ML022890556
| ML022890556 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/25/2002 |
| From: | Caniano R, Grobe J Division of Reactor Safety III |
| To: | Skolds J Exelon Generation Co, Exelon Nuclear |
| References | |
| 50-456/02301, 50-457/02301 | |
| Download: ML022890556 (114) | |
Text
{{#Wiki_filter:Facility: Braidwood Scenario No.: 2 OpITCst No.: Examiners: Operators: SRO RO BOP Initial Conditions: IC-21; 100% power, BOL, equilibrium Xenon, steady state, 1B Diesel Generator OOS, IC lID pumnp OOS, U-2 SAC OOS. Turnover: 100% power, BO1L, equilibrium Xenon, steady state. The IB Diesel Generator is OOS for replacement of Turbo Charger. The DG has been OOS for 18 hours and is expected to be returned to service by the end of the shift. IC Heater Drain Pump is OOS for motor bearing replacement. Unit 2 SAC is OOS for an oil change and is expected to be returned to service by the end of the shift. The lB CCW Pump is running for ASME testing. A tube leak being trended on the IC SG has increased over the last hour and has been confirmed at 5 gpm requiring a unit shutdown. Event Malf. Event Event No. No. Type* Description Preload RF EG09 I B DG OOS MAINTO Preload Preload - RO Steam Generator IC Tube Leak (5 gpm) TI-103C BOP SRO N BOP Reduce Turbine Load for Unit Shutdown due to SG leakage > Tech SRO Spec R RO Lower reactor power using rods and/or boration 2 RX18A I RO IA RCS loop Tcold RTD failed High SRO 3 EG03 C BOP Voltage Regulator malfunction Field Forcing SRO 4 RX06K I BOP Steam Generator I C controlling level channel I LT539 Failed High on a SRO 3 sec ramp. 5 CV01A C RO Centrifugal Charging Pump Trip SRO 6 TI103C M RO Steam Generator IC Tube Rupture (460 gpm) BOP SRO 7 EDIIA C RO Loss of Instrument Bus II I coincident with Reactor Trip BOP SRO 8 RF RP84 C RO I B SI Pump fails to start automatically, ManuLally start an SI pumpI and RP1 51) BOP Manually Align train A I'CCS for lnjcction due to failurec to auto start SRO Irom loss of instrument bus II I
- .(N)ormal, (R)cactivity (l)nstrtinent, (C'oinpolenlt. (Nfl)aJol Iranisicnit I*,jid,.wod 1NI N(*4 V.xam ;ccnar
- I12I
SCENARIO 02-2 OVERVIEW The unit Is at I00% power, BOI , equilibrium Xenon, steady state. The lB Diesel Generator is OOS for Turbo Charger replacement. The Diesel Generator has been OOS tbr 18 hours and is expected to be returned to service by the end of the shift. IC Heater Drain Pump is OOS for motor bearing replacement. Unit 2 SAC is OOS for an oil change and is expected to be returned to service by the end of the shift. A known steam generator tube leak on the IC SiG hasjust been confirmed to have increased beyond that allowed for continued plant operations and a unit shutdown has been ordered at 5 MW/min. A unit shutdown will be commenced in accordance with IBwOA SEC-8 step 10 and Tech Spec 3.4.13, "Operational Leakage". Once the ramp has been initiated a failure of the IA Tcold narrow range RTD instrument high will occur. The US will enter BwOA INST-2 for the failed instrument. The crew should identify the failed Tcold instrument by abnormal rod motion and place rod control in manual. The crew should identify bistables to be tripped within 6 hours for the failed RTD channel. After an adequate power change is observed and the actions for failed RTD are completed, a Voltage Regulator malfunction will result in field forcing. The crew should take the Voltage Regulator to OFF and use the Base Adjuster to reduce Exciter field current to less than 100 amps. The Voltage Regulator should remain OFF and control will be manual operation of the Base Adjuster to control main generator voltage. After the actions for the Voltage Regulator failure are complete, IC Steam Generator Level Channel 1LT-539 will fail high causing I FW530 (IC FRV) to close. The operators will take manual control of the IC FRV and restore feedwater flow to normal. The US will enter BwOA INST-2 and direct actions for failed SG Level channel and establish normal automatic steam generator level control. After actions are complete for the level channel failure, the 1A CV pump will trip. The operators will perform actions to isolate letdown, then restore charging and restore letdown JAW 1BwOA PRI-15, "LOSS OF NORMAL CHARGING" After the actions are complete for the CV pump trip, the IC S/G tube leak will increase to 460 gpm requiring a Reactor Trip and Safety Injection. Coincident with the reactor trip and safety injection a fault of instrument bus 111 will result in de-energization of the bus. The crew will enter IBwEP-0 and manually align A train of ECCS due to the de-energized instrument bus. The lB Safety injection pump will fail to auto start and the crew will take actions to manually start IA and I B SI pumps. The US will transition to IBwEP-3 at step 28 of 1BwEP-0. The crew should take actions of I BwEP-3 to stabilize the plant by cooling down and depressurizing the RCS. Completion criteria is the performance of I BwEP-3 through ECCS termination step 21. Critical Tasks I ;-3--A: Isolate feedwater flow into and steam flow from the ruptured S/G before transition to 1!CA-3. I occurs.
- 2. 1'-3--13: l2stablish/maintain RCS temperature so that transition from E-3 does not occur because telilperature is either of the I'ollowing: Too high to maintain minimulni required subcooling OR Bclow the R('S temperature that cause an cxtrellcm or severe challenge to the subcriticality and/or theh 1ntegri ty C'SI.
- 3. I-0 I: Manually itiate SI flow Via I A or 113 SI P1ump bcfoIC transitioning out of IF -0.
-I. `1-3 --( : I)cprcssuriz/c RCS to mect SI termination critcriaK bc'orC water cntlcrs the stcam lincs. vC P;I!, S ck I11, 1 " 1k l W _.-
SCENARIO 2001-3 SIMULATOR OPERATOR NOTES Simulator Setup: IC-21, 100% power, BOL, equilibrium Xenon, steady state. Align switches: 113 DG C/S PTL. and OOS ACB 1423 PTL and OOS IC HD pump C/S PLT and OOS U-2 SAC C/S PTL and OOS, ensure U-I SAC running Perform "Ready for Training" checklist. Swap running CC Pumps-- I B in RUN, 1A in STANDBY Insert PRELOAD Events:
- RF EG09, MAINT 0 - 13B DG OOS
- RF RP84 - OPEN - Auto start failure of 1B SI pump
- IMF RP15D - Auto start failure of lB SI pump
- IMF: TH03C, 5 gpm - SG tube leak in I C SG is intended to force a unit shutdown based on exceeding allowable limits per Tech Specs and the procedure.
Acknowledge RM-1 I Grid 1 alarms Open I BwOA SEC-8 and place keep through step 1 c Event 1 Power reduction. Event 2 1A RCS loop Tcold narrow range RTD failed high SDG: RXI Malf: RX18A, 630 Initiate event after clearly observing reactivity change/response of plant to requested power ramp and with lead examiners concurrence. Acknowledge all info passed to the SM, WEC, and maintenance. SDG RX4, RX2 Cabinet door #1 open RF RP20 OPEN OPDT Trip TB4I IG CI-124 BS-1 RF RX014 TRIP OPDT Runback TB41 111 CI-124 BS-2 RF RX136 TRIP OTDT Trip TB4I C C1-124 BS-3 RF RXO13 TRIP OTDT Runback TB4I ID C1-124 BS-4 RF RX135 TRIP Low Tave TB412G CI-121 BS-2 RF RX016 TRIP Lo-L0o Tave TB412D CI-121 BS-1 RF RX015 TRIP Cabinet door #I Close RF RP20 CLOSE Event 3 Voltage Regulator malfunction Field Forcing. SI)G: EGI Mall': I "G03, 94% Initiatc malfunction after actions are takcn for the I'ailed lTID and with lead examiners concurrence. S"asked role play as U -2 adiin aind'or cxtra. NS() f'or Unit 2 Main Generator V.\Rs have decreased. Acknow ledge all inf'o passed to the SM\I \\' )(',and inailecnance. NOT)I ': Ifailure to take action to rcducc cxcilcr field current w\ill result in a cnerator 1rip) reactor (rip. lf)(O Mý( JAý1111 1'. ýý . ?;c*.,,:tri*, IC-.?
Event 4 SG IC controlling level channel 1LT-539 fails high. SDG: RXI9 Malf: RX06K. 100% Initiate malfunction after actions are taken to manually control main generator exciter hield current and with lead examiners concurrence. Use the following to trip bistables for the failed channel Cabinet door #1 open RIF RP20 OPEN P14 I,13539A C2-753 BS-1 RF RX063 TRIP Lo-2 Rx Trip,;AF Pumnp Start LB539B C2-753 BS-2 RF RX064 TRIP Cabinet door +/-'l Close RI RP20 CLOSE Event 5 Centrifugal Charging Pump trip SDG: CV5 Malf: CVOIA Initiate this event after actions for SG level channel failuire are completed and with lead examiners concurrrence. If sent to locally investigate the I A CV pump and breaker, wait 3 minutes, perform first check, and report no apparent cause at the breaker (bus 141 cub 11 ). If sent to check the lB CV pump, wait 3 minutes, perform first check, and report "normal operating conditions". Acknowledge all info passed to the SM, WEC., and maintenance. Remote Starts or Stops of the Aux Lube Oil pumps can be accomplished by RF CV76 Event 6 SGTR IC SG. Leakage increases to 460 gpm over 3 minutes. SDG: TH5 Malf: TH03C, 460 gpm, 180 sec ramp. Initiate failure after tech specs are investigated for the CV pump and with lead examiners concurrence. Acknowledge all info passed to the SM, WEC, and chemistry. Event 7 Loss of Instrument Bus III SD): ED6 Malf: FDIlA Trigger - When Reactor trip breakers are open The loss of Instrument Bus I II occurs after the reactor trip and prior to initiation of Safety Injection. This will prevent the auto actuation of Train A ESFAS. The loss of the instrument bus is non-recoverable for the duration of' the scenario and probably won't be pursued by the crewv. If requested to investigate as NIO wait 3)minutes, perform first check and report that Instrument Bus II I indicates evidence of electrical damage. Acknowledge all inlbo passed to the SM, WEC, and maintenance. Event 8 lIB SI pureI) fails to start aiitomatically. Start and Manually Align train A ECCS for Injection due to fail ure to auto start fi-om loss of instrument bus 111 Malt: (pcload) Rl 151) RI: (prclohad) M)X4 /\Cklioxrlcd.\ c, 11iliCnto
'11k 'Cd lot the SMl. \\'l'(. anld nualnlinlwllcl C.
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Scenario No.: 02-2 I x ent No.: I t\ cnt
Description:
Plant shutdo\n due to excessiVe S'G leakage lime [Position ,Applicant's Actions or Behax ior CUF: As a result of the excessi\ e steam Generator tube leakagc. I1Bx OA SI.C-8 dictates a power reduction to I lot Shutdow n within 6 hours rof exceeding 1-50 gpd US Implement actions of 11?fiG P 100-4 US Direct load reduction to MvODE 3 within 6 hours CR IW Rex iexw applicableI PI rCqiitCs e s Precautions, limitations and .\ctIons of I B\ GP 100 -4 RO Verify rod position and boron concentration. Initiate boration, if required. (BwOP CV-6)
- Determine required boric acid volume by:
"o Effects of previously performed borations "o Boration Dilution Tables
"* Determine required boric acid flow rate.
"* Set I FK- 110 BA Flow Cont to desired boration rate.
- Set IFY-01 10 BA Blender Preset Counter to desired volume.
"* Place MAKE-UP MODE CONT SWITCH to STOP position.
"* Set MU MODE SELECT to BOR position.
"* Place MAKE-UP MODE CONT Switch to START
"* Verify proper operation of valves and BA transfer pump (CVI 10B open, BA pump is running, CVI IOA throttles opens, BA flow on recorder.
OR Batch addition:
", Open CV]1l1B.
"* Open CVI\10A.
"* Start BA Transfer pump.
"* When desired amount of B3A added, stop BA Transfer pump.
"* Close CV1IOA o Flush BA. line.
- Close CVIIOB.
Comn ncn e ts: 1I', (.
Scenario No.: 02 2 F vent No.: I txent
Description:
Plant shutdown dile to excessi\'c S G leakage Time Pooition Applicant's Actions or Behavior 1301' Initiatc turbine load reduction:
"* Depress L.OAD RAIF.AMW.MIN
"* F-ter desired value for rate
"* Depress RhF Inter power level 620 MW.
E
"* When ready to begin load decrease. depress GO
"* Verify load decreases.
RO BOP Monitor power load decrease:
- Monitor reactor powver, Tarc. Al RO During boration:
- Monitor VCTI level
"* Verify RCS boron concentration increasing
"* Monitor BA blender counter
"* Verify boration stops at preset value NOTE: Following clearly observable plant response from the reactivity changes and with lead examiners cue, Event 2 is entered.
CommIents: 1"" , "
Scenario No.: 02-2 \ cnt No.: 2 l\ ent l)escription: IA R(CS loop [cold t'ailed high I ime Position Applicant's Actions or Behax ior (CUPF. Annunciators: 1-14-Dt TA1V1F CONTROL I)FV H1IGH 1-14-BI 01TAT HIGH RX TRIP AFI.RT 1-14-F2 AUCT T AE HIGH I-I14-A5 OOP01IAA FT DEV LOW 1-14-B3, C3. D3 L.OOP 1B,C,D TAVE DI.V ILOW Control rods steppinge in IA Tave indication higih RO US Identify /report IA Tave channel failure RO Determine turbine load stable and place rods in Manual. US Implement I BwOA INST-2, "OPERATION WITH A FAILED INSTRUMENT CHANNEL" Attachment A and direct operator actions. RO Verify rod bank select switch in manual RO Manually defeat failed RTD channel:
"* Select failed Tave channel with TAVE DEFEAT switch
"* Select failed AT channel with AT DEFEAT s'witch RO Select an operable RTD channel to the AT recorder RO Check if rod control can be placed in auto
"* TURBINE ILOW POWER INTLK C5 NOT lit
"* Tave-Trefdeviation Stable and within I°F
- IF NOT restore '[ave-Tref deviation to within I 0 F
# Adjust rods
"* Place ROD BANK SEF1 C'T switch in AUTO RO Check PZR level
- PZR level NORMAL and STABLE RO/US Dispatch operator to locally trip bistables for failed channel by placing switches to "1TPST" Conme ncits:
S.Scenario No.: 02-2 t{) em No.: l\ct
Description:
IA RCS loop Icold faied high Timc Position .\pplicatt's Actions or Bchavior R() Check P12 interlock 1\ a e greatcr than 550°t: IC.- 2 1AVI STMI DI)U.II INTl K P12 NOTl IllT 130P Moni0or secondary plant parameters as a1r'C.ul1 of the primary transient Assist RO as reqiIestecd directed b\ US
- Coordinate bistable tripping
- Investigate Bo\\ARs
- Make phone calls as diiected b\ US RO
"* Provide appropriate peer checks to R,) a'. requested
"* CotIrol 1urbHine loading as directed [, U'S RO US Refer to Tech Spec
- 3.3.1 Reactor' Trip Instrumentation 0 3.3.2 ESFAS Instiumentation
- TRM 3.3.h US Inform SMiMaint of RCS loop I A Tcold RT D failure'status.
NOTE: After actions are complete for failed Tave channel and lead examiners concurrence, Event 3 is entered. Comment's: (. 1 ,l~HS
Scenario No.: 0(2-2 I seni No.: 3 EIeut I)csCription: Voltaec Rcgula*or nul Unction Fied Forcnr T inic Position ] Applicant's Actions or Behavior TUI: Annunciators: 1- 19-136 GI NIRRAIOR FHEL I:O ,RC'ING I- 19 (gS G(iNF RATI OR VOLT RI:G TROUB3[ 1 1- 19-1`8 TGTMS Al.ARNI SETPOINT EXCEEDED Increasing IExciter Ihicld Current 30P ldcrtif\,report umain generator field forcing. I3ORiUS Pciform immediate actions of I BwAR 1-19-136: If Voltage Regulator failure is suspected then,
- SI11T Voltage Regulator to OF1F
"* Using the Base Adjuster, Reduce exciter field current to <100 amps
- Notify Electric Operations BOP/US Perform subsequent operator actions of I BwAR I- 19-B6:
- Refer to Bw-GP 100-3A6i3A7 for MW and VAR limits with regulator out of service US Inform SMiElectrical Operations of Voltage Regulator failure.
RO Monitor Primary plant response during the secondary transient Assist BOP as directed/requested by US!BOP
"* Determine MW vs VAR loading
"* Investigate Bwv\ARs
"* Provided appropriate peer checks to BOP as requested
"* Make phone callsinotifications as directed NOTE: IF Exciter field is NOT reduced far enough Turbine Generator Temperature monitoring System may alarm and the following actions might be required.
CUE: Anrnuncators: 1-19-F3 1(GITMS GEN TFMP TRIP STPT EXCEIDED 1- 19-18 TG1TMS GIEN IEMP ALARM STPT1EXCEIEDED US Implement 1Ivf OA TG-2, "01GTMS TROUBI1E" and direct operator actions. (CRI:W Veril'y Main Generator operating within limits.
- Refer to I BwvGI 100-3A0. 3A7 f'or excitation limits
( I(1111i1c lts:
, "'. i, , , , j -', ýi ý-, ,ý ; ýý( I . ;I III I'll"c ' )
%,ccnai o No.: 2 lent No vent 1)Descript on.: Voltagc Regulator mialfinction F*ld FoFrcin Time Position Applicnt's Actions or lcha\ ior BO3 l)ispitch operator to check proper opcration of thlc folloxvgin turihine generator Nupport s,vste0s
- Stator wxater 0 Ilydrogen cooling
,. lydiogen seal oil
* !xciter cooling
"* Bus duct cooling
" 'Iubine oil BOP IU )ectermine that problcm is due to excessi\e V,\\Rs and reduce Exciter field current with Base adjuster to clear condition.
NOTE: Wheii actions are complete for voltage regulator failure and with lead evaluators concurrence, Events 4 is entered Comments: J':!:':. I + 1: .'I (l .)
Scenario No.: 02-2 ecrit
\ No.: 4 vent
Description:
Stcmn ( cncrator IU controlling le ciChannel 1 1T539 Failed 11igh on a scc riamp Time Position Applicant's Actions or Bchav ior (CU[: A 111ln11c ators: I - 15(4, "'S l(I ICOW NISM.AT'I FI \" 1CWILO..W"' 1-15-0C8,"S G C [.VI 111-2) TURB IRIP P-14 A IRT" 1- 15 -'9, ".'G IC I IV1:V I )1VIATION I lG I I I -OW'" I:RV I FW53 0 closing I 1V-539 meter indicatin , full scale I cedwmaer flow decreasing BOP' [9S Identify repoit failure of I.T-539 IC SG Narrow Range Level C(alnncl US Implement 13\vOA INSI-2, "OPZRAT[ION WITI A FAAILED INSTRUMFNI[" Attachment E and direct operator actions. 3OP Take mantial control of IC SG Feed\r atcr Regulating Valve 1IFV'50 Increase demand to control feedwater flow greater than steam flow to restore level to normal IOP Check affected SG lex cl:
" SG level normal
- If NOT
"* Place feed reg valve in manual
"* Restore SG level to a stable condition
"* Operable SG level control channel selected a Select IIT558 as control IOP I)ispatch operator to locally trip bistable for failed channel by placing indicated switches to test 11II1-539 I C SG Narrow Range LIevel Channel 1 1I4 L3539A Io-2 Rx Trip/AF pump start I-B 539B L
US Determine Status of AMS System to be ok for this failure Commenltsll ,: 1;: 11,:A, -'! _,ýh, \!,ý ! I-11 ['TI::," i i
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Scenario No.: 92 2Hew o NY:. 5 I %cult
\ fDcscriptionl (ieiiti ifucllal (1aLreinii PumpIi)Yip I imlc Posiitionl -Applicant' A\ctions' or Becim\ 01r I 9 .\3 QIW P1JNI P IR 11P 1-(9-13 ('JIG I [NF FLOW HIGH I OW C harging puiiip trip indicatioin I 0'-.\ of'scal in~jection Ilowx indication RO Idenitii\ report trip of' the IA CA(,pump ROUS Refero BwAR fry charoing pump trip Or nmmediat operator actions:
Initiate and dii cet the actions of I IBwOA PRI-I 15 NOSS OF NORMAL CI IARG ING" C oimltte i I"( ,,:ik, I.,, j- ýý ,ý( I , 1 1A ý Q ý-,
Scenario No.: 02 2 Fent No.: S Fsent D1escriptlon: Centrifugal ('harging Pump rIip
'I ine Position \pplicait's
> \ctions or Beha\ ior R() Perform actions of I IxwOA.\ PRI- 15:
Identify neither CV pump is running Place IA (A'\Pump CS in 1pII P Isolate normal letdown
"* ('lose ICVS8149A.\.,C
" (Close ICV459 and ICV460 Check \CI suLction valves ('pen 0 1CVI 1213 and I CV I 12C Monitor and maintain VC I level greater than 2(,)
Check VCT T emperature II igh alarm (1- 9 -C2) not lit Check previously running CV pump was not gas boutid
"° !'I Seal leakoff flow not fluctuating prior to pump trip "o CV pump flows not fluctuating prior to the pump trip "o CV discharge press not fluctuating prior to the pump trip "o CV pump amps not fluctuating prior to the putmp trip Restore normal chartgitg flow "o Check miniflows open I CV1S 10 and IC\:S 116 "o Check RCS pressure at NOP Start the standby I B CV pump Check CV alignment
- 1CV8146 OR ICV8147 open
- 1CV8324A OR ICV8324B open I1CV8105 AND ICV8106 open
- Check charging flow established Re)US Refer to BwAR for charging pump trip for subsequent operator actions:
('o III ctIIts:
,, ýj ",I"( !
FScenario No.- 02 -)\cnt 2 No.; S [:\ nt l)escriiptioll (entlrfugal ChLnr'iii' Pum~p r rip Tine Positioin App, clia Actions or , chav ior l(OPPR() Restore normal leldo\kn flo\\ ptC I BiOA F\.SI'-2 "t.-I.. ,.SI:I1 1 N ( CV III DO\V'N DURING I-IONS. AI3NORMZ,\l CONI)I
* \'crifl' CI 0.St1:1) 1CV 14 9A, 13. le. tdo,,wn orifice isolation Nah c.
- Verify C1 OSFI) IC \ 459 & II'CV460 letdo,,vn line isolation vaxe's
- Check 1I \8401.-\ lctdov, n lix isolation valve OPFlN SVer ify IC\,8,324 \ and I(CVS3899A regen lix isol vaIl es OPWIN
- Veify I C815 V I and ,160 letdown C'nnit Isolation vail es OPE]N
* \critv BTIRS mode sclecct N\Vitch (OFF
- Place I CVI _'I controlIler in MANUAl. at 40'*,, demand P'lace I CCl 30AN 13 flow controller in MANUAI, at 60" odcmand C(heck CV flow established I CV8 105 and I ('V8106 open
- Throttle I C'V 1 2 and I CV 12 1 to establish - 13 gpin seal inj and 100 gpm charging flows
- Open ICV459 and ICV460 if'closed
- Simultaneously perot rm the tollwing:
- Open orifice isolation valves I CV8 149A B.'C for desired flow
- Adjust I CV 13 1 controller to maintain letdowN n header pressure at 360 psig and place in AUTO Ensure I CC1 30.N\B controller maintains letdown temperature 90' to 1150F E
and place in A U TO
- Verify IPR06J in seri ice RO/'US Dispatch operator to investigate cause of I A CV\ puImp trip.
US Refer to Tech Specs for tripped CV pump.
- 3.5.2 Restore in 72 hours
- TRM 3.l.a thru d
- 3.8.1 DG Required Actton 13.3 declare bolh CV pumps inop if condition of DG and opposite train CV purmp exists for 4 hours.
US Inform SM/Maint of IAi CV pump trip/status. NOTE: After the actions for charging pump trip are complete and with lead exniners concurrence, Events 6-8 are entered. (C(Iiii Ceits: i:: ...i * ".' *i'lI ",.~ ' ,'1 ,. . ..
* . ., , . N )Il
Scenario No.: ()'-2 I ,,ct No.: (6, -7 and 8 I ,ciit DcsCriptio01: Steam 6cfcriator W T ube Rupture (4(60 gpm).(7) intrumentCM Lus I I I failt whCien the reactor is tripped (8) l13 S1 Pump f1ils to s-tart automatically, NManually start an SI pump and Manually Align train
\ I ('('S 'or Injection due to f1i liiire to autlo Stalrt f'rom1 loss of insti ument bus I1 (9)
Time Position Applicant's Actions or Behavior C(U1: A 1\inc Iators: I 14 P/R [ IiVFI1 CONIT DI W ILOW 1- 12-C' P/R PRI-SS CONTI DEV I.O\V I IiRS ON SO blowdown radiation monitor I PROS.I increasing SJA\ Gland Steam 1I haustcr i adiat1ion monitor I PR 27.J increasing Increased chargimg flow P/R level dropping PZR pressure dropt)iiig F W flow Steam flow mismatch for I D SG Fced Reg Valves and FW Isol valves will remain open Main FW Pumps continue to run (fail to trip) CRE`W Identify/report increase in RCS leakage RO Report inability to maintain PZR level > 17% US Direct reactor trip and Safety Injection initiation RO Manually trip reactor Manually actuate St US Implement I13tN-P-0 "-REACTOR TRIP OR SAFETY INJECTION" and direct operator actions. RO Perform immediate operator actions of 113xx FEP-0: Verify reactor trip 0 Rod bottom lights IIt
- Reactor trip & Bypass bircakers open
- NCulron f]l\ decCieasing C ommenten I.s:
Scenario No.: 02-2 F\ cn No-: 0, 7 and ,
]ctDIl
Description:
Steam ( cncrator C I['ubc Rupture (460 gpmn).(7) IistruitltCnt Bus I11I fault when thC reactor is trippcd (S) 113 SI Ln putp and Manually Ain train A t' C'(S for Inect1ion (duC to failure to autto start trom loss of in1str1unCrlt bus 1 1 (9) Time PositIon Applicant's Actions or l3Fhavior B3OP Perf'orm immediate operator actions of' I lv*,IP-0: VCrifd turbine trip I urbibic throttle \ alves closed a 1urbine governor \ ah es closed HOP Verity powcr to 4KV busses
- Bus 141 alive li t lit
- Bus 142 alive hlit lit CREW Check SI status:
- SI First OUT annunciator lit (I-I -CI)
"* SI ACTUATEID lit (I -BP-4. 1)
"* St Equipment actuated (CV Cold leg intjection S188011B open)
Determine SI actuated Identify/report train A ESFAS components did NOTI actuate due to instmrment bus Il1 de-energized. Actuate SI by taking either SI switch to ACTUATE
" IPM05J "o tPM06J BOP Verify FW isolated
- FW pumps tripped
- FW Isolation Monitor lights lit a FW pump discharge valves stroking closed I W002A-C R)O Verify ECCS pumps running
"* CENT1 Chg pumps IA CV pump is una\ ailable ' 113 running
"* RI I pumps- manually start IA RI I pump IC SI pumps - manually start IA SI pump and or 113 SI pump E-0--4 C'om eIt,1 s:
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Scenario No.: 02-2 1 \ ct N.: 6.7 and 8 lcut l)escripton: Stcam (Generator I C uhe , tipture (460 gpm).(7) l1StrumeuCI Bus I I Iault w\hen the r eactor is tripped (8) I B SI PuMp faiN to start automatically. M\anual ly start an SI pump and ManuaIly Ali-n train A I (CS fR Injection due to failurc to auto start from loss of instrument bus I 1 (9) limc Position \pplicaant's Actions or Behavior IMP Verifyý ",,\ systeml: S113 A\F puunps running
- Manuall Starll IA\ AF:IpLinp
* ,\ isolation \ ax cs open (At I 3A\- I)
A\l flow control \ at\cs throttled (AFl005F-t 1) NOTE: The A train AF005A-I) ill Abe closed due to loss of instrument bus 111. Vcri C'C Pumpruns rmunning SMNanually start I \ C C pump Verify SX Pumps running SNManually star I A SX pump Check Mlain Steamline [solation NOI required (heck C SG pressure > 640 psig
- Check CNMI pressure <8.2 psig 13OP Check ifiCNMTF Spray is required
- CNMI pressure < 20 psig Determine/report CNNtI Spray NOT required BOC) Verif'y total AF flow
- AlI flow > 500 gpm 0
- SG levels maintained betweie 10"0 , and 50%
BOPRUS Check for NR level NOJ increasing in uncontrolled manner Identify/report IC as ruptured SG. ICTi If ruptured SG suspected. isolate AF Isol \ alves: E-3-A l1:013C 1A
- I AF0 13(
Con)mIItIse Is:
Scenario NO . ) -2 F cut No.: 6, 7 and I cut D)escription: StCam ( icuerator 1C TIube upturc (460 gpm).(7) IstrttumeCnt Bus I I I fault \\lui the rCmactor is tripped (8) IB SI Pump fbids to starl auIlltolmaticaI , MIanually start an Sl pump and Mlanuallv Alien train A\ 1[('(S for Injection due to IbtliurC to auto Start Ftlo10loss of HiuStruIeuCtI bus I 1 I (9) Time o iositIio Applicant's Actions or Beha\xior RO Vcri *, J('S valve alignnent (iro~p 2 (I lnjcction monitor lights NO all lit Manually align train A valves as required:
- IC V11 2B CLOSED
- 1C~V II-)12) OPIFN 0 lCVSl106 (CLOSEID
- 1IS18801 A OI-N RO \kic I I CC'S flow%:
, 1 igh Ilead SI flow x>100 gpm
- RCS pressure is NOT <1700 psig RO Check at least ONE PZR PORV relief path available:
- PORV Isol valves at least one energized
- PORV relief path at least one available
- PORV in auto and isolation open BOP Veritv Generator trip
- Main Transformer output breakers open
- OCB 1-8
- OCB 7-8
- PMG output breaker open BOP Verify t)G running
- Manually start IA DG (11B DG OOS)
- SX valve open ISXI69A
- Dispatch operator locally to check operation C o I I i I I [ts:
-; I " , (),ýt I
Scenarro No.: 01-2 ,cnl \No.: 0u and 8 FI,.ent D)escription: Steam (Gencrator I C Iube Rupturc (460 gpm).(7) hlstR-urnCent Bus I I I ault when the reactor is tripped (8) LB1 SI Pump fails to stall autonratically, Manually start an SI pump and NManually AIlign train A I CCS for Inject ion due to failuIIrC to auto start from loss of instruntenit bus I 11 (9) Time Position Applicant's Actions or B~eha\ ior 1301) Verit,'Y Control Room ent-i alion aligned for emeirgency operations:
"* Check RM- I I Grid 2 ('ontrol Room outside air rad monitors less than alcit alarm setpoint.
"* Operating VC train equi ipment running Train A
- Supply fan SReturitn la NI N f,an manuallk start 0A \VNC NI U fan
- Chilled watCr puLI11p
- M(R chiller 0A
"* M'U fan outlet damper NOT full closed OVC24Y
- VC train NI U filter light IIT
"* Operating VC train Charcoal Adsorber aligned for train A
- Place Recire Charcoal Adsorber selector switch to Adsorb
"* OVC43Y closed
"* 0VC2IY open
"* OV22Y open
"* Control Room pressure greater than 0. 125 inches water on 0PI)--VC038 130P Verify. Auxiliary Building ventilation aligned Two inaccessible filtcr plenums aligned T
"* Plenum A fan OV:\03C13 running
"* Damper 0VA023Y open
"* Damper 0VA436Y closed
"* Plenum C fan 0\NA03CF running
"* Damper OVA067Y open
"* Damper OVA052Y closed BOP Veritfv R113 ventilation aligned Train F B fan OVA04CB running OVA055Y open O
0VA062Y open O 0VA435Y closed O RO Check PZR spray valkes and PORVs
- Normal spray valvcs closed
- PORVs closed (Com m1rents:
i,ý; ;.
Scenar io \Ioý .)2-2 em"llNo. 0. id 8 Ivcent tce'erI lion Steaml Genleraýtor IC Tlube Ruplture (400 um)( Instruenilt Rus Ill fal when1 the veacoi is tIippedl (S) 11B SI IuPl11) Calls to Start anolaia MWIMCII l\\tIanuall Stalt an1StI)I1) pum ad Manua~lly Align tiami A F(CCS Ior In jection due to tai liii to auto 'stait fromlos1 IoSOf' inStRIuMent buIS I 1II (9) T iime Position .\pplcanits Actiions oi Rehavior, R) MIaintain RC'S temnpetature- Connol0
- Check RC*I)s, aim' i-1.inn1in1
- Id\e Stable or t-rending to S557 T R() tUS Check StatI~S of' RCPS anld dete-imine RC PS Canl Iemlain nnin If llan influning, afpl\ trip cri 1cma "o h11,ig Ilead St flow I100 -,pm on t I 0- t17 OR "0 SI flow 200 (,Pml on 11:1-9 t18 9~2)
"o RC S preCSSuIIc < 1425 psi 1101) C heck if SG secondary pressure boundaries are intact
- Check pressuire in all SGs
*No SG pressure dcierasing in anl nLCOnltrOlled manner
- No SG completel'y dcpressurizled CREVV Identif'y ruptured SG "o Unexpected rise in NR level onl IC Steam Generator "o Main steamlinec rad monitor s NOTI normal for plant conditions onl I C Steamn L inc "0 RT-AR022 Grid t 4A[)3'-
"o RI AR023 Grud 1 4AD32)3 "o ItI igh activity foi any SG sample CREW Identil'y'report IC SCJ as ru~ptured us Implement IMwEP-3 "STEAMI GENERATOR TUBE RUPTURE" WOG-IC anid (lirect op~erator a ctons.
R() I S C heck statuIs Of RCTS and de~tei m ine RC Ps canl remain r unn ing
- Ifany irunning, apply trip Criteria o Itigh Ilead 81 flov.,>t100gpin onl IFII917 C)R 0 S51flow >2100 gpmn on 11:1-9918 922 o RC'S preCssure- < 425 psig C'onniments:
S*wcnnrio No. 0t -221I ciii No.: (0. ,7.and , x cni It)cscriptionl StCam (CIencIralor C tIubc Rnpture (460 gpm).(7) lsnsti-neCntI tBisI I I tanLh \VhCn the ieaeteor is tripped (8) 11 S[Iunip fails to stt-t atitonhitiCally- Muiuilly stat an SI ptump and NIanually Align train A 1CC('S for Injection due to failure to auto start from loss of instrument bus 1 1 1 (9) time lPosition Applicant's Actions or Belhavior CRI \\' IdCnlti'c ruptured S(
"o Unexpected rise in NR level "o lain steamline rad monitor o 1RT-AR022 Grid I 4AD322 o 1RT-AR0 2 3 Grid 1 4.\D...
"o IIiligh activ ity tfor amy S sample Ideinit 'i-cpoi- IW SGS is i upitured SG Isolate flow trom rupiuie SC
- SG PORV IMS0 I(SC in AUTO
- Check SG PORV t %ISOI 8C closed
- Veri fy closed k]hen SG pressure < I 115 psig
"* Verify SG blowdown isolation valves closed
- I SD002G
- ISD00211
[C"I "* Close MSIV and MSIV bypass valves for IC SG E-3--A o Check PORVs on intact SGs available for RCS cooldown BORPUS Check iuptured SG level [CTI "* Narrox, Ranige > 100 E-3--A "* Verify/close AF isol valves (should have been closed in I BEP-0) 1AF01 3C (Close if flow is present indicating leakage past the closed I AN005)
- IAF013G BOll Check Rupture SG pressure
- Ruptured SG pressure greater than 320 psig
- IfNOT go to I BvCA 3. 1
'Oxi I IIn tis'
'5', I
Sc<enario No (,I2-2 cnt No-: 6, 7 and 8 I vent
Description:
Steam (CentCator IC 'ubc Rupture (460 gpm).(7) Instrument ,us I I I I'null whhen the reactor is tripped (8) 113 SI PIuimp [ails to start automatically, ManLIal ly start an SI p-}um1p and MarmiaulyI Align train I ((.'S torI- Inheittoon dlue to t'ailurW to auto stat t horo loss o1" irstturcnt bus II 1 (9) Iiimec Position Applicant's Action:s or Behavior B10) Initiate RCS Cooldown 1CTI
- Deternmine required core exit temperaturie friom table based on Currcnt ruptured SG pressure I+-3--B
- Check P/R pressure < 1930 psig
* /R IPO v PR*.SS Sl 131LOCK PIRMISSIVE [-I I[.it 0 II'NO I..ontinue wxith pi oce(luirc until P- I ILit beforie blocking S MNI[.IN: SI a Block Steamlinc ISol 1(0 I1 il
, Place STM I INE SI 1L3OCK sw,itches to II.()C(K t\or train A and 13
- Dump Stean to condenser from intact SGs it nixaminul rate NOTE: After cooldown is intitiated the operators may h1old( the Steam Dump Interlock switches in Bypass as temperature approaches the P-12 setpoint to prevent interruption of the cooldowin.
If the interlock occurs the operator N,,ill have to place the main steam pressure controller in manual and at minimum dlemandcl, bypass P-12 using both switches and then re-establish the cooldown.
"* Check average of ten highest CECs less than required temperature
- If NOT continue With procedure and stop cooldown when less than required temperature
"* Stop RCS cooldown (continuous action in effect) when < required temperature BOP Check intact SG levels:
"* Narrow range levels > 10%.
"* Control feed flow to maintain narrow range le\ els between 10% and 500.
"* Check narrow range cle els not increasing in a-n uncontrolled manner.
RO Check PZR PORVs and isolation .alves
"* Power to PORV Isol valves I1RY8000A 1RY800013
"* PORVs closed I -RY455A I1RY456
"* At least ONE PORV Isol valxe OPEFN o IRY8000A o 1RY80001 I303 R () Reset SI if necessary Comments:
,I: 0
Sccnario No.- 02-2 I cuit No . 7' and 8 I iet Descriptlion: StCemI (GiCnCrtor IW" IubC Rupture (460 gpm).(7) Illnsl'tllrlCluIm B IS I I I faut11 \ henl the I-cactor is tripped (S 113 SI Plumnp fhils to staMt tomatically, MaMnully start aMn SI pun1 and 1 la1 ually Align train A ]C('CS for InIjcCtion duc to fa lr auto to sta0rt from loss of inlStIullelCt bhus Il 1 (9) Inme Position Applicanlt's .ctions oi l3cha%ior 3OP Reset (NM T Isolation: a Reset CNNI I Isolation Phase A.
- Check SACs anm running
- Open instrumelit air CNNIT isolation valt es.
- IIA065 II \t)6 ,
MOP \Vcrifiy all AC\(' busses eierizic1td by ol 'fite po\ cr ROP Check if RII pumps should be stopped:
"* Suction aligned to RWST
"* RCS pressure greater than 325 psig
"* Stop RI I pumps and place in standby RO Check if RCS cooldoxWn shoutd be stopped
"* Check average of ten highest CFTCs less than required temperature If INOT then do NO T proceed until required temperature achiex ed.
"* Stop RCS cooldown
"* Maintain average often highest CETCs less than required temperature BOP Check ruptured SG pressure:
- Stable or increasirg B. k j '..IIec iK _ suDcOO lin g:
Acceptable per Attachment A and Figure 1BwIP 3-2 ( 20°1) Co1in citin .t
.. f.. . ,"
.. , ( ",. !!
'*1'
Scenarito No.- ~ctN (1, -7 and S l-\,cu DesciipIioii: Steam (nciiator 1(C Tubc Rupture (460 gpm).7 InstillnmCet Bus I I I faIult w\hCn thc reactor is tripped (') IB SI PLIImp fails to stairt automaticalBs.\, Manually start an SI pump and Manuall\ly Align train A -(CCS f10 InhjCct ion due to failure to auto -tall r"oi0111 loss ()'oinstrLuiient bus I 1 1 (9)
-lime Position Applicant's Actions or I3cha ior RO I)cprcssuriz e RCS usin, }!tR spirays to minimize break flow and rcfill PZR:
[(T]
- Normal sprays available E-3--C
- Spray P/R with maximum Sprai Until any of the ol lowing are satisfied 0 [3011 1:
- RCS pi esSLre less than ruptured pi-c-SUlV
- P/R Ilc\ cl grcatr than 1t")
o I' R lc\el rieater than 69',o o RCS subcooling N(T)acceptable ( 'lose normal spray vaalv es
- Check P/R Aux spray valve closed Use ONE PZR PORV if normal PZR spray is inadequate ROeBOP Check i 'ECCS flow should be terminated
"* RCS subcooling acceptable
"* Secondary heat sink 0 Narrow range level in at least ONE SG >10%
OR 0 >500 pgm total feed flow to SGs
- RCS Pressure stable or increasing
- PZR lexel >12I'o ROB OP Stop FCCS pumps and place in standby
"* Sl PIinps
"* All but one CV PuiMP NOTE: The scenario can be terminated once ECCS termination steps are complete wvith lead examiners concurrence
('Om m1!cII1S:
' ." . "; ,C ,P I',: ' " '! !
SHIFT MANAGER TURNOVER Weekday, Today, 2001 ONCOMING SHIFT 2
'UNIT I STATUS. UNIT 0 & I MAJOR OOS's MODE .. 1 lB Emergency Diesel Rx Pwr ............ 100 Generator Generator MWe ..... 1256 Max Load/Power .... 100% IC Heater Drain Pump Min Load/Power .... 700 MW Max Ramp Rate ..... 5 MW/Min Desired Delta I ..... Target On-Line Risk ....... Green Boron @ .......... 934 Control Bank ....... D @ 214 UCOAR ENTRIES PREVIOUS 48 HRS . UNIT 0 & I MAJOR SURVEILLANCES 3.8.1 Condition B for 1B EDG BBwOSR 3.8.1.1 - due in 6 hours 18 hours ago. Est RTS by end of shift 3.4.13 RCS Leakage - IC Steam Generator at 5 gpm UNIT 0 & I IN PROGRESS IB EDG turbo charger replacement UNIT & 1' PENDING, Following step 10.c RNO of 1BwOA SEC-8, Shutdown Unit 1 per 1BwGP 100-4 due to IC HDP bearing replacement increased operational leakage - IC SG.
Shutdown unit to MODE 3 within 6 hours. tB CCW Pump run for ASME Testing ll3wOA SEC-8 has been in progress and has been performed up to and including step I0.c Focus Areas:
- Verification Practices
- Command and Control Standard for Execution of Critical Steps TIlINK CONFIGURATION CONTROL and SAkFETY'!!!
SCHEDULED ACTIVITY CONFLICT IC21 (!oQ
SHIFT MANAGER TURNOVER INIT 2 STATUS r
,1OD E ............ 1 Rx Pwr ............ 97.6 Generator MWe ..... 1197 Max Load/Power .... 97.6 impulse pressure Min Load/Power .... 700 Max Ramp Rate ..... 5 mw/min Desired Delta I ..... Target On-Line Risk ....... Green Boron @ .......... 1037 Control Bank ....... 210 LCOAR ENTR.IES PRE)
"icoar num" "Affected Oil change on Unit 2 Station Air Compressor. RTS by end of shift today.
)ose INFO: Dose goal for day 10 mr SCHEDULED ACTIVITY CONFLICT 1c21.,; )C
SHIFT MANAGER TURNOVER Administrative Iemporary Procedures I Modifications T-mod Ul Trn B RVLIS. Jumper Installed on tfC U-I MPT Disconnect. 1FW009A T-Mod for Hyd Pp Press Sw 1PS-FW162. T-mod for drain on 1 B AF casing. Tmod for no disc in 2CC9502B installed. Daily Orders / Special Oo Orders Daily Manning Schedule See sheet for restricted duty personnel and overtime restrictions Oncomina STA h-rn ('hf Control Room Rounds (GSEP / LER / DVR / ENS) Material TS Conditioning SFP High Level alarm did not alarm during calibration RWP's / Releases / Precautions / ALARA Infrequent Evolution Activities Lesson learned files L:shared\opex then ctrl F to search SPSO / Division LD Alternate BPO Outside # 815-727-5902/5903 Tie # 8-565-5902/5903
..... Unit...I Comments' `,"'-Unit Common Comments Battery 112 cell 32 has floating naterial in electrolyte, eval'd OK U! FC Cleanup SFP D.O. 0OS prevents filling U- I tanks normally, but BwOP DO-6 U2 FC Cleanup OFFLINE (leak) can be used to fill tanks. T-NIOD is installed allowing U-I boiler FC Cooling Ul ops. 50K DO Tank empty IAF006A is leaking by from (ST. 125K DO Tank and FRAC Tks Certified Aux Steam U-1 ES ->U1 HDT U-0 CC Hx U1 U-0 CC Pump Bus 141 U1 Aux boiler Wet lay-up U2 Aux boiler Wet lay-up SAC / Dryer UL1/U0 MUDs U-1 CST CW Makeup Running OA/OB CW Blowdown On Lake Level 5.8' r; /Air--U I M eaKing Unit 2 Comments Dy .3 gpm, AR 990116738 S/G sampling lines/valves at HRSS are not correct. Do not IConference Call Phone Number-folder ID #=472664085 neral Comments 1 800-232-1234 TeleconferenCe hang COS on any 2PS181 valves till further notice. Meeting Place 630-663-7120 +code 2PS229A still blows fuse 2PA32J Ckt 9 Duty Team is located @ SITE APPS, NRC Duty list in book CV seal leakage: Substation construction (John Strle) Cell phone 815-351-8472 2A Running 200cc/min shutdown about 6 drops/min 2B Running -12 dpm; S/D- none CCNM PN Caution Cards Abnormal Positioned Components (C,,* NiU A~ rt~ i ,AonormajnOSilbOn SM BEEPER TU-RNOVER Shift I To 2 Time Now Date Today OfUgoing
SHIFT MANAGER TURNOVER
.OPIRATORS CONCERN LIST p' venry Kz Concern I 2B CV Pump Monitor seal leakage shiftly - Notify System Engineering if > 0.5 gpm 98-049 UNIT 0 CONTROL ROOM ANNUNCIATORS LIT I Aonypdoator 0AncuatbrDescrFptn__ 4ý21PoI, R#NVR# ýýt S taus UNIT 1 CONTROL ROOM ANNUNCIATORS LIT ;Annunciato'r Annunciator Description ~ r-oblc-ýn.>. . AR#,IWR Status ~ 2 UNIT 2 CONTROL ROOM ANNUNCIATORS LIT IAnn JI 'Us Concerns and/or Pending OP-AA-101-301 Evaluations EPN
_ I__
-Unit 1__~fto Unit 0 I__
Resolution,. 1("" hi()
BwAP 335-1T( Revision E Information Use UNIT 1 NSO TURNOVER Weekday, Today, Oncoming Shift 2 _______________-_________________ Unit I Status Mode 1 Max, load/power 100% Power 100.0% Max ramp rate 5 mw/min. Mw electric . 1256 MWe Unit Risk . Green Min .oadi/power . 900 MWe Control, Rods 214 Desired Delta-I Target Boron concentration 934 PPM IN PROGRESS- PENDING 1 1B EDG turbo charger replacement. RTS by end of shift today BwOSR 3.8,1.1 1C Heater Drain Pump bearing replacement Per Step 10.c RNO of 1BwOA SEC-8, shutdown Unit 1 due to RCS operational leakage to MODE 3 within the next 6 1B Component Cooling Water Pump run for ASME Testing hours. 1C Steam Generator leakage at 5 gpm 1BwOA SEC-8 is in progress at step 10. LONG TERM. . * .' ADMINISTRATIVE Temporary procedures Temporary alterations New caution cards Unit logbook Unit routine BDPS Icoar in mode 3. Aux. Electric room access Daily orders Control board walk down LCO/TLCO RETS DEQUIP/AAR 3.8.1 1B EDG 3.4.13 Leakage It
BwAP 335-1 T( Revision ý Information UsE TURNOVER ITEMS qSO SHIFTLY/DAILY SURVEILLANCE z) SSPS CHANNELS/BISTABLES B train SSPS logic ground to chassis ground had higher than expected readings during SSPS, AR written.
- 3) SYS - SAFEGUARDS
- 4) SYS - PRIMARY CC to spent fuel pool hx is at 2800 gprn.
- 5) SYS - BALANCE OF PLANT Spent fuel pool cooling now on Unit 1.
- 6) ALARMS-SER/ANNUNCIATOR
- 7) ALARMS - PROCESS/RM-1 I
- 8) ALARMS - FP/OTHERS
- 9) CHEMISTRY - Max flow through condensate polishers at full power is -2000 gprn without causing a low npsh alarm. This is only a guideline and not an absolute value.
- 10) RADIATION PRECAUTIONS
- 11) NUCLEAR INSTRUMENTATION
- 12) MCB INSTRUMENTATION
- 13) MCB CONTROLLERS
- 14) ELECTRICAL DISTRIBUTION - AC MIPT transformer disconnects has bad seat on one phase. Jumper installed, SOC on disconnect -do not operate.
- DC
- 15) ELECTRICAL DISTRIBUTION
- 16) EGC STATUS
- 17) BWOP (PROCEDURE AND STEP IN EFFECT)
COMMENTS 13 gals of PW will Raise RCS .1 F 1 FW009B has small nitrogen leak on 1 PS-FW1 65, AR written.
-POST.REVIEW us. .M FS TIME: NOW SHIFT OFF GOING DATE: TODAY SHIFT ONCOMING
'2
'I
Simulation FlICIxrk i ood Scenario No. i (O)pcr lng Icst No..()." "
]Fxa incrls: .,\ppl Cant: ___________________ S R( )
R*() 1301 Initial (onditions:, I('-21 , 1000( poxwCr, 130(), cquilibrium Xenon. steady stale TurnoveC: 93`1) power following ramp from1 00"(). IA CS Punip is (O)OS 6or a motor bearing replacement. 11) ('I)1('B pump is O)S for an alignment and vibration problen. 1Load Was reduced 1Om111 1()(0)% power due to ('13 pump suction strainer delta-p. Furtlher load reduction is anticipated to allow isolation and lLIlShinrio (l'thC W(-'R1 Pump ScCtion strainer. [H'vent Malf. No. Lv cnt vx'cnt No. Ivpe* Description PIlod RP() I IM R() Failure of R A&B to auto AND manual open (can bc opned locally) SRO I A CS pump OOS CS01A BOP Failure of CS and Phase B to Actuate on I1i-3 Cnnit Press. Train B must be manually started from the MCR __ FW 221) 11) CD/CB pumnp OOS l'ICload (preload note) C RO I SI8801 A will not auto open nor open from the MC13 SRO I S18801 B will not open automatically. Will open manually froni MC13 N 13)P Ramp down turbine power to 900 Mwe at directed MW/min SRO R R0 ILower reactor power using rods and/or boration. SRO 2 NIO9A I RO Power Range N-41 fails high. SRO 3 FW2213 C BOP Trip of IC CD/CB Pump. Standby CD/C13 Pump not available SRO 4 RD09, I C RO) Automatic rod motion fails at I step per minute. SRI 5 RX031, 4.8 1 130)P Steam Flow Transmitter FT-532 (input to controlling channel) fails high. SRO 6 RP()2A,13 NI RO Reactor Trip Breakers fail to open / ATWS BOP SRO 7 11106 M RC) Large l3rcak IOCA inside contairnlelt. I.cads to high-3 containment pressure SI) 8 T[I()6 (OR,) CS () 113 C I10 P F'ailur c of CS to auto actuate.
."dR P63it cat, R()
SR() (I)rn -trrun lCut. (( ')onlpoilc ll, (.').joi I rannicr/t
S('1:NA\IO OV'ER\VIEIW T'he [,niit I is at 93"o power. 11 I I)('B putmp is (0))S for a io nlnit and %ibration problcms. IA CS Pump is (0).S for a motor bearing rCeplaccutrilPowcr vxas reccntly (decreased firoil 100' due to ('[3 Pumnp suction strainer dClta-p pmc blemis.
"urtheC load decrease Will be required to stop the Iuun nln ( C ('B pum p anid Iush the suction st a iner.
Followingc eamly observable plant response Iiom the icactix'ity changes, PowFer Range NLiclear Instrumncrt N-41 %,iIll f'alil high cauLisinig a demanid 1`1- Inward rod notion. Tihe crew will diagnose the PR failure and perform actions of 113\\ .\ INS I -1, NUJCI I'AAR INSTRUMI NTATION FAIAURE- Atlachment A," to defceat the channel and restore Tavel'rel'. The SR( will reii ew 'I'S and direct tripping of tic associatcd bistablcs. Alter completion ol'thc actions specified in I lNw(A INST-1 the IC CD C) (' pump vIil l trip on o ercurrient. The Crew will enter IBw().\ SICC-I, "StCONDARY PUMNP TRIP", and commence a runback to reduce load to within the capacity of the rCmaining two C)!C'B pumps (-700 Mw e). Rod Control is failed such that any auto rod motion wx ill occur only at I step per minute, which is less than the expectedI minimum rod speed for the temIperaturle transient ill progress. hc crew may elect to perborm steps of 113BwOA ROD-I , "UNCONTROI I'ED ROD MOTION", but it is NOT required. Rod Control Wxvill be shifted to manual to mnatch Taxe and Tret'at the new lower value. Following completion of actions for the CD/CB pump and rapid load reduction, the I C SiG selected steam flow channel Will fail high, resulting in indications of increased steain flow and initial opening of I C SiG feed reg valxe to attempt to match feed flow xwith steam flow. An equilibrium level should be reached if manual control of the feed reg valve is not expeditiously taken. The crew xvill perform the actions of IBxwOA INST-2, "FAILTED INSTRUMENT CIIANNE[, Attachment I1". After the unit is stablilized following the SF channel malfunction, a large break LOCA of 50,000 gpm occurs, increasing to 400,000 gpim over 2 minutes. 1The size of'the ILOCA will result in an automatic SI actuation and lead to the discovery of the failure of the reactor to automatically trip. 1BxwIR S. 1, "RESPONSE TO NUCILEAR POWER GENERATION x IWS' will bc entered. After dispatching an operator to locally trip Unit I reactor, the reactor trip breakers xwill be opened only after placing the steam d(umps in OftTReset per step 7 of x3wER S.l. Follow,,ing the safety injection actuation, cold leg injection valves I SI8801 A&B xxill fail to open. I S1880113 must be opened manually from the MCB. CS Will fail to automatically occur at the high-3 pressure setpoints. Manual action by the crew will be required to actuate train B of CS, either while performing the actions of 13w 1tP-0 or the SRO may elect to perform IBwFxR Z. 1, "RISPONSF, TOI lIGItI CONTAINMFNT PRFSSURE" The scenario ends xvith completion ofestep 6 in II3xxT 'S-1.3 Critical Tasks
- 1. :R-S. I insert negative reactivity into the core by nan ually inserting RCCAs before completing step 4 of tR-S l.
- 2. 1:1-0--1 Manually initiate high head inject ion flow via I SI880113 before exitingI 13wNl1-0
- 2. FlP-0--I': Manually actuate at leaSt the minimum reqtuircd comlpliment of'containnlent cooling equipment be f ic an extrcine (red path) challenge develops to the conlaitnlmclt ('SI
SIMIUlATOR OPERA EA O R NOTE S: Simulator Setup: IC-2 1, 100% power. Complete the *reidv for trarin ing' checklist. I lang YI -I,[\(V)\ risk placard. l)ccrease Unit load to 1150 MW\ usinge turbine load decrease and iods only. Allow to sta'-bilize. Take I A CS pump OOS. Control s\\ itch to PU[l, OUT. Itang' I g Take 1I) CDiCD pump OOS. Con0i-ol Switchl to PUILI, OUT. [Iang TaogIa. Take 11) Cl) CBi3pumpIax lube 01 ptmp O(O)S. Control switch to PUI -1, OIU. I lang Iag. Go to 'Action I.ist' and use the t'o\ving ovecrrides and ma Ifunct ions: Z/O0I SISSO(IA I ON ZLO I S18801 AI ON (must do both C\en though they are identical tags to get both indications) RF FDO53I OPEN (opens breaker for I SIS() IA at 131 Xl :F4. When used with the overrides it appears the Valve is closed and energized. If operators are dispatched to dc-energize and open this yaixe, then use the Overrides to de-energize the valve, but do NOT open I S18801 A. Turn ON annunciator 1-17-AI0, CD PUMP SUCT STRN DP IIIGt, PN0991 (ON) Modifv Remote Function: Rp75 (on SDG RP15) to OUT. This prevents slave relay K603 froom energizing. Components affected are: ISISSO 113 will not stroke open on an SI, but can be manually opened from the MCI3 1CV8105 will not automatically close, but can be closed manually. I B AFW pump lube oil pump won't auto start, will not affect this scenario as the AF Pump xv,,:ill still auto start.
ýctivate the following malfunctions:
RP02A&A3 Faillure of Reactor ITrip Breakers to open in AuLo and Manual. May be locally opened after steam Dunips are taken to OFF in IBxwFR S. I CSO IA IA CS Pump Fail to StartIiTrip. Modify the following remote functions (after closing the valves): FID062A OPEN Breaker forl CSO07A ED053M OPEN Breaker for ICS0O A FD053A OPEN Breaker for ICSO0 IA F:D05313 O11-N B3reaker For ICS009A IMTodifv the following remote function: R1P63 OUTI to prevent 113 (R C )Sulnip Ioin staittiIg Until I CS)I 913 is manually opened. Insert the 1b loxx inlg overrides to complete the ()()S foi the 11) CDI) ý( pumip: Z/1I()13113D)(I) OFF- Open Iiglit 01]: /I,() 1('111 1f)(2) OH-' ('lose .'l1i1t ()FF
EAvcnt I Load RamI) to 700) MIVWe Evecnt 2 Po~ver Range Channel N-41 fails high (NI093B. 120) Insert malluIntioll to hu11 power range channel N41 high (Nl09)1. I20) aicr clearly observing plant response to reactivity Chan ces. or at the lead exllailincl-S direction. Pcrl'orIn the followx illg to trip PR channel histables: On SI)G RX4: Open Protection Cabinet D)oor I1 RX020 OPFN O'IT "Trip '1341 1(' (' -124 BS-3 RX013 TRIP OTIT)T Runback T1[341 I) C(-124 BS-4 RX135 TRI) Protection C'ab I"1 (,lose I)oor Rx020 CILOSE Event 3 Automatic Rod Motion fails at I Step per Minute (RI)09, i) Insert Rod Speed F'ailure Malfunction (RD09, 1) immediately prior to inserting the CD/CB pump trip Event Trip of IC CD/CB Pumnp with standby CI)/CB Pump not available (FW22C) Insert malfunction to trip IC CD/CB pump (FW22C) after all actions for the failed NI channel have been competed and MNV loading has decreased beloxv 1050 MWe Event 5 Steam Flow Transmitter FT-532 (controlling channel) fails high Insert maltfunction to fail IC SG controlling steam flow channel, FT-532 HIGH (RXO3E, 4.8) on SDG RX16 after
,istables for PR channel N-41 are tripped.
Event 6 Reactor Trip Breakers fail to open (ATWS) The ATWS mallfunction(s) are in Pre-load. When directed as a local operator to open the unit I reactor trip breakers, wait until after the steam dumps have been placed in OFF/RLSET. DEL' TEPmalfunctions RP02A and RP0213. Important: If the reactor is still at power after the S/Gs reach 10% ;wide range level, the RCS pressure x'will start to rise rapidly aboxe the Pzr Safety setpoints. Use triggers to delete malfunctions RP02A and RP02Bt when the steam dUmL1ps are taken to off. DNIF RI102A and B Event 7 large Break IOCA inside Cunit. Leads to failure of l1i-3 automatic actuations Insert 1,131OC)'A inall'unction (TI HOC', 50K to 400K over 2 minutes) inside coii talinment to ensure the I i-3 containment prCsslri'C sctpoint is reached. lItaskcd for I:1'R on I A C'S, 2-4 hours is opti)IistiC. ['vent 8 Failmie of (CS to auitormatically actuate The tui/iluc ot1('(S to aIto actutelC is in the Pic-load. ()p*cl'tors \\.ill Ima uallk alin the ('S xstei h0a(-Opci tiou.
Scenario No: 02- I I\,cnt No. I IlvCnt
Description:
Ramp do\\'n tnirhine and ract(or po\\er to 700 l\\'c T ie Position Applicant's Actions or chlia\ ior IUJI 1 rtle\ cr. (,cv icws and I oad S w i nlst-uction Shoe t may have been initiated in Ias.roon) 1S Irmplemcnt actions of' IIf\iv( iP 100-4 , rc\ 17, step I. I US Direct load ireduction to 700JNlxce at 5 M\NVmin S Ilnitiate load s\\win inistructiotn sheet, IB\',GP 100-4T1'2
- Contact chemistry and I P for load change --I in one hour C RIFW lR-,c\JeapplicIblh-cPrecautiloi,,, I irnitations and Actions of I I[w (Fi'i )4 lRDO Vet it rod positil aid borton concentl ratioti Initiate boratton. if required. (Bw'OlP CV-6)
- DCtcrtiine required boric acid volume
° Effects ot prexviOusIl performed borations
- Boration Dilution tables
- Determine reqcIircd boric acid flow rate
- Set 1I K- I 0 BA IFlow Control to desired boration rate
- Set IFY-0 110 B1A Blendcr Preset Countet to desired volume.
I:lace NI\AKf-P MODE CONT SWITChI to STOP position P
- Set NMU MODE SELECT to BOR position
- Place NMAKI-UP NIODE CONT Switch to START
- Verify proper- operationt of valves and BA transfer pump (I CVII 0B open, 13A Pump runnintg, ICVI 10A throttles open. BA flowý indicated on recorder.
OR Batch addition of BA:
"* Open ICVII OB
"* Open ICVI IOA
"* Start the BA Transfer pump
"* When desired amount of" BA has been added, Stop the BA Transfer PLtump
"* Close I CVII OA
- Close ICV1 lOB I 1 Co(i ill ellIs:
ý, I !1' !II, It i .) I
Scellm-lo Noý 02-1 ['\ciit No. I i-cactor I)o\N*ci- to -f)() \IN\ tý 11 Time RdIIII) Clo\Vll Wl-hillC
ýllld Applicant's Actions ol- Bella\ ior 11Fcill Descliptioll:
130P 11116ý11C tLIl-1)111C IkMd I-C(IUC6011: Dcpi-css LOAD RA IT' \M\VMIN 1"1)tCl- CICSil-Cd \ýIILIC 1'01- 1-ýItC (ý \MW Mill) Depi-css RIT I-II[Cl- CiCS11-Cd I'Mill tLll-hil)C loadIng ( /00 M\V)
\Vhcn read\ to begin load deci-ca,,c. depi-es,", GO Vei-il'), load t-ccluction OCCUI-illl-l RO, 130P Mollitol* l-cactol- powel. and load dccleasmý Monitoi- Nl',.,. Tave, Al. Pzi- pt-cs,,, lc\ cl MOllitOl- Nl\\C, Ullb 10ýldilll-', FIIC RO 1XII-111,11 BOK16011:
" Monitor \,'C-['I.e\fcl and PI-CSSLII-C
" Verify RC', boi-on concciin-ation inct-casim,
" Monitor 13A blenclei- counter
" Vei-ifY bonition Slops at I)rc,,,ct Ný11LIC NOTE: Following the required plant response, Event 2 may be started Com ments:
Scenario No: (2) I I,\ent No 2 [{vent
Description:
Po\\,riRange NI Channel N-41 Faill s liuh Time Pos',ition \pplicat's A.\ction',of 0 Bleha ior CUi InIlnlclatols. I- 0-A3 P\\,R RN(i 1l1(6ll S FP-I RNI RIP AI IRI" I-I!) B5 P\WRt RN(GFI.UX II IGJI R()D STOP 1-10-('3 P\VIR RNG I.UX RT\I RX TRIP I.FRT I 0 -C4 PWR RN(G C ..\NNI. DIV Rods mov\ing in response to High .,\u ctioncercd Nucleir Pow\ er PRNfIN41 indication, Failed high. ROf SRO Mdcntifx.'repoi tfailurC of PINI N41. US [liter 1IwOA INS-1 "'Nt(' I.AIR INST,RUMINI.ATION NIAIF IUNC"I ION" Attachment A PR 'hannel Failure, and direct actions. RO Place Rod Control in MANUAl Check Rod Stop (I-10-B5) Iit BOP Bypas>s the Rod Stop oir Channel N-41 at 1107, RO Control Tave - Tref to within I degree via manual rod control, boration or turbine loading BOP Check SiG (evels normal and stable IBypass/defeat PR N42 at I PM07J:
" Detector Current Comparaior (Upper and I.ower Section)
"* Pow\er Mismatch Bypass
"* Rod Stop Bypass (if'not previously pcr oimcd)
"* Comparator Channel d ceat
"* Remo c Control Power Fuses lfor high and Io% flux and rate trips.
USiRO Trip , istables for OTI0I)F TIrip and Runback (2 Bistablcs: TB4 I IC and I'B4 II D) Select operable I oop D[ recorder
\\1hen conditons are slable and Taxe is writhin I degree ofl ref return rod control to aultomalic US Reler to Tcch Specs (3.3.13. 2.4. TRM 3.3.11)
RLequCsLt to have risk performance done Notify SM N'aintenance of NI failure F C(o tInII I Ien ts: S ,', II:I iI, , (I. - 1
Scenario No.: (2- 1 l\cti No. I & l'\ ent
Description:
l1ip of I( CD ('B Pump. Stb\ not a\ ailahle. Rod speed Cails at 1 spin In auto Time Posithio Appr, liat's Actions of- Behavior ('CUF: ,n\uuunciaIor,: S1)-7-.\9 Cl) CB IUMP I RIP 1-17-I ('A PU P\IP SU"TIZI N DI' 1I GlI I I- 17-A (3 PUMNIP SUCT Sf RN 1)1) 11 l(111 I-17-B 1 ('1B PUMP D)ISCII FI.OW IIIGII A\nber pole disagreement light for (IC CD ('13 pump breaker. Inkcreasing flows on irunn11 ('1C
) ('13 pumps.
t3OlP U.S- IdCniify ieport trip of runiing IC C() ('B pump US Implement IBwOA SI-C'- I, "SI CONDARY PUNMP IRIP-Attachmcnt B'", and direct operator actions o Notifs chemistrV to mon itoi secondary chIenmistry due to transient
"* Complete applicable steps of 1w13\vGPl 100-4
" I lave risk assessment performed Noti f's' chemistry and I)IP if power change > I 5% in one hour f'or tech spec and RETS samples HOP Pierform actions of I BwOA SEC- I as directed by SRO:
"* Check turbine load > 700 Mwe
"* D)etermine standby CD'CB pump is NOT available
"* Depress Turbine Runback pushbutton
* \'erif'y turbine load decreasing Verify'('lose recire valke ICBI 13C If It' pump flows oscillating: Reduce NIFP turbine speed Check alarms NOT 111CI IEAR:
- 1-17-1311 CB PUMP DSCI FLOW llIGHl
- 1-16-4l FW PUMP NPSII LOW If either of the above alarms ILIT, perform the following:
"* Manually open CP Bypass (I CD2 I OA and ICD2 103)
"* Verify.'CI OSP CD pumps recirc (I CI 152)
"* VerifvyOpen GS Condenser bypass (I CDI 7A and ICI) 15711)
"* Vcrit' I IDP discharge valves opening in auto (II ID046A and 11I ID046B)
- Veiritfy ('B pump recirc valves closed (1 ('111 3A-I))
\\'hen load has stabilized and when directed by US. depress turbine runback puslibutton to clfear the i'unback Circuit COl 1l1ccnt":
N "" C'i '1 01 I
't t.I d lI ) , t \ - It xc111 No. _5 -(4 I I. - i) Niiiii - .il
%"" Colt t )'..S,; I lp~tltn: Trip of IWC C D B 13tInnPp. .tbv not i\ ailable. Rod spced Ia*il' at I sl-lm in ILt,0 Filimc Po,.itiori
\ppllicant's Actions or 13cha\ ioI
\erit\ ('Onltl'oIN hi .utoinatic andl~tresndinoi rlectly to the load decracsoe 0 Tiurbine dri\cNl I'lls
. 1 ID046.\ and 13
* (1311 3s
* (CD152
* ('131 7A and 13 a Shutdown tripped CD) (13 pLIump1 pCr lWOP ('C(13,-2 o .\d just 131) flows and CalOrnimetFiC input.- aN necessary o \crifi' DAIIC fecdback loops in scr\ ice (Impulse and 1B\)
N(OIT,: ..At some time dLuring the turbine runtback the crew should question the rod control response and discover the rod speed problem. From that time forward they should remain in Manual Rod Control. If they select Auto for rods they should note the rod speed indicator too low for mininiuni autio rod speed (<8spm) and return to Manual. IF BwOA RO1)-2 is entered for failure of rods to move the actions start on page 10 CUE: 1-14-1)1 TAVE CONT DENV HlIGIH - ,11T Re Perform actions of I B\ OA SEC- I as directed by SRO:
"* Verify rod control in Automnatic.
"* Initiate Boration as necessary.
- Maintain I ave and Fref within 3 degrees I While monitoring rod control response. identif\x the response is inadequate to maintain Tave 1Tref during the load reduction.
Tlake manual control of rods
- Manuallv insert rods to maintain Tarc and Treideviation within acceptable limits.
- Inform SM of rod control speed failire Re (Check PDMS operable as follows:
- 1-10F8 PDMS INOP[RAI.I not lit
- I lwOS PDMS- Ia. PDMS AAR not implemented
- 1-10-D7 PDMS .NIMIT NOT I lXCF1l)tD not lit Control delta I near tarect 1-10-136 ROI) BANK ILOW INSI-RTION LIIMIT not lit (if lit, borate as necessary, refer to TS 3.1.6)
I-[3l)-4.6 1LOSS 01: TURB IOAD INTILK (C7 not lit ('omlClIcts: l ri .. . . \1' W ( I riiI " :,I l " I, (, , - I
Scenario No. 02-I 1'\ cut No. 3 &. 4 [-vent D*cicriptiol: ITrip of W (CD)(13 Pump. Stbh not ax ilablc. Rod peed lfaik at 1 Spin In amto Time Positiol A\pplicant's .Cion:.. or liha, ior If I B*,()\A ROI)-2 is entered, the actions are below: US Il.i c I1B ) \ RO)) -2 and d'icrt actions: US RO Pci form actions axs (irecte: 0 Place Rod Control In MANUAL o Stop unnecessary Turbine I oad and Boron changes
"* C'heck Rod Stops NOTI [it:
"* PWR RNG F1.UX I111 I ROD S 1O)P ( 1-1)-B)
"* IR IHl(ilI 11 UX ROD STOP (I 1-0-A-)
"* TIURBINI ILOW PO\W:IR INT1 K C(-5 "3BANK 1) ROD STOP C- 11 (1-10-D5)
"* Check ROD CONT URGF`NT FAI URF (I 10-C'6) NOT Lit.
"* I)etermine if Rod Control Should be placed in AUTOMATIC:
SC-5 Not it
- faxe- Tre dceviation < I degree 1F.
- Determine that placin.g rod control into automatic will result inl wrong rod speed response NOTIE: \'hern the plant has been stabilized at 700 Ilw'e, the next event may be inserted Com1mnct1s:
I() N, "c:1, 11,, .
Scenario No: 02- 1 cnt No. I cnt D\e'scription: Sten FIo TIr31Iansn1itter I- -32 (input to Contiolling Channel) fails hgh Timc Positio A\pplicant's Actions or Reh a\ior (UI: \ nnLnc iatolrS: 1-1 5-('4 S( IA I. OW\IISI.\I'('lA IF \\'FLOW I.O\V 1I 1-532 indication reading hilh 1 FAV530 throtliing open FWV flo'A increasing 5( lev cl increasing aboeC program 13OF1 US Identify report steam llo\\ channel IFI-532 failuie Tlake manual conti of I F\V53) and balance fced flowk with steam flo\x to stabilize level as necessary. US Implement 1Bv, OA INST-2. 'OPI-RATIION \VIIt A FAI ED INSTRUF.NT", Attachment 11 "STEAMIFLOW CHtANNEIL FAI.UR",- and direct actions. 1OP Pcriform actions as directed:
- Check affected SG levels Normal. IF NOT:
- Place FRV in Mlanual
- Verify adequate FW DP
- Restore level to a stable condition.
"* Select operable Steam flow channel o 1Establish Auto level contiol
- Verify.Steam Pressure Channels Normal Re Assist
. BOP as required to identify, failed instiument channel and tabilize SC! levels Monitor RCS and stabilkie changing parameters resultinmg rom FFI SF imbalance:
- RCS l[ae u PIor Pressure US Inform SM and maintenanee of lhilnre.
('omill CInts:
ý1I "i( . II*),(
\dn )II N*',,'!l*:!i, !l.'_ [
Scenario No: 02-I I x cnt No. 6, 7, 8 lx cnt D)cscription: larnc Brcak I.().\ ATIWVS lFailure of('S to actuatc T imc Position Applicant", .\ctions or B~chai ior (U I ario Break I.OC(, result- in Ilowcring im cntor\ and Reactor trip RD FIRS F 01 IT t , Imnplement I Bw110` "RI\A(ITOR I RIP OR SI" RO ICITcf orn immcdiatc operator actions of I BwITP-0 Verify the reactor is NOT tripped:
- Rod bottom Ilihts NOT IITI
"* Reactor trip & bypass breakers NOTFopcn
" Neutron flux NOT dccrcasilnU NManually attempt to trip reactor with both switchcs at:
SIPM05J
- 1PM06,I RO Identify/ report that reactor trip breakers did not open.
US Transition to IBLwFR-S.1 "RESPONSE 10 NUCI.FAR POWER GENIRATION/ATWS" o Contact W1C for STA duties CR]z1W Dispatch operator to locally open reactor trip breakers RO Perform immediate operator actions of FR-S. 1:
- Verify reactor is NOT tripped
"* Rod Bottom lights NOT lit
"* Reactor trip breakers NOT open; Bypass breakers open (not racked in)
"* Neutr on flux stableNOT decreasing from Post lrip.
- Manually attempt to trip reactor with switch
- IPM05J 0 1PM06,I RO Insci-t control rods at 48 spin in Manual. (Auto is failcd to I spin)
ICR-S.I --( Commentscl:
Scmenaio N*o,: 0(2-1 I cnt No. 6. 7.X
\xCnt [)ecNI iption: Iarge iBreak I1'C, .\T\ S FMailuir ,.lCS t, actuate ImI PosIior Applicant's \ctions or Bell a,01r I3OF1 Vcril'y turblih trip TIurbine throttle \alvcxs Closed TuIrbine f goxeCIrnor x ax CS\
Ccosed Check ,,\F\V Punips Run1ing
- Al Pump rIn lights - ],it R()130P Veritfy Flmergencv Boration of the RCS is occurriMg (with SI actuation):
0 ICV II 2D and F are OIPE N 0 ICV 11213 and C are (I-()S {I) 1Both CV PUMps RUNNING Check PZR pressuIe ILes than 2335 Re BOP Verify Containment Ventilation Isolationl
- Group 6 CNMT Vent Vsol monitor lights II (Note: US may assign an operator to verify proper ESF Actuations per OAS as time permits.)
Re Verify reactor subcritical
"* PRZ channels < 5%
"* IR channels SUR < 0 Determine the power is still abox e 5('/ and continue with steps of I DBxxER-S. 1.
(NOTE: If the values above are satisfied the crewv will transition to I BIN-EP-0. actions for IBwEP-0 begin on page 15) 1301 Isolate Steam Dumps
- Place steam dump B1YPtASS INTIRI.OCK switches to OF: RI-SI T for both Trains.
(NOTE: Reactor trip breakers will be locally opened after dunmps are in OFF/RESET. If S/G WNR levels reach 8% before the reactor is tripped, RCS pressure rapidly rises to the Pzr Safety setpoint.) CR FW Check trips haxve occurred
"* Reactor trip. If NOT - Direct the operator to locally open the trip breakers bt depressing the ImaIlual trip buttons
" Turbine I trip en (CotnI CIts:
I :..,
Scelnar o No. 02-1 lxcat No. ( 7. F-vent
Description:
I ar'c Break [I()E'A A.IN\"S F ailuic of(E"S to alcujlc Time Position .Applicant's Actions or Bella\ ior 0P Eolicck (s Ic\ cls SI c\ clii) at lcast oneG -5 10 IF, NE)NO\ crif\ .000 'pm A[ flow
- Eoinitol Iced flow to maintain SG lexcls bcetl\cu I 0', (31" adx crse) and 50%
- Chcck SG hlo\xdows iisol vah cs closed ISl)D00.d II RO Vcri\-
lall dilution pith valves closed
"* Reactor M Lakeup dilution vxaIes I CVI I I and I(EVII 11 closed
"* \ier if'v FB1RS Mode Selector in OFF
"* D)ispatch operator to locally check ahCs Closod pcr 113\\ IT S. I step I 0c
- I(CAX8-4 I P\V to linerogen, beoation 1 0E'V8435 & ICV8453 (Y C' chemical mixiing tank
- I \B,56 29A Recyclc c\ p I'ced pumps to (ENl ('(I I( I pumps suction I
C RI-NV Stop reactixity insertion from RCS cooldowx n
"* RCS tCmperiatnre NOT decreasing in uncontrolled manner
"* Note: RCS temperature may be decreasing due to FCCS injection and AF F"low to SGs.
- SG pressure, none decreasing in uncontrolled manner RO Check CTICs < 1200°F Re Verifx' reactor subcritical
"* PR channels < 5%
"* ]R channels SUR - 0 Cr ,-%V Iransition to Procedure and step in eifect. 13wEIP-0. 'RX TRIP OR SFI.
(Note: Actions of IBwEP-0 continue on next page) Eomi rlt cl ll s: I., - I
,'>Ccwlrio No.: 02- 1 caIt No S.
-,nlt IDescription: I aar-c -icikI C' \. \I'WS I ailure of(S to actuate I inC Position Applicanit's Actions Or Bcha%ior IM() Plciform Iiiiiriedialte Actions of I 13\\ IPF-O vcil I\ *cactor trip
"* Rod bottom l ights lit
"* Rx trip and bypass hieakers openi
" Flux decreasing l3()P Veirify Irbine tripped
- I'V's closed G V\N's closed Vcii-i 4KV FSI Busses CnerCizedi Bus L 141
- Bus 142 CRLW IDetermine SI is actuated required
"* SI First Out annunciator ILit (I I B,'11 CD'I)
"* SI ACTUATIF.D Iit (IBP-4.I)
"* SI Equipment actuated (St Pumps running)
Recognize Adverse Containment conditions exist
- Cnmt Pressure >5psig RO US Trip RCP's per Operator Action Summary "o CC Water lost to RCP's "o Cnnit Phase B actuated "o Al of'the fol lowing exist:
"* Controlled RCS Cooldown not in progress
"* RCS Pressuic < 1425 psig
"* IIIISI Flow >SO gpm OR SI pump flow >100 gpm 1301/ US Verily Feed \Vater is isolated
"* 1:W PuIIips tripped
"* Isolation monitor lights lit
"* IFW discharge %alv cs ( I W002A:\1.'C) closed RO US Verify I((CS pumps rulnlng:
- CV puInIps
[CTI o I SI880 13ma. be opened at this point while er if' ing pump alignments EP-O--I
- S[ pumps
- RI I pLIIu)ps Commrn ts:
0 'I I
Sccnario No- 02 I lvcnt No. 607,8 F ecat Dcscl iption: I arn,c Ricak IOCA ..V I WS Failur o'CS to actuLatc Time Position \pplica*nt's c tions oI Behavior 13()P 1 S \crif\ C'olaimiiuncnt Conditions: 0 R(T(' ,C\Cidcnt Mode IzightS ll ((11oup 2) 0 Plhasc A I ghts ITIY (Group 3) o (ContaiMInent Vecntilation I1ihtsIl 1l ((ionp ) BOP`US \.criIN the following: AI .\l ned:
- IA and 113 ASI\V pumps rui
- 1..5\01 ,A-11 Open 1 F'\t0O5A-II Throttled S1.,\ and 1B CCW pumps running
- 1A and 113 SX pumps running
- MSIVs and B/P Isolated ihen Cnmt PrCssurC >8.2 psig oi Steam I.1inc Pressure < 640 psig BOP/US ('hec.k If Containmcnt Spray required:
* (innt pressure > 20 psig
- Stop All RCPs
- Group 6 lights NOT lit
- Phase B lights NOT Lit Identifies!reports I B CS pump failed to start.
Ilentifics'reports failure of Phase B actuation 'positioning of Phase B valves
- Manually actuates Both sxvitChes for CS ald PlhasC B actuation at I 1PM05J and I1PM06.J
[CT]
- Determines manual actuation unsuccessful. Performs Attachment 13. (Train A CS is OOS)
EP-0--E Checks I CS00 I B open
- Opens ICS00713
- Places I B CS pump TEST switch to TF.SI
- Opens ICS019B
- Returns TEST switch to Normal C'hecks I CSO 1013 open
- Vii y 113 CS pump running S'crifics Iductor Suction 1low > 15 gpm ( I1 -(.S014)
Vcri tics CS Additive flow > 5 gpm (11 ('I5016) Co- 1111cts: S.. .........
,_ I ; I ' , . ,
Scenario No: 02- 1 I\,cat No. (. X I:%elt
Description:
I a-e Bircak I A((.\ I W\SS I ailht o01(S' to amtuate Time Position ,Applicant's Actions or Beha\ RV NOTE: A( some time CNMT pressure may rise to an ORANGE Path condition (N illiot CS pu nips running). If so, performance of I Iw F, ZJ. -RESPONSE TO HitIIGH CONTA INMENT PRESSUIRE"' is required. Actions 1are covered below. (t F1will be provided by the SEA after monitoring (lie BwS'IEs. US Implement and direct as ad' iscd by the STA the actions of"I I.\ FR- / 1. 'IMSPONSF 1TO H!IGHI CONI AINM I-NT PRI SSLRFI. BolP Verilv Containment Isolations
"* Phase A Gro,up 3 lights lit
"* ('l1it V\Cntilation Group 6 lilits lit Check if'Contaimnert Pressure has increased to > 20 psig (I PR-937 or I P-CSQ)34 tin1-i 937)
- Stop all RCPs (prec\ iously completed)
Verify CS alignment: (previotsly complete for I3 Frain) US/BOP Verify Group 6 Phase B Isolation lights lit (pre viously completed) Verity RCICs running inl ACCIDFN-F MODF (Group 2 lights lit). Verify MS Isolation, NISXVs and B P closed. (precvirously completed) Determine NO SGs are faulted:
- No Steam Generator pressure decreasing in an uncontrolled manner
- No Steam Generator completely depressurized Rctur-n to step and procedure in elfect.
NOTE: Actions below resume from I BwIEP-0. BOP Verify AFW flow
- 500 >-pm
"* Control SG levels 3 1-501
"* Deterrmine no SG levcel increasing in an uncontrolled manner CorI mcnlts:
Scenario No: 02-1 \e ent No. 6,7.S F[vent
Description:
Iargc Break MCA / AT\VS Failure of CS to actuate l Time Position Applicant's Actions or Behavior RO Verikl\ the follow ing: ICII E1P-0--4
- Group 2 Cold Leg Injection lights lit - OPFN IS18801 B FCCS Operations:
- High tlead SI flow> 100 gpm
- RCS pressure < 1700 psig
"* SI purnp flow > 200 gpm
"* RCS pressure < 325 psig
"* R I[pump flow > 1000 gpin PZR Porv Relief path available:
"* At least one block valve energized
"* Porv in Auto
"* Associated Block valve open BOP Verify the following:
Main Generator Trip:
"* Output Breakers Open
"* PMG Breaker Open EDGs running 0 1SX I69A and B Open
, Dispatch operator for local check of EDG operation Ventilation aligned:
- Control room
"* Aux bldg
"* Fuel Handling bldg Comments:
- .:!.; , , --' - i
SHIFT MANAGER TURNOVER Weekday, Today, 2001 ONCOMING SHIFT 2 m UNII 1 STATUS UNIT 0 & 1 MAJOR OOS's MO DE ............ 1 i IA CS Pump Rx Pw r ............ 93 Generator MWe ..... 1150 1D CD CB Pump Max Load/Power .... 100% Min Load/Power .... 500 MW Max Ramp Rate ..... 5 MW/Min Desired Delta I.... Target On-Line Risk ....... Green Boron @ .......... 934 Control Bank ....... D @ 175 LCOAR ENTRIES PREVIOUS 48 HRS UNIT 0 & 1MAJORSURVEILLANCES LCO 3.6.6 1A Containment Spray Pump UNIT 0 &'I INPROGRESS " UNIT 0 & I PENDING . IA CS Pump bearing replacement. Hour 36 of a 7 day Ramp unit 1 to 700 MW at 5 MW/min in LCOAR. preparation for removing IC CD/CB pump from service and flushing suction strainer. 1D CD/CB Pump alignment. Estimated RTS in 48 hours IC CB Pump suction strainer delta-p problems. Ramped unit from 100% to 1150 MW over last 15 Focus Areas: minutes using EHC and control rods only.
"* Verification Practices
"* Command and Control Standard for Execution of Critical Steps THINK CONFIGURATION CONTROL and SAFETY!!!
SCHEDULED ACTIVITY CONFLICT lC21 .doc
SHIFT MANAGER TURNOVER JK117 -) C-rA-r II411T~~ II %3*A UINII1
,,. 2 MiiAJ(}
. . . nt-)Q'lq MO DE ............ '1*1 1 I-----I - MAJOR OOS' -
IUNI ______________________________ Rx Pw r ............ 97.6 Generator MWe ..... 1197 Max Load/Power .... 97.6 impulse pressure Min Load/Power .... 700 Max Ramp Rate ..... 5 mw/min Desired Delta I ..... Target On-Line Risk ....... Green Boron @ .......... 1037 Control Bank ....... D@210 LCOAR ENTRIES PREVIOUS 48 HRS UNIT 2 MAJOR SURVEILLANCES none UNIT 2 IN PROGRESS x/. UNIT 2 PENDING . . Dose INFO: Dose goal for day 10 mr C*' I Ii- t l ii i- *r A FTII**. S*... i.. i.l.l....... ULrlr'UULt"U AU I Ivi Y UUNI-LIU I I IC21.doe U*..* I /*I *,.,,1 II
SHIFT MANAGER TURNOVER Administrative Temporary Procedures / Modifications T-mod Ul Trn B RVLIS. Jumper Installed on 4C U-1 MPT Disconnect. 1FW009A T-Mod for Hyd Pp Press Sw 1PS-FW1 62. Daily Orders / Special Op Orders Daily Manning Schedule See sheet for restricted duty personnel and overtime restrictions Oncoming STA Fire Chief Control Room Rounds (GSEP / LER / DVR / ENS) Material TS Conditioning SFP High Level alarm did not alarm during calibration RWP's / Releases / Precautions / ALARA Infrequent Evolution Activities Lesson learned files L:\shared\opex then ctrl F to search SPS0 / Division LD Alternate BPO Outside # 815-727-5902/5903 Tie # 8-565-5902/5903 Unit 1 Comments Unit Common Comments Air line break at 15/16 heaters, temp repair in place, fix Al F34 U 1 FC Cleanup SFP 1HD046A jerky last 30% of travel. Problem on pp swaps U2 FC Cleanup OFFLINE (leak) Battery 112 cell 32 has floating material in electrolyte, eval'd OK FC Cooling Ul D.O. OOS prevents filling U-I tanks normally, but BwvOP DO-6 50K DO Tank empty can be used to fill tanks. T-MOD is installed allowing U-I boiler 125K DO Tank and FRAC Tks Certified ops Aux Steam U-1 ES -->Ul HDT U-0 CC Hx Ul U-0 CC Pump Bus 141 Ul Aux boiler Wet lay-up U2 Aux boiler Wet lay-up SAC / Dryer U1/U0 MUDs U-1 CST CW Makeup Running 0A/0B CW Blowdown On Lake Level 5.8' Unit 2 Comments General Comments 2AF017A leaking by .3 gpm, AR 990116738 Conference Call Phone Number- 1-800-232-1234 Teleconference S/G sampling lines/valves at HRSS are not correct. Do not folder ID #=472664085 hang OOS on any 2PS181 valves till further notice. Meeting Place 630-663-7120 +code 2PS229A still blows fuse 2PA32J Ckt 9 Duty Team is located @ SITE APPS, NRC Duty list in book CV seal leakage: Substation construction (John Strle) Cell phone 815-351-8472 2A Running 200cc/min shutdown about 6 drops/min 2B Running -12 dpm; S/D- none Caution Cards Abnormal Positioned Components CCNUM EPN CCNUM EPN AbnormalPosition SM BEEPER TURNOVER Shift 1 To 2 Time Now Date Today Offgoing _Oncoming KC21 .do(
SHIFT MANAGER TURNOVER
.OPERATORS CONCER,N l"ST Equipment Unit 0 BswAP 330-10 Compensatory Actions .:Operability
~ :7 7,
. ~Determination Equipment Unit I BwAP 330-10 Compensatory Actions Operability E n Determination PZR PORV Verify PZR PORV's Open at Setpoint or Open PZR PORV - Spurious SI 97-159 Concern Equipment 'Ui 2JI. BwAP 330-10 Compensator Actions Operability~
PZR PORV Verify PZR PORV's Open at Setpoint or Open PZR PORV- Spurious Si 97-159 Concern 2B CV Pump Monitor seal leakage shiftly - Notify System Engineering if > 0.5 gpm 98-049 UNIT 0 CONTROL ROOM ANNUNCIATORS LIT Annunciator.Annunci.tor Description lem .AR#.WR# Status UNIT 1 CONTROL ROOM ANNUNCIATORS LIT Annunciator Annunciator Description Problem AR#iWR# status UNIT 2 CONTROL ROOM ANNUNCIATORS LIT Concerns and/or Pending OP-AA-101-301 Evaluations EPNi UnitO ~ Resolution EPN Unit 1 Resolution EPN y Unit 2 -Resolution ________ I __________________________ _____________ 1C21 .d((-
BwAP 335-1T( Revision , Information Us( UNIT 1 NSO TURNOVER Weekday, Today, Oncoming Shift 2 Unit I Status Mode 1 Max load/power 100% Power 93.0% Max ramp rate 5 mw/min. Mw electric 1150 MWe Unit Risk Yellow MiMn load/power 500 MWe Control Rods 175
.Desired Delta-I Target Boron concentration 934 PPM IN PROGRESS ... . :_-.. PENDING Bearing replacement on the 1A CS Pump Ramp Unit 1 to 700 MW at 5 MW/min. Preparations for removing 1C CD/CB pump from service and flushing of 1D CD/CB Pump alignment due to vibration problems suction strainer.
Est. RTS is 48 hours Ramped Unit 1 from 100% to 1150 MW over last 15 minutes using turbine EHC and control rods only due to 1C CD/CB pump suction strainer problems. LONG TERM
. * ' ADMINISTRATIVE ... ,
Temporary procedures Temporary alterations New caution cards Unit logbook Unit routine BDPS Icoar in mode 3. Aux. Electric room access Daily orders Control board walk down LCO/TLCO RETS DEQUIP/AAR 3.6.6 1A CS
BwAP 335-1T6 Revision 8 Information Use TURNOVER ITEMS NSO SHIFTLY/DAILY SURVEILLANCE
- 2) SSPS CHANNELS/BISTABLES B1train SSPS logic ground to chassis ground had hi.her than expected readings during SSPS, AR \\ritten.
- 3) SYS - SAFEGUARDS
- 4) SYS - PRIMARY CC to spent fuel pool hx is at 2800 gpm.
- 5) SYS - BALANCE OF PLANT Spent fuel pool cooling now on Unit 1.
- 6) ALARMS-SER/ANNUNCIATOR
- 7) ALARMS - PROCESS/RM-1 1
- 8) ALARMS - FP/OTHERS
- 9) CHEMISTRY Max flow through condensate polishers at full power is -2000 gpm without causing a low npsh alarm. This is only a guideline and not an absolute value.
- 10) RADIATION PRECAUTIONS
- 11) NUCLEAR INSTRUMENTATION
- 12) MCB INSTRUMENTATION
- 13) MCB CONTROLLERS
- 14) ELECTRICAL DISTRIBUTION - AC MPT transformer disconnects has bad seat on one phase. Jumper installed, SOC on disconnect - do not operate.
- 15) ELECTRICAL DISTRIBUTION - DC
- 16) EGC STATUS
- 17) BWOP_ (PROCEDURE AND STEP IN FFFECT)
COMMENTS 13 gals of PW will Raise RCS .1 F
- POST REVIEW US . FS SM.
TIME: NOW SHIFT OFF GOING DATE: TODAY SHIFT ONCOMING S2 .......... ..... ... PI U.
Simulation Facility Braiawooci Scenario No. 3 Operating Test No. 2002 Examiners: Applicant: SRO RO BOP Initial Conditions: IC- 18, 76% power MOL. Equil. Xe. Turnover:, Steady state with IA CS Pump OOS for motor bearing replacement and 1D CD/CB pump OOS for an alignment and vibration problem. Electric Operations requests Bwd U~nit-lI increase power. to 1250 Mwe @ 5MW/min to meet grid demand. A .2-Event Malf. No. "I Event ., Event No:.. '"7 ~. Description'
- . . -I. Ji rreladu (9 K()
Sil 2A LA.SI Pump fdiuls to Auto start, can be manualsare -' '12 SI01 B BOP 1 SI Pump fail s to Auito start, cannot be 'manually started SRO 1N BOP Ramp up turbine power to 1250 MWe at directed MW/mmn, SRO R RO Raise reactor power using rods and/or dilution SRO 2: RXO5, 0 I BOP Main Steam Header Press'ure controller (PT-507) fails low' 5 min ramp SRO A
.3 CV17, 0 1 RO. Volume Conitrol Tank (VCT) level chafhnel I1LT-l 12 fails high SRO 4 RX2 1A I RO PT-455 Controlling Pressurizer Pressure channel fails high SRO 5 MSO4B3, 100 C BOP lMS018B, LB Steam IGenerato r ~PORV fails open .
______ ~~SRO ___________________ ____ 6 MRF RP61 C RO All MSIV's fail closed at power SRO ______BOP 7 MSO3B/F M RO Pressure surge causes Main Steam Safety valves (2) to stick open, Loop 100 SRO lB BOP 8 FW009B C RO FRV-520 fails to close as required on EWI signal. Cannot be manually BOP closed. 9 TH03B M RO SGTL occurs on lB Steam Generator after Steam Generator has reached 600 gpm BOP dry out conditions. SRO kN)ormai, ýK~eactivity (1)nstrument, (C)omponent, (M)ajor TIransient Braidwood 2002 NRC ExamScnro0- Scenario 02-3
SCENARIO OVERVIEW The Unit is at 76% power, MOL, equilibrium xenon. ID CD/CB pump is OOS for alignment and vibration problems. IA CS Pump is OOS for a motor bearing replacement. Power is to be increased at direction of Electric Operations using iormal procedures. On-Line Risk is YELLOW because of the CS Pump OOS. Following clearly observable plant response from the reactivity changes, the Main Steam Line pressure controller (PT 507) will fail low, resulting in decreased MFP speed and lowering main feedwater flow to the SGs. The crew should take manual control of MFP speed and adjust /increase MFW to the SGs. The Crew should match steam flow and feed flow and control MFP speed in, manua.. ., After thesecondary plant is'stabilized, VolUme Control Tank (VCT) Lever Controller (LT-112) will failthigl.This will
.result indiverting letdownflow'from the"VCT týo:heHoii up Tank (HI-T).Thefailure-of LT-I12 l&eve chariihelwill .result in the loss of automatic level-control and makeup.tohe.VCT-..- ... ,"--:.' '..-..V- . .;.,-.
After actions have been taken to restore normal letdown flow, the controlling Pzr Pressure channel (PT-455) will fail high, causing a Pzr PORV'(1RY-'5ýA) and Pzr Spray valves to open, decreasing: 'a{al RCS pressure. The RO will diagnose the pressure malfunction from alarms, meter indications, andc decreasing Pzr pressure. The RO must close the PORV or PORV block valve to stop the pressure decrease. Manual action will also be required to close the Pzr spray valves which will open due to the master'pressure controller demand. The SRO will enter and direct actions of 1BwOP INST-2, Attachment B, "PRESSURIZER PRESSURE CHANNEL FAILURE", to select an Operable controlling channel and restore automatic pressurizer pressure control, trip TS bistables, and identify TS Action requirements. After actions have been completed for the failed Pzr Pressure channel, the 1B SG PORV controilerwill c'aiuse the IB SG PORV to open. RCS Tave will decrease causing control rod motion in' the outward direction. The crew will investigate the cause of the temperature decrease and diaghose the inadvertent PORV'opening. EmergencTy'closure of the PORV will be available. The PORV may be isolated locally by closure' of the manual upstream isolation valve, rMS019B. '-- After the unit is Stabilized folllowing thte penSG"PORV, a failed capacitor in Instrment v,rerter11 will generate a spurious Main Steam Line Isolation signal (Bwd LER).'All 4 MS1V's will autoinatically close at power, resulting in a Reactor Trip and Safety Injection. The Crew will enter and perform the immediate actions of 1BwEP-0, "REACTOR TRIP OR SAFETY INJECTION". The resultant pressure increase following the spurious MSIV closure causes 2 Main Steam Line Safety valves on Loop lB to open and stick open. The Operators will diagnose a fault on the 1B Steam Line while performing the actions of 1BwEP-0 as a faulted steam generator and transition to 1BwEP-2, "FAULTED STEAM GENERATOR ISOLATION", and will take actions to isolate the lB Steam Generator. FRV-520 has failed to close following the Feedwater Isolation signal and the operators will have to take actions of step 4d RNO to manually close the upstream isolation valve, 1FW006B. Comments: Braidwood 2002 NRC Exam 2 Scenario 02-X
Once the faulted steam generator has been depressurized and dried out, the pressure delta P will cause a steam generator tube leak of 600gpm on the 1B SG. The crew will diagnose this by decreasing RCS pressure and inventory. They must perform the actions of lBwEP-3, "STEAM GENERATOR TUBE RUPTURE", and finally transition to lBwCA-3.1, "SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED", when it is noted that the uptured SG pressure is less than 320psig. The Scenario ends with the establishment of RCS Cooldown in 1BwCA-3.1. Critical Tasks
- 1. E-0-J Establish flow from at least 1 intermediate head SI pump before transition out of EP-0
- 2. EP-2-A Isolate the fauI ted SG. before transition out of EP-2 .,
- 3. ECA-3. 1-B Take necessary operator actions to control the RCS cooldown rate at the highest rate achievable but less-,
than 100 degte-s F per hour in all RCS cold legs. .. s<.&. .i.u ..
~~~~~~~..
...... .. . . .... : ' -.... : ' i . -'-
" :2 .:*:(.;": ,I.!~.***.*-:' .:<*.** .. *.,. .. L.,,,'! .'*."
SIMULATOR OPERATOR NOTES: Simulator Setup: IC-18, 76% power. Complete the 'ready for training' checklist. Hang YELLOW risk placard. Take 1A CS pump OOS. Control switch to PULL OUT. Hang Tag... a,;.. . .... ,. >.-,:.. Take ID CD/CD pump OOS. Control switch to PULL OUT.. Hang Tag. .. , .... ...- +/-K r .. Take 1D CD/CB pump aux lube oil pump OOS. Control switch to PULL OUT. Hang.Tag.;..... IOR ZLOI.CB13D(l) OFF Open Light OFF _ .. . . . ",:' : -. . . . .
"-OR ZLO 1CB 113D(2) OFF Close Light OFF P. .. . . "Setupthe following overrides/malfunctions for the 1A CS OOS:. ,. . .. ,
IMF CSOlA to fail 1A CS pump from starting MRF ED062A OPEN Breaker for 1CS007A MRF ED053M OPEN Breaker for ICS019A MRF ED053A OPEN Breaker for lCS001A MRF ED053B OPEN Breaker for 1CS009A Setup the following overrides/malfunctions: IMF FW22D to fail ID CD/CB pump from starting IMF SI12A 1A SI pump fails to auto start, can be manually started IMF SI01B lB SI pump fails to auto start, cannot be manually started Comments: Braidwood 2002 NRC Exam 3 Scenario 02-X
Event 1 Power Increase - ramp power from 76% to 100% As SM acknowledge ramp initiation As RP/HP/Chemistry acknowledge sample requirements for power change >15% in one hour "--Tvent2 Main Steam Pressure Controller PT-507 Failure low SDG: RX22 IMF RX05, 0, 600sec Initiate malfunction after clearly observable reactivity changes/plant response from requested ramp and/or wi:, concurrence from lead examiner Acknowledge all,.info passed to SM, WEC, and maintenance .. . ... .. Event 3
" " "., ~ VCT
~'
-S G. .
Level Channel LT-112 FailurelHigh C V. 3 . . . .. ., * . ,'z % * ' .' , , *
. . . - ,,-A , g, ' . ,* . . -*: .' .r ".':-: : k ' ' '?
y-.H WFVI0, u10 Initiate malfunction after actions for PT-507 havebeen completed and with concurrence from ie~d examiner. Acknowledge all info passed to SM, WEC, and maintenance 4 Event Event 4 Pzr Pressure Channel PT-455 failure high (2500#) .... IMF RX21A, 2.500 .. . , Initiate malfunction's 'after actions are complete for LT- 112 failure and With concurrence of lead,* Role Play as U-2 admin/extra NSO to accomplish bitfable tripping.. . i Acknowledge all info passed as SM, WEC, and maintenance. Perform the following to trip Pressurizer channel bistables: On S D G R X 10 :" " . ° * , : . ,, , is I Open Protection Cabinet Door #1 RX020 OPEN Pzr Press Hi Trip PB455A CI-153 BS-1 RX032 TRIP Pzr Press Lo Trip PB455C Cl-153 BS-4 RX034 TRIP Pzr Lo Press SI PB455D C 1-153 BS-3 RX035 TRIP Pzr Press P-11 PB455B Cl-153 BS-2 RX033 TRIP On SDG RX4: OTDT Trip TB411C C1-124 BS-3 RX013 TRIP OTDT Runback TB411D C1-124 BS-4 RX135 Protection Cab #1 Close Door RX020 CLOSE Comments: Braidwood 2002 NRC Exam 4 Scenario 02-X
Event 5 1MS018B, 1B Steam Generator PORV fails open SDG MS4 Initiate after actions are completed for the PT-455 failure and with concurrence of lead examiner. MF MS04B, 100, no ramp If dispatched to controller box in AEER, report no obvious problems. If sent to locally close 1MSO 19B, wait 5 minutes, call CR for first check, and close 1MS019B Acknowledge all info passed to SM, WEC, and maintenance., Event 6-8 ARE SMIMULTANEOUJS.EVENTS.. ., . FRV-520 fails to close on FWI signal, MSiV auto. closure occusr(al4 MSI*s), IteamnLine Fault " outside containnment. (Loop 1B) .,.. Initiate events after actions are completedfor S/G PORV failure and with concurrence of cad examiner. IOR ZLOl SLFW520, OFF FWI Status light to OFF IOR ZLOlFW5202, ON FRV 520 Open light to ON IMF FW09B, As Is FRV 520 failure MRF RP61, IN - Closure of all MSIVs IMF MS03B and MS03F, 100 MS Safeties (2) to OPEN Insert malfunctions after actions are completed for PORV failure and with concurrence of leadexaminer' Acknowledge all info passed to SM, WEC, and maintenance Event 9 - Steam Generator Tube Rupture, 1B SG, after 1BwEP-2 transition and SG dryout is reached X
'SDG TM6 IMqF THO3B, 600gpm, I minute ramp . .
Initiate malfunction after lB SG Wide Range level is <10% and transition has occurred out of lBwEP-2,
,- ..... and with concurrence of lead examiner "
Acknowledge all info passed to SM, WEC, and maintenance Comments: Braidwood 2002 NRC Exam 5 Scenario 02-X
Scenario No: 02-3 Event No. 1 Event
Description:
Raise turbine load and reactor power Time Position I Applicant's Actions or Behavior CUE Turnover information includes request from Electric Operations for an increase in Unit 1 MW to full load "1(1260MW) to begin ASAP at 5 MWe/minute. US Implement actions of 1BwGP 100-3 step 61.
- Initiate load swing instruction sheet (1BwGP 100-4T2 Boration Dilution Boundary Calculation)_.
o Contact chemistry and Health Physics for load change > 15% in one hr.
"*Inform SM of plant Statug, aiidtEleOi oframp start.
CREW Review applicable Preautins, mtatons and Actions of IBwGPIl00-3. . .' ..
- RO .. Verify' rod position and boron cohcentration. . :. , ,..:,,.: ,, ,
Perform reactivity manipulation calculation to determine amount of RCS dilution and expected rod outward movement to maintain Delta I within the limits of BwCB-1 Fig. 19. .. Determine required dilution volume by: o Effects of previously performed dilutions. o Braidwood Boration Dilution Tables. =: Initiate Dilution in accordance with BwOP CV-5: . ; . i.. :, ... ;i " * ,.,SetDetermine 1FK-111required Primary'Water flow rate. . . Pw/Total Fl6w"C bintýifI 6ýdesired dil~iiti , 'r~e .. ..
. ;: ' : :.! !*2*.,?5;!
.. IFY-0111 Primary Water Control Preset Counter to desired volume . ;.
Place MAKE-UP CONT Switch to ST posi ion.. 6 -V
** Set MU MODE SELECT Switch to ALT DIL position.
- Place MAKE-UP CONT Switch to0"STAT. . . .
o Verify proper operation of valves (1CV1TIA throttles'open, PW flow indicated on recorder). OR Batch Addition:
- OPEN lCV110B.
- OPEN lCV1I1A.
When desired amount of Primary Water added:
"* CLOSE ICVll1A.
"* CLOSE 1CV110B.
Comments: Braidwood 2002 NRC Exam 6 Scenario 02-X
Scenario No: 02-3 Event No. 1 Event
Description:
Raise turbine load and reactor power Time Position Applicant's Actions or Behavior BOP Initiate turbine load increase:
- VERIFY the DEHC IMP IN, SPEED IN, and MW IN half of the pushbuttons are illuminated.
- DEPRESS the LOAD RATE MW/MIN pushbutton.
- ENTER the desired load rate (< 5).
- DEPRESS the ENTER pushbutton.
- DEPRESS the REF pushbution.
- ENTER the desired MW on ihe REFERENCE DEMAND Window using the,numbered pushbuttons (1120).
. DEPRESS the ENTERpushbutton. hn rt by , . : ;,.
- .-
- DEPRESS the ENTE pushbutton. whe &6' dbh U iz
, VERIFY load begins to increase. ý. .. . .. : .
- r-:... . . . ... .. . .
RO Monitor power increase:
- Monitor Reactor power, Tave, and Delta I. " .
- Verify control rods automatically move to maintain Tave within + 1.0 degree F of Tref.
If Diluting:
- Monitor VCT level.
o Verify RCS boronconcenritfrtion decreasing.
. Monitor PW/Total counter.
0 Yerify dilution auto stops at:presetqvalue."
. ReturnReactor Makeup system to blended flow at'current boron concentration.
NOTE: Following clearly observable plant response from the reactivity changes, and with concurrence of the lead examiner, event 2 may be entered. Comments: Braidwood 2002 NRC Exam 7 Scenario 02-X
Scenario No: 02-3 Event No. 2 Event
Description:
Main Steam Header Pressure Controller (IPT-507) Fails low over 5 minutes.
'I ... I lime Position Applicant's Actions or Behavior CUE Annunciators:
I-18-B7 MSR SHELL DRAIN TANK LEVEL HIGH LOW 1-1 8-A7 MSR SHELL DRAIN TANK EMER DRAIN VALVE OPEN 1-15-A/B/C/D4 SG 1A/B/C/D FLOW MISMATCH FW FLOW LOW 1-15-A/B/C/D9 SG'IA/B/C/D LEVEL DEVIATION HIGH LOW Indications;....:"- ::: :;:* . *:: : . .. .. . . . . . .. . Feed flow indication decreasing" Feed Pumps Speed Decreasingfi g. .. . .... : -..
V S~levels de reitsin . H .:: :
'-'; Feed*Reg Valves Indnition.g."- .. :.:.) " '!:..
1PI-507 Decreasing . .. : . .. , BOP/US Diagnose/Report decreasing feed pump Spieed and SG levels as a result of 1PT-507 failing low. RO Monitor Reactor power and primary parameters. Refer to BwARs as directed by US. Assist BOP as directed/necessary. US Direct actions stabilize the plant and restore normal feedwater conditions:
. Place Master feed 'pump speed cntirol in Manual and Increase feed pumips speed to increase feet flow.*
o Direct'flagging of Master Feed pump speed Controller, 1Pi-507, and Steam'Dumps Steam Pressure. o Review effect of failure with crew with regard to Steam Dumps.'. ...
' " _ o Informi SM of plant status, and direct WEC to write AR, CR, and get maintenance involved.';*:':,..:"-;
BOP Perform actions as directed by US:
. Place Master feed pump speed control in Manual and Increasefeed pumps speed to'increase feed flow.
- Control feed flow to recover SG levels in a controlled manner without over cooling the RCS.
"* Stabilize feed flow/ pump speed to maintain SG levels at -60%.
J fNOTE: After crew stablilizes SG levels, initiate event 3 Comments: Braidwood 2002 NRC Exam 8 Scena~rio 02-X
Scenario No: 02-3 Event No. 3 Event
Description:
Volume Control Tank (VCT) level channel 1LT- 112 fails high I i meS , -. rositon Applicant's Actions or Behavior
%-U r't Annunciators:
1-9-A2 VCT LEVEL HIGH 1LT 112 CVT Level indication full scale high 1CV1 12A VCT Inlet valve diverting to the HUT S. ,. I RO/USROU Identify/report Identif .... failure of LT-CVI of1L-C11 12.... .'.*'...'.'.:*,'*:a..-*.q,,l,., .. :,!x..: RO Refer to I~wAR 1-9-A2 for oper-ator actioný . Place 1LCV CV-1 12A to the VCT position to restore*fetdown flow to the VCT I, BOP-. Assist RO as directed by US /retffested'by 'RO ... . . .. . .;
- Investigate BwARs
- Make phone notifications as -directedby US/RO
- Provide appropriate peer checks as requested by RO . .. .
Control turbine loading as directed by US . . CREW Identify loss of auto makeup capabilities to the VCT Identify 1os§, bf auto suction swapover to the RWST on low VCT level ,. . i}::~~~~~~~~~~~~~..,...
- "i;." :'..... . . . " .-':... *..-...:. .. *",.:, ,-,.. .-.. ,: "
NOTE: When actions have been completed for the failed VCT level channel, and with the lead examiners concurrence event 4 is entered Comments: Braidwood 2002 NRC Exam 9 Scenario 02-X
Scenario No: 02-3 Event No. 4 Event
Description:
PT-455 Controlling Pressurizer Pressure Channel fails high Iime rosition Applicant's Actions or Behavior r -- r
.. Ut. Annunciators:
1-12-B2 PZR PORV OR SAF VLV OPEN 1-12-C6 PZR PORV DSCH TEMP HIGH 1-12-D2 PZR PRESS CONT DEV HIGH Porv 1RY455A OPEN Position Indicating Light Lit. 999 * .9 . I. 1PI-455 Indicating 2500 psig. , , S.. 9:- , .. - / .. . * .: Decreasing PZR pressure .
':" RO'/U'S .. ...." ... ...... . ... . . . ~. .. F...
R' , .. Diagn6se/Ann6unce PZR Pres.'suire Transmitter failure, IRY455A and Pzr snra.'bp'n
- Verify PZR Pressurte is decreasingIentify 61Sen PORv and spiha vaves :, ...
.. Close..RY455A!.. ,. . .. ! .
.. ~.... .............
"M Manually Close spray valves .. _ . . .... .
US Implement 1BwOA INST-2 "OPERATION WITH A FAILED CHANNEL", ATTACHMENT B, "PZR PRESSURE CHANNEL FAILURE", and direct actions: e Get acknowledgements from RO and BOP.
- Inform SM of plant status, evaluate for GSEP. . ..
. . -Direct WEC to write AR, CR, and get m'aintenance involved.
. Briefs Unit 1 NSO and Unit 2 Admin NSO onqBistable tripping,. .
.9. .. . ..* 9. . . 9 ' 9 , p 9' 9 .. I
*999 . 9.......: 9. .99
- 9. . . . . . . . .
.- 9W. 999 .
.9 9 9 9 9 .. t.99 9
*9.p-.,,
S . . . 9 9 .. 9.9 .9 . 9 -
9 999 9
-9 Comments:
Braidwood 2002 NRC Exam 10 Scenario 02-X
Scenario No: 02-3 Event No. 4 Event
Description:
PT-455 Controlling Pressurizer Pressure Channel fails high Time Position Applicant's Actions or Behavior KtU Perform actions of 1BwOA INST-2 as directed:
"* Determine PZR Pressure NOT NORMAL, and take Manual Control to restore Pressure.
"* Determine Operable Channel NOT selected, Place the Master PZR Pressure Controller in Manual, Control PZR Pressure, and Select an Operable Channel.
" Check PZR Porvs, Spray Valves and Heaters:
*PORVS Closed. If NOT, and PZR Pressure < 2315 psig, manually close PORV (IRY455A).
*PZR Spray Valves NORMAL. If not, then manually control.
*PZRHeaters NORMAL.. P:
"* Check PZR Pressuri&Coniiotlnl Auto 'ý ..
I1RY455 'retuthi&c to Aut& -. >,-W ~ *~; I Ri-456in Auto.'.~,I
- Sjpiays in Aut o a.ter operableýchaninel s~electe'd for control).
*Master PZR Pressure Controller in Auto.
~~~~~~~~~~~~~~~~~~~.
*Select Operable. Channels to.. . Recorders:
. . ., .' ' .* ",,. ' - " * . ..... - , q'*:*
*PZR Presue
- Loop DT.
*Coordinates Bistable Tripping:
*Places colored dots on bistable, indications, and annunciators. .
*Maintains communications with NSO tripping bistables.
RO ', Ensures thefollowing Bistables aye tripped : .:-.'
- PB455A . . . ... ., i" "" .
- PB455C ":. , -. .:.
*.PB455D . . .
*PB455B o TB41IC e TB4l1D . .
Checks PZR Pressure > 1930 psig and P- 11 eýrmissive is NOT Lit (Bypass Permissive 3.3). US Refers to Tech Specs, and determines the following:
- 3.3.1. Conditions E and K apply - Trip channel within 6 hrs.
- 3.3.2 Condition D applies - Trip channel within 6 hrs.
- 3.3.4 Condition A applies - Restore within 30 days e 3.4.1 Condition A applies - Restore DNB within 2 hrs.
Comments: Braidwood 2002 NRC Exam I1 Scenario 02-X
Scenario No: 02-3 Event No. 4 Event
Description:
PT-455 Controlling Pressurizer Pressure Channel fails high Time Position Applicant's Actions or Behavior BOP Perform actions as directed:
"o Assist Unit NSO in monitoring panels and parameters.
"o Investigate BwARs.
"o Make phone calls as directed to WEC and maintenance.
"o Control load ramp
- 4. NOTE: after completion of allactions and TS determination.,for the Pzr Instrument .filire,and
*i*th; the concurrence of the lead examiner, the next eveiit aybe initiated I . , . .5 S... . ..... . . .2 . :.:.. : ,. . .
Comments: Braidwood 2002 NRC Exam 12 Scenario 02-X
Scenario No: 02-3 Event No. 5 Event
Description:
lB Steam Generator PORV fails open, 1MSO 18B Time Position Applicant's Actions or Behavior CUE Indications: RCS Tave decreasing Control rods stepping out Reactor Power increasing Reactor power/ turbine power mismatch increasing . . , Red Porv OPEN position indication light lit. . LVDT meter indication incresing above 0%....................... BOP Diagnoses IB SG PORV OPEN, determines SG 'pr'siiire is belowvsdtpoint ('1115 psig)and report§ failure't6'.
.. . U S. * . . . ..: .!.'
"Per6orms actions directed by US:
- Take MANUAL control at the M/A Station and attempt to reduce demand.
- Report MANUAL control has no eftect to US.
0 PLACE EMERGENCY CLOSE switch to CLOSE. . o Report/Acknowledge SG 1B PORV TROUBLE annunciator (1-15-B l0)'As-expected alarm.
- REPORT 1B SG PORV CLOSED. , .
o Dispatch operator to AEER to PORV controller box. ,... .. . ... o Dispatch operator to locally isolate lMSOI8B by closing 1M'S019B..
- Report status to US. "..
US Diagnose/Acknowledge failure of 1B SG PORV'OPEN and direct actions: o Determine SG pressure < PORV setpo6ifi-t. * .
- Attempt MANUAL Control via M/A station to CLOSE PORV.
- PLACE EMERGENCY CLOSE switch to CLOSE. ,. . . .
o Dispatch operator to isolate PORV by closing IMSO 19B.
"* Inform SM of plant status.
"* Order WEC to generate AR,' CR, and get maintenance involved for repairs.
"* Refer to Tech Spec 3.7.4. (30 days to restore operability).
o May refer to Tech Spec 3.6.3. (not applicable, porv is in its isolation positon.) Comments: Braidwood 2002 NRC Exam 13 Scenario 02-X
Scenario No: 02-3 Event No. 5 Event
Description:
lB Steam Generator PORV fails open, 1MSO18B Time Position Applicant's Actions or Behavior RO Diagnose/Acknowledge failure of lB SG PORV OPEN. Monitor Reactor and Primary parameters for effects and expected response:
"* Reactor Power
"* Tave, Delta I and rod motion.
". Assistgas directed by US.
- Investigate BwARs. . .
".. . . . . . . .. .. i... . :. ..... :, .:i:, .. . ....
. ,,..,,.. * ... ...... .**i:'., . :..
*.~~~~..
" .. " . . . . .. . . .. , -" , .) . ', ." ". ' " .. ,.; ,,-, . , -.. ,,.. - ,:..,p,* .",;* *;-.
-, .,33 S~~~~~~~~~~~................... :.".".r..".... ' ..... *.... '".; A ' ' : ', NOTE: After PORV is closed/Isolated, TS actions have been identified, and with concurrene with the lead examiner the next event may be initiated. __ I ____ I. Comments: Braidwood 2002 NRC Exam 14 Scenario 02-X
Scenario No: 02-3 Event No. 6 - 9 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI, faulted-ruptured SG Time Position Applicant's Actions or Behavior CUE Annunciators: MSIV Closed Steam Flows all 4 Steam Generators decreasing All MSIV position indicators closing/closed CREW Identify closure of MSIVs . <. Initiate a manual reactor trip / respond to an automatic reactor tri. ..
. .US .. Implementand t af rect actions 1BwEP-0"ReiactorTrip or Safet5 Inectin" - '- ,
RO Perform Immediate actions of LBwEP-0: ........ . ...... . Verify reactor trip
- Rod bottomlights lit.
0 Reactor trip and bypass breakers open
- Neutron flux decreasing Check SI Status
& Determines that Pzr pressure is decreasing abnormally
- Determines Pzr level can not be maintained >4% level
- Annotinces automatic SI actuation ahocc rred. ....... .- * .
, Manually actuates SI 13%j1 reriorm immeanate actions of I13wEk'-U:
Verify Turbine trip
"* All throttle valves closed
"* All governor valves closed Verify 4KV ESF Busses energized
"* Bus 141 bus alive light lit
"* Bus 142 bus alive light lit Comments:
Braidwood 2002 NRC Exam 15 Scenario 02-X
N.T.r- r~ - 3%AIdIeIU INo : U0-- Event IN o. 6-9 II fl. fl riLption: MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI, faulted-ruptured SG 11 EveLV DcJ Applicant's Actions or Behavior Performs subsequent automatic actions of lBwEP-0, as directed: Verify FW Isolation:
*FW pumps TRIPPED.
*FW Isolation monitor lights LIT.
*FW pumps discharge valves (IFW002A, B, and C) CLOSED.
*FW Isolation monitor lights NOT ALL LIT
- Identify failure 6f FRV-520'to close
- Attempt manual closure of 1FRV-520
- Manually close upstream isolation valve lFW-006B Verify RCFCs Running in Accident Model -:
6Gop2 RCFC Accidenit Mode status lights LIT. Verify Cnmt Isolations: e Cnmt Isolation Phase A:
- Group 3 CNMT Isol monitor lights LIT.
*Cnmt Ventilation Isolation:
- Group 6 CNMT Vent Isol monitor lights LIT.
Verify AF System: sAF Pumps BOTH RUW ,N oAF Isol valves (IAFO13A-H) OPEN oAF Flow Control valves (1AF005A-H) THROTTLED. Verify CC Pumps BOTH RUNNING. Verify SX Pumps BOTH RUNNING, \ Verify all MSIVs are Closed Determine CS DOES NOT need to be actuated:
*CNMT Pressure has remained < 20 psig.
Verify Total AF Flow:
*AF Flow > 500 gpm.
*Control feed flow to maintain narrow range level BETWEEN 10% and 50%.
Comments: Braidwood 2002 NRC Exam 16 Scenario 02-X
Scenario No: 02-3 Event No. 6 - 9 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI, faulted-ruptured SG Time Position Applicant's Actions or Behavior I KU Performs subsequent automatic actions of 1BwEP-0, as directed:
"o Verify ECCS Pumps Running:
"o CV Pumps BOTH RUNNING CT: SSl Pumps:
E-O"J.
- Determines NEITHER RUNNING, and MANUALLY STARTS IA SI pump. (IB SI pump fails to start.) . ,, ,.
"o RH Pumps BOTH RUNNING . *' ' 7,:;\
"o Reports SI pump failure to US. ... , "LY,.,:4 .1 :.. .; .
o Dispatches operaiors to investigate IB SI pump andbireaker......... ... .)... . .. RO .'".... Perfbi-ubsequentactions of IBwEP-0," directed:' . - i.. -.-. . . Verify ECCS Valve Aignmenf: . . ,... . ,
*Group 2 Cold Leg Injection monitor lights LIT.
Verify ECCS Flow:
*lHigh head SI Flow (1FI-917) > 100 gpm.
-IF RCS Pressure < 1700 psig (lPI-403A/405), THEN verify IA SI Pump Discharge Flow (1FI-922) >
200 gpm. o IF RCS Pressure < 325 psig, THEN verify RH Pump Discharge Flow (1FI-618/619) > 1000 gpm. Check at Least One PZR POR"' Relief Pat* Available: '... ' "
"oPORV Isol valves (1RY80.0A and 1RY8000B) AT'LEAST ONE ENERGIZED.
*PORV Relief Path AT LEAST ONE AVAILABLE:.. . .
...PORVinAUTO.
- Associated isol valve OPEN. . . . . ,
BOP Performs subsequent actions of lBwEP-0, as directed: Verify Generator Trip:
*Main Transformer output breakers (OCB 1-8 and OCB7-8) OPEN.
*PMG Output Breaker OPEN.
Verify DGs Running: eDGs BOTH RUNNING. e DGs BOTH SX Cooling Valves (1SX 169A and 1SX 169B) OPEN.
- Dispatch operator to LOCALLY check operation.
*1 i Comments:
Braidwood 2002 NRC Exam 17 Scenario 02-X
Scenario No: 02-3 Event No. 6 - 9 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI, faulted-ruptured SG Time Position Applicant's Actions or Behavior BOP Verify Control Room Ventilation Aligned for Emergency Operation: ' **Checks RM- 11, Grid 2, OPR3IJ-OPR34J < high alarm setpoint.
*Checks operating VC train equipment running:
Supply fan
- Return fan
- M/U fan ,
....2. Chilled Water pump ... .
- _:;.0 MCRChiller' .....
..:. *:: .. . 1.. .. .. :..
*Checks Operating VC tiain dampeis aligned:
IfM/U fan outlet damper (bVC024Y/0c.08Y)NOT FULLY CLOSED. . .* YCtrain'M/UJ Filter Light Lit . >
.r Checks Operating VC Train Charcoal Absorbed Aligned:. .. .. , ,
e Bypass damper closed (0VC43Y/OVC444Y). e Inlet damper Open (OVC21 Y/OVC05Y) e Outlet Damper Open (0VC22Y/OVC06Y) e Control Room pressure (MCR/TB DP, OPDI-VC038) > +0.125" H20. BOP Verify Aux Bldg Ventilation Aligned for Emergency Operation: .
- Inaccessible Filter Plenums - Only TWO Aligned with Charcoal Abgofbers On Line:
o Plenum A: o Fan 0VA03CA Runnring with Flow Control Damper (OVA022Y) Open and Byp Isol Damper S.. (OVA020y) Closed. * ,,,..... o Fan OVA03CB Running with Flow Control Damper (OVA023Y)' Open and Byp Isol Damper (0VA436Y) Closed. *. .
- o. Plenum B:
o Fan OVA03CC Running-with Flow Control Damper (0VA024Y) Open and Byp Isol Damper (OVA02 IY) Closed. .. ,* . o Fan OVA03CD Running with Flow Control Damper (OVA025Y) Open and Byp Isol Damper (0VA437Y) Closed. o Plenum C:
" Fan OVA03CE Running with Flow Control Damper (OVA067Y) Open and Byp Isol Damper (OVA052Y) Closed.
"o Fan OVA03CF Running with Flow Control Damper (0VA072Y) Open and Byp Isol Damper (0VA438Y) Closed.
Comments: Braidwood 2002 NRC Exam 18 Scenario 02-X
Ii Scenrin Ncr (V)A ..XTh. £ ( I . . . V .- ,VenIIt INo). 0 - Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI, faulted-ruptured SG Time Position Applicant's Actions or Behavior BOP Verify FHB Ventilation Aligned for Emergency Operation:
*FHB Charcoal Absorbers -One Train Aligned:
o Train A:
- Fan OVA04CA Running
- OVA060Y Charcoal Absorber Inlet Isol Damper - Open.
. 0VA057Y Filter Flow Control Damper - Open.
1: , 0VA05 IY Charcoal Absorber Bypass Isolation Damper - Closed.
. B . .Ta .. k ,.. . . .B.:.
-VA055Y Charcoal Absorber inletsol Damper- 0 en.".. ..
...... 0VA062Y Filter'Flw ontrol]Damper7- Open.
0VA435Y Charcoal Absorber Bypass Isolation Damper - Closed. RO Check PZR Spray Valves and Porvs: e .. Spray. valves (1RY455B and 1RY455C) Closed.
- Porvs: 1RY455A and IRY456 Closed Attempt to Maintain RCS Temperature Control: .
S2 .... With ANY RCPs running - RCS average temperature STABLE AT OR.TRENDING TO 557 Degrees F. o Maintains > 500 gpm AF flow until at least one SG is 10% (31% Adverse).
*Check RCP Status:
- Determines RCPs RUNNING. '. .
. Check IfRCPS should be Stopped: .-. ....... ,, .
*ECCS Flow > 100 gpm on IFI-917 or SI pump'Flow> 200 gpm on 1FI-922.
*RCS Pressure NOT LESS THAN 1425 psig. 8 . . .
Check Secondary Pressure Boundaries Intact:
- Identify the 11B Steam Generator pressure decreasing in a uncontrolled manner US Diagnoses/Announces Faulted Steam Generator, Transitions to 1BwEP-2, "FAULTED STEAM GENERATOR ISOLATION", and directs actions:
- Gets acknowledgement from RO and BOP.
e Informs SM of plant status, and evaluates for GSEP. e Contacts WEC to have the STA commence monitoring Status Trees. _ - [ _ Comments: Braidwood 2002 NRC Exam 19 Scenario 02-X
Scenario No: 02-3 Event No. 6,7,8 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI Time Position Applicant's Actions or Behavior BOP Acknowledge transition to 1BwEP-2 and performs actions: Re-verify all MSIV's closed Check if any Steam Generator secondary pressure boundary is intact: 4- Identify 1A,1C, and ID steam generator press§iArs appear stable or increasing
- Identify lB Stea G3enerator as faulted 'i.'-.
Pr~susre decreasing~ hinanunonroe marmaier nd/or completelyr dep'esunized BOP Isolate Faulted SG . -:. .-.. , , , .:, [CT] I1AF013B closed E-2--A
- 1AF013F closed Check FW to faulted SG isolated
. Associated row of FW ISOLATION MONITOR LIGHTS panel lit for faulted SG.
- 1FW009B open I*FW034B closed . . . . .
FW3B closed. . .. ..
*1F520NOTclosed ~
"FW I 036B closed .
- Verify SG PORV on faulted SG closed lMS018B .
Verify SG blowdown isolation valves on faulted SO - closed ' . .
- ISDO02E .
lSDO02F Verify SG blowdown sample isolation valve on faulted SG - closed
- 1SDO05C BOP Monitor AF Pump Suction Pressure
- AF PUMP SX SUCT VLVS ARMED alarm - NOT LIT Check secondary radiation
- No radiation monitors in alarm indicating steam generator tube rupture Comments:
Braidwood 2002 NRC Exam 20 Scenario 02-X
Scenario No: 02-3 Event No. 6,7,8 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI Time TI Position Applicant's Actions or Behavior Us Diagnoses/Announces transition to 1BwEP-1, "LOSS OF REACTOR OR SECONDARY COOLANT", and directs actions:
"* Gets acknowledgement from RO and BOP.
"* Informs SM of plant status, and evaluates for GSEP.
"* Directs STA to continue monitoring Status Trees.
"NOTE:Upon transition to IBwEP-1 and' after 1B SG Wide Range level reaches <10% level, the SGTR on 1B Steam Generator will Occur resulting in a faulted / ruptured Steai 'Generatorvia the 2 open'.
MS Safety , lV0 on"' the 11l p. K ;...v:..ý 2i' , . ""., " .Yi. i . CUE Increasing Radiation'/ Radiatiof alarms on IB MS Rad Monitors Indicated pressure increase in lB Steam Generator .;,...". Indicated steam flow from lB Steam Generator , ... Decreasing RCS Pressure and level CREW
- Identify increased radiation sensed on the 1B Steam Generator MS Line Identify decreasing RCS prdssure and level , ,. .
. Identify indicated pressure increase and steam flow on the lB Steam Generator US Diagnose by use of board indications and/or: 3 ',* ;. ,. . ,'. .. ,
- Operator Action Summary page of 1BwEP-lfor abnormal secondary r'adiation
. Step 4 of 1BwEP-1 for abno6rmal secondary radiation ., .
That 1B.SG is faulted and ruptured and make the transition to 1BwEP-3 "STEAM GENERATOR TUBE RUPTURE" .. .,.
. Gets acknowledgement from RO and BOP. . ..- , ., . " ,
. Informs SM of plant status, and to evaluate for GSEP. - . . .
RO Performs actions of 1BwEP-3, "SGTR" as directed:
- Check If RCPS should be Stopped if not previously stopped
- ECCS Flow > 100 gpm on 1FI-917 or SI pump Flow > 200 gpm on 1FI-922.
- RCS Pressure NOT LESS THAN 1425 psig.
Comments: Braidwood 2002 NRC Exam 21 Scenario 02-X
Scenario No: 02-3 Event No. 6,7,8 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI Time Position Applicant's Actions or Behavior BOP Performs actions of 1BwEP-3, "SGTR", as directed: Identify Ruptured SG fom any of the following means:
*Unexpected level rise in 1B SG.
*MS Line Rad lB MSL/ MSIV room NOT NORMAL FOR PLANT CONDITIONS.
*High Activity from lB SG sample.
. .Indicatedsteam flow and pressure on faulted / isolated steam generator BOP Verify*B...,-VCLOSLD Isolate Flow from 1B SG" ., 2. .. . .
- Verify IB SGBwdown olation valv`e(1SD002' and SDO02F) CLOSED.-,,.
* * " *Verify lB MSIV and Bypasý valves CEOSED . .. '.......'
Determine PORVs on intact Steam Generat6rs are available (IMS018A, IMS018C, 1MS018D) US/BOP Identify ruptured Steam Generator level is <10% Narrow Range DO NOT initiate AFW flow to ruptured / faulted Steam Generator Verify AF Isol Valves remain CLOSED 11AF013B .. ' , : ..
. .AF.13F .- . . ,. . .
I'I US Evaluate Ruptured Steam Generator pressuire less than 320 psig and transition to 1BwCA-3.1, "SGTR WITH LOSS OF REACTOR COOLANT- SUBCOOLED RECOVERY DESIRED" . .'., . Gets G acknowledgement from RO and BOP. -. ,,
. Informs SM of plant status, andto evaluate for GSEP.' ,..
RO/BOP: Perform actions of 1BwCA-3.1 as directed: ., , , ........ -- *,4
- ResetSI ........ . . , .
o Reset Cnmt Isolations (Previously perfortmed) . ,...,,.' 9 Verify all AC buses Energized e Check if CS should be stopped (CS is not initiated) BOP Perform actions as directed:
"* Check ruptured SG (1B) Narrow Range level < 10%.
"* DOES NOT Initiate feed to lB SG Level.
"* Stop RH pumps if RCS pressure >325 psig, stable or increasing Comments:
Braidwood 2002 NRC Exam 22 Scenario 02-X
Scenario No: 02-3 Event No. 6,7,8 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI T- . *.* ,T. . .. II I lie tion Applicant's Actions or Behavior
+
BOP Perform subsequent actions as directed to initiate plant status evaluation:
"* Check Aux Bldg Rad Trends for both Unit 1 and Unit 2 on RM- 11 or HMI:
eVent Stack effluent 1PR28J, 1PR30J, 2PR28J, 2PR30J.
*ECCS Pump Cubicles - 1PR13J through IPR18J.
*Grid 4 Aux Bldg Area.
"* Place Hydrogen Monitors in service per BwOP PS-9, POST LOCA CNMT H2 MONITORING SYSTEM OPERATION, . ', . .. ' -", .
I. US .... Perform actions of lBwCA-3.1 ,I , .. , .. ,..
*Call-Cheniistry for samples: 'i* kf:~ K; ORCS Activity.. ....... .. * *; . ..
*RCS Boron Concentration . .. , .:.." .-. " , .,W '.,,...
9RCS Hydrogen Concentration .
*Ruptured SG (ID) Activity
- Cnmt Atmosphere .
- Evaluate equipment needed in CC and RH systems to assist in plant recovery.
US Get Concurrence from SM that the Hydrogen Recombiners DO NOT need to be run. Note: Crew will decide that they have accomplished the Isolation of the Faulted ID SG in accordance with 1BwEP-2, "FAULTED SG ISOLATION" . .. .,.: v ... .. BOP Performs actions as directed to continue in 1BwCA-3. 1: .. . . " -. ...
- Controls Intact SG levels between 10%,and 50%. : . . ".
e Verifies NO INTACT SG level INCREASING IN AN UNCONTROLLED' MANNER.' RO Performs actions as directed to continue in 1BwCA-3. 1: . ',
"* Determines Cooldown in RCS Cold Legs is NOT LESS THAN 100 Degrees F in any 1 hr period.
CT: "* DOES NOT Initiate any further Operator Controlled Cooldown of the RCS until the Cooldown rate in the CA3.1 RCS Cold Legs is < 100 degrees F in any 1 hr. B. BOP Check if Subcooled Recovery is appropriate:
- Determines RWST level is > 67%.
t Determines 1B SG level < 93% RO/US Checks RCS Subcooling: e Determines RCS Subcooling is acceptable by Iconic or Attachment A. Comments: Braidwood 2002 NRC Exam 23 Scenario 02-X
Scenario No: 02-3 Event No. 6,7,8 Event
Description:
MSIV Closure (all), MS Safeties stick open (2), FRV-520 fails to isolate on FWI Time Position Applicant's Actions or Behavior
/'
? I
-f +i i
Scenario is complete at this point or at the Chief examiners discretion S .... " "'. ".. . . ' ... .
- i*.':> . ',. -. '. .. '-i:* -' ,.. 'o:, ,
/ S. .11.. j Comments: Braidwood 2002 NRC Exam2 24 Scenario 02-X
SHIFT MANAGER TURNOVER Weekday, Today, 2001 ONCOMING SHIFT 2 UNIT 1 STATUS UNIT 0 & 1 MAJOR OOS's MO DE ............ 1 I A Containifnrit, Spray Rx Pw r ............ 77 IPump Generator MWe ..... 942 1D CDCOB Pump Max Load/Power .... 100% Min Load/Power .... 700 MW Max Ramp Rate ..... 5 MW/Min Desired Delta I ..... Target On-Line Risk ....... Green Boron @ .......... 926 Control Bank ....... D @ 170 LCOAR ENTRIES PREVIOUS 48 HRS UNIT 0 & I MAJOR SURVEILLANCES 3.6.6 Condition A for 1A CS Pump hour 36 of 7 day I COAR UNIT 0 & I IN PROGRESS UNIT 0 & I PENDING 1A CS Pump motor bearing replacement. Unit I load increase to 1250 NMIwe to meet load demand @ 5 MW/min per electric operations Alignment on I D CD/CB Pump. Est. RTS by end of shift today Focus Areas: U Verification Practices U Command and Control Standard for Execution of Critical Steps THiINK CONFIGURATION CONTROL and SAIFEV !!! SCHEDULED ACTIVITY CONFLICT C10 8.Joe
SHIFT NIANAGER TURNOVER ILE9 f*F A
- F- - -
UNIT 2 MAJOR OOS's* MO DE ............ 1 UNI T 2 MAJO _________________ Rx Pw r ............ 97.6 Generator MWe ..... 1197 Max Load/Power .... 97.6 impulse pressure Min Load/Power .... 700 Max Ramp Rate ..... 5 mw/min Desired Delta I ..... Target On-Line Risk ....... Green Boron @ .......... 1037 Control Bank ....... D @210 LCOAR ENTRIES PREVIOUS 48 HRS UNIT 2 MAJOR SURVEILLANCES "icoar-num' .AffectedEquipment" UNIT 2 IN PROGRESS UNIT 2 PENDING Make sure that equipment such as ladders, fans, hoses, electrical cords either have tags on them, are put away, or notify SM so they can help get responsible persons out. Safety: Electrical: SH-AA-131 Inspecting & Testing Extension Cords and Generators Dose INFO: Dose goal for day 10 mr SCHEDULED ACTIVITY CONFLICT IC18.doc
S!IiFT MANAGER TURNOVER Administrative Temporary Procedures I Modifications T- mod U1 Trn B RVLIS. Jumper Install6d on (I)C U-1 MPT Disconnect. 1FW009A T-Mod for Hyd Pp Press Sw 1PS-FW162. T-mod for drain on 1B AF casing. Tmod for no disc in 2CC9502B installed. Daily Orders / Special Op Orders Daily Manning Schedule Sec Ž4hect for restrictcd duty perso'nncl and ovcrilimc rcstricnions Oncoming STA Fire Chief Control Room Rounds (GSEP / LER / DVR / ENS) Material TS Conditioning SFP High Level alarm did not alarm during calibration RWP's Releases / Precautions ALARA A Infrequent Evolution Activities Lesson learned files L:\shared\opex then ctrl F to search SPSO / Division LD Alternate BPO Outside # 815-727-5902/5903 Tie # 8-565-5902/5903 Unit 1 Comments Unit Common Comments Battery 112 cell 32 has floating material in electrolyte, eval'd OK U1 FC Cleanup SFP D.O. OOS prevents filling U- I tanks normally, but BwOP DO-6 U2 FC Cleanup OFFLINE (leak) can be used to fill tanks. T-MOD is installed allowing U- I boiler FC Cooling Ul ops. 50K DO Tank empty IAF006A is Icaking by from CST. 125K DO Tank and FRAC Tks Certified Aux Steam U-1 ES -U1 HDT U-0 CC Hx U1 U-0 CC Pump Bus 141 U1 Aux boiler Wet lay-up U2 Aux boiler Wet lay-up SAC / Dryer U1/U0 MUDs U-1 CST CW Makeup Running OA/OB CW Blowdown On Lake Level 5.8' Unit 2 Comments General Comments 2AF017A leaking by .3 gpm, AR 990116738 Conference Call Phone Number 800-232-1234 Teleconference S/G sampling lines/valves at HRSS are not correct. Do not folder ID #=472664085 hang OOS on any 2PS181 valves till further notice. Meeting Place 630-663-7120 +code 2PS229A still blows fuse 2PA32J Ckt 9 Duty Team is located @ SITE APPS. NRC Duty list in book CV seal leakage: Substation construction (John Strle) Cell phone 815-351-8472 2A Running 200cc/min shutdown about 6 drops/min 2B Running -12 dpm; S/D- none Caution Cards Abnormal Positioned Components Cl '.A,'IN UJV 'J CCNUM EPN AbnormalPosition SM BEEPER TURNOVER Shift 1 To 2 Time Now Date Today Offgoing Oncoming IC18.doe
l\ I 1.VNIkN \I F R 'F RN 0VIFR
.()I'I R1\ OlI"* (()N( I *IN I' Equipment Unit 0 BwAP 330-10 Compensatory Actions Equipment Unit 1 BwAP 330-10 Compensatory Actions P/P PORV V(orify -1/MPORVs Open1)M Stpoint or Op(n PWR PORV Spurious SI C('oncrn Equipment .Unit 2 BwAP 330-10 Compensatory Actions; i n-T rmn~ ,, - - -. . . .. ..
I "' I, I k tii V V(iily F /k1ýH()Vs Open at Selpoint or Open P7R PORV Spurious SI 2A3 (V PUMkr ) Monitio sij il I(kiý (; shiftly Notify System FniF incerinoi if > 0.5 lpm UNIT 0 CONTROL ROOM ANNUNCIATORS LIT UNIT 1 CONTROL ROOM ANNUNCIATORS LIT Annunciator Annunciator Description Problem AR#/WR# Status UNIT 2 CONTROL ROOM ANNUNCIATORS LIT
-XH~t~at6 Ahhuncliatcr Descr~fifVn scrsto r i -tl R tusIRN I~
OP-AA-101-301 Evaluations
BwAP 335-1T6 Revision 8 Information Use UNIT 1 NSO TURNOVER Weekday, Today, Oncoming Shift 2 Unit 1 Status Mode 1 Max load/power 100% Power 77% Max ramp rate 5 mw/min. Mw electric 942 MW Unit Risk Green Min load/power 900 Control Rods 171 Desired Delta-I Target Boron concentration 926 PPM IN PROGRESS PENDING Containment Spray Pump 1A motor bearing replacement Unit 1 load increase to 1250 Mwe per electric operations Alignment of 1D CD/CB Pump LONG TERM . . .. .. . . ADMINISTRATIVE Temporary procedures Temporary alterations New caution cards Unit logbook Unit routine BDPS Icoar in mode 3. Aux. Electric room access Daily orders Control board walk down LCO/TLCO RETS DEQUIP/AAR 3.6.6 1A CS Pump
BwAP 335-1T( Revision ý Information Us( TURNOVER ITEMS NSO SHIFTLY/DAILY SURVEILLANCE
- 2) SSPS CHANNELS/BISTABLES 13train SSI), logic ground to chassis ground had higher han cxpecLted readings durini SSPS, AR written.
- 3) SYS - SAFEGUARDS
- 4) SYS - PRIMARY 1. CC to spent fucl pool hx is at 2100 "pm.
- 5) SYS - BALANCE OF PLANT Spent Iflel pool cooling now on Unit I.
- 6) ALARMS-SER/ANNUNCIATOR
- 7) ALARMS - PROCESS/RM-11
- 8) ALARMS - FP/OTHERS
- 9) CHEMISTRY Max flow through condensate polishers at Ilill power is -2000 gpm without causing a low npsh alani. This is only a guideline and not an absolute value.
- 10) RADIATION PRECAUTIONS
- 11) NUCLEAR INSTRUMENTATION
- 12) MCB INSTRUMENTATION
- 13) MCB CONTROLLERS
- 14) ELECTRICAL DISTRIBUTION - AC MPT transfonrer disconnects has bad seal on one phase. Jumper installed, SOC on disconnect - do not operate.
- 15) ELECTRICAL DISTRIBUTION - DC
- 16) EGC STATUS
- 17) BWOP_ (PROCEDURE AND STEP IN FECT)
COMMENTS 15 gals PW will raise RCS Temps .1 F 1FW009B has small nitrogen leak on 1PS-FW1 65, AR written. POST REVIEW } US FS SM TIME: NOW SHIFT " OFF GOING DATE: TODAY SHIFT ONCOMING 2 1
Simulation Facility Braidwood Scenario No. 4 Operating Test No. 2002 Examiners: Applicant: SRO RO BOP Initial Conditions: IC-7, 24% power, BOL Turnover: 24% power, BOL. The 1B Diesel Generator is OOS for replacementfof Turbo Charger. The DG has been OS for 18 hours and is expected to be returned to service by the end of the shift. 1C Heater Drain. Pump is OOS for motor bearing replacement. Unit 2 SAC is OOS for an oil change and is expected to
'I', ,
be returned to service by the end of the shift. The BRCCW Pump is runniing for ASME testing. -.
- Eyent Maif.No. Eyent .. .. .. Event No. Type* ."Description Preload MF RP1 5 C RO 1A Emergency Diesel Geherator Sequencer Failure RD12F SRO C-Il Rod Stop Failure (Preload) BOP .
1 N BOP Ramp up Turbine Power to 620 Mwe at directed MW/min SRO R RO. Raise Reactor Power using rods and/ordilution SRO .. 2 RX04A,0 I BOP Main Feedwater Flow Transmitter (I FT-5 IG) failure low (controlling
'SRO channel failure) ..- . ..
3 RX13A, 0 I RO Controlling Pzr Level Channel (LT-459) failure low ___ _ .SRO _.,___ _ S4 ... CC10A C BOP Loss of ESF Bus 142. Failureof lACCWlp'imptoato.0start. SRO 5 OR ZDIBKSEL C RO Rod Control fails in Automatic Mode - Manual Mode is not available (AUTO) . SRO Tref Programmer fails HIGH MF RX12,586 Uncontrolled Outward Rod Motion 6 TH01 M RO Manual Reactor Trip BOP Pzr Vapor Space Leak / RCS LOCA resulting from rod control transient. SRO 7 ED15C C RO Loss of SAT feed to ESF Bus 141. EDG LA load sequencer does not BOP function. SRO I. I 1 I I j t i
-I.......... _t *(N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Braidwood 2002 NRC Exam Scenario 02-4
SCENARIO OVERVIEW The unit is at 24% power, BOL. The 1B Diesel Generator is OOS for Turbo Charger replacement. The Diesel Generator has been OOS for 18 hours and is expected to be returned to service by the end of the shift. 1C Heater Drain Pump is
)OS for motor bearing replacement. Unit 2 SAC is OOS for an oil change and is expected to be returned to service by
"----the end of the shift. The lB CCW Pump is running for ASME testing. Power is to be increased to 620 Mwe following 1BwGP 100-3, "POWER ASCENSION". Following clearly observable plant response from the reactivity changes, the 1A Steam Generator controlling feed water flow transmitter (1FT 5 AiDvill fail low, resulting in lowering feed, flow f'othe*A.l SG and decreasing level. The crew,ý will dimgnose the feed flowi, steam flow mismatch and take actionsito restore normal.feed flow by taking madnial control ofFRV-510 an restoring normal flow. The.SRO wal: enter and direct actions of 1BwOA INST-2, Attachment G
.. FEEDW\ATER FLO'w 'Cf IN:L FAILURE";, and-establish notrmal stUa nferiatn6r level. control prior to re,a-hgii n'(', a:.
lo-2 water level reactor tri*6 ondition in the IA SG. , . After actions for the feed flow failure are completed, a failure of the controlling channel 6fiPzr Level will occur causing letdown to isolate. The crew will respond by diagnosifig ýthe failure of the level channel and entering and performing the actions of 1BwOA INST-2, Attachment C, "PRESSURIZER LEVEL CHANNEL FAILURE." An alternate controlling channel will be selected, letdown will be manually restored, and the crew will take actions to restore Pzr level to program level. Bistable(s) will be tripped for the failed channel, and Tech Specs will -be'reviewed for applicability. LCO 3.3.1, Condition K will apply. '.... . After the actions for the Lý-459 failure are completed, an overcurrent condi'fion. on ESF Bus 142 will result in a loss of one ESF Bus. The Crew should diagnose the electrical failure and enter 1BwOA ELEC-3, "LOSS OF 4KV ESF BUS'.".
- At the same tne, the '13 CCW Pump that wass iruinnimig for an ASME test wil be deenergized, and the lA CCW Pump will fail to automatically start -on low discharge pressure. The crew must restore CCW flow to the unit by either manually '..
starting the 1A CCW pump oir the common CCW pump. The SRO will identify that DC Crosstie is required within one "iourfor DC Bus 112, and Offsite AC Power Availability Surveillances must be performed within one hour. After the actions are complete for the loss of an ESF bus, the Tref Programmer will fail to it's highest value at 5861F. This will cause ý Tref>Tave temperature mismatch and trigger rods to withdraw in automatic. Rod control will fail such that only automatic control is available (Manual will not function). Since the Tref program temperature cannot be defeated, this will result in a continuous, uncontrolled outward rod motion. The crew will recognize that no change in turbine loading has occurred and attempt to stop the outward rod motion by placing rod control in manual and taking the actions of lBwOA ROD-i, "UNCONTROLLED ROD MOTION." When rod motion cannot be stopped the crew will manually trip Unit-1 reactor and perform the immediate actions of 1BwEP-0, "REACTOR TRIP OR SAFETY INJECTION." Immediately following the manual reactor trip, a Pressurizer Vapor Space Leak develops. The crew should diagnose the decreasing pressurizer pressure and manually initiate Safety Injection. An automatic Safety Injection will occur if not manually actuated by the operators. Sixty seconds after the manual reactor trip is initiated, the Main Generator will trip as designed. Coincident with the generator trip, the SAT feed to ESF Bus 141 is lost. This will deenergize the remaining ESF Bus. Emergency Diesel Generator 1A will close onto the bus as designed, but the SI and safe shutdown sequencers will fail to function correctly, resulting in an energized ESF Bus (141) but no ESF loads running. The crew will have to manually load/start safeguards equipment on Train A to restore one train of Safety Injection. 1BwOA ELEC-3 may be entered to perform the bus loading. Once SI flow is restored the crew will continue the remaining actions of 1BwEP-0 and transition to 1BwEP-1, "LOSS OF REACTOR OR SECONDARY COOLANT" to mitigate the Vapor Space LOCA in progress. Completion criteria is entry of 1BwEP ES-1.2. Braidwood 2002 NRC Exam 2 Scenario 02-4
Critical Tasks
"* E-0--A: Manually trip the reactor from the control room before exiting 1BwOA ROD-1.
SE-0--D: Manually actuate at least one train of SIS actuated safeguards equipment before transition to 1BwEP-1
- 3. EO--H,I: Manually start the LA RH and 1A SI Pump before transition out of lBwEP-0
* ... '
- 2 " .l ' ". - "4" 9 .. .,*
*.* ,3!:* .*.;*
* , ': : ; '! ¢ . / ' *", -* *': * , : "* * ; , ; .:;, . . ., .: v . .: : .. .:f. . .. , ¢. ' *,. :
it 4
.. . ....... . .4 .4.. ..... . . ...... .... ....- . .. . ..........
4- :"* ' . . * :,-". " :*,id : .,*. (
- .-.. v .* ~......
.... " . . .. ... ..... >..,: i... .
i * ' .. . i ;m Braidwood 2002 NRC Exam3 3 Scenario 02-4
4. SIMULATOR OPERATOR NOTES:
-imulator Setup:
IC-7, 28% power, BOL Align switches: lB DG C/S PTL and OOS ACB 1423 PTL and OOS .... I C HD pump C/S PLT and OOS. OOS -' *i: .. ..
-2 -1 and U-0 SAC running ' , ' .
""Ready for.Training" cec l ist. -,. - " -- h
- Insert PRELOAD Events: . " . RF EGO9, MATNT_0 BDGOO 008'..: ý: -4< . Swap running CCW Pumps, LB in RUN, IA in Standby IMF RD12F Rod Stop Failure of I... 11 . . , The following defeats auto loading of 1A EDG loads: IMF RP15C 1A SIPump IMF RP15E 1ARH Pump .. IMF RP150 IA CC Pump 1MF RP15Q IA SX.Pump .... IMF ,R1 AF Pump Initiate flowchart for load increase, lBwGP 100-3, step 42 . i;;. .. . . :- -:
.: .. ~~.
.. ,. ... . ',Y : ;,
Event 1 Power increase - - ........ " " . , ,.. Event 2 Main Feedwater flow transmitter 1FT-510A failure SDG RX15 IMF RX04A, 0, 120 Insert malfunction after clearly observable reactivity changes/plant response to power increase and with lead examiner concurrence. Acknowledge all info passed for SM, WEC, and maintenance Event 3 Controlling Pzr Level channel failure (LT-459) SDG RX6 MF RX13A, 0, no ramp Initiate after actions for the feed flow transmitter failure have been completed and the plant stabilized with FF and SF matched and level on the lB SG normal. Role play as Unit-2 admin/extra NSO to accomplish bistable tripping. Trip Bistable(s) as follows: SDG RX6 Cabinet Door #1 OPEN RF RP20 OPEN Hi Level Trip C1-751 BS-1 RP RX029 TRIP Cabinet Door #1 CLOSE RF RP20 CLOSE Acknowledge all info passed as SM, WEC, and maintenance Braidwood 2002 NRC Exam 4 Scenario 02-4
Event 4 Loss of ESF Bus 142. Failure to 1A CCW Pump to auto start The failure of lA CCW pump to auto start on low discharge pressure MUST be inserted first. SDG CCl MF CC02A, 150 fail discharge pressure detector to 150# to prevent low pressure auto start of IA CCW pump
, ext - insert loss of ESF Bus 142 SDG ED2B MF ED07B fault generated on ESF Bus 142 If dispatched to investigate status of ESF Bus 142 report physical damage is evident to the bus If asked, report there is NO known fire in the plant If dispatched to investigate the 1A CCW Pump, report pump is running OK and no signs of abnormalities Acknowledge all info passed as SM, WEC, and maintenance .
vEent. Uncontrolled Rod Motion " .- i '. -. , . ..t .,. . ..... * . First, ov erri*de rod control such that automatic is thie"bnlj mode available . .c A' IOR ZDIBKSEL (AUTO) Then, fail Tref program to 586 0 F IMF RX12, 586 Fails Tref to 5861F and generates an automatic rod withdrawal signal IMF RX 17 (+3.1 'F) Fails the Terror signal to rod control to ensure continuous withdrawal Acknowledge all info passed to SM, WEC,aýnd nimaintenance "Event6 Manual Rx Trip - Pzr Vapor Spa6ce Leak .,-2, . Insert inmnediately following the manual reactor trip: t2 *.: .',*,7 , MF TH01,(4) Initiates a Pzr Vap6r Space LOCA: .. .. Acknowledge all info passed to SM, WEC, and maintenance ., ..
- -iEvent 7 Loss of SAT feed to ESF bus 141 - failuIe of EDG 1A sequencer to load safe shutdown loads Verify the following preload malfunctions are active - the following loads will fail to sequence:
RP15C 1A SIPump RP15E lA RH Pump RP150. 1A CC Pump RP15Q 1A SX Pump RP15S 1A AF Pump Modify the following Override to cause a temporary loss of power to ESF bus 141 Override CS for bkr 1412 (ZDI1HSAP041) to TRIP If dispatched to investigate status of Bkr 1412 report no apparent damage Acknowledge all info passed to SM, WEC, and maintenance Braidwood 2002 NRC Exam 5 Scenaario 02-4
Scenario No: 02-4 Event No. 1 Event
Description:
Continue ramp towards full power by raising turbine and reactor power Time Position I Applicant's Actions or Behavior J CUE Turnover information contained instructions to continue power ascension to 620 MW T I US Implement actions of 1BwGP 100-3 Direct load increase to 620 MW at 5 MW/mm.
- Initiate/continue iBwGP 100-3 flow chart power increase . , . -...
. , Conftact Chemistry andHP for load change > 15%/hr. . .- ' ,.., ,.. .: . - :. .. .
CREW Review applicable Precautions, and and Actions of 1BwGP100-3_:0mi0tations RO Verify rod position and boron concentration. Initiate dilution (BwOP CV-5) Determine required dilution volume by: o Effects of previously performed dilutions o Braidwood.BorationDilution Tables . . 0 Determine required PW flow rate.
- Set 1FK- 111 PW/Total Flow Control to desired dilution'rate. . . ....
- Set 1FY-0 111 Primary Water Control Preset Counter to desired volume..... ......... .. .:"
& Place MAKE-UP CONT SWITCH to STOP position. .. .. , .
- Set MU MODE SELECT to Alt DIL 'position. .............
. Place MAKE-UP CONT Switch to START . ..... ...........
o Verify proper operation of valves (CV1 IA throttles open, CV101B open, PW flow on recorder) OR Batch addition:
"* Open CV11OB.
"* OpenCV111A.
0 When desired amount of primary water added:
"* CloseCV111A.
"* CloseCV1IOB.
Comments: Braidwood 2002 NRC Exam 6 Scenario 02-X
Ii .-, - 11Scenario No: 02-4 Event No. 1 Continue ramp towards full power by raising turbine and reactor power Event
Description:
Applicant's Actions or Behavior Initiate turbine load increase:
"* Depress LOAD RATE MW/MIN
"* Enter 5 MW/min
"* DepressgREF'
"* Enter power level (620 MW)L ., :...
"* When ready to begin load Increase, depress GO SVerify load increases. .. ... . ..
RO¸ Monitor power increase:
- Monitor reactor power, Tave, Al
- Verify rods move in AUTO to maintain Tave within +/- 1.0°F of Tref.
If diluting:- 0 Monitor VCT level 0 Verify RCS boron concentration decreasing .,. 0 Monitor PW/Total counter .. '. . .,., . .. 0 Verify dilution auto stops at preset value. .. *.'. 0 Return ReactorMakeup System to blended flow at current boron concentration. t I ,Note: Following clearly observable plant response from the reactivity changes, Event 2 is entered. Comments: Braidwood 2002 NRC Exam 7 Scenario 02-X
Scenario No: 02-4 Event No. 2 Event
Description:
Main Feedwater Flow Transmitter (1FT-5 1 A) failure low (controlling channel) I . I Time Position Applicant's Actions or Behavior I (Note: Ensure swap has been made to Main FRV's before running first malfunction) CUE: Annunciators: 1-15-A4, "SG IC FLOW MISMATCH FW FLOW LOW" SG *1 Feed 1-15-A3 "SG IC FLOW MISMATCH STEAM FLOW LOW"' S G*IA Feed Water Regulating Valve opens SG IA level increases BOP/IUS Identifv'/Rep~ort failure of Feed'water flow'chanY~1d
- BOP Take maiual control of lA Feed Water Regulating Valve and rtýain; control of IC SG level. * .:. . ,
US Enter 1BwOA INST-2, OPERATION WITH AFAILED INSTRUMENT CHANNEL, NTT. G," 1;. *..
"FEEDWATER FLOW CHANNNEL FAILURE" US Direct actions of ATT. G, "FEEDWATER FLOW CHANNNEL FAILURE" BOP Check affected SG levels "SGlevels -NORMAL . ..
. Place feed reg. valve in manual . ......
' ,, 'estore level to a stable condition ....
Operable feed flow control ciinel SELECTED .. .
*! Sefle~ct an operable channel Automatic level control ESTABLISHED .. .. ..
- Return SG 1A level control to automatic when conditions are stable. "
RO/US Check HD System operation HD pump discharge flow control valve position NORMAL US Inform SM/Maint of SG 1A feed flow channel failure. NOTE: After actions are complete for the feed flow channel failure, EVENT 3 may be entered. Comments: Braidwood 2002 NRC Exam 8 Scenario 02-X
Scenario No: 02-4 Event No. 3 Event
Description:
1LT-459 - Controlling Pressurizer Level Channel failure low Time Position[ Applicant's Actions or Behavior CUE Annunciators: 1-12-A4 PZR LVL LOW HTRS OFF LTDWN SECURED 1-12-A5 PZR HTR TRIP 1-12-B4 PZR LEVEL CONT DEV LOW 1-12-C5 PZR PHASE LOSS OR REVERSAL , . 1-12-D5PZRHTRSCRCLGFANFAILtJRE"; ý. .. .<YI",'> i'"f ..
. .. .RO ' Diagnose failure of lLT-459. . . . ... ,. . .
Announce failure and loss of letdown flow.!
..... Perform aitii* of B;wOA iIST-2 Attachment C, Rev. , "PRESSURIZER LEVrC. ŽNLT
... FAILURE" directed b.-
y U2 -. . . ..
- Evaluate PZR level. If NOT'NORMAL, takes manual control (PZR MastervLevl controller and! or
lCV121) to restore level. o Reduces charging to a minimum (seal injection), then close either ICV8105 or 1CV8106.
. SELECT operable channel (461/460, left position) for PZR level control. .... .
o SELECT operable channel to level recorder (ANY but 459, normally on 460).
- VERIFY PZR level > 17%.."
- Re-establishes Letdown IAW BwOP CV1 7, "ESTABLISHING AND SECURING NORMAL'AND RH LETDOWN FLOW" (may be performed by either RO or BOP. See page 10). "
- Restores Variable heaters to NORMAL. . . ..
. Restores Automatic level control (PZR Master LevelIController and/or 1cv121). ....
- Coordinates bistable tripping (expected alarm I-12-A3). .. . . -. . .. ,.
US Diagnose/Acknowledge failure of 1LT-459', Cbntrolling PZR Level channel and loss of letdown.. Enters IBwOAINST-2 Attachment C, "PkESSURIZER LEVL CHN LTAILURE"and diiects actins:
- Orders manual control of PZR level if not normal. . . . . .
o Charging reduced to a minimum (seal injection), then 1CV8 105 or ICV8106 closed.
"* Operable channel selected for control.
"* Operable channel selected for recorder.
"* Re-establish letdown when level >17%.
- Restore heaters to normal.
"* Restore Automatic level control (Master controller, and/or 1CV 121).
"* Bistable Tripping.
"* Refers to Tech Specs 3.3.1. cond K, 3.3.4., 3.3.3., and determines a 6 hr action to trip bistables applies.
"* Informs SM of plant status.
"* Orders WEC to generate AR, CR, and get maintenance involved.
Comments: Braidwood 2002 NRC Exam 9 Scenario 02-X
Scenario No: 02-4 Event No. 3 Event
Description:
I LT-459 - Controlling Pressurizer Level Channel failure low Time Position Applicant's Actions or Behavior BOP Performs actions as directed by US/RO:
- Re-establishes Letdown IAW BwOP CV-17, "ESTABLISHING AND SECURING NORMAL AND RH LETDOWN FLOW" (may be performed by either RO or BOP).
- Assists RO as directed by US/RO with panel monitoring.
e Investigates BwARs. o Holds/controls ramp as requested RO/BOP Re-establishing Letdown per BwiOP CV- 17..
- VErJyC~ *O 1CVSIT49A,tS, and O .... <>*"*,*.*.'*..: :,t;:1*, *.>,;.,.:.:- °...*,
o Assumes CC is still aligned properly to tetdown HX. .
* ,PLAE1C.VI3. inMANUAL and RASE demand to40%, ,.,..'
- PLACE 1CC- 130 in MANUAL and RAISE demand to 60%. :
V1PlwY OPEN 1CV459 and ICV460.
- VERIFY OPEN 1CV8324A/B and 1CV8389A/B ' ...
- VERIFY OPEN 1CV8160 and 1CV8152.
- VERIFY OPEN 1CV381B.
- VERIFY CLOSE 1CV38 1A, .. ,.
- VERIFY OPEN 1CV8401A/B. . .
- VERIFY CLOSE 1CV8145. ..
* .*VERIFY OPEN 1CV8147A/B. . "
- VERFIY OPEN ICV8105 and1CV8106. .
- ADJUST in MANUAL ICv121 to establish A'00 gpm charging flow.,%.
.* ADJUST 1CV182 to obtain 8-10 gpm seal injection flow to each RCP..,
, SIMULTANEOUSLY OPE., CV8149A/C and ADJUST 1CV13 1to control letdown pressure between
. 369 and 380 Sl.IP-1431) .. . . .
- PLACE ICV13 1 in AUTO aid verify properpressure control.
. ADJUST 1CC-130 to control temperature between 90 and 115 degrees F (ITI-130).
- PLACE 1CC-130 in AUTO and verify proper temperature control.
. PLACE 1CV- 121 in AUTO .when conditions allow automatic charging control..:
. VERIFY/PLACE 1PRO06 in service.
NOTE: Once letdown has been restored, initiate EVENT 4. Comments: Braidwood 2002 NRC Exam 10 Scenario 02-X
Ii - - -- 11Scenario No: 02-4 Event No. 4 Event
Description:
Loss of ESF Bus 142. Failure of 1A CCW Pump to Automatically start Time Position I Applicant's Actions or Behavior "CUE Annunciators 1-22-A7 "BUS 142 FD BKR 1422 TRIP" 1-22-C7 "BUS 142 OVERLOAD OR LOW VOLTAGE" 1-2-A7 "SEAL WTR HX CC FLOW LOW" 1-2-E4 "RCP THERM BARR CC WTR FLOW HIGH LOW" 0 Volts and 0 Amps indicated on Bus 142 ...
*' US , Enter a~id Direct actions ofBwOA ELEC-3 "Loss of 4KV ESF Bus"
,.;:BOP ' Determine Affect&1 Bus is ESFI us 142 and transitin to Attachment C.
RO/BOP Verify Required ESF Loads Energized on Bus 141
*Bus 131X 1ACVPump 1A&ICRCFC
- 1Aor0CCPump 1ASXPump .
*OA VC Train BOP Verify Bus 142 IS Faulted .. . .
*,.?,
,¢.......
** Place breaker control
;:~~~~~~~~..,*..: ............
switches in Pull Out . .. "...... . . ACB 1423'" ACB 1421 ý -". .. -.. .. S. . .. ACB'4Z2Ž C B 1424 " ' - " "" :!' :>. " ". ... " : ; . . . . . .. C.. -. .. ' .- .:. ... ACB, 1424- .. Check' Bus 141 ldcko'utaalns LIT
. Determine NO fire has occurred BOP Identify DC Crosstie Required
- Check battery charger 112 energized
- Crosstie DC Bus 112 to 212 CREW Investigate/identify failure of CC to auto start on low discharge pressure Monitor CC parameters for proper operation and restoration of CC flow
"* RCPs
"* CC flow, temperature and pressures
"* Letdown temperature Comments:
Braidwood 2002 NRC Exam I1I Scenario 02-X
Scenario No: 02-4 Event No. 4 Event
Description:
Loss of ESF Bus 142. Failure of IA CCW Pump to Automatically start Time Position Applicant's Actions or Behavior US Refer to Tech Specs
/ Perform the following Tech Spec surveillances within 1 hour 1BwOSR 3.8.1.1 2BwOSR 3.8.1.1
- 3.8.1 3.18.4.' . .
* *1 * ~~~3.8.9 ~ .~w. *.
S ." 3.8.10 . . " : '" ".. . . .. " NOTE: 38.4 . .
........... ............ .. ....... ... " .. i 5 ,e I : *, [ N...OTE: After Tech Specs have been referenced, initiate Event 5: . :, :.:,,,.,;,- *<-. ,-.,..:. ,., .
-r - '
- 2 ;1 : 2
- I Comments:
Braidwood 2002 NRC Exam 12 Scenario 02-X
Scenario No: 02-4 Event No. 5 Event
Description:
Uncontrolled outward Rod Motion lllI 1o t* onl~ Applicant's Actions or Behavior I i
. T.. ..O Annunciators:
1-14-El TAVE CONTDEV LOW Treference indicates 586°F PT-505 and PT-506 indicate NORMAL for current conditions Control Rods withdrawing in AUTO Turbine Load stable ,* t .,I
*!., RO/US, :, Identify a failed instrument chanrnel and no Qhange is turbine loading is causing automatic rod withdiawl.-,
Place Rod control in Manual to stop rod withdrawl .. ... ...
" "" ... " Identify failure of Rod Control to stop Withdrawl of rod when placed in MANUAL NOTE: The CREW may perform all of the following actions including tripping the reactor without entering lBwOA ROD-1 US Implement and direct actions of 1BwOA ROD-1 "UNCONTROLLED ROD MOTION"
*. *Turbine Tcu*rbian power y poawtstatus stable
'.5
!1 Check Rod Control Status .. ... , ., . ,:,,.
"* Rod control in Manual - rods continue to move . .
"* Cycle the Rod Control IN-OUT Switch in both directions -rods continue to move
"* Place Bank Select switch to Shutdown Bank D - rods continue to move Manually Trip Unit-I reactor US Implement and direct the actions of 1BwEP-0 "REACTOR TRIP OR SAFETY INJECTION" RO Perform Immediate actions of IBwEP-0:
Verify reactor trip
"* Rod bottom lights lit
"* Reactor trip and bypass breakers open
"* Neutron flux decreasing Comments:
Braidwood 2002 NRC Exam 13 Scenario 02-X
Scenario No: 02-4 Event No. 5 Event
Description:
Uncontrolled outward Rod Motion Time Position Applicant's Actions or Behavior IDnD I T) relj X_ julr Il
~ ediitauitieactions ofI sw.r-P u0:
Verify Turbine trip
"* All throttle valves closed
"* All governor valves closed Verify 4KV ESF Busses energized . . .
* +. Bus 141 bus alive light lit o *Bus142 .bus . .previously
.. . . . de-energized
- . . " .. + -* i ' .. . ,.. . .:
+ . * . . . .
A . . . .. : ". .. , . . . . . 7. 7 . i: .. 5 ..A. . . . .... . .5' : .. . ": . 4.
' + A
- 4. , , - .1
- .A. .;. A '.
/ .,
Comments: Braidwood 2002 NRC Exam 14 Scenario 02-X
Scenario No: 02-4 Event No. 6 Event
Description:
Manual Rx Trip & Pzr Vapor Space Leak/LOCA Time Position Applicant's Actions or Behavior CUE: RCS Temperature and Pressure decreasing Pzr Level Increasing Containment pressure increasing Containment Rad Monitors alarming US/RO Determine SI needed/actuated: .. *
- SI First Out Annunciator Lit (1-11 -B/C/D f) - -
- SI ACTUATED lit (1-BP-4. 1) - - .:..r - ,. .
- SI Equipment actuated (1A SI pump runningi1SI8801A 6p)n) .. .:v& :....
. - . .. M anually
. a.. . I .
Actuate ,. ... .tu .. .. BOP Recognize ADVERSE Containment Conditionswhein: . .
" Cnmt Pressure> 5 psig "o Cnint Rad level> -E5 R"llr (Grid 4- 4AS120 or 4AS121)
RO/US Trip RCPs per Operator Action Summary: , .. . , o CC water lost to RCP . .. o Cnmt Phase B Actuated o All of the following exist: . . ,., ,,. , A.* Controlled RCS Cooldown NOT in progress......... . . RCS Pressure < 1425 psig
- HHSI flow > 50 gpm OR SI pump discharge flow > 100 gpm.
BOP/US Verify FW Isolated: .. ,-.. o FW pumps tripped o Isolation Monitor lights lit ... " ..
- FW discharge valves (1FW002A/B/C) Closed .
RO/US Verify ECCS pumps running: 0 1A CV pump [CTJ 0 Manually start 1A SI pump E-0--D 0 Manually start 1A RH pump Comments: Braidwood 2002 NRC Exam 15 Scenario 02-X
Scenario No: 02-4 Event No. 6 Event
Description:
Manual Rx Trip & Pzr Vapor Space Leak/LOCA Time Position Applicant's Actions or Behavior BOP/US Verify Containment Conditions - for Train A (Div 11):
- RCFC Accident Mode Lights LIT (Group 2)
- Phase A Lights LIT (Group 3)
- Containment Ventilation Lights LIT (Group 6)
BOP/US Verify the following:
- AF Aligned:':
.,: .. *,*", " M.. a u lystr.., ~m A AF. U.... tp2 i::: - .-, ,5 *2';: ,. :1/4:t
.,: ,.'1/2 i~'i. i:;i*:':*i!i:~, :
IB AFW ptturiiý'ij g............ g .i
* . .. 1AF013A-H Open .. ,. . . .. . . : . . .... . '. .
'AFOO5A-I4 Throttled .. I" 4 ~c
[CTJ
- Manually start IA and/or "0" CCW pulmp E-0--D
- Manually start IA SX pump o MSIVs and B/P Isolated when Cnmt Pressure >8.2 psig or Steam Lin'e Pressute < 640 psig Check If Containment Spray required:
- If Cnmt pressure > 20 psig then
- Stop All RCPs
" Verify Group 6 lights lit
- Verify Phase B lights lit Verify AFW flow:. ,.
* >500gpm
- Control SG levels 31-50% ...... . ... ..
... Determine no SG level increasing in an uncontrolled manner-..
Comments: Braidwood 2002 NRC Exam 16 Scenario 02-X
11Scenario No: 02-4 Event No. 6 11Event
Description:
Manual Rx Trip & Pzr Vapor Space Leak/LOCA Applicant's Actions or Behavior Verify the following: Verify ECCS operations:
"* Group 2 Cold Leg Injection lights lit (train A)
"* High Head SI flow > 100 gpm
"* RCS pressure < 1700 psig
"* Sl pump flow > 200 gpi 4 . .
"* RCS pressure < 325 psig .
SRH pumpflow> 1000gp i.' .. PZR Porv Relief path available:....
-.At least one bl'ock valve energized .. t
- PorvinAuto
- Associated Block valve open ,
-1 -
BOP Verify the following: Main Generator Trip:
"* Output Breakers Open
"* PMG Breaker Open EDGs running I1SX169AOpen
- Dispatch operator for local check of 1A EDG operation "
Ventilation aligned:
"* Control room
"* Aux bldg
"* Fuel Handling bldg Comments:
Braidwood 2002 NRC Exam 17 Scenario 02-X
Scenario No: 02-4 Event No. 6 Event
Description:
Manual Rx Trip & Pzr Vapor Space Leak/LOCA Time Position Applicant's Actions or Behavior RO Check the following: PZR PORVs and Sprays Closed Cold leg temperatures NOT stable at or trending to 557: o Stop dumping steam
, Control'AFW'flow to maintain > 500 gpm until at least 1 SG">31% NRý. N ..
..RCPs tripped . * . ... .. ,,
Secondary Pressure Boundaries are Intact:' .. , . ... . . 4P No SG pressure decreasing u-nfcontrollably . : .... . ..- !
- No SG completely depressurized BOP/US Check SG Tubes Intact: .
- NO rads on RM-11 for:
"* SJAE / GS Exhauster 1PR27J
"* SG Blowdown 1PR08J .
"* Main Steam Lines 1AR022, and 23 (all MSIV rooms)
CREW Determine RCS is NOT Intact:. . . . .. o CNMT ARMs in alert or alarm 1AR014, 011, 012,021, 022 . . , . o Cnmt Pressure > 3.4 psig ..... .. .
"o Cnmt Floor water level > 5 inches. . '
US Transitions to 1BwEP-1, "LOSS OF REACTOR OR SECONDARY COOLANT". 0 Gets acknowledgement from RO and BOP
- Informs SM of plant status and to evaluate for the Emergency Plan RO Check RCPs all Tripped.
Comments: Braidwood 2002 NRC Exam 18 Scenario 02-X
Scenario No: 02-4 Event No. 6 Event
Description:
Manual Rx Trip & Pzr Vapor Space Leak/LOCA Time Position Applicant's Actions or Behavior BO, Determine NO S(is are Faulted:
- .,.. J "* No SG Pressure decreasing uncontrollably
"* No SG completely depressurized Control Intact SG levels to 10% (31% Adverse) to 50% NR level Check Secondary Radiation levels normal' No evidence of SGTR....
RO . Check PZR PORVs'and Islto1avs:1; 2 ' .. PORV Isolation valves open and enerlized ...... ,..
- PORVs Closed ... ;, : :
CREW Check if ECCS flow should be reduced:
. RCS Subcooling NOT Acceptable Determine ECCS flow should NOT be reduced.
CREW Check ifCS should be stopped .
- Reset CS signal e If spray additive tank lo-2 lights are lit then close eductor valve 1CS019A
- Determine CS must run for 2 hours due to the LOCA in progress e Do not stop CS if operating . . . .... .
US/BOP Check if RH Pumps should be stopped.: .....:.- :.. .;, -.--.....
"* RESETSI -. '.'-,', '.: ,'
"* Check RH suction align to RWST W!
"* Check RCS Pressure > 325 psig. .... .
S°Stop 1A RH pump place in Standby ifpress stable&or increasing- ,.., Check if DGs should be stopped: . . ..... ,,
"* Determine 4KV ESF bus ENERGIZED (Bus 141) ONLY by EDG IA
"* Determine 4KV Non ESF Busses Energized (bus 143 and 144)
"* DO NOT stop lA EDG Comments:
Braidwood 2002 NRC Exam 19 Scenario 02-X
Scenario No: 02-4 Event No. 6 Event
Description:
Manual Rx Trip & Pzr Vapor Space Leak/LOCA Time Position Applicant's Actions or Behavior CREW Initiate evaluation of plant status 0 Determine Cold Leg Recirc Capability exists Power Available to IA RH pump and 1S1881 IA 0 Aux Bldg rads are normal for plant conditions 1/2PR28J and 1/2PR30J, ECCS Cubicle PRMs.. 0 Reset Containment Isolation Phase A 0 Place Hydrogen Monitors in service per BwOP PS-9, "POST LOCA H2 MONITORS" Lr. 0 Obtain samples: RCS Activity, RCS Boron, Cnmt Atm, Cnmt Sump . ii.,.': 0 Contact SM for evaluation to place H2 recombiners in operation. ". 0 0 Shutdown lB and 1C MFP, (BwOP FW-2), CD/CB pumps (BwOP CD/CB-2) ..: . 0 Shutdown VC Chiller on Non operating Train. Control switch to trip. c . .. .
, ,.!..el.
US Check next procedure transition: RCS pressure < 325 psig RH pump flow > 1000 gpm Transition to 1BwEP ES-1.2 "POST LOCA COOLDOWN AND DEPRESSURIZATION"
. Gets acknowledgement from RO and BOP
- Informs SM of plant status and to evaluate for GSEP . .. . .
Scenario is completed at this point at the lead exaiminers discretion
- j Comments:
Braidwood 2002 NRC Exam 20 Scenario 02-X
SHIFT MANAGER TURNOVER Weekday, Today, 2001 ONCOMING SHIFT 2
,UNIT I STATUS FUNI T0 & I MAJOR OOS's MO DE ............ 1 I B Emergency Diesel Rx Pw r ............ 24% Generator Generator MWe ..... 235 Max Load/Power .... 100% 1C Heater Drain Pump Min Load/Power .... NA Max Ramp Rate ..... 5 MW/Min Desired Delta I ..... Target On-Line Risk ....... Green Boron @ .......... 1411 Control Bank ....... D@ 145 LCOAR ENTRIES PREVIOUS 48 HRS UNIT 0 & I MAJOR SURVEILLANCES 3.8.1 Condition B for 1B EDG BwOSR 3.8.1.1 -due in 6 hours 18 hours ago. Est RTS by end of shift UNIT 0 & I IN PROGRESS UNIT 0 & PENDING .. .
IB EDG turbo charger replacement Unit 1 load increase to 620 Mwe per electric operations. Current procedure and step in effect IC HDP bearing replacement is 1BwGP 100-3, step 42. 1B CCW Pump run for ASME Testing Focus Areas: N Verification Practices N Command and Control Standard for Execution of Critical Steps THINK CONFIGURATION CONTROL and SAFETY!!! SCHEDULED ACTIVITY CONFLICT IC21 .doc
SHIFT MANAGER TURNOVER INIT 2 STATUS UNIT 2 MAJOR OOS's MODE ............ 1 Unit 2 SAC- Oil change Rx Pw r ............ 97.6 Generator MWe ..... 1197 Max Load/Power .... 97.6 impulse pressure Min Load/Power .... 700 Max Ramp Rate ..... 5 mw/min Desired Delta I ..... Target On-Line Risk ....... Green Boron @ .......... 1037 Control Bank...... D@ 210 LCOAR ENTRIES PREVIOUS 48 HRIS JUNIT 21 MAJOR SURVEILLANCES. "icoar num" "AffectedEquipment" UNIT 2 IN*PROPGRESS UNIT 2 PENDING Oil change on Unit 2 Station Air Compressor. RTS by end of shift today. Dose INFO: Dose goal for day 10 rnr SCHEDULED ACTIVITY CONFLICT IC21 .doc
SHIFT MANAGER TURNOVER ________________________ _ .: Administrative Temporary Procedures / Modifications T-mod Ul Tm B RVLIS. Jumper Installed on 4C U-1 MPT Disconnect. 1 FW009A T-Mod for Hyd Pp Press Sw 1PS-FW1 62. T-mod for drain on 1 B AF casing. Tmod for no disc in 2CC9502B installed. Daily Orders / Special Op Orders Daily Manning Schedule See sheet for restricted duty personnel and o\ ertime restrictions Oncoming STA Fire Chief Control Room Rounds (GSEP / LER / DVR / ENS) Material TS Conditioning SFP High Level alarm did not alarm during calibration RWP's / Releases / Precautions / ALARA Infrequent Evolution Activities Lesson learned files L:\shared\opex then.ctrl F to search SPSO / Division LD Alternate BPO Outside # 815-727-5902/5903 Tie # 8-565-5902/5903 Unit I Comments . , Un~it Common Comments Battery 112 cell 32 has floating material in electrolyte, eval'd OK U1 FC Cleanup SFP D.O. OS prevents filling U- tanks normally, but BwOP DO-6 U2 FC Cleanup OFFLINE (leak) can be used to fill tanks. T-MOD is installed allowing U-I boiler FC Cooling U1 ops. 50K DO Tank empty IAF006A is leaking by from CST. 125K DO Tank and FRAC Tks Certified Aux Steam U-1 ES ->U1 HDT U-0 CC Hx Ul U-0 CC Pump Bus 141 UL1Aux boiler Wet lay-up U2 Aux boiler Wet lay-up SAC / Dryer UL/U0 MUDs U-1 CST CW Makeup Running 0A/GB CW Blowdown On Lake Level 5.8' 2AF-17A *"<Unit 2 C,,omments General Comments 2AF017A leaking by .3 gpm, AR 990116738 Conference Call Phone Number- 1-800-232-1234 Teleconference S/G sampling lines/valves at HRSS are not correct. Do not folder ID #=472664085 hang 0OS on any 2PS181 valves till further notice. Meeting Place 630-663-7120 +code 2PS229A still blows fuse 2PA32J Ckt 9 Duty Team is located @ SITE APPS, NRC Duty list in book CV seal leakage: Substation construction (John Strle) Cell phone 815-351-8472 2A Running 200cc/min shutdown about 6 drops/min 2B Running -12 dpm; S/D- none Caution Cards Abnormal Positioned Components CCNUM EPN CCNUM EPN AbnormalPosition SM BEEPER TURNOVER Shift 1 To 2 Time Now Date Today Offgoing Oncoming IC21 .doc
S! I ! FI !AAN,,\k E R TU R N O(VE R
.)II*1,.V I()RS (ONCI.RN I.IST Equipment Unit 0 BwAP 330-10 Compensatory Actions Operability
_ _ _Determination Equipment Unit 1 BwAP 330-10 Compensatory Actions Operability Determination PZR PORV Verify PZR PORV's Open at Setpoint or Open PZR PORV Spurious SI 97-159 Concern Equipment Unit 2 BwAP 330-10 Compensatory Actions Operability,
~ - ~'-'*
- eterminiation I PZk POPV Verify PZR PORV's Open at Selpoint or Open PZR PORV Spurious SI 97-159 Concern 2B C .V.u.p .. Monitor seeakage shiftly Notify System Engineering if > 0.5 gpm - 98-049 UNIT 0 CONTROL ROOM ANNUNCIATORS LIT Annuciator Annunciator Description Problem AR#/WR# Status UNIT 1 CONTROL ROOM ANNUNCIATORS LIT Annunciator Annunciator Description Problem AR#/WR# Status UNIT 2 CONTROL ROOM ANNUNCIATORS LIT I# ,
T'%l I !I-{ OIAJ11- tJ*O l IJ I VI F-. I~JI~iitJ) jIr~f~vv~7* - '~:,LdtUS ~ a; Concerns and/or Pending OP-AA-101-301 Evaluations EPN Unit 1Resolution EPN ]Unit 1 Resolution EPN Unit 2 --- t ~ 4Resolution - z'- I ________________________________________________________________ Kt- 1 1,)(,
BwAP 335-1T6 Revision 8 Information Use UNIT 1 NSO TURNOVER Weekday, Today, Oncoming Shift 2
... . Unit I Status Mode .. 1 Max load/power 100%
Pow.er A.. 24% Max rarip rate 5 mw/min. Mw electric., 235 MWe Unit Risk Green
":,Min load/power! NA Control Rods CBD @ 145 Desired Delta-I Target _T Boroh concentration 1411 PPM IN PROGRESS . K*PENDING 1B EDG turbo charger replacement. RTS by end of shift today BwOSR 3.8.1.1 1C Heater Drain Pump bearing replacement Unit 1 load increase per electric operations to 620 Mwe.
Current procedure is 1BwGP 100-3, step 42 - transfer FW 1B Component Cooling Water Pump run for ASME Testing control to the MFRV's. Unit 2 SAC OOS for oil change
.~. ~iK/J.LONG TERM./
iADMINISTRATIVE Temporary procedures Temporary alterations New caution cards Unit logbook Unit routine BDPS Icoar in mode 3. Aux. Electric room access Daily orders Control board walk down LCO/TLCO RETS DEQUIP/AAR 3.8.1 1B EDG I( Ido,
BwAP 335-1T6 Revision 8 Information Use _____________________ TURNOVER ITEMS NSO SHIFTLY/DAILY SURVEILLANCE
- 2) SSPS CHANNELS/BISTABLES B train SSPS logic g-round to chassis ground had higher than expected readings during SSPS. AR written.
- 3) SYS - SAFEGUARDS
- 4) SYS - PRIMARY CC to spent fuel pool hx is at 2800 gpm.
- 5) SYS - BALANCE OF PLANT Spent fuel pool cooling now on Unit 1.
.6) ALARMS-SER/ANNUNCIATOR
- 7) ALARMS - PROCESS/RM-1 1
- 8) ALARMS - FP/OTHERS
- 9) CHEMISTRY Max flow through condensate polishers at full power is -2000 gpm without causing a low npsh alarm. This is only a guideline and not an absolute value.
- 10) RADIATION PRECAUTIONS
- 11) NUCLEAR INSTRUMENTATION
- 12) MCB INSTRUMENTATION
- 13) MCB CONTROLLERS
- 14) ELECTRICAL DISTRIBUTION - AC MPT transformer disconnects has bad seat on one phase. Jumper installed, SOC on disconnect - do not operate.
- 15) ELECTRICAL DISTRIBUTION - DC
- 16) EGC STATUS
- 17) BWOP_ (PROCEDURE AND STEP IN
-FECT) 13 ~COMMENTS 13 gals of PW will Raise RCS .1 F POST REVIEW : US FS SM TIME: NOW , SHIFT OFF GOING DATE: TODAY SHIFT ONCOMING 2_ _ _ _ _
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