes - Expecteed Crew Re~spons e ____________

Key Event: FW Break in Steam Tunnel I H 13P6C)3-A409l - FW Control Rx Vessel Lo Level 4 1H1I3-P601I-F404 - LD NISL Pipe Tu-nnel Amb Temp Hi I1H1I3-P601I-F405 -LD MSL Pipe Tunnel Diff Temp Hi Reactor Operator Response:

Per LOP-3-2, completes the actions of the Scram Hardcard and follow,' uIP with the procedure:

  • ARM and DEPRESS Scramn Pu1shbuttons
  • PLACE Reactor Mode Switch in SHUTDOWVN
  • INSERT IRNTs and SRMs
  • INFORM ]Unit Suipervisor Of Rod Status and Reactor Power
  • Operate EW as necessary within the level bank- 32 to 45 inches
  • REPORT to the Unit Super-visor the sta~tuS (an1d trend) of RPV Lev el and Pressure
  • VERIFY Reactor Recirculation Pumrps have dowvnshifted
  • STABILIZE Reactor PreCssure- < 1020 psigy
  • GO TO Step E. 2) of LGP-3 -21 BOP Operator Response:
  • Trip I TDRFP and close discharge valve.
  • Verify Main Generator/Turbine Trip
  • STABILIZE Reactor Pressure <1020 psigr
  • GO TO Step E. 2) of LGP-3-2 Unit Supervisor Response:

0 Orders scram of reactor and directs actions per LGP-3-2 (See RO and BOP operator responses above) tPAt sal ic 1Pxan\Sccnario Iir .doc tI I

en ii n I Key Event 1-8 Initiation: Initiate after Main Tut hine Trips.

Time/Notes Expected Crew Response Key Event 1-7 FW Break in Steam Tunnel (Continued)

Bus 143-1 Overcurrent Condition Panel Operator Response:

Per LGA-00 I RPV Level Control Lee

  • CONTROL Level I1 to 59.5 inches using ECCS Systems
  • Isolates leak by shutting RT-040, (RWCLU Isolation vlv), shuts FW065A & B (Feedwater isolation valves).
  • When level can't be held >- 150 inches, then:
  • Maximize injection with all Preferired Injection
  • WAIT until level drops to -150 inches on WR then ENTER LGA-004 RPV Pressure Control Leg 0 Stabilize Pressure Below 1059 psig 0 Depressurize RPV using Turbine Bypass Valves at <I 00°F/hour NOTE: If the crew is aggressive and uses the "anticipate a blowdown" override of LGA-001, a rapid depressurization with the Turbine Bypass Valves will allow LPCS injection and level recovery before RPV level drops to -150 inches.

cCRITICAL Panel Operator Response:

T REPORTS that HPCS failed to start, initiates RCIC for level control.

T 1 Identifies that Bus 143Y has overcurrent condition.

  • Does NOT attempt to start HPCS.
  • Enters LOA-AP-103, Loss of Bus 143 Abnormal Procedure
1. DISPATCHES operator to Bus 143Y.

Unit Supervisor Response:

"* Directs actions per LGA-001 (See RO and BOP Operator Responses above)

"* Directs maximum injection with CRD pump JAW LGA-RD-101.

P ':\ iI.all I, 1 " \ rn\I c l Iio0 r l .d11- Ic i/

)Scenaio, 1 Tinme/Notes Expected Crew Respuon-,

K- Event 1-7. FW Break in Steam Tunnel (continued)

Panel Operator Response:

Per [,C A-002

"* OPERA-\TE Area Coolers and VR if possible

"* OPERATE Sump Pumps to hold sump level -w overflowino

" If any .Lrea Temperature or Radiation is abo\ ',.lax Norriial or if a sump is ovci flowing, then:

"* ISOLATE discharges into the area excej-ý those needed to fight fires or needed by other LGAs (crew she. _:_olate FW, CB/CD and RT)

"* NIONITOR release rates for LGA-009 c:-e:: Conditions

"* WAIT until 2 or more areas are greater t. Mlax Safe and then:

"* SHUTDOWN the Reactor (LGP-3-2

"* ENTER LGA-004 (Blowdown)

Per CLGA-004 VERIFY Drywell Pressure is greater than I.- .Nig (no)

S VERIFY Suppression Pool Level is greater --.- 18 feet (no)

CRITICAL S Anticipates Blowdown and Depressurize RP'. Ning Turbine Bypass STEPS Valves at <100°F/hour or Initiates ADS.

0 WAIT until Shutdown Cooling Interlocks cl. "135 psig) 0 COOLDOWN to Cold Shutdown using Shk-.v n Cooling (per LOP-RH-07)

Unit Supervisor Response:

  • Directs actions per LGA-002, (See Operator 7,.,ponse above)
  • Directs actions per LGA-004, (See Operator 7F' ponse above)

Terminating 0 Restores and maintains RPV level 1.1 - 59.5 Conditions

  • Commences cooldown at <100°F/Hr if Emerczncy Depressurization was not required.

0 Cue fiori lead examiner i' [ý JC Exam\Scenall I d)c

SIMULATOR OPERATOR IMF r)S 13 off Fvent2: ior p3e0Lald 060 Event 3: WR pump dischati .lke - throttle to -35z, for alarm over 4 minutes.

Inf R1307 on Alter pump swap: dc. -" r1307 & open valve fully.

If crew slow to react. r._:Ilp disch pressure to low trip setpoint -50 psig.

Events 3 & 4 Timing: Lead Fxaminer should cue when to have simulator operator make the call as RP from the '4' line. This will give the field Supv. or Operator dispatched time to investigate.

Event 4: Call as RPT that 4 monitors going off Field Sup dispatched -am leak coming flrOm under 'B' HP FW heat er door. Steam leak in valve room If: around ESOG LB. Need to isolate-soon.

As QNE: Recommern,  :-,,ducing power to less than 60 Mlbrn/hr core f low.

Event 5: No actions Event 6: Collet failure - CR.-.\, rods not available, Select rod NOT full out, Crd 22-47 mrd 097 -- 23 mrd 096 Event 7: imf mcf 033 100LS, Imfmcf 111 1 Event 8: imfmcc021 after-. :inetrips Fail RPS & ARI ALT -) imf mrp 005 P' \i -11c [ ,x ml\sce lrit[o!( , , , t,

]4

Scenario #2 L aSalle County Station Operations Scenario #2 April 8, 2002 Developed By: Raymond Keith Walton Date March 25, 2002 PA\Lsalle Exam\Scc ni 11

Scenario f12 NARRATrIVE SuMMIARY RacItor is at 100/ power. Operators will place 'B' RI IR in sUpplrCSionl pool cooling Clue to leaking SRV. C APRM will fail high causing a halt scram. Rcactor Building Ventilation CXhaLtSt fan will trip. An SRV will stick open but will be reseated after operators remove fu,,

The FCV on one RR pump fails open. Subsequent high vibration and a Cooler leak on the RR pure1) equires the operators to manually trip the RR pump. Finally, a small LOCA requires L cntry to stabilize the plant.

Scenario segments

  • Place 'B" RHR in Suppression Pool cooling Clue to leaking SRV
  • SRV opens, operator closes valve, will reopen. until operators remove fuses 0 Reduce reactor power 100 Mwe using recirc flow
  • I A RR FCV Fails Open a I A RR Pump High Vibration wv/Winding leakage/ sirlgle loop operations

'B' Train of drywell spray fails clue to stuck closed valve P'\I asallc I'xam\Sccni ioai I.d, , -)

Scenario 1-2 Facility: LaSalle County Station Scenario Nc 2 Op-Test No.: 2002301 Examiners: Ope- :ors:

Initial Conditions: 100% power.

Turnover: Place 'B' RHR in Suppression Pool C::ling due to a leaking SRV. 1B VP Chiller is OOS Event Malf. Event Event No. No. Type* Description 1 N Place 'B' RHR ir Sjppression Pool Cooling due to leaking (BOP) SRV 2 C Reactor Buildinc *'entilation Supply Damper Fails closed (BOP) 3 C Stuck Open SR\ Dperator closes valve, but 30 seconds (BOP) later, valve reopens. Valve remains closed after pulling fuses.

4 R Reduce Reactor Dawer 100 Mwe using Recirculation Flow (RO) control.

5 I 1A Recirculation -CV Fails Open (RO) 6 C 1A Recirculation DJmp High Vibration/Winding Leak (RO) Manual Trip of 1-' Recirculation pump - Single Loop Ops 7 M Small Break LOCA Inside Primary Containment 8 C 'B' Train of Drywv- Spray Fails due to stuck closed valve

  • (N)ormal, (R)eactivity, (1)nstrL-ent, (C)omponent, (M)ajor LGA-001, RPV Control LGA-003, Prim-rv C-,ninment PALLýýallc , ýju' U

Scenario #2 SHIFT TURNOVER INFORMATION Day of we. __::d slfitt

)iy Shift

~ Weather c. _ ions

_,_ld-SLH11nllcF

  • Wan._
  • Wind,

= (Plant po\\,

+ Unit I P[ower, 095* :C. Unit 2 - 100 1c Power. 108.5c/ FCI

+ 3489, 3489 MWt

  • 1189'. 1189 MWe
  • 93 N .
  • CORP FL O\V 93 Mlhm/hr CORE FLOW SThermal L:: "Problerns/Powcr Evolutions
  • , None
  • None

= Existing LC ,date of next surveillance

  • Nonc None

= LOSs in pr *-ess or major maintenance

  • . Place RHR in Suppression Pool Cooling
  • None mode _ o leaking SRV.

Equipment be taken out of or returned to service this shift/maintenance on major plant equipment

+ I3V" "1er is OOS

  • None
  • Mmin

'r perforn-ing Ventilation Q; tly

  • . tiowns.

SConant <. l,:*ions, problems, etc

+ , .' ' Grceen

  • Online Risk ., ,

i .d...... il,,. l'xa+......

4

Scenario #2 SIMULAITOR SEITTUP A. CARDS/TAGS To BE HtUNG:

  • 13 VP Chillcr Beaker OOS B. MISCELLANEOUS:

Reactor Building Ventilation LinCup:

A & B Exhaust fans in operation A & B Supply fans in opeiration C. TURNOVER INSTRUCTIONS:

  • Gather the crew in an appropriate classroom setting, use the SRO and NSO turnover sheets to provide a shift turnover. Stress the following itcms:

I. Unit I is at 100% power, 109%/ Flow Control Rod Line.

2. Place 'B' RHR in Suppression Pool Cooling, in anticipating of running of RCIC
3. No Time Clocks in effect.
4. 1B VP Chiller OOS due to freon leak
5. Unit 2 is at rated power.
6. Do pre-evolutionary briefs before taking the watch.

' .i 1()'I j oc

Scenario #2 Kex Event 2-1 Initiation: After completion )I shift turnover and after iroin lead examiner.

Time/Notes Expectedl C~r-ewRe o'ns Start RHR Service Water BOP Operator Response:

Starts RHR Service Water per LOP-RH-05

  • PLACE the appropriate Thernmal Overload Bypass . h to BYPASS
  • LOG positioning of O/L Bypass switch in the Unit L
  • If required. START an S hour clock
  • MAKE PA Announcement and START the first RHF -,VS Pump C/D
  • OPEN the IE12-F068B, Heat Exchanger Outlet Val,
  • When RHR-WS Flow is >3000 gpm, then START t?. -cond Pump DIC
  • When IE12-F068B is full open, then CHECK Flow i. >7400 gpm.
  • PLACE the appropriate Thermal Overload Bypass ,. .- h in NORMAL
  • LOG positioning of O/L Bypass switch in Unit Log
  • If started, STOP the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> clock
  • NOTIFY Chemistry to take required samples RHR-\ . .Ssamples
  • Dispatch an NLO to locally place the strainer back\\. in AUTO
  • Dispatch an NLO to locally VERIFY the CSCS Cub: . Fan is running
  • VERIFY the RHR-WS Strainer high differential pre- -:.e alarm is clear I

Reactor Operator Response:

  • Monitors Reactor Power and P603 panel for abnornm, .-nusual conditions I --

i Unit Supervisor Response:

  • Directs starting Suppression Pool Cooling i'. \l .I sa l bi ,I...

, I)2 1 l d G;

Scenario #2 Time/Notes Expected Cre Resnone Key Event 2-1 I Expected Crew ReSDOnSe Start RHR 'B' in Suppression Pool Cooling (cont'd) -

I -

1OP Operitor Response Start RHR .. Suppression Pool Cooling Mode pci LOP-RI-113

"* PLACE -- propriate Thermal Overload Bypass switch in BYPASS

"* VERIF' CLOSED 1E12-FO06B

"* VERIF: ,-PEN 1E12-F004B, -F047B, and -F048B

"* MAKE -...announcement and START 11B RIIR Pump

"* TIHROTTLE OPEN 1E12-F024B to maintain I500 to 7450 gpm

"* TFIRO77LE CLOSED 1E12-F048B

"* THRG77LE 1E12-F003B

"* VERIF': -.ow between 1500 and 7450 gpm (but as high as possible)

"* DispaT:. -n NLO to VERIFY RHR Pump Room Fan STARTS

"* VERIF> Diesel Generator Cooling Water Pump is STARTED

"* PLAC 2 -e O/L Bypass switch back to NORMAL

"* MONIE -R Pool Temperature RO Response:

  • Mon it,:. Reactor Power and P603 panel Unit Super\ isor Response:

0 Direct- .:.arting Suppression Pool Cooling Simulator Operator: When requested, make appropriate field reports that indicate sta---:p of the RHR-WS and RHR Suppression Pool Cooling is normal.

ITERMINUS: RHRSW a "B' RHR operating in Suppression Pool Cooling Mode.

Scenario #2 Kev Event 2-2 Initiation: After completion of [vent 2-I and cue f roni lead cXmliner.

Trime/N otes Expected Crew Response Reactor Building Supply Damper 1VR04YB Trips PM06J-A308: Supply Fans No Air Flow P601-C410, D507, F404: Various Room Temp Hi Alarms BOP Operator Response:

Per PI06J -A308.

0 VERIFY RB Vent Supply Fans Tripped

  • MONITOR Temperatures as needed.

Per LOA-VR- 101:

  • Place VR Exhaust and Supply Fans in PTL position.

BYPASS Trips by installing keys and turning key switches to BYPASS B

position at Panel I [-I 3-P642 to defeat Div 2, Gp I isolation:

1. MSL Pipe Tunnel Diff. Temp. Sig B Bypass Key #85.
2. MSL Pipe Tunnel Diff. Temp. Sig D Bypass Key #87.
3. Start appropriate TS Time Clock.

0 Place key \witches to TEST to defeat RWCU Isolations:

0 Div II RWCU LD Isol Bypass Key 4 to TEST at H 13-P642

  • Div I RWCU LD Isol Bypass Key I to TEST at FI 3-P632
  • Start appropriate TS Time Clock.
  • Operator calls U2 to install MSL pipe Tunnel Diff. Temp Di\ 2 Sig B & D (Keys #85 & 87) installed and placed in BYPASS position.
  • CHECK Div 2 Group I Isolation channels Normal
  • Reset Inboard and Outboard PCIS Isolations for Unit I and Unit 2.

CUE: 1(2)B21H-K7B & K7D logic relays on 1H13-P611 & 2HI3-P611 picked up.

0 CHECKS 1H13-P601-E504 clear.

CUE: 2H13-P601-E504 clear.

  • CHECK I\VR04YA & 04YB and IVR05YA & 05YB dampers open.
  • Restart RB Ventilation Exhaust Fan then supply fan, repeat such that 2 exhaust fans and 2 supply fans operating.
  • CHECK PM06J-A308 and A408 alarms CLEAR.
  • Check RB differential pressure negative.

RO Response:

a Monitors Reactor Power and P603 panel for abnor-mal/tinusual conditions.

Unit Supervisor Response:

  • RE:J."l 'i 'wechSpecs 3.3.6.1 PCI Actions Note 3 (12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> gp I isol.).. i 2II' lhi) for operability
  • Acki;,,,v~cdcs Starting/Stopping TS Time clock for Bypassing Gp I SINIfl ', iI'S aippropriate corrective acti,,i iCoii. ition Report)
  • /\uiIthi ;'Cs entiry into LGA-002, based on varitous room temperature al ,,.,  !

(Aii\ l, P601-C410, D507, F404 i L * . Criew i' ,,- RBR ,ctilation, SRO review., ,l ,.jte Tech Specs.

I. . CC11 )I"' I I .(to(

Scenario #2 Key Event 2-3 Initiation: Aftci comipletion of Event 2-2 and aftel cuC Ifroim lead eXaminer Time/Notes Expected Crew Response Stuck Open SRV (B21-FO13C)

H 13-P601 -E 102, ADS or SRV Leakage H 13-P601 -F201, ADS Valve Fully Open BOP Operator Response:

In response to F1I 13-P601 -F201 alarm:

"* CHECK Dry\\ cll Pressure, Reactor Vessel Level and low pressure ECCS system is running to \erify and ADS is required to be open.

(Not IrquirLied to he open)

"* Refers to IOA-S RV- 101, (Stuck Open SRV):

I. IDENTIFY SRV haS spuriously actuated or is stuck OPEN

2. DECLAR- SRV B2 I-F01 3C mop
3. Cycle B2 1+-0 13C control Switch from AUTO to OPEN and back to AUTO.
4. CHECK B2 1-101 3C open (SRV closed but will reopen -30 sec later).
5. Monitor Suppiressioni Pool water temperature every 5 niln.
6. REFER to Table I of LOA-SRV-101 to identify fuses associated with stuck open B2 1-FI01 3C
7. Have Aux Operator remove fuses F3A, F4A, F5A, & F6A in Panel H 13 P628 in A\u\ilirary Electric Equipment Room
8. Have AuXiliary Operator remove fuses F5B & F6B in Panel H13-P631 in Auxiliary [-lectric Equipment Room.
9. CHECK B_21FI-I*3C OPEN (SRV indicates closed)
10. Wait I minute then replace fuses removed in steps 8 and 9.
11. CHECK Open B2 I-FO*3C (SRV indicates open)
12. Remove fuses installed in step 10.

RO Response:

"* Monitors Reactor Power and P603 panel for abnormal/unusual conditions.

"* REDUCE Generator Load to maintain Rx power < 100%.

(See Key' Event 2-4)

Unit Supervisor Response:

  • REFERS to Tech Specs 3.4.4, 3.5.1, 3.6.1.6 (after 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) for operahility.
  • Aiceptable actions should include:
1. REFERS to TRM Section 3.3.*.
2. .'.,, 0 i/os entry into I.J \ ' i,ih1141 room tcpi'iti1 "iURNMINUS: After SRO reviews appropriate Tech',i,-;i Specifications i' ,. ,'IeC Fxý, IAS c-Im Iio, II .ýhw

Scenario #2

[ Event 2-4 Initiation: After event 2-3 complc- .aId at ter cue ur(n le]ad e x :m ner Time/Notes Expected (re\y Response Power Decrease with Recirculation Flow Reactor Operator Response:

Takes actions to establish a pov~ci :- per LGP 1 and LOP-RR-07. to decrease load 100 Mwe:

"* VERIFY Manual light on Reci:, -.,op Flow Controller M/A station A/B is ON.

"* Change Flow evenly in both lo, :)-, pressing LOWER button and observing flow indication to FH .,ontroller M/A Stations.

"* REDUCE core flow to approx\ I.,y (2) Mlb m/hour using Attachment C unless otherwvise _ tered by the QNE

"* At a rate up to 100 MWe/hour

"* At a higher rate specified by a - E, BOP Operator Response:

  • MAINTAIN condensate flow t.r -.:eh the polishers per LOP-CD-03 Unit Supervisor Response:

"* DIRECTS crew to reduce po,\ - <100 MWe/hour using recirculation flow control.

"* Notifies Electric Operations of'. - .er reduction TERMINUS: Clearly observable plant response .: -n change in power level.

Pýd -ýIhc [I,

Scenario -:Z 2, -

Key E'Nc n t Initiation: Af[ter Event 2-4 completes and crIe firo1n lead examinel.

Time/Notets Expected Crew Response LB RR FCV Fails Open I H 13-P602-B 101: 1B RR Flow Control Vlv Trouble Reactor Operator Response:

Takes actions per LOA-RR-101 for RR FCV failing OPEN

  • CHECK FCV position is STABLE (no)
  • PRESS HPU I B TRIP pushbutton to lock up I B RR FCV.
  • CHECK recirculation loop jet pump flows LESS THAN T/S MISMATCH (w/in 5.425 Mlbm/houIr if core flow is >75.95 Mlbmn/hour. and w/in 10.85 Mlbm/hour it core flow is <75.95 Mlbm/hour) (no)

& If>TS MISMIATCt I:

" Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, either:

o. Restore flow nmismatch. OR
o. REDUCE Power rapidly per LGP 3- 1, including shifting both recirculation pumps to slow speed OR
o. TRIP the low-flow RR pump per step B. 10.4.1

"* START 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time clock either to RESTORE the flow mismatch OR to DECLARE one RR loop Not In Operation per TS 3.4. 1, Condition F.

  • Evaluate Core performance.
  • CHECK IA FCV NOT locked up (IA FCV Motion Inhibit light OFF.)
  • Push RAISE PB at 1A FCV M/A station to reduce mismatch.

BOP Operator Response:

  • Monitors panels for changes in plant conditions Unit Supervisor Response:

"* Starts a 2-hour time clock per Tech Spec 3.4.1 condition F. 1. (2 hrs loop inop)

"* Contacts QNE to evaluate concerns for balancing loop flows.

Simulator Operator: As the QNE, when contacted, tell them you'll check thermal limits and get back to then:.. Wait 10 mini. then report that thermal liiits have NOT been exceeded but would like them to ?:alance flows as soon as possible.

TERMINUS: Crew has taken actions for tl" 7'-,1 RR FCV and SRO has reviewed I aprheable Technical Specifi*i._*,_ __ ____s.

11

Scenario #2 Key Event 2-6 Initiation: After cuC fIom lead examiner and attcrl SRO (IINClNSSCS RR vibration bullet with crew.

Time/Notes Expected Crew Response 1B RR Pump Hi Vibrations / Winding Leak 1H13-P602-B305 lB RR Pmp Mtr Vibr Hi 1H 13-P602-B304 lB RR Prop Mtr CIg Wtr Flow Low/Clr Lkg Reactor Operator Response:

Takes actions per LOR- 1H13-P602-A304 for motor cooling abnormal:

  • CHECK motor bearing temperatures, motor arnp\. and loop flow
  • CHECKS SOR typer for R-points
  • TRIPS RR Pump when both R-points are received (R 1001 and R0998)
  • REFER to LOA-RR- 101, RR System Abnormal.
  • Continue to MONITOR abnormal trends or parameters.

BOP Operator Response:

Takes actions per LOR- 1H13-P602-A305 for RR motor vibrations

  • PUSH Vibration RESET pushbutton
  • If alarm can't be reset IMMEDIATELY NOTIFY System Engineering to MONITOR and EVALUATE
  • CHECK Loose Parts Monitor
  • If abnormal conditions exist IMMEDIATELY trip the pump REFER to LOA-RR- 101.

Unit Supervisor Response:

  • Contacts System Engineering and IMD for assistance

,'-\I ,as:01i, 1-1\.111,\S,- ,, ,, '0r (1 ,C 12

Scenario #2 Time/Notes ILxpccted Crew Response Key Event 2-6 I

Expected Crew Response

- Hi Vibrations/XVinding Leak IA RR Pump (Cont'd) Manual Trip of IA RR Pump I

Reactor Operator Response:

Takes actions per I[OA-RR- 101 step B.2 when directed to manually I: RR pump

"* CHECK at least one RR pump running (yes)

"* PElRFORM Ctre Instability checks while continuing

"* CHI-CK FCI is below 95.217/ (yes)

"* CHIl-(_CK Reactor Power OUTSIDE of Region A (yes)

"* CHICK Reactor Power OUTSIDE of Region B (no)

"* INITI.'T LOS-RR-SRI within 15 minutes per T.S. 3-1 , .

"* INS'RT Ci amtrrays AND (RAISE core flow OR INSF -sequence rods) to IMMEDIATELY EXIT Region B.

"* START 2-hour timcclock per T/S 3.4.1 if required

"* CHFCK APRM Noise <2 x Normal (yes)

"* CHFCK core flow to RIGHT of Natural Circulation line (ye>

"* CHECK LPRM Noise <2 x Normal (yes)

"* CHICK APRM -- OPERABLE APRMs within +/-_2% ofualca aore thermal Pov, Cr.

"* MONITOR and EVAILUATE Core Performance

  • CHECK ecCitculation flow in activ e loop >_21,000 gpm
  • CHFECK SLO condition allowed with existing EOOS
  • CHECK Operating RR Pumnp inl list speed (yes)
  • INITFIATF* actions of T/S 3.4. I lo single loop (REDUCE MCPR ,P[HGR, ADJUST APRM and RBMI setpoints)
  • NOTIFY INID to adjust APRM/RBM Flow Converters
  • DECREASE FCV to minimum on tripped RR pump
  • PLACE all breakers [or tripped pumpqa in PTL (when less than 35
  • REDUCE loop flow to <34.425 gpm
  • MAINTFAIN tripped pump's suction and discharge valves FULL C
  • COMMENCE ILOP-RR- 13 Single Loop Baseline Date
  • CHECK RR Loop AT <50'F t

BOP Operator Response:

  • Assists RO in establishing single loop operations:

"* ISOLATE CPs as needed

"* MAINTAIN Condensate Flow 5,000 to 8,000 gprn.

  • If both TDRFPs are running SHUTDOWN one as time  :- ts.
  • INITIATE special log to monitor loop AT JT3/4it Supervisor Respo',,

Directs actions pci- LOI,-/,,..-101 D

S R I.FERS toTS 3.2.l1, '3 -,.3.1.1,3.3.2.1.

, Contacts Chemisir\ fo! - , power change in I hour TERMINUS. .\(r paat stabilized :.d " *,reviewed applicable Tc*e I, , :ons.

1 dtcl reactor scrams o,; lhii.

0, ,. level.

[>:\l~asalle Fll~l f\k,*'I, lo~c 17

Scenario #2 Key Event 2-7 Initiation: Alter E% 2 6 completed ard after cue from lead CXamliner or after Unit scrams.

Time/Notes Expected Crew Response Small Break LOCA Insi(de Primary Containment IPM 13J-A3 0_ RB North/DW Flr Sump Trouble IPM 13J-A20- DW Cooler Cond Flow Rate Hi IH 13-P603-BS1, I Pri Crnt Pressure Hi/Lo Reactor Operator Response:

Takes actions to marnulally scram per LGP-3-2, completes the actions of the Scram Hardcard and .llows up wxith the procedure when a LOCA is discovered;

"* ARM and DEPRESS Scram Pushbuttons

"* PLACE Reactor \,ode Switch in SHUTDOWN

"* INSERT IRMs :,SRMs

"* CHECK all Con: , Rods in and Po\\ er Decreasing

"* INFORM Unit S :ervisor Of Rod Status and Reactor Power

"* Operate FW as incessary within the level bank 32 to 45 inches

"* REPORT to the L nit Supcrvisoi the status (and trend) of RPV Level and Pressure

"* VERIFY Reacto7 Recirculation Pumps have downshifted

"* STABILIZE Re,.tor Pressure <1020 psig

"* GO TO Step E. ,,ftLGP-3-2 BOP Operator Response:

  • VERIFY Main T. rbine and Generator Trip
  • STABILIZE Rect,:tor Pressure <1020 psig
  • GO TO Step E.2 ,)fLGP-3-2 Makes plant announ,ýement for Reactor Scram and DW leak.

Takes actions per LGA-00I when level drops below 11 inches (see next page)

  • Verify Main Gencrator/Turbine Trip
  • GO TO Step E. 2 of LGP-3-2 i

Unit Supervisor Response:

  • Directs actions to manually scram per LGP-3-2 14

Sc.-- -Drio #2 lKc Event 2-8 Initiation: \Vhen operator hcad " P6 ()l I ancl to start DW snrta\.

"1-ineline/Notes Expected Crew Response Key Event 2-7 SB LOCA Inside Primary Containment (Continued)

Drywell Spray Admission Valve E12-FO16A/B Fails to Open Panel Operator Response:

Takes Actions per LGA-001, RPV Control RPV Level Control Leg

"* CONTROL Level II to 59.5 inches using Preferred Injection Systems (primarily CD & FW)

"* Verify Auto Isolations occur.

RPV Pressure Control Lce

"* Stabilize Pressure Below 1059 psig Takes actions per LGA-003 when high drywell pressure is received Containment Pressure Lee

"* Start Suppression Chamber Sprays

"* When >12 psig;

"* VERIFY within the Drywell Spray Initiation Limit (Figure D)

"* TRIP both RR pumps

"* START DW Sprays (pcr LGA-RH- 103 hard card)

=CRITVICAL

  • Operator identifies that E t2-F016A/B valve fails to open.

STEPU"

  • Operator shifts drywell spray to E12-FO16B/A valve.

Drywell Temperature Lee

"* VERIFY all available Dr\w\ell Cooling is running (per LGA-VP-0 1)

Suppression Pool Temperature Leg

"* START all available Pool Cooling (LGA-RH- 103) if temperature reaches 105°F/hour

"* Monitor Suppression Pool Level Containment Hydrogen Lee

  • START Hydrogen and Oxygen Monitors (LGA-CM-01) i Unit Supervisor Response:
  • Makes plant announcement for LGA entries
  • Directs actions foi LGA-001 (See Panel Operator Response above)
  • Directs actions fol I C;A-003 (See Panel Operator Response above)
  • Makes plant annom (mýt ii for GSEP Alert Terndi!i:- , "* Maintains RPV Condit:... "* Primary Coaai:..: :an rs under control

"* Cue from 1I.;3:

P. 1 I Il )

2 I 15

Scenario #2 SIMUILAT(OR O)'iRAT()IR SLI:TU;P: RccaIll 1('91)

Ind- 1-08 13 oft 1B3V P C0illecr Q9d6 1 ls off Event I: No simulaltor setup Event 2: inf zivr4yho close If called by crew: -'FIN team working on air leak. isolated wrong valve.

Event 3: trigset 9 -1kI26bnl.ecq. l Tig 9 "dni1f mnb023"U To start event: i'f mnb023 0 30 seconds after c/s closes valve: imf mnb023 0 Pull/install fuses as directed AFTER power is lowered.

Event 4: No simulator setup Event 5: imf mrcO4O 100-120 Event 6: Time 0: mrf iarrvibb high high vibes Time +5: iinfr 1410 on loose parts Time +20: imf r0998 on cooling water flow low Time +25$ imfr1001 on winding cooler leak Event 7: imfmrc036 5 8:00 Event 8: set unirh 16ar le9 Set umrh I6br le9 P \I asalh -*n

!i ý II(Ao,

sma 1k)hI

ýi 3 LaSalle County Station Operations Scenario #3 Exam Date: April 8, 2002

,, 2',*, -,,, P '7' R*,m ... v -,thWalton Date: tMlr-h P P -ýý I,,,. .;1 .,:, ý I

Sceaiu o10 NARRATIVE

SUMMARY

The plant is at appiox ii 86"( power on the 10(, I'low control line. Power will he raied to the 105% rod linc by pr control rods. The Div II DG surveillancc is in progress The IA DG coolingr water puip),AI. !followed by a rod drift. HPCS Will spuriousl\ initiate follow\ed by failure of both CR1) pu: Multiple scram accumulator alarms rCsult, With a tail ure oftolds to manually scram. The S- .Suib valve will fail to open.

Scenario segments

  • Raise Reactor Po\ c withdrawing control rods I1A DG Monthly SL.: :lance 1IA DG Cooling W. "Pump Trip
  • Rod Drift Inwards

"* Clogged CRD Suet: 3ilter and CRD Pump Trip, Multiple rod drifts - Scram

"* ATWS

"* SBLC Squib valve. to open P":\1 , a I ;.- {. ,*,i

' 1"%... - harlo t:

ScC lIzl 1I)

Facirity: La~alie uounty Station Scenario No.: 3 Op-Test No.: 2002301 Examiners: Operators:

Initial Conditions: Unit 1 is at 86% power, on 103% FCL.

Turnover: Need to increase reactor power per load dispatcher request from 86% to 100%

using rods and recirculation flow lAW with approved REMA. 1A EDG runninq for LOS-DG-M2, EDG Monthly Surveillance, need to synchronize 1A EDG. 'A' RBM OOS_

Event Malf. Event Event No. No. Type* Description 1 R Increase Reactor Power by Rod Withdraw from 103% FCL to (RO) 105% FCL.

2 N Emergency Diesel Generator Surveillance Test (EDG 1A)

(BOP) 3 C EDGCWP 1A Trips, Operators unload then trip 1A EDG (BOP) 4 C Control Rod Drive Drifts Inwards Scram Outlet Valve Leaking (RO) 5 C HPCS Inadvertent Initiation, placed in PTL after (BOP) determination that not needed for injection.

6 C Clogged CRD Filter/CRD pump trip, Receive multiple (RO) accumulator alarms, requires a Manual Scram 7 M ATWS 8 C SBLC Squib Valves Fail to Open

.!,:,-rmal, (R)eactiv;'!:,, (C)omponrent, QA-001, RPV Control LOA 010, Failure to Scram Pý'\!k -\;[1]S 'X CIIzIn 11 ,ý)

S CCl rlIo 10 SHIFT TURNO()VE INFORXIATION

-4 Dal of week and shift

+ Today, Day Shift

=* Weather conditions

+ Warm, mid-summer

+ Windy

= (Plant power levels)

  • Unit I - 86% Power, 103% FCL + Unit 2 100 1( Power, 108.5% FCL
  • 2960 MWt + 3489 MWt
  • 979 MWe + 1189 MWe
  • 77.1 MIbm/hr CORE FLOW + 93 Mlhm/hr CORE FLOW

= Thermal Limit Problems/Power Evolutions

  • Raise FCL from 103% to 105% FCL lAW + None REMA sheet.

= Existing LCOs, date of next surveillance

+ A RBM OOS

  • None LOSs in progress or major maintenance
  • LOS-DG-M2 completed through step 3.0 of
  • None attachment I A-IDLE, ready to sync.

Equipment to be taken out of or returned to service this shift/maintenance on major pl nt equipment

  • 1ARBM
  • None
  • lB OG Refrigeration Uii 0 OOS Comments, evolutions, I"nts, etc.
  • Online Safety is Yeli * ( . icen (RAW = 1.0) i' F i'rn\Sccnario3r I .doc

SINIUIUA 1 R SETUP A. ('ARI)S/TAGS TO BE HUNG:

0 (Common SA Compressor B. MISCELI,ANEOUS:

11B OG Refrigeration Machine

  • Split 142X and 142Y Buses (for LC< -DG-M2, Attachment IA-IDLE Step 1.7)
  • VciIfy IA DG Voltmeter is not in OF?

C. TURNOVER INSTRUCTIONS:

Gather the crew in an appropriate class: :m setting and use the turnover sheet to provide a shift turnover. Stress the following itcm, I. The plant is at 86% power on 103% FCL.

2. [land SRO approved REMA sheet to :.rise reactor power from 103% FCL to 105%

FCL

3. LOS-DG-M2 is in progress and conr- ted through Step 3.0 of attachment IA-IDLE, ready to synchronize. Hand SRO co-,. of LOS-DG-M2 completed up to step 3.0.
4. Tech Staff and Electrical Maintenan. aire standing by in the DG room.
5. 'A' Rod Block Monitor is INOP.
6. Common SA Compressor is OOS f<.: oil change D. Items Needed to Start this Scenario:
1. Approved REMA sheet to raise reacti- power from 103% FCL to 105% FCL.
2. LOS-DG-M2 completed through Ste- >.0 of attachment LA-IDLE, ready to synchronize.

i I['ýsý- -, !:Xlll A\, tSc I ý' ),)IrI k 5

Key i: c.nt 3-1I lnitiation: Aker completion of shift ttirnov'er anld cic hrom le tad CXaminel*.

Tirme/Notes { Expected Crew Response Power Increase by Withdraw of Control Rods & RR Flow Reactor Operator Response:

Takcs actions to establish a power ramp per IG P-: I:

"* Pull control rods per LAPIO- 13, Att. G (REMA Sheet)

"* Increases recirculation flow LAW LOP-RR 07 and REMA sheet:

I. VERIFY Manual light on Recirc Loop Flow Controller M/A station A/B is ON.

2. Change Flow evenly in both loops by pressing RAISE button and observing flow indication to Flow controlleri M/A Stations.
3. Increase core flow using REMA sheet to reach 100%c power.

"* At a rate up to 300 MWe/hour.

BOP Operator Response:

Takes actions to establish a power ramp per I-GP to decrease load:

  • MAINTAIN condensate flow through the polishers per LOP-CD-03.

Unit Supervisor Response:

  • DIRECTS crew to increase reactor power at <300 MWe/hour to 100%
  • Notifies Electric Operations of power reduction TERMIINUS: Clearly observable plant response from change in power level.

. P AI F: i, , , ý -1,"

ScCI1111o #

Key Event 3-2 Initiation: .\ fItC- completion of shift tir novCl and cuIC ruroi lead Ce\a1iuci.

Time/Notes Expected Crew Response IA DG Monthly Surveillance Test (LOS-DG-M2)

Reactor Operator Response:

  • Monitors panel P603 panel for changes in reactor parameters.

BOP Operator Response:

Performs actions per LOS-DG-M2, Step E.2, and Attachment IA-IDLE starting at step 3.0:

"* Has NLO set DG Droop Switch to 50.

"* VERIFIES I A DG Voltage 4050 to 4300 Volts on IEI-DG027.

"* VERIFIES IA DG Frequency 59.8 to 60.2 Hz on ISI-DG028

"* PLACE Synchroscope to ON

"* ADJUST DG Speed with LA Diesel Gen Governor Adjust switch until synchroscopc rotates slowly (approximately one (1) rpm) in the FAST (clockwise) direction.

"* ADJUST Incoming Volts with IA Diesel Gen Terminal Volts Adjust switch until it is slightly above Running Volts.

"* When synchroscope is just before 12 o'clock, CLOSE ACB 1423, IA Diesel Gen to Bus 142Y.

"* PLACE Synchroscope switch for ACB 1423 to OFF.

"* Using IA Diesel Gen Governor Adjust switch to control kW and IA Diesel Gen Terminal Volt Adjust switch to control kvar, SLOW LOAD DG as follows:

"* MAINTAIN 1000/1300 kW and 350/750 kvar for 2 minutes

"* MAINTAIN 1750/2000 kW and 500/1300 kvar for 2 minutes

"* MAINTAIN 2400/2600 kW and 650/1750 kvar for 60 minutes Unit Supervisor Response:

  • VERIFY Surveillance is compatible with current plant conditions
  • DETERMINE DG time clock (if applicable) and RECORD Note: The Simulator Operator will not be able to observe actions at or near the IA DG controls.

His view from the control booth is obstructed. Therefore, the Chief Examiner will have to keep the Simulator Operator informed of the status as the student operates at the IPM0O!I ,anel.

TERMINUS: I I TOG is running loaded.

PA>:\] a IIc F xatI ', *.cc trI,, ýý[ ...... 7

",CCn1,11io 43 Key Event 3-3 Initiation: I A [:I); Is loadeIld aId C fo lead cxai Time/Notes Expected Crew Response 1A DG Cooling Water Pump Trip 1PM0 IJ-B206 IA DG Trouble Reactor Operator Response:

0 Monitors panel P603 panel for changes in reactoi .,:anieters.

BOP Operator Response:

Takes actions per LOR- IPM0IJ-B206:

"* DISPATCH NLO to I A DG Control Panel to DETERMINE cause

"* REFER to SOE typer Takes actions to unload and shutdown IA DG per LOP-DG-03:

  • PERFORM the following to unload the IA DG

"* CHECK bus is supplied by either SAT or UAT

"* REDUCE load and vars

"* When at or below 200 kW and 200 kvars then OPEN the 1A DG output breaker

  • DISPATCH NLO to place Speed Droop to 0
  • VERIFY speed at 900 rpm
  • Let I A DG run unloaded for 5 to 10 minutes
  • VERIFY lA DG Engine Control Switch in AUTO
  • PLACE I A DG Control Switch to STOP
  • CHECK DG shuts down
  • PLACE I A DG Maintenance Switch to MAINT Unit Supervisor Response:
  • Calls WCC SRO for assistance and repairs.

TERMINUS: (Tp,,,irntor places EDG in sha'-wclv,'n . '! reviews Technical Specifications.

8

c'cll),II I*() ""

Kev Event 3-4 Initiation: IA EDG is loaded and ltatCr CLtC I'lcu om Icad cxam iner.

'ine/Notes -- Expected Crew Response CRD Drift A:-.7unciator I H13-P603-A504 CRD Drift (Rod 26-23 drifts in)

Reactor Operator Response:

Perform- .--tions per LOA-RD- 101 for Individual Rod Drift or Scram

"* CHECK only one rod is drifting oi scrammed (yes)

"* SELE Ts the drifting control rod 26-23

"* CHECK-insert block light is off at rod select matrix (on)

"* REM -NE INSERT block by either BYPASSING the RWM or DISA.DLE blocks to 1(00

"* INSEET rod to position 00 (full-in). By either:

1. C ýtinuously DEPRESS notch in Pushbutton OR
2. C -tinuously DEPRESS Continuous In push button

"* CHECK the control rod remains at 00 (yes)

"* VER*7Y cooling water is normal (<63 gpm, <30 psid)

"* OBT_-,,JN OD-7 Option 2

"* RUN ýDD-20

"* NOT7Y QNE to MONITOR core parameters or RECOMMEND addi-:- nal power level changes

  • CHECK all other rods are at correct positions
  • INVESTIGATE Cause of Rod
  • CONTACT System Engineering to troubleshoot BOP Operator Response:
  • Mon: -rs panels
  • Assi.> RO as necessary Unit Supervisor Response:
  • Decl]:.s Rod Inoperable TERMINUS: {Drifted c.,ntrol rod inserte(l to 00 SRO reviews annlic'),hlV Teehnirn5l1 17-ccifi c a-io ns __

I itII~.as~,Itr~ IF II 99

Sqt_ LIl ]

Key Event 3-5 Initiation: Event 3-4 complete, r activityr nd co eatr A iemcinr.

Time/Notes Expected Crew ResponseR Inadvertent HPCS Initiation TH 13-P601-A205 HPCS SHYS Actuated I H att3-P601 -A204 HPCS P Bkr aip 2 Closed I H13-PC01 -A406 HPCS Hdr Press Hi Reactor Operator Response:

SREonItors changes in core reactPIEvity fro coldET uaterhtion (d BOP Operator Response:

Recognizes HPCS inadvertent initiation Takes actions0Hper t3-P601 LOR- -As05:

  • VERIFY automatic actions (HPCS aligns for injection)
  • CHECK initiation signal present (yes)

If HPCS is not required then SHUTDOWN pel LOP-HP-04.

SRESET the HPCS logic by DEPRESSING RESET pushbutton (doesn't work-)

SPlaces HPCS pump in PTL.

PREVENTS IB re-start of DG by placing Maintenance Switch in MA1NT DISPATCHES NLO to 1a DG room SECURES DB DG By pressing STOP pushbutton Pe+ LOP-HP-04 to shutdown HPCS DG

  • VERIFY HPCS injection is NOT needed by multiple indications U VERIFY Initiation Signals Clear
  • VERIFY IE22-F012 Minimum Flow Valve OPENS SSTOP HPCS pump - Place HPCS puanp in pull-to-lock
  • VERIFYIE22-F012 Minimum Flow Valve CLOSES
  • When HPCS room fan automnatically stops, then SHUTDOWN the I1B DG Cooling Water Pump When plant conditions permit, PLACE HPCS in standby per LOP-HP-03 Unit Supervisor Response:

,,Refers to Tech Spec 31.5.1I.H.1I and declares HPCS INOP.

~ Fwnets into Tech ,Sn*-c '103 (based on Div I and D'iv 3 "i-op)

,.m~csIND anklu ý,-,.,tli Engineering for assista,,*.L iii

ýIoublcshootitlg TER-\iIN, "c,. TTIIC I -RO reviews applicable lrcT l,,/i,-a

______________________ca; ia 5 I ý,i, ,:týl ,. 1I A t+ 'C !,', . in

sccll:vio ,#3 Key Event 3-6 Initiation: [ 2 vcn t 3-5 is compilted and after cued yv lced cexaminer Time/Notes Expected Crew Response CRD Suction Filter Clogged IH 13-P603-A303 CRD Feed Prop Suet Filter DP Hi 1H13-P603-A203 CRD Feed Pmp Suction Press Lo 1H13-P603-A103 1A CRD Feed Prnp Auto Tri_

Reactor Operator Response:

Pet P603-A303, CRD Feed Prop Suet Filter DP Ii:

"* Dispatches NLO to CRD Pump area

"* Directs an NLO to switch to the STBY suction hilter per LOP-RD- 14 (Local operation of valves)

Per P603-A203 CRD Feed Prop Suction Press Lo:

"* REDUCEs system flow by closing FCV to clear alarm and keep pump from tripping on low suction pressure.

"* THROTTLEs down on drive water pressure to maintain about 280 psid.

"* Places standby CRD suction filter in service Per P603-A103 1A CRD Feed Pmp Auto Trip:

"* Has the NLO expedite switching filters.

"* STARTs STBY pump:

I. If CRD pressure is >500 psig then immediately starts pump, or

2. Starts pump per LOP-RD-03.

BOP Operator Response:

  • Monitors panels for alarms/abnormal conditions Unit Supervisor Response:

TERMINUS: Reactor Scram by crew.

1 NT

.8 lIe 1 ' eii !03r I .(VC ;Il

Sccenario #3 Time/Notes Eplected Crew Response Key Event CRD Suction Filter Clogged (Cont'd) 3-6 Manual Scram after Receiving Multiple Accumulator alarms Reactor Operator Response:

"* ARM and DEPRESS Sceam PL.--buttons

"* PLACE Reactor Mode Switch 1-.SHUTDOWN

"* INSERT IRMs and SRMs CRITICAL "* CHECK aill Control Rods in ar,, Power Decreasingý

  • REPORTS ATWS conditions t,: U'nit Supervisor (- 14K pwr).

STEP

  • INFORM Unit Supervisor Of R -iStatus and Reactor Power

"* Operate FWLas necessary withPir: -he level bank -60 to -100 inches.

"* REPORT to the IUnit Supervise: -he status (and trend) of RPV Level and Pressure

"* VERIFY Reactor Recirculatioi. Pumps have downshifted

"* GO TO Step E.2 ot LGP-3-2 i

BOP Operator Response:

  • STABILIZE Reactor Pressure <'020 psig
  • GO TO Step E.2 of LGP-3-2 t

Unit Supervisor Response:

"* Take actions per LGA-001.

CRITICAL

"* When reactor power is greater ',.n 3% and/or all rods are NOT in to at STEP least 02 and the reactor will not -:ayshutdown without Boron then EXITs LGA-001 and ENTERs LGA-010

.[I ,' l io3r1 .doc ,2

S'CCc lrl&

Tiine/Nott"'

Expected C(eNCResponse Key Events ATWS 3-7 & 3-8 Failure of SBLC Squibb Valves to Open Panel Operator Response:

Per LGA-0 10:

  • Prevent injection torm IIPCS, LPCS and LPCI LGA-010 Power Lee
  • RUNBACK Reactor Recirculation flow to minimum Ifpower is >3% then TRIP RR Pumps U
  • ENTER LGA-NB-01, Alternate Rod Insertion
1. Remove Scram Solenoid Fuses and SDV vent and drain fuses (NLO)
2. Depressurize scram air header (NLO local operation)
3. Single rod insertion (RO bypasses RWM and drives rods in)
  • If power is >3% then START SBLC
1. Places lA/B SBLC Pump keylock switch to Sys A/Sys B position
2. Checks C41-FO04A/B SBLC Inj Squib Vlv ON light extinguishes (ON light does NOT extinguish)

CRITICAL 3. SBLC Squib Vlv Continuity Loss alarm (A105) does NOT alarm

  • Identifies that SBLC does not initiate STEP
1. Attempts to initiate Alternate Boron Injection using RWCU JAW LGA-RT- 103.

Unit Supervisor Response:

  • Acknowledges that SBLC does not actuate
  • Directs actions per LGA-NB-0 1, (See panel operator response above)
  • Directs actions per LGA-001 and LGA-010, (See panel operator response above)
  • Authorizes Alternate Boron injection using RWCU per LGA-RT-103 rjrI.doc ii;

S f:llal I')-

"ljinie/Notes Expected Crew Res!ponse Key Events ATWS (Cont'd) 3-7 & 3-8 Failure of SBLC Squibb Valves to Open (Cont'd) -_----

Panel Operator Response:

LGA-010 Pressure LeE

  • If SRVs are cycling then OPEN SRVs to lower pie'ssure to 935 psig
  • Okay to reduce pressure so CB pumps can be used to control RPV level before stabilizing pressure. Do NOT exceed cooldown rate of 100'F

/hr.

  • Use Alternate Pressure Control Systems if needed
  • EHC Pressure Set at 870 psig keeps SRVs closed when LLS is reset.
  • WAIT until Reactor is Shutdown or Cold Shutdown Boron is injected

(<3100 gal in SBLC Tank)

LGA-010 Level Leg

  • VERIFY Automatic actions occur (Isolations and DGs Start)
  • If Steam Lines are open then BYPASS MSIV isolations per LGA-MS-01 CRITICALST
  • If reactor power >3% or unknown then Rapidly LOWER Level to at STEP least -60 inches and use only preferred systems to hold level between 150 and -60 inches.

i Unit Supervisor Response:

  • Directs actions per LGA-010 (See panel operator response above)
  • EXITs LGA-010 and ENTERs LGA-001 when all rods are in, or Cold Shutdown Boron is injected, or the reactor will stay shutdown without Boron.

F.,-i

- ,na ~ mo 3

ii-` i I .dcn.

Time/Notes .E'pected Crew Response Key Event ATWS (Continued) 3-7 Failure of SBLC Squib Valves to Open (Cont'd) 3-8 Panel Operator Response:

Thie following actions will only be taken if level drops be 1150 inches Take actions per LGA-006 when directed by LGA-0 10:

"* VERIFY Suppression Pool Level is greater than -18 Ic'C

"* PREVENT all RPV injection except Boron, CRD and RCI[C CRITICALI

"* INITIATE ADS (using BOTH pushbuttons)

STEPý

"* VERIFY 7 ADS Valves are OPEN

"* RETURN to LGA-010 at Step 10

"* Commence re-injection when Reactor Pressure reache- -'40 psig

"* WAIT until Shutdown Cooling Interlocks clear (143 pý:;,

"* WAIT until Reactor is shutdown or cold shutdown bor,:. is injected

"* COOLDOWN to Cold Shutdown using Shutdown Coo::.2 (per LOP-RH-07) t Unit Supervisor Response:

"* Directs actions per LGA-010

"* Directs actions per LGA-006 Terminating a Maintain level 11" to 59.5" Conditions

  • All rods are in, or Cold Shutdown Boron is injected, or :-e reactor will stay shutdown without Boron.
  • Cue from lead examiner I nrn\Sccnario3i II c

Sv':C1) ýIIIo 1.3 Siimujlator (Operator:

I . Recall IK 71

2. Run thc setip cac fro1 C. " * .>C e Ih:ll 1(.),Cae
3. 1,oad/vcrI ly sequence CI
4. Split 142X & Y buses fo: -)(I test. Start IA DO, speed droop at 50.
5. Place ',A RBM in BYP.\ Place DEL, tag on switch.
6. TS Timeclock: 3.3.2. \ -,-)l RA A. I Restore RBM to Operable in 24 [1our-1s.
7. Sequence c IOsd.3acc Event 1: No Actions Event 2: No Actions Event 3: irnf mdg023 Event 4: irnf rnrd078 Event 5: imfmnb078 50 Event 6: imf r0091 on Closesuct. Valve from dwg RD I Accumulators zcl11016 to zcl III Event 7: ATWS imf mrd277 60 Imf mrd278 60 Event 8: imfr0744 off imrfr0742 ior g3fOOgl0 4800 Ior q3h02 Lro off ior q3h0 3 rF for q3h02 rgo on irf vhs 100, 0 Ior g3f17g26 4.25 iorq3h03'S anr Ior g3fl8gz6 4.25

',. m\cc,,ario3rl Id.

10 LaSalle County Station Operations Scenario #4 April 8, 2002 Developed By: Raymond Keith Walton Oate: March 24, 2002

- ,ý

......;,,  :.'.' I

it) #4 NARRATI'IVI S tANIIARY Th ['IIit P, at S5-' power. CreIw Will rCdUce *cactor pmer ci using RR flow to less than 827 powcr. Pciforin a. I OS-RP-Q3 for 'A' inboard and outboard MSIVs. The RO wvill identify the B R R :( 'V sdowly drifting closed. The RO may or n\ay not compen satc with the 'A' RR FCV dependuing on the mismatch between loop flows. Contai men t Chill watCr pump B' trips. 'C'

.\PRM fat Is upscale without RPS half-trip. The operating IA IN compressor will fail. A small hrieak ILOCA dluC to a recirc pump seal failure OCCLIFs followed by trip of bus 142Y.

Scenario segments

  • Reduce reactor power to less than 8 2 % power

'A' inboard and outboard MSIV Surveillance Test S1B' RR FCV Drifts Closed

  • Containment chill water pump 'B' trips
  • APRM 'C' Fails High without an RPS half-trip occurring
  • Trip of 1A IN compressor
  • Bus 142Y trips

.'LasalI C ExaI\S cc IIar II J

Sccn' ii #4 Facility: LaSalle County Station Scenario No.: 4 Op-Test No.: 2002301 Examiners: Operators:

Initial Conditions: Reactor oower 85%. 'B' IN comoressor of service Turnover: Perform MSIV Surveillance Test for only 'A' In, J:-.

and Outboard Isolation valves lAW LCDS-RP-Q3.

Event Malf. Event - -. nt No. No. Type* Des : otion 1 R Reduce Reactor Power usirp !R flow to less than 82% pwr (RO) 2 N Performs LOS-RP-Q3 for 1/- -ooard and Outboard MSIVs (BOP) 3 I RR FCV Controller output d- causing 'B' RR FCV to drift (RO) closed, operator may need :- secrease RR flow on 'A' RR loop at M/A station 4 C Containment Chill Water Pu-: *A' trips (BOP) 5 I 'C' APRM Fails Upscale wit:h RPS half-trip (RO) 6 C Trip of 'A' Instrument Nitroge- IN) compressor.

(BOP) 7 M SBLOCA in Drywell 8 C Bus 142Y trips

+ +

. (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M))ajor LGA-001, RPV C."....

LGA-003, Primary Coritainment Control 3

Scenario #4 SHIFT TURNOE-R INFORMAvrTION

~ Day oi week .1 shift

  • Today. , Shift S Weather coix:.:nis
  • Warm. 7:-. [l-SUlmer
  • Windy

=> (Plant power. .21s)

  • Unit I - ,. Power. 1007- FCL
  • Unit 2- 100 % Power, I 08.5c FCL.
  • 2965 NIV,
  • 3489 MWt
  • 1189 MWe
  • 85 Mlbm. CORE FLOW
  • 93 Mlbmnhr CORE FLOW

= Thermal Lirm: Problems/Power Evolutions

  • None
  • None

=> Existing LCO-. date of next surveillance

+ None SLOSs in progr-ess or major maintenance

  • LOS-RP--- for 'A' MSIVs only + None

=> Equipment to pe taken out of or returned to service this shift/maintenance on major plant equipment

+ I B IN c( :- -ressor OOS for oil change + None

= Comments, ev. lutions, problems, etc.

  • Online R.:-. is Green + Online Risk is Green P:\LasalleEam.:;a.* do 4

Scenario #4 SIMULATOR SETUP A. CARDS/TAGS TO BE HUNG:

"* Place the >95.2% FCL placard on near the mode selector switch

"* Place OOS tags on IB IN compressor B. MISCELLANEOUS:

  • Time Clock Board None C. EQUIPMENT:

0 D. TURNOVER INSTRUCTIONS:

Gather the crew in an appropriate classroom setting; use the turnover sheets to provide a shift turnover. Stress the following items:

1. Unit I is at 85% power
2. Perform LOS-RP-Q3 for 'A' MSIVs only.
3. Complete all pre-evolutionary shift briefs before taking the watch.
4. U2 Assist NSO is available at X2999 to watch relays during LOS-RP-Q3.
5. 1B Instrument Nitrogen Compressor OOS for oil change.
6. FCL >95.2%
7. Unit 2 is at rated power P :\I isa1 c , nnri ulr.doc F)

Scenario #4 Event 4-1 Initiation: After conmplction of 'shift turnover and cue from CXaminer.

Time/Notes Expected Crew Response Power Decrease with Recirculation Flow Reactor Operator Response:

Takes actions to establish a power ramp per LGP-3-1, Att C ":crease load:

"* Decrease core flow pet LOP-RR- 107

"* At a rate up to 300 MWe/hour

"* At a higher rate specified by a QNE Per LOP-RR-07:

"* Verify manual light on recirculation loop flow controlle: .' k station AMB is ON.

"* Change flow evenly in both loops by pressing LOWER -b:_on and observing flow indication to flow controller M/A station.

BOP Operator Response:

  • MAINTAIN condensate flow through the polishers per L ?-CD-03
  • Monitors panels for unusual/abnormal alarms/condition, Unit Supervisor Response:

"* DIRECTS crew to decrease power at <300 MWe/hour to 0% power using recirculation flow

"* Notifies Electric Operations of power change

"* Enforces OPS expectations and standards

"* Ensures RO monitors critical parameters carefully

"* Ensures operations are conducted within bounds of TS TERMINUS: Clearly observable plant response from change in power leve'.

P:\Lasalle Exar,.';'ccnario4rI.doc 6

Scenario #4 Event 4-2 Initiation: Follox\ c Shilt turnover on signal rom lead examiner.

Time/Notes Expected Crew Response Key Event: Perform LOS-RP-Q3 MSIV Scram Functional Test BOP Operator Response:

Takes actions to pe:: rm LOS-RP-Q3. MSIV Scram Functional Test for IA inboard MSIV a::J IA outboard MSIV:

"* VERIFIES Rx P :-.ver <82%, all MSIV switches in AUTO, Scrams RESET, and MNSTIV Relays energized.

"* Activate the MSIV Test Mode at DSOO I and record power level.

"* One at a time, pl:ices IA inboard MSIV control Sw. in OPEN SLOW TEST

"* Depresses and Hlds IA inboard MSIV Slow Test PB until 2 relays deenergize or for about 10 sec. After receiving dual indication.

"* Then Releases PB.

"* VERIFIES IA irboard MSIV reopens and 2 relays deenergize then reenergize.

"* Checks that IA 'B MSIV inbd/outbd Not Full Open alarm received.

"* Verify IA inbola.rJ MSIV open.

"* Verify all MSIV relays energized (IC71A-K3A through K3H).

"* Reset 1A/lB MSIV Inbd/Otbd Not Full Open alarm.

"* Place 1B21-F022A, Inbd MSIV control switch in AUTO.

"* Waits 2 minutes :o stabilizeflows.

"* Repeats above s':eps with IA outboard MSIV.

Reactor Operator Response:

"* VERIFIES Rx Power <82%, all MSIV switches in AUTO, Scrams RESET, and MSPV Relays energized.

"* Monitors steam :'ow indication and assists in testing.

"* Monitors plant parameters for alarms/unusual conditions.

Unit Supervisor Response:

"* HOLDS power decrease to perform MSIV surveillance test

"* MONITORs crew.V performing LOS-RP-Q3

"* Refers toTS 3 1.1

_TF_,TMINUS: Completion of surveillance test PA~:\,' !l , .:v:,:: \cenario4rl .do" 7

"-. :ario #4 Key Event 4-3 Initiation: After SRO reviews TS for MSIVs and CLIC from lead examincr.

Time/Notes Expected Crew Response

'B' RR FCV Controller Output Drifts - Closure of 'B' FCV 1H 13-P603-A408, OPRM Trip Controller Low or Power 1H13-P602-B 101, 'B' RR Flow Control Vlv Trouble Reactor Operator Response:

Detects loss of reactor power on LED screen on P601 panel.

Identifies that 'B' RR Flow Control Valve closing.

Takes actions per LOA-RR-101 for RR FCV failing CLOSED

  • CHECK FCV position is STABLE (no)
  • PRESS HPU 1B TRIP pushbutton to lock up lB RR FCV.
  • CHECK recirculation loop jet pump flows LESS THAN T/S MISMATCH (w/in 5.425 Mlbm/hour if core flow is >75.95 Mlbm/hour, and w/in 10.85 Mlbm/hour if core flow is <75.95 Mlbm/hour) (no) o If>TS MISMATCH:

"* Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, either:

o. RESTORE flow mismatch
o. REDUCE Power rapidly per LGP 3-1, including shifting both recirculation pumps to slow speed.
o. TRIP the low-flow RR pump per step B. 10.4.1

"* START 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time clock either to RESTORE the flow mismatch OR to DECLARE one RR loop Not In Operation per TS 3.4. 1, Condition F.

"* Evaluate Core performance.

  • CHECK IA FCV NOT locked up (LA FCV Motion Inhibit light OFF.)
  • Push LOWER PB at IlA FCV M/A station to reduce mismatch.

N DTE: If candidates detect failure quickly and take immediate actions by locking up IB RR FCV by tripping HPU, may not exceed TS Mismatch.

BOP Operator Response:

  • MONITORS panels for abnormal conditions and alarms.

Unit Supervisor Response:

"* Refers to Tech Spec 3.4.1, Condition F.

"* Authorizes entry into LOA-RR-101.

i EiCVIINUS: RO baian,.- ýiup *lows, if required. Su ,,' .,.'s applicable Technical Specification,__

,allc' :an\Sccnario ri.doc,

Scenario #4 Key Event 4-4 Initiation: Event 4-3 complete, and cue from lead examiner.

Time/Notes Expected Crew Response Containment Chill Water Pump 'A' Trips PM06J-A201, Primary Ctmt Water Chiller Pump VPO1PA Trip PM06J-A501, Primary Ctmt IA Water Chiller Cont. Pnl Trouble BOP Operator Response:

Response to PM06J-A201:

0 VERIFY Automatic Isolations Occur:

1. TRIPS Primary Containment Water Chiller Pump 1VPO I PA, (Loss of Primary Containment Cooling).
2. TRIPS Primary Containment Water Chiller Unit I VP0 1CA.

0 MONITORS Drywell temperature and pressure

  • DISPATCH operator to CHECK Protective Relays at compressor motor starter panel. 'A' chill water pump is fed from MCC 133- 1.
  • OPERATE available chillers per LOP-VP-02 to maintain adequate Drywell Cooling.

0 MONITOR Drywell Temperature (Reference LOP-CM-04).

  • MONITOR Drywell Pressure from recorders l PR-CM027 and IPR CM028 on panel 1PM 13J.

Response to PM06J-A501:

0 Start lB Primary containment chill water compressor and vent system per LOP-VP-02 Response to LOP-VP-02:

  • Coordinates with NLO and Starts the IB VP Chill water pump from CR by taking VPO1PB to START.
  • 1VP084 & 1VP086 valves open.

0 After more local checks, Starts the 'B' Supply fan from PM06J.

  • After 30 seconds, ensures 'B' Supply Fan is still running.

0 Local operator starts chiller unit.

0 CLOSES lB VP Chiller Feed Bkr to VPO1CB (action doesn't start the VP chiller).

  • Locally, NLO starts IB VP chiller and checks for proper local operation.

o Shuts down 'A' Chilled Water loop per LOP-VP-02, Step E.8 I. Opens 1A VP Chiller Feed Bkr 1VPO ICA

2. Opens IA Supply Fan Bki, 1%/i'02CA.

P:\Lasalle Exam\Scenario4r] .doc c)

Retrieved from "https://kanterella.com/w/index.php?title=ML022140041&oldid=2697369"