ML20195B390
| ML20195B390 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/18/1988 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20195B388 | List: |
| References | |
| PROC-881018, NUDOCS 8811010550 | |
| Download: ML20195B390 (277) | |
Text
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'".V "* SIMULATION FACILITY CERTIFICATION im"e s. .
.wIRUCTiONS. Tees form .: to tw feled for in tial certificat.on. recertif ation ( f reou. rect sad for any cPenge to va s.m iste facihty perforecance te.t,ag osan m40s a tf e' in. tad' twbmittai of sucM 4 Dian. P'ov.oe the folloerug enformation. and check the sopropriate boa to indicate reenon for tutwnertAl.
8 aclu r v loocairNyusia A.W. Vogtle Unit 1 Nuclear Power Plant I g 424 UCt % sit joart Georgia Power Company i
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10/31/88
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See Attachment 2: Performance Tests Completed
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. ATUR( . AUTH0mi t e m t S E N T A TIN E lT'f48 GENERAL MANAGER I0'f4 j
in acc oroave ..tm to C8 a i SS S Cc.am a<4t kW w PLANT V0GTLE oat. ta's form s'en te swDmitted to tae N M C et 'ooo s M /'8//M 4y Wall A00at5580 TO 0.,,cior. 0f t.e4 of Nwene., aeacio, R.,wist.oa ev of Livt av lN pg n$oN U S. Nwetesa Repelatory Comm won to f Mt NRC 088tct AT 71M Peorio en A. eave inna.aston. DC MSSS Betheos 40
Attachment 1 EXCPTICt!S 10/31/88 Plant A.W. Vogtle, Unit 1 Docket t 50-424 Georgia Pow r Ca pany
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FORM: 00-01 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 10 FORM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O PERFORMED BY: M. Pellechi DATE: 9/21/88 REVIEWED BYt Gibson
,M_. DATE: 9/21/88 APPROVED BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 ANSI SPECIFICATION:3.1.1(7) TITLE:Startup. Shutdown & Pwr Oper W/
Less Than Full Reascor Coolant Flow EXCEPTION:
GPC takes exception to this requirement. There is no Performance Test which will be performed as part of the Plant Vogtle simulator certification process 1
JUSTIFICATION:
Plant Vogtle is prevented from performing a plant startup or operate at power without full reactor flow by the plant's Technical Specifications l
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i FORM: 00-01 PLANT A.W. V0GTLE SIMULAIOR CERIIFICATION PLAN PAGE 2 0F 10 FORM TITLE: ANSI /ANS 3.S EXCEPTIONS WORKSHEET REVISION NO O PERFORMED BY: M. Pellechi DATE: 9/21/88 REVIEWED BY M. Gibson DATE: 9/21/88 APPROVED BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 ANSI SPECIFICATION 3.1.1(9) TITLE Core Performance Testing Using Permanently Installed Instrumentation EXCEPTION:
GPC takes exception to this requirement only so far as permanently installed instrumentation will not be used. Core performance tests will be conducted as part of the Plant Vogtle simulator certification process using alternate means for sonitoring core reactivity. -
JUSTIFICATION:
Plant Vogtle, by design, has no permanently installed instrumentation for core reactivity tests.
FORM: 00-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 10 FORM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O FERFORMED BY: M. Pe11echi DATE: 9/21/88 REVIEWED BY: M. Gibson DATE: 9/21/88 APPROVED BY R. Dorsan OPERATICMS SUPERINTENDENT (TRAINING) DATE: 10/17/88 ANSI SPECIFICATION 3.1.2(12) TITLE: Control Rod Failures Including Stuck Rods. Uncoupled Rods. Drifting Roda. and Misaligned Rods EXCEPTION:
GPC takes exception to this requirement only so far as uncoupled rods or drifting rods are not appropriate salfunctions on Plant Vogtle JUSTIFICATION:
Malfunctions of this n.2ture are not applicable to the Westinghouse designed control rod drives. The following malfunctions are presently available:
- 1. RCCA Withdrawal Interlock C1, C2 C3 & C4 Fail to Block Rod Movement in Manual or Autoestic
- 2. Automatic RCCA Speed Signal Fails to Maximum
- 3. Uncontrolled Withdrawal of RCCA Bank
- 4. Uncontrolled Insertion of RCCA Bank
- 5. Uncontrolled Withdrawal of RCCA
- 6. Uncontrolled Ipeertion of RCCA
- 7. Control Banks / ail to Move on Auto Desand
- 8. Control Banks Fail to Nove on Auto or Manual Desand
- 9. Control Rod Urgent Failure
- 10. Stuck RCCA
- 11. RCCA Fails to Move
- 12. Dropped RCCA
,13 . RCCA Primary Position Indication Fails Low 14 RCCA Primary Position Indication Fails As Is
- 15. RCCA H-8 Ejected 9
FORM: 00-01 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 4 0F 10 FORM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVTSION NO O PERFORMED BY: M. Pe11echi DATE: 9/21/88 REVIEWED BY: M. Gibson DATE: 9/21/88 APPROVED BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 ANSI SPECIFICATION:3.1.2(25) TITLE: Reactor Pressure Control System Failure Including Turbine Bypass Valve (BWR)
EXCEPTION:
GPC takes exception to this requirement. There is no Performance Test which will be performed as part of the Plant Vogtle simulator certification process JU5TIFICATION:
Plant Vogtle is a Westinghouse Pressurized Water Reactor (PWR). This requirement is not applicable to the Vogtle sisuistor
B FORM: 00-01 PLANT A.W. V0 GILE SIMULAIOR CERTIFICATION PLAN PAGE $ OF 10 FORM TITLE! ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O PERFORMED BY: M. Pe11echi DATE: 9/21/88 REVIEWED BY: M. Gibson DATE: 9/21/88 APPROVED BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 ANSI SPECIFICATION:4.1(3)(f) TITLE Recirculation Flow EXCEPTION:
GPC takes exception to this requirement. This critical parameter will not be recorded as part of the Plant Vogtle simulator certification process JUSTIFICATION:
Plant Vogtle is a Westinghouse Pressurized Water Reactor (PWR). This requirement is not applicable to the Vogtle simulator
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FURM: 00-01 PLANT A.W. V0GTLE SIMUIATOR CERTIFICATION PLAN PAGE 6 0F 10 FORM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O PERFORMED BY: M. Pellechi DATE: 9/21/88 REVIEWED BY: M. Gibson DATE: 9/21/88 APPROVED BY R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/68 ANSI SPECIFICATION 4.3(5) TITLE:bWR Suppression Pool Temp EXCEPTION:
GPC takes enception to this requirement. This operating limit will not be monitored as part of alerting the instructor when certain parameters reach model or plant design limits on the Plant Vogtle simulator.
JUSTIFICATION:
Plant Vogtle is a Westinghouse Pressurized Water Reactor (PWR). This requirement is not applicable to the Vogtle simulator.
The current parameters which are monitored for compliance with Section 4.3 of the ANS 3.5 standard are:
Containment Pressure RCS Pressure RCS Vaid Fraction Average Fuel Temperature Average Clad Teeperature A "computer fault" light will illuminate at the instructor's console when any of the above parameters exceed their predetermined limit.
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4 FORMr 00-01 PLANT A.W. VOGILE SIMULATOR CERTIFICATION PLAN PAGE 7 0F 10 FORM TITLE: ANST/ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O :
PERFORMED BY: M. Pe11echi DATE: 9/21/88 REVIEWED BY: M. Gibson DATE: 9/21/88 APPROVED BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 ANSI SPECIFICATION:5.3 TITLE: Simulator Modification EXCEPTION:
This requirement specifies that the simulator shall be modified as required within 12 months following the annual establishment of the simulator update design data referenced in Section 5.2 of the ANS 3.5 standard. GPC takes exception to this requirement only so far as the following discrepancy report (DR) has not been resolved within the time period permitted by the ANS standard:
DR #8507001 SG 1evels sensitive to AFW flow d
JUSTIFICATION:
Numerous attempts have been made to resolve DR #8507001. These efforts have !
, not been successful. GPC has contracted to replace the simulator models ,
(core. reactor coolant systes, steam generator, and containment) with newer '
a
' "state of the art" models. Model replacement will result in elimination of this DR by 1/30/90.
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FORM 00-01 PLANT A.W. V0 GILE SIMULATOR CERTIFICATION PLAN PAGE 8 0F 10 FORM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O PERFORMED BY: M. Pe11echi DATE: 9/21/88 REVIEWED BY: M. Gibson DATE: 9/21/88 APPROVED BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 ANSI SPECIFICATION:B2.1 TITLE: Steady State Performance EXCEPTION:
GPC will substitute a steady state test at 30% power for the ANSI required 25% steady state test. Steady state tests at 75% and 100% will be performed as required by the standard.
JUSTIFICATION:
Plant data exists for 30% steady state power.
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FORM: 00-01 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 9 0F 10 FORM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O PERFORMED BY: M. Pe11echi DATE: 9/21/88 REVIEWED BY: M. Gibson DATE: 9/21/88 APPROVED BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 l
l ANSI SPECIFICATION:B2.2 TITLE: Transient Performance EXCEPTION:
' The Standard requires all transient tests listed in Section 82.2 of Appendix B be performed from an initial condition of 100%
power, steady state xenon and decay heat. GPC takes exception to the requirement to run all tests at 100% power.
GPC intends on nanning the following transients at the power level indicated. All remaining transients will be ran at 100% power.
B2.2(5) - Trip of any single reactor coolant pump - 13%
B2.2(6) - Main turbine trip without a reactor trip - 30%
B2.2(9) - Maximum size unisolable main steam line rupture - 10E-8%.
! l JUSTIFICATION:
The intent of the Standard is still met insofar as the transients will be tested annually but at a power level that will provide more meaningful data to GPC. Specifically, each power level was selected because:
82.2(5) - Highest available initial condition (power level) that GPC could be certain the reactor would not trip (due to something other than a low RCS flow). It was felt that not having the reactor trip was preferred since response of the plant to a complete loss of RCS flow would be conducted at 100% power and result in a reactor trip.
B2.2(6) - Highest available initial condition (power level) that would not result in a reactor trip as required by the Standard B2.2(9) - Response is more severe at this power level and was close to the power level used in the FSAR analysis of this transient (the FSAR started with a suberitical core).
FORM: 00-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 10 0F 10 FORM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O PERFORMED BY: M. Pe11echi DATE: 9/21/88 REVIEWED BY: M.. Gibson DATE: 9/21/88 APPROVED BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 ANSI SPECIFICATION B2.2.1/2/3/4 TITLE. Transient Performance EXCEPTIOc; '
This section of Appendix B requires that all Appendix B listed tranais st tests be recorded with a resolution of .5 second or less. UPC takes exception to this requirement of recording at .5 second intervals. GPC has a record program on the simulator ,
cooputer which records critical parameter data at i second - '
intervals for transients and at 30 second inte rvals for normal operation tests.
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JUSTIFICATION:
Current data recording capabilities meet the requirement of Section 4.4. Monitorins capability, of the Standard. With a i i
resolution of 1 second intervals. it is GPC's view that no anomalies would be missed at this rate which could cause nesative ,
trainina. This is balanced against the amount of data that is i stored and plotted. '
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,1 5:MULATOR DR'S 70;tle simulatcr DR's are prioriti:ed under the f:ll: wing levels-
- 1) Emergency
- 2) Ncn-emergency
- 2) Testing / Upgrades -
/Or invels 1 & 1 the sub 'evels are i
A) Non-obvious /Non-recoverable B) Obvious /Nen-recoverable C) Non-obvicus/ recoverable !
l D) Cbvious/ recoverable E) Modeling error requiring major
, medel revision or replacement. '
Tor level 2 A) outstanding tesign change Package El Non-fidelity testing discrepancy C) Hardware D) Physical Tidelity ,
The rating system is a modified version of the EPRI methcdology. .
We currently have a c:ntract with Westingh:use Electri:
Corporation to replace the Ore. ROS, Steam Generator,and 0:ntainment models. We also have a centra:t with them to adt.
- imulation of the PSMS system. Please n
- te that the OE L E ' s W 11 *.
be fixed by these contracts with the exception of the SRDC panels (IE ?.ad Moniter panels) and upgrade of the "Pr teus" ::mputer
- ystem. These items will be handled separately.
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Page No. . 1 09'29/6s SIHULATOR SCFTWAP.E MAINTENANCE DR'S H:dification Problem Description Priority Anticipated Number Completion 1702001 MSR Stm Supply Press increases 2C too fast.
06/15/39 17:iO31 Sim. Stm Flew & Feed Flow 2B 06/15/69 Transmitters need noise component.
3706021 With a LCFW/ATWS, Trip occurs 2A on high MSR Drn Tnk Lvl. 06/15/89 5706C34 With the EPRI THI & HSLB 2E scenarios RHR pressure is too 06/15/69 high.
1711:01 FW flow & discharge pressure 2A are higher than the plant when 12/31/58 other pump is run-back.
3712027 Some controllers do not control as well as the plant.
2D 06/15/89 5202022 Rad H:nitor typer is not 3C driven.
09/15/89 5502024 MTP Coast-down is too fast per 3B requal student.
06/15/$9 31C4004 Check Valves are no: simulated 2A 12/31/38 in the AFW lines.
3324042 With a loss of 1 NAB 02 the 2A 06/15/89 turbine tripped on high MS Drn tank levels.
8504047 Motwell response was not as expected with a loss of 3B 09/15/89 hotwell level control, a305013 SSMP does not have a reflash 25 feature.
03/15/89 3305014 3GTPT Controller is too 2C 06/15/89 responsive per plant operator.
3305028 CCP's are sized too small. 2D 03/15/89 3605029 Condensate storage tank 2B 09/15/89 decreases during start-up.
!i06012 controller Up/Down lights 2D 12/31/a8 reversed.
1137023 AFW flow is inconsistent with 2B 03/15/89 SG pressure.
4307C61 Need remote functions for 3D 06/15/89 FV-455,456,HVs00A,30008 SiO6334 HV-3508, 3514, AND 2500 2D 12/31/$a re-opened on reset of CIA c after 5I5.
ii29001 Did not receive "Rod 2cntr 1 2D 12/31/a3
'.'r g e n t Failure" when reds e c '.' e r e n : was demand +1 w::'.'.
rode disecanected, s i i c '.1 The McF lighting :: : .; r. *. : 1 ;
- d 2 E :L15/)0 by two relays & d : n.*. + r swat:hes. $1m has :n+ r+;sy 5 no d;rner switcheJ.
Page No. . 1 09/29/a8 SIMULATOR HAROWARE MAINTENANCE DR'S liedificat10n Problem Lescript10n Priority Anticipated
- tumber Completion 31050;; N
- s drawer lights labeled wrcng.
3C 06/15/69 4501015 HCB phene cords are too short. 3C 12/31/83 i6030:2 H5-15215B doesn't maintain 3C 06/15/89 position properly d609006 15 annunciator windows have 3C 06/15/89 engraving errors 65C9007 46 Status lights have minor engraving errors.
3C 06/15/69 3609003 04 Handswitch engravings are 30 06/15/89 incorrect.
3509009 TR-917 has a linear scale.
' 3C 06/15/89 should be non-linear. LR-1310 has a temporary scale. TR-6193
& TR-10463 are missing the -
second scale.
5509010 Sir.ulator has minor labelling 3C 06/15/89 problems on NI's, waste water counter & A/M stations.
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.. Page No. . I t 09/29/63 SIMULATOR ./.0 JECT DR'S Modification Problem Description Priority Anticipated Number Completion rs 4507001 SG Levels sensitive to ATW. 2E 01/31/90 6703002 CNHT RAD too high with Pt,? 2E 01/31/90 rup4ure.
5707001 RCP Bus' amps did not ccme back 2E 01/31/90 doirn with core voids.
3706002 With SGTR, the Reactor takes 2E 01/31/90 tea long to trip ccmpared tc RETRAN.
3706003 T-ave drops too low on trip 2E 01/31/90 ccmpared to RETRAN.
8706004 P:r Level Recovers too fast 2E
'31/96 ccmpared to RETRAM.
3706005 P:r Press and HL Lcop-1 WR 2E 04/2: .)
Press. go too low en trip ccmpared to RETRAN. -
3706006 SG NR & WR levels swell after 2E 01/31/90 trip with a SGTR.
, , 6706007 SL-1 & SL-4 Pressures were too 2E 01/31/30 l far apart during a 3GTR.
t 4706010 SI Flow is inconsistent during 2E 01/31/90 a SGTR. Tha RCS seems to be the cause.
$706011 The simulator shows core 2E 01/31/90 voiding during a SGTR. RETRAN doesn't, a706015 SG Lwell was less than 2E 01/31/90 expected with a 501 increase in steam flow per a Westinghouse service Rep.
S706016 NI's,T-ave,& SG NR oscillated 2E 01/31/90 on LOTW/ATWS. RETRAN didn't.
8706019 With LorW/ATWS WR SG Lvl held 2E 01/31/90 l constant.
3706022 With a locked rotor the SG NR 2E 01/31/90 Lvl is too high.
! 5706023 Intermediate Range SUR hai 2E 01/31/90 l step changes with the EPRI THI Scenario.
!?06024 With the EPRI TH! Scenario 2E 01/31/90 T-ave dropped too low per RETRAN.
i 3706025 With the EPRI THI scenar;o the 2E 01/1 /90 l SG Lvle swelled at rip.
67C6316 Stn Line Pressures were 2E 01/31/90 different with the EPE: TM:
scenario.
'370502" With the EPRI TM: 3 : e r. T r i 2:? 2E 01/37/30 fica transients c::trrid 3736001 With the EFR: THI 3 e u ; .- lE 2E 01 's i ,1 C Pr6Js Oscillateds I
- Page No. - 2 C9l*9/53 SIMULATCE PROJECT OR'S M dificati
- n Problem Lescription Priority Anticipated Number Completion i
5 36022 With the EPRI THI Scenario 2E 01/31/90 Cnmt Pr3ss goes tco high.
2706045 With the EPR: MSt.B Transient 2E 01/31/90 the 31mulator had a step change in IR SUR.
5705 26 With a MSLB there was not 2E 01/31/90 l enough ba:kflow 5.n the faulted l SG. l
. 270s;37 With a HSLB P:r Press is tco OE 01/31/90 lcw when the P:r is enpty per RETRAN.
5706041 With a MSLB P:r Level doesn't 2E 01/31/90 follow RETRAN.
1 0604* With a MSLB P:r Level and 2E 01/31/90 ~
pressure were incentistent.
4705042 With a LCAC SG Lvis don't go 2E 01/31/90 off scale low.
3706044 With a LCAC the 5L Press and 2E 01/31/90 RCS Temp are too icw after trip per RETRAN.
5706045 With a LOAC P:r Preis did not 2E 01/31/90 follow RETRAM.
3707003 With a small RCS leak the 2E . 01/31/90 Containment Rad monitors did j not respond.
1707004 With an RCP trip saw no flow 2E 01/31/90 l
reversal.
3707005 With a locked rotor P:r Press. 2E 01/31/90 did not respond properly.
6707007 With a letdovn leak inside 2E 01/31/90 Cnmt the Cnmt rad monitors did not respond.
S7C3003 With HF-35 SG-1 pressure goes 2E 01/31/90 very low.
E709006 Opening a HFIV causes 2E 01/31/90 significant SG Lvl disturbance.
6733009 With a low power trip 5: 2E 01/31/90 occurred.
S?03012 On a trip from 7!; T-ave ;E 31,'31/90 coeled down too fas: ::npared to the plant.
3 06013 With a LCFW/ATW5 the T4 ;E 01/31/90 oscillated.
i 02046 xt h an EPRI TM tr3.- .
i; ;E 01/21/90 Lvl did not fo'1:w . I7: -
571:0:9 With a '. css : f RH A :-:t -
- ;E 0;,31/FC overpressurl:at;;:. :+
greater.
i7'..:13 cn M31V ci:sure 55 . ;E :1/2'./?:
resp;nse is inc0rr+
c Page NO. -
3 li/;9/ii SIMULATOR PROJECT DR'S M:.dift:stion Problem Descript100 Pricrity Anticipated RJ b e r Corpletion s'1:330 !annot obtain 100 PSID LP from 2E 01/31/90 chg Hdr to RCS press.
l'11* i 5/G Level response is 2E 01/31/90 incorrect for trip when ecmpared to the plant.
171103C 5/G Press respcnse is 2E 01/31/90 incorrect for MSIV closure when compared to the plant.
3711:31 RC5 press drops too much on 2E C1/31/90 MSIV closure when compared to the plant, i71103* S/G Level response incorrect 2E 31/31/90 en MSIV cloJure when compared to the plant.
1711:31 3/G Press does not match plant 2E 01/31/90 -
en trip.
47010C1 SRLC Panel should be added to 2E 03/15/39 simulation.
51C:016 Emergency Boration causes too 2E 01/31/9C-much pressuri:er pressure upset, 33030:5 sc Levels are too responsive 2E 01/31/90 when on BTRV'S per Requal i student.
l ss34034 Mot leg temp climbs too high 2E 01/31/90 after stopping an RCP.
5104035 Rad Monitor responses are. 2E 01/31/90 incorrect with a SGTR.
3304C36 Cnmt pressure did not increase 2E vi/31/90 eneugh with a LOCA IRC.
3404054 With main steamline break, we 2E 01/31/90
( did not get enmt spray actuatien, 5504055 With failed fuel the enmt area 2E 01/31/90 monitors did not respond to increased RC3 activity, isC5003 Pr:r safety valves did not 2E 01/31/90 lift with a loss of feedwater.
1505009 SI actuated on low p:r press 2E 01/31/93 after manual rx trip.
450!C10 Reacter tripped with a turbine 2E 01/31/90 trip at 30% power.
1535C11 With a M5LB in 33 3G, il 5G's 2E 01/31/90 press. decreased after M5IV's closad.
!!!:22 5:eam dumps are insens :;re. OE 01/21/9C 15:554; With cnly two RCP's runn:n; 2E 01/21/90
'2:p f;;w still shews ... .
ii:i::5 Ix:ess Letdown press.re 'ner :E C1'31/93 in00rre0*
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Page No.- . .4 09/;9/63
' i
$IMULATOR PROJECT DR'S l f
M0fift:ation Problem Description Priority Anticipated Number Completion t
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!!MS;6 Inappropriate responses from 2E 01/31/90 Tave.Pr:r lvl, 6. R SUR during ,
a SGTR.
34?7027 50 levels have a step change 2E 01/31/90 after trip during a SGTR.
4507023 Inexplicable changes in RCS 2E 01/31/90 !
temp & press, and in .
pressuri:er level during LOCA. I i !!07024 $G WP. level response was not 2E 01/31/90 as expected in relation to NR !
for shrink / swell [
34C7025 :ndicatien of flashing during 2E 01/31/90 i i a main steam header rupture. !
{ 3307040 With a feedline isolation the 2E 01/31/90 !
55 level increased. -
3507041 .With loss of shutdown cooling 2E 01/31/90 ;
the temperature TI4133 goes i down.
i
, 5407043 Pr:r pressure doesn't recover 2E 01/31/90 !
l fast enough.
l l 3507044 3G level decreases on loss of 2E 01/31/90 :
- TW.
! ss07045 P:r pressure did not respond 2E 01/31/90 (
1 to an insurge.
l e607046- Some parameters spike on 2E 01/31/90 7
i i simultaneous trip of all i RCP's. I 6607043 SG pressure oscillates too 2E 01/31/90 l much after a trip.
l 3307049 After turbine trip ST 2E 01/31/90 oscillated excessively. !
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$507057 on total loss of TW the SG's 2E 01/31/90 i dry out too slowly. !
2507053 ?ar pressure decreased on trip 2E 01/31/90 of turbine on turbine trip w/o l Rx trip.
- 3507060 T-hot temperatures are too far 2E 01/31/90 g apart in solid plant t operation. f 3509012 Froteus Computer System 2E 09/15/91 I simulation is not current. !
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PEFL%WcE ETS COPIETED 10/31/88 Plant A.W. Vo9tle, Ohit 1 Docket i 50-424 Georgia Power Capany l
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FORM 05-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 TORM TITLE: MALFUNCTION PERFORMANCE TEST LIST REVISION 1 -
PREPARED BY: M. Pellechi DATE: 4/06/88 REVIEWED BY: LGibson _ DATE: $/04/88 APPROVED BYr R. Dorman
_ OPERATIONS SUPERINTE G ENT (TRAINING) DATE: 10/17/88 MALFUNCTION MALTUNCTION TEST TEST NLMBER TITLE 05-01 Loss of coolant, significant PhR steam generator leaks 05-02 Loss of coolant. Inside primary containment -
05-03 Loss of coolant. Outside primary containment 05-04 Loss of coolant. Large reactor coolant breaks including i
demonstration of saturation conditions 05-05 Loss of coolant. Small reactor coolant breaks includina 1
demonstration of saturation conditions 05-06 Failure of safety and relief valves 05-07 Loss of instrument air tr the extent that the whole systes or individual headers can lose pressure and affect the plant's static or dynamic perfor1mance l
05-08 ;
Loss or degraded electrical power to the station, including loss of offsite power 05-09 loss or degraded electrical power to the station, loss of emergency power 05-10 Loss or degraded electrical power to the station loss of energency generators 05-11 Loss or degraded electrical power to the station loss of power to the plant's electrical distribution buses 05-12 Loss or degraded electrical power to the station. loss of power to the individual instrumentation buses (AC) that provide power to the control room indication or plant control functions affecting the plant's response
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t FORM: 05-01' PLANT A.W. V0 GILE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: MALFUNCTION PERIORMANCE TEST LIST REVISION 1 PREPARED BY: M. Pellecht DATE: 4/06/88 REVIEWED BY: M. Gibson DATE: 5/04/88 APPROSTD BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 MALFUNCTION MALFUNCTION TEST TEST NUMBER TITLE 0$-13 Loss or degraded electrical power to the station. loss of power to the individual instrumentation buses (DC) that provide power to the control room indication or plant control functions -
affecting the plant's response ~
Loss of forced core coolant flow due to single or multiple pump failure (This test is a duplicate of Tests 07-04 & 07-05) 05-14 Loss of condanser vacuum including loss of condenser level control 05-15 ,
Loss of service water or cooling to individual components 05-16 Loss of shutdown cooling 05-17 Loss of component cooling system or cooling to individual components Loss of normal feedwater or normal feedwater system failure (This test is a duplicate of Test 07-02) 05-18 Loss of all feedwatet (normal and emergency)
Loss of protective system channel (This test is covered in Test 05-12) 05-19 Control rod failure including stuck roc =.
rod drops, and misaligned rods 05-20 Inability to drive control rods 05-21 Fuel cladding failure resulting in high activity in reactor coolant or off gas and the associated high radiation alarms
Turbine trip (This test ts 4 duplicata of Test 07-06)
FURM: 05-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 3 FORM TITLE: MALFUNCTION PERFORMANCE TEST LIST REVISION 1 PREPARED BY: M. Pe11echi DATE: 4/06/88 REVIEWED BYr M. Cibson DATE: 5/04/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE 10/17/88 MALFUNCTION KALFUNCTION TEST TEST NUMBER TITLE 05-22 Generator trip _
05-23 Failure in automatic control systea(s) that affect reactivity and core heat removal
- 05-24 Failure of reactor coolant pressure and volume control systems (PWR)
Reactor trip (This test is a duplicate of T,est 07-01)
Main stema line break inside containment (This test is a duplicate of Test 07-09) 05-25 Main stema line break outside containment 05-26 Main feed line break inside containment 05-27 Main feed line break outside containment 05-28 Nuclear instrumentation failure (s) 05-29 Process instrumentation, alarms, and control system failures 05-30 Passive malfuretions in systems, such as engineered safety features, emergency feedwater systes 05-31 Failure of the automatic reactor trip systen
i FORM; 06-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 1 FORM TITLE: NORMAL OPERATIOWS TEST LIST REVISION 2 PREPARED BY: M. Pe11echi__ DATE: 4/26/88 REVTEWED BY: M. Cibson DATE: 5/04/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 NORMAL AND STEADY STATE TEST NUMBER TEST TITLE 06-01 Plant startup - cold to hot standby. The starting conditions shall be cold shutdown conditions of temperature and pressure.
Operations at hot standby (This test is redundant with portions of Test 06-01) 06-02 Nuclear startup from hot standby to rated power Turbine startup and generator synchronization (This test is
_ redundant with portions of Test 06-02) 06-03 Load changes 06-04 Plant shutdown from rated power to hot standby 06-05 Cooldown to cold shutdown conditions 06-06 Reactor trip followed by recovery to rated power Core performance testing. Heat Balance (This test is performed as part of Tests 06-09. 06-10 and 06-11)
Core performance testing. Shutdown Marsin Demonstration (Thia test is performed as part of Tests 06-01 and 06-05) 06-07 Core performance testina. Reactivity Coefficient Measurements Core performance testing. Control Rod Worth using permanently ;
installed instrumentation (This test is performed as part of '
Test 06-07) 06-08 Operator conducted surveillance testing on safety-related r equipment or systems 06-09 Steady State Performance at 30% Power for 60 Minutes 06-10 Steady State Performance at 75% Power for 60 Minutes 06-11 Steady State Performance at 100% Power for 60 minutes '
FURM: 07-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 1 FOP.M TITLE! TRANSIENT OPERATIONS TEST LIST REVISION O PREPARED BY: M. Pe11echi DATE: 3/30/88 REVIEWED BY: M. Gibson DATE: S/04/88 APPROVED BYt R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 TRANSIENT TRANSIENT OPERATIONS TEST NUMBER TEST TITI.E 07-01 Transient Performance. Manual reactor trip 07-02 Transient Performance. Simultaneous trip of all feedwater pumps 07-03 Transient Performance. Simultaneous closure of all Main Steam Isolation Valves 07-04 Transient Performance. Simultaneous trip of all reactor coolant pumps 07-05 Transient Performance. Single reactor coolant pump trip 07-06 Transient Performance. Main turbine trip (from the maximum power level which will not result in an immediate reactor trip) 07-07 Transient Performance. Maximum rate power reap (100% down to approximately 75% and back to 100%)
07-08 Transient Performance. Maximum size reactor coolant systes rupture combined with a loss of offsite power 07-09 Transient Perfor1*ance. Maximum size unisolable main steam line rupture 07-10 Transient Performance. Slow primary system depressuritation to saturated condition using pressurizer relief or safety valve stuck open.(Inhibit activation of the high pressure is.ergency Core Cooling Systems)
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FORM: 05-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE L OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPAAED BY: M. Pellechi DATE: 9/8/88 REVIEWED BY M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : LOCA: Significant SG Leaks (05-01)
The Vogtle simulator is initialized to 100% power. IOL. Equilibrium Xe. A SG-1 tube rupture (salf #84) is inserted one minute after the simulator is placed in run 0 10% severity. The leak is increased to 50% severity after 6 minutes. At 11 minutes from the beginning of the session. the malfunction severity is
,- increased to 100%. The exercise is terminated once the pressurizer level is stable or slowly increasing above 20%.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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t FORM: 05-02 PLANT A.W. V0GTLE SIMUIATOR CERTIFICATION PLAN PAGE 2 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pellechi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPROVED BY R. Derman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMUIATOR PERFORMANCE TEST ASSTRACT
- 'ITLE LOCA: Inside Containment (05-02)
The Vogtle simulator is initialized to 100% power. EOL. Equilibrius Xe. A Mot Leg #2 rupture (malf #37) is inserted 6 100% severity one minute after the simulator is placed in run. The exercise is terminated 3 minutes after safety injection actuates.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
FORMt 05-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pellechi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorsan , OPERATIONS SLTPERINTENDENT (TRAINING) DATE: 10/17/88 SINUIATOR PERFORMANCE TEST AR$ TRACT TITLE : LOCA: Outside containment (05-03)
The Vogtle simulator is initialized to 0% power. BOL. Not Standby. positive displacement charging pump is in service. A letdown line leak in the auxiliary building (malf #76) is inserted 9 10% severity one minute after the simulator is placed in run. The exercise is terminated af ter the leak has been autoestically
- isolated and the pressurizer level is increasing.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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F FURM: 0$-02 PLANT A.W. V0 GILE SIMULATOR CERTIFICATION PLAN PAGE 4 UF 33 FORM TITLE PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/8/88 REVTEWED BY: M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERI'lTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : LOCA: Large Break (05-04)
The Vogtle simulator is initialized to 100% power. EOL. Equilibrius Xe. A RCS Loop 3 cold leg rupture (malf v35) is inserted one minute after the simulator is placed in run.
The exercise is terminated 11 minutes after the simulator has been placed in run.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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- FOM: 05-02 PIANI A.W. V0 GILE SIMULATOR CERTIFICATION PLAN PAGE 5 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : LOCA: Small Break (05-05)
The Vogtle simulator is initialized to 100% power. EOL. Equilibrius Xe. A het les leak at SG #2 inlet (salf #37) is inserted 6 20% severity one minute after the simulator is placed in run.
safety injection actuates. The exercise is terminated 3 minutes after The simulator response is evaluated against best estimate judgement where Vogtle
, plant data is not available.
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FURM 05-02 PLANT A.W. V0GTLE SIMULATOR CERI1FICATION PLAN PAGE 6 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVTSION O PREPARED BY: M. Pe11echt DATE: 9/8/88 REVIEWED BYt M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 r
SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Failure of Par SVs and PORVs (05-06) r The Vogtle simulator is initialized to 100% power, EOL. Equilibrium Xe. -A pressurizer safety valvc PSV-8010e leakage (salf #58) is inserted 0 10% severity one minute after the simulator is placed in run. At 6 minutes from the beginning of the simulator run, the malfunction severity is increased to 100%. The ;
y exercise is terminated 3 minutes after safety injection actuates. '
The Vogtle simulator is reinitialized to 100% power, EOL. Equilibrius Xe. PORV '
block NV-8000A open with I/O override. A pressurizer relief valve PV-455a leakage (malf #63) is inseri d 9 100% severity one minute after the simulator is placed in run. The exercise is terniaated 3 minutes after safety injection actuates.
The staulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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,j FORM: 05-02 PLANT A.W. V0GTLE SIMVLATUR CERTIFICATION PLAN PAGE 7 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT P.EVISION O PREPARED BY M. Pe11echi DATE: 9/8/88 REVIEWED SY M. Gibson DATE: 9/13/88 APPROVID BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERTORMANCE TEST ASSTRACT TITLE : Loss of Instrument Air (05-07)
The Vogtle simulator is initialized to 1005 power. EOL. Equilibrius Xe. A loss of instrument air (malf #198) is inserted 0 705 severity one minute after the simulator is placed in run. The main turbine is tripped at 70 psia. When the instrument air pressure decreases to 10 psig. the malfunction is removed. The exercise is terminated 3 minutes after the instrument air pressure returns to normal.
The simulator response is evaluated against best estimate judgement.
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FOM: 05-02 PLANT A.W. VOGTLE SIMtuTOR CERTIFICATION PLAN PAGE 8 Of 33 FORM TITLEt PERF0MANCE TEST A35 TRACT REVISION 0 f PREPARED BYr M. Pe11echt DATE: 9/8/88 REVIEWED BY M. Gibson DATE: 9/13/88 APPROVED BY R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 l
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$INLU TOR PERFORMANCE TEST AS$ TRACT TITLE : Loss of of f aite Power. (05-08)
The Vogtle simulator is initialized to 1005 power. EOL. Equilibrius Xe. A loss of reserve auxiliary transformers 1NXRA/S (malf 126 & 127) and loss of unit auxiliary transformers INXAA/S (malf 124 & 129) is inserted one minute after the -
simulator is placed in run. The salfunctiens are removed after specified LORs are verified not able to be reset. The LORs are reset after malfunction removal and the 4160 SWGR transferred from the Emergency Diesels to the RATS. The exercise is terminated after the Emergency Diesels are unloaded. ,
The staulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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FukMr 05-02 PLANT A.W. V0GTLE $1MUI.ATOR CERTIFICATION PLAN PAGE 9 Of 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 0, PREPARED BY: M. Pe11echt DATE: 9/8/88 REVIEWED BY: M. Citson DATE: 9/13/83 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 l~~
SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Loss of Energency Power (05-09)
The Vogtle simulator is initialized to 1001 power EOL. Equilibrius Xe. A less of control building 4.16 KV swgr 1AA02 (salf #132) is inserted one minute after the simulator is placed in run. The salfunction is removed after the proper loads have been verified deenergired. The exercise is terminated after the appropriate loads have been restarted.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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FORM: 05-02 Pl. ANT A.W. V0GTLE SIMULAIOR CERTIFICATION PLAN PAGE 10 or 33 FORM TITt.Et PERFORMANCE TES1 ASSTRACT REVISION 0 !
PREPARED BY: M. Pe11echi DATE: 9/8/88 REVIEWED BY M. Gibson DATE: 9/13/88 i APPROVED BY: R. Dorman I OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 l
l SIMULATOR PERFORMANCE TEST ABSTRACT l
r TITLE : Loss of Emersency Generators (05-10)
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The Vogtle simulator is initialized to 100% powe r. E0L. Fquilibrius Xe. An t emergency diesel DG 1A fails to start (salf $139A) is inserted one minute after i the steulator is placed in run. The DG is verified not to manually start and then placed in standby. A loss of reserve auxiliary transformer INXRA (salf 4 126) is inserted. The DC 1A is verified that it starts and loads properly. The !
exercise is terminated after the appropriate equipment has started, i The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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FURMt 05-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 11 of 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 0 PREPARED BY: M. Pellechi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 r
APPRO\TD BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 l
1 SIMULATOR PERTORMANCE TEST ABSTRACT i
TITLE : Loss of Elec. Dist. Buses (05-11)
The Vogtle simulator is initialized to 100% power. EOL Equilibrius Xe. A less of turbine building 13.8 KV swgr 1NAA (salf #130A) is inserted one minute after the simulator is placed in run. The salfunction is removed after the proper loads have been verified deenergized. The malfunction is then removed. The exercise is terminated af ter the appropriate loads have been restarted.
The Vogtle simulator is initialized to 100% power. EOL. Equilibrius Xe. A loss <
of control building 4.16 KV swar 1BA03 (malf #1328) is inserted one minute after the steulator is placed in run. The malfunction is removed after the proper loads have been verified deenergized. The malfunction is then removed. The exercise is terminated af ter the appropriate loads have been restarted.
The Vogtle simulator is initialized to 100% power. EOL. Equilibrium Xe. A loss of 440 V swar INB03 (malf 9134A) is inserted one minute after the simulator is placed in run.
The malfunction is removed after the proper loads have been :
l verified deenergized. The selfunction is then removed. The exercise is !
terminated af ter the appropriate loads have been restarted.
The Vogtle simulator is initialized to 100% power. E0L. Equilibrius Xe. A loss I of 480 V swer 1NB02 (malf $134D) is inserted one minute after the simulator is placed in run. The malfunction is removed af ter the proper loads have been verified deenergized. The malfunction is then removed. The exercise is tetuinated af ter the appropriate loads have been restarted.
The Vogtle simulator is initialized to 100% power. EOL. Equilibrius Xe. A loss ,
of 480 V swer 1NB09 (salf #135A) is inserted one minute after the stuulator is placed in run.
The salfunction is removed after the proper loads have been verified deenergized. The malfunction is then removed. The exercise is terminated af ter the appropriate loads have been restarted.
The Vogtle simulator is initialized to 100% power. EOL. Equilibrius Xe. A loss of 480 V swgr IBB06 (malf e135H) is inserted one minute after the simulator is placed in run. The malfunction ts removed after the proper loads have been verified deenergized. The malfunction is then removed. The exercise is terminated af ter the appropriate loads have been restarted.
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FORM: 05-02 PLANT A.W. V0GTLE SINULATOR CERTIFICATION PLAN PAGE 12 UF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE Loss of Elee. Dist. Suses (05-11)
The simulator response is evaluated against best estimate judgement where Vogt4e plant data is not available.
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FokM: 05-02 PLANT A.W. V0GTLE $1MULATOR CERTIFICATION PLAN PAGE 13 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pellechi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPh0VED BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFOMANCE TEST ABSTRACT TITLE : Loss of Instrument AC Buses (05-12) the Vogtle simulator is initialized to 100% power. EOL. Equilibrium Me.
unaffected SG control channel selected for input to SGWLC. A vital instrument panel 1AY1A failure (salf #138A) is inserted one minute after the simulator is placed in run. The salfunction is removed after the proper loads have been verified deenergized. The exercise is terminated after the appropriate loads have been restarted.
The Vogtle simulator is initialized to 100% power. EOL. Equilibrius Xe.
unaf fected SG control channel selected for input to SGWLC. A vital instrument panel 1CY1A failure (malf 4138C) is inserted one minute after the simulator is placed in run. The selfunction is removed after the proper loads have been verified deenergized. The exercise is terminated af ter the appropriate loads have been restarted.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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FURM: 05-02 PLANT A.W. V0GTLE SIMULA10R CERTIFICATION PLAN PAGE 14 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echt DATE: 9/8/88 REVIEliED BY: M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorean OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ASSTRACT TITLE : Loss of Instrue e DC Buses (05-13)
The Vogtle simulator is initialized to 100% power. EOL. Equilibrius Xe. An EfF 12$ V DC swar 1AD1 fault (malf #136A) is inserted one minute after the simulator is placed in run. The malfunction is removed after the proper loads have been verified deenergized. The exercise is terminated after the appropriate loads have been restarted.
The Vogtle simulator is initialized to 100% power. EOL. Equilibrius Xe. An ESF 125 V DC swar IDDI f ault (salf 8136D) is inserted one minute af ter the simulator is placed in run. The s41 function is removed after the proper loads have been verified deenergized. The exercise is terminated after the appropriate loads have been restarted.
The Vogtle simulator is initialized to 100% power. EOL. Equilibrius Xe. An non-EST 125 V DC swar IND1 fault (malf #137A) is inserted one minute after the simulator is placed in run. The malfunction is removed after the proper losts have been verified deenergized. The exercise is terminated after the appropriate loads have been restarted.
The Vogtle simulator is initialized to 100% power. EOL. Equilibrius Xe. An non-ESF 125 V DC owgr IND3 fault (malf e137C) is inserted one minute after the simulator is placed in run. The malfunction is removed after 1)the proper loads have been verified deenergized and 2) the 480 Y ESS instrument panel power auto transfers to the alternate supply. The exercise is terminated after the appropriate loads have been restarted.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
s FORM 05-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 15 0F 31 FORM TITLEt PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/8/04 REVIEWED SY: M. Gibson DATE: 9/13/84 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAININC) DATE: 10/17/88 SIMULAT0il PERFORMANCE TEST ABSTRACT TITLE : Loss of cond Vacuus/Lvl Control (05-14)
The Yostle simulator is initlalized to 10 M power. BOL, Equilibrium Xe. A less of condenser vacuus (salf 8141) is inserted 610M severity one minute after the simulator is placed in run.
reaches 7 psia.
The malfunction is removed when condenser vacuus psia.
The exercise is terminated after condenser vacuum reaches 5 The Vogtle simulator is initialized to 10M power. BOL. Equilibrius Xe. A hotwell level transmitter LT-6415 failure (salf $142) is inserted 9 1M severity one minute after the simulator is placed in run. The malfunction is removed 8 minutes after the simulator has been placed in run. The exercise is terminated after condenser level returns to normal.
The simulator response is evaluated against best estimate $wisement where Vogtle plant data is not available.
1 FOM: 05-02 PLANT A.W. VOGTLE SLWLATOR CERTIFICATION PLAN PAGE 16 0F ))
FORM TITLEr PERFORMANCE TEST ABSTRACT REVISION O FREPARED BY: M. Pe11echt DATE: 9/8/88 REVIEWED BY: M. Gibson DATE' 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DAfra 10/17/88 l
SIMUIATOR PERFORMANCE TEST ABSTRACT TITLE : Loss of Service Water (05-15)
The Vogtle simulator is initialized to 100% power. BOL. Equilibrium Xe. standby NSCW pump in auto. A NSCW train B pump P-2 shaf t break (nelf #191A) is inserted one sinute after the simulator is placed in run. The NSCW pump P-2 handswitch is placed to STOP and then START. The salfunction is removed when pump P-2 is
, verified not started. Both NSCW pumps P-2 & 3 handswitches are placed to STOP.
( Pump P-2 is then manually started. The exercise is terminated after NSCW flow returns to normal. '
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The Vogtle simulator is initialized to 100% power. 30L. Equilibrius Xe. standby NSCW pump in auto. A NSCW train A pipe break to CCW Mx il (malf $192) is inserted one minute after the simulator is placed in run. The malfunction is removed after 5 additional minutes. The exercise is terminated after NSCW pressure returns to normal.
The Vogtle simulator is initialized to 100% power. 30L. Equilibriue Xe. standby NSCW pump in auto. A NSCW train R pipe b'eak to ACCW Rx $2 (malf #193) is i inserted one minute atter the simulator is placed in run. The selfunction is !
removed after 5 additional minutes. The exercise is terminated after NSCW r pressure returns to normal.
i The simulator response is evaluated against best estimate judgement.
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4 FORM: 05-02 PLANT A.W. VOCTLE $1MULATOR CERTIP1 CATION PMN PAGE 17 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echt DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88
.tPPROVID BY R. Dorsan OPERATIONS $UPERINTENDENT (TRAINING) DATE: _10/17/88
$1MULATOR PERFORMANCE TEST ABSTRACT TITLE Loss of $hutdown Coolina (05-16)
The Vogtle simulator is initialized to 0% power. SOL 197 Des F. Mode 4 A R!Gt pump P-1 trip (self #45A) is inserted one etnute after the simulator is placed in run. The RNA pump P-1 handswitch is placed to STOP and then START. RNR pump P-1 is verified not started. RJDt pump P-1 handswitch is placed to STOP and the malfunction removed. Pump P-1 is then manually started.- The exercise is terminated after RNR flow returns to normal.
The simulator response is evaluated against best estimate judgement.
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ivkMr 05-02 FLANI A.W. V0GTLE SIMUI.A70R cEATIFICATION PLAN PAGE 18 uf 33 Ff;,l e, TITLE: PERTORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pellecht DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorman OPERATTONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 51MUI.ATOR PERFORMANCE TEST A45 TRACT TITLE : Loss of component Coolina (05-17) t j
The Vogtle simulator is initialized to 50% power. SQL. Equilibrium Xe. standby CCW ptusp in AUTO. A CCW pump P-3 trip (self #1948) is inserted one minute after the simulator is placed in run. The CCW pump P-3 handswitch is placed to STOP and then START. CCW pump P-3 is verified not started. CCW pump P-3 handswitch is placed to STOP and the malfunction recoved. Pump P-3 is then manually started. The exercise is terminated af ter CCW flow stabilizes.
The Vogtle simulator is initialized to 0% power. SOL. Not Shutdown, standby CCW pump in AUTO. A CCW train a pipe break to RMR Ex #2 (self 6196) is inserted one minute after the simulator is placed in run. The malfunction is removed after the CCW pumps have tripped. Two tal pumps on trsin B ate then manually statted.
The exercise is terminated after CCW train 8 pressure returna to normal.
The Vogtle simulator is initialized to 50% power. Bot. Equilibrius Xe. standby ACCW pump in AUTO. A ACCW pump P-1 locked rotor (asif $197A) is inserted one minute after the simulator is placed in run. The ACCW pump P-1 handswitch is placed to STOP and then START. ACCW pump P-1 is verified not started. ACCW pump P-1 handswitch is placed to STOP and the selfunction removed. Pump P-1 is then manually started. The exercise is terminated after ACCY flow stabilizes.
The simulator response is evaluated against best estimate judaesent.
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FORM: 05-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 19 0F 33 TORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O_
PREPARED BY: M. Pellechi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPP.0VED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/g i
SIMULATOR PERFORMANCE TEST ABSTRACT i
TITLE : Loss of All Feedwater (05-18)
The Vogtle simulator is initialized to 100% power. EOL, Equilibrium Xe. -A complete loss of all feedwater is initiated by inserting a trip of both main feedwater pumps (malf 146A & B) and a trip of all emergency feedwater pomps (salf 160A & B and 151) one minute after the sieuLetor is placed in run. Malfunctions
( 160A & B are removed after the pressurizer PORVs have opened and when all SGs are emptied. AFWPs P-2 & 3 are then manually started.
The exercise is terminated after the pressurizar safety relief valves close.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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i FORM: 05-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 20 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi _ DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88, APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Control Rod Failures (05-19)
The Vogtle simulator is initialized to 50% power. EOL.EquilibriumXe.iA dropped RCCA H8 (salf d281) is inserted one minute after the simulator is placed in run. The rod is verified unmovable in all rod control modes. The salfunction is removed and the dropped rod retrieved using the appropriate plant procedure.
The exercise is terminated af ter the rod is within 2 preps of its aroup.
The Vogtle simulator is initialized to 1E-8% power. BOL. 557 Deg F, RCCA bank D not fully inserted or withdrawn.
A stuck RCCA H8 (malf #24I) is inserted one minute after the simulator is placed in run. RCCA bank CD is withdrawn and then inserted 10 steps. The rod is verified to remain stationary. The lift coils for all rods except H8 in bank CD are opened. Again an attempt to withdraw / insert H8 is made. This is followed by a manual reactor trip. The exercise is terminated ;
after the rod is verified stuck following a reactor trip.
The simulator response is evaluated against best estimate judgement where Vogtle l plant data is not available.
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FOM : 05-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 21 0F 33 FORM TITLE PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pellechi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPROVED BY: R. Dor 1 san OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMUI.ATOR PERFORMANCE TEST ABSTRACT TITLE : Inability to Drive Control Rrxis (05-20)
The Vogtle simulator is initialized to 50% power. BOL. Equilibrius Xe. tod control in Manual. A control banks fail to move on auto or manual demand (self
- 22) is inserted. The rods are verified tausovable in Manual. Rod control is shifted to Auto. This is followed by adjusting turbine load by + 10%. After the
, rods are verified stationary, the reactor is tripped. The exercise is terminated after all the rods are verified on the bottom.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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FORM: 05-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 22 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Fuel Cladding Failure (05-21)
The Vogtle simulator is initialized to 50% power. SOL, Equilibriua Xe. A failed fuel (salf #608) is inserted 9 10% severity one minute after the simulator is placed in run. This is followed by inse.rting a SG #2 tube rupture (malf 86) 9 10% severity 6 minutes after the simulator is placed in run. The exercise is
_ terminated after 11 minutes after the simulator is placed in run.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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FORM: 05-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 23 0F 33 FORh TITLE: PERFORMANCE TEST ABSTRACT REVTSION O PREPARED BY: M. Pellecht DATE: 9/8/88 REVIE5 FED BY M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATI: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Generator Trip (05 ,22)
The Vogtle simulator is initialized to 100% power. BOL, Equilibrius Xe. A main generator trip (salf W116) is inserted one minute after the simulator is placed in run. The malfunction is removed after it is verified that LOR 386-G9 will not reset. The exercise is terminated af ter LOR 386-G9 is reset.
The simulator response is evaluated against D-se estimate judgsment where Vogtle plant data is not available.
e FORM: 05-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN FAGE 24 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE T%ST ABSTRACT TITLE : Failure in Auto Control Sys That Affect Reactivity in Core Heat Removal (05-23)
The Vogtle simulator is initialized to 100% power. BOL, Equilibrius Xe. A spurious train B safety injection signal (salf #168) is inserted one minute after the simulator is placed in run This is followed by verifyina selected SI signals can be reset after the blo(k/ reset time delay has timed out. The exercise 1.s terisinated af ter the SI signals are rest.
The Vog*.le simulator is initialized to 100% power. BOL. Equilibrius Xe. control rods in AUTO. one BATP running. A RCS boration (salf 882) is inserted 9 100%
severity one minute after the simulator is placed in run. The salfunction is removed after 11 minutes after the simulator is placed in run. This is followed by manually closing valve HV-8104. The exercise is terminated 5 minutes after valve HV-8104 is closed.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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FORM: 05-02 PLANT A.W. V0 GILE SIMULATOR CERTIFICATION PLAN PAGE 25 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/8/88 REVIEWED BY: M. Gibson s DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE4 10/17/88 I!
SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Failure in Reactor Coolant Pressure and Volume control System (05-24)
The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe. A pressurizer pressure transmitter PT-455 fails (malf #59A) is inserted 0 100%
severity one minute after the simulator is placed in run. The malfunction is removed after 5 additional minutes. The exercise is terminated after the actual pressurizer level increases to 30%.
The Vogtle simulator is initialized to 100% power. BOL, Equilibrium Xe. A pressurizer pressure transmitter PT-459 fails (salf #61A) is inserted 9 0%
severity one minute after the simulator is placed in run. The malfunction is removed after 5 additional minutes. The exercise is terminated after 10 minutes.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available, l
5 FORM: 05-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 26 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pellech _ DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPROVED BY: R. Do rman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Main Steam Line Break Outside containment (05-25)
The Vogtle simulator is initialized to 49% power. EOL, Equilibrium Xe. A main steam safety valve PSV-3001 leek (malf #94A) is inserted S 100% severity one minute after the simulator is placed in run. The exercise is terminated 6 minutes after the simulator is placed in run.
The Vogtle simulator is initialized to 100% power EOL, Equilibrium Xe. A main steam bypass valve header rupture (salf #92) is inserted S 100% severity one w'.nute after the simulator is placed in run. The exercise is terminated 11 minuwes after the simulator is placed in run.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available, r
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z FORM: 05-02 PLANT A.W. VOGILE SIMULATOR CERTIFICATION PLAN PAGE 27 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERf0RMANCE TEST ABSTRACT TITLE : Main Feed Line Break Inside Containment (05-26)
The Vogtle simulator is initialized to 100% power. EOL Equilibrius Xe. A ~
feedwater line #2 rupture inside containment (malf #153) is inserted 9 50%
severity one minute after the simulator is placed in run. The exercise is terminated 11 minutes after the simulator is placed in run.
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The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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FORM: 05-02 PLANT A.W. V0GTLE SIMUIATOR CERTIFICATION PLAN PAGE 28 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISIJN O PREPARED BY: M. Pellechi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDEht (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT l
TITLE : Main Feed Line Break Outside Containment (05-27)
The Vogtle simulator is initialized to 100% power. EOL, Equilibrius Xe. A feedwater line #1 rupture outside containment (malf #154) is inserted 0 100%
severity one minute after the simulator is placed in run. The exercise is terminated 11 minutes after the simulator is placed in run.
The sd.aulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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FORM: 05-02 PLAAT A.W. V0GTLE SIMULATOR GERTIFICArION PLAN PAGE 29 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/1?/88 APPROVED BY: R. Dorman _ OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Nuclear Instrument Failures (05-28)
The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe. A power range chan 42 upper detector fails (salf #7B) is inserted 9 50% severity one minute after the simulator is placed in run. Three minutes after the simulator is placed in run, reactor / turbine load is reduced 10%. The malfunction is then removed. The exercise is terminated 1 minute af ter malfunction removal.
The Vogtle simulator is initialized to 100% power, BOL, Equilibrius Xe. A power range chan 44 high voltage failure (malf #8D) is inserted 9 30% severity one minute after the simulator is placed in run. Three minutes after the simulator is placed in run, reactor / turbine load is reduced 10%. The malfunction is then removed. The exercise is terminated 1 minute after salfunction renoval.
The Vogtle simulator is initialized to 50% power BOL. Equilibrium Xe. A power range output oscillation (malf 411A) is inserted 9 30% severity one minute after the simulator is placed in run. Three minutes after the simulator is placed in run, reactor / turbine load is increased 10%. The malfunction is then removed.
The exercise is terminated 1 minute af ter malfunction renoval.
The simulator response is evaluated against best estimate judgement.
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FORM 05-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 30 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAININC) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Process Instrument Failures (05-29)
The Vogtle simulator is initialized to 0% power. BOL, cold shutdown, sol, lid pressurizer, RHR train A in operation. A loop pressure transmitter PT-438 fails high (salf #38A) is inserted one minute after the simulator is placed in run.
The RHR pump for loop 1 is secured and an attempt to open RHR valve KV-8701A is made. The malfunction is removed after 5 minutes after the simulator is placed in run. The exercise is terminated 7 minutes af ter malfunction removal.
The Vogtle simulator is initialized to 100% power. BOL. Equilibrius Xe. A hot leg RTD TE-411A fails (salf $40A) is inserted 0 0% severity one minute after the simulator is placed in run. After 5 additional minutes, the malfunction is removed. The exercise is terminated 1 minute af ter malfunction removal.
The Vogtle simulator is initialized to 100% power. BOL Equilibrius Xe. A cold leg RTD TE-413B fails (salf #41A) is inserted 9 90% severity one minute after the simulator is placed in run. After 2 additional minutes, the malfunction is removed. The exercise is terminated 1 minute af ter malfunction removal.
The Vogtle simulator is initialized to 30% power. BOL Equilibrius Xe. A channel 1 RCS flow elements fail (malf $44C) is inserted 9 50% severity one air.ute after the simulator is placed in run. After 2 additional minutes, the malfunction severity is reduced to 0%.
The malfunction is removed 6 minutes after the simulator is placed in run. The exercise is terminated 1 minute after malfunction removal.
Ihe Vogtle simulator is initialized to 100% power. BOL. Equilibrius Xe. LT 459 selected for control. A pressurizer level transmitter LT-459 fails (malf W61A) is inserted 6 100% severity one minute after the simulator is placed in run.
After 2 additional minutes, the malfunction is removed. The exercise is terminated 1 minute af ter salfunction removal.
The Vogtle simulator is initialized to 100% power. BOL. Equilibrium Xe. A steam generator level transmitter LT-519 fails (malf 688A) is inserted 9 90% severity one minute after the simulator is placed tn run. Eleven minutes after the simulator is placed in run, the malfunctton is removed. The exercise is terminated 1 minute after malfunction removal.
FORM: 05-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 31 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Process Instrument Failures (05-29)
The Vogtle simulator is initialized to 100% power, BOL, Equilibrius Xe, control rods in AUTO. A main turbine impulse pressure transmitter PT-505 fails (salf
- 62A) is inserted 9 10% severity one minute after the simulator is placed in run.
The malfunction severity is increased to 85% after 2 additional sinutes. Five minutes after the simulator is placed in run, the malfunction is removed. The
{ exercise is terminated 1 minute after malfunction removal.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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l FukM: 05-02 PLANT A.W. V0GTLE SINULATOR CERTIFICATION PLAN PAGE 32 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 0 l
PREPARED BY: M. Pe11echi DATE: 9/8/88 REVIEWED BY: M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 4
SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Passive Malfunctions in ESF (05-30) J L
The Vogtle simulator is initialized to 100% power. EOL. Equilibrius Xe. A train A main steam line isolation automatic actuation failure (malf #164) is inserted. L A main steam line #3 rupture.inside containment (self #91) is inserted at 100% i severity one minute after the simulator is placed in run. After 2 additional 1
minutes the train A NSIV handswitch is placed to close. The exercise is terminated 6 minutes af ter the simulator is placed in run. ,
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The Vogtle simulator is initialized to 100% power. EOL, Equilibrius Xe. A train A containment spray automatic actuation failure (salf #164) is inserted. A RCS f loop 3 cold les rupture (salf #35) is inserted one minute after the simulator is ,
placed in run. After 2 additional minutes the containment spray pump #1 (
handswitch is placed to start. Four minutes after the simulator is placed in run i valves NV-9001A & NY- 8994A handswitches are placed to open. The exercise is terminated 6 minutes af ter the steulator is placed in run. i r
i The Vogtle simulator is initialized to 100% power. E0L. Equilibrius Xe. A train j B safety injection manual actuation failure (salf #170) is inserted. Three i
minutes after the simulator is placed in run an attempt to manually initiate !
safety injection on both channels is made. The exercise is terminated 6 minutes !
af ter the simulator is placed in run. !
The simulator response is esaluated against best estincte judgement. .
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FORM: 05-02 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 33 0F 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/8/88 REVIEWED BY; M. Gibson DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Failure in Auto Reactor Trip (05-31)
The Vogtle simulator is initialized to 100% power. EOL Equilibrius Xe. contr.o1 rods in manual. A failure of automatic reactor trip (malf #12) is inserted. - A main turbine trip (malf # 98) is inserted one minute after the simulator is placed in run. After 10 additional minutes, the reactor is manually tripped.
The exercise is terminated 16 minute:s after the simulator is placed in run.
The simulator response is evaluated against best estimate jitdgement where Vogtle plant data is not available.
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FORM: 06-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 11 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pellechi DATE: 9/22/88 REVIEWED BY: M. Gibson DATE: 9/22/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Plant Startup to Hot Standby (06-01)
The Vogtle simulator is initialized to 0% power. BOL, < 160 Deg F. Mode 5. A plant startup is performed from cold shutdown to Hot Standby. The exercise is conducted using controlled copies of the Vogtle plant procedures. If a step.is performed and the response of the simulator does not meet the startup test criteria or if a step can not be performed, or if an alars annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
This scenario includes coming off Shutdown Cooling (i.e.. RHR). forming a bubble in the pressurizer, starting the reactor coolant pumps, warsup of the secondary side, forming a condenser vacuum, maintaining steam generator levels with auxiliary feedwater, and performing boron dilution. The exercise is terminated when the plant is stable at 557 Deg F.
- The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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FORM: 06-02 PLANT A.W. V0GTLE SLMULATOR CERTIFICATION PLAN PAGE 2 0F 11 FOR't TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/22/88 REVIEWED BY: M. Gibson DATE: 9/22/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMUIATOR PERFORMANCE TEST ABSTRACT TITLE : Nuclear Startup free Hot Standby to Rated Power (06-02)
The Vogtle simulator is initialized to 0% power. BOL, 557 Des F. A nuclear startup is performed from Hot Standby to rated power. The exercise is conducted using controlled copies of the Vogtle plant procedures. If a step is performed and the response of the simulator does not meet the startup test criteria, or if a step can not be performed, or if an alars annunciates but shouldn't or doesn't
, annunciate but should, then a discrepancy report is written.
This scenario includes conducting a 1/M plot during rod withdrawal, transferring steam generator level control from the auxiliary feedwater systes to the main feedwater system, rolling the turbine up to speed, synchronizing the main generator to the grid, and perf'rming boron dilution to 100% power. The exercise is terminated when the plant is stable at 100% power.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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t FORM: 06-02 PLANT A.W. V0GTLE SINULATOR CERTIFICATION PLAN PAGE 3 of 11 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/22/88 REVIEWED BY: M. Gibson DATE: 9/22/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Load Changes (06-03 The Vogtle simulator is initialized to 100% power. BOL. A plant load chanae is performed f rom 100% to 80% and back to 90%. The exercise is conducted using controlled copies of the Vogtle plant procedures. If a step is performed and the response of the simulator does not meet the startup test criteria, or if a step can not be performed, or if an alars annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
This scenario includes a load reduction of 20% at a rate of 11 per minute. The plant is allowed to stabilize for 5 minutes. This is followed by a load increase of 10% at a rate of 8% per hour. The exercise is terminated when the plant is stable at 90% power.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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FORM: 06-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN f- PAGE 4 0F 11 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/22/88 REVIEWED BY: M. Gibson DATE: 9/22/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMUIATOR PERFORMANCE TEST ABSTRACT TITLE : Plant Shutdown from Rated Power to Hot Standby (06-04)
The Vogtle simulator is initialized to 100% power. BOL. . A plant shutdown is performed froe rated power to Hot Standby. The exercise is conducted uafhs controlled copies of the Vogtle plant procedures. If a step is performed and the response of the simulator does not meet the startup test criteria, or if a step can not be pe rfo rmed, or if an alars annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
This scenario includes commencing a power descent to 5% at a rate of 1% per minute, inserting all control rods, transferrina steam generator level control from the main feedwater system to the auxiliary feedwater systes, and tripping the main turbine. The exercise is terminated when the plant is stable at Hot Standby.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
FORM: 06-02 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 5 0F 11 F0Pff TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/22/88 REVIEWED BY: M. Gibson DATE: 9/22/88 APPROVED BY: R. Dorman OPEMTIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT ;
TITLE : Cooldown to Cold Shutdown
_ Conditions (06-05)
The Vogtle simulator is initialized to 0% power. 80L. Not Standby. A plant shutdown is performed from Not Standby to cold shutdown conditions. The exerc he '
is conducted using controlled copies of the Vogtle plant procedures. If a step is performed and the response of the simulator does not meet the startup test criteria. or if a step can not be performed, or if an alara annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
This scenario includes coar.encing a plant shutdown to < 200 Des F. verifying an i adequate shutdown margin exists, borating the RCS. securing the reactor coolant pumps. going on shutdown cooling, and collapsing the pressurizer bubble. The exercise is terminated when the plant is stable at < 110 Deg F.
The simulator respouse is evaluated against best estimate judgement where Vogtle plant data is not available.
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FORM: 06-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 6 0F 11 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O FREPARED BY: M. Pellechi DATE: 9/22/88 REVTEWED BY M. Gibson DATE: 9/22/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCF TEST ABSTRACT TITLE : Reactor Trip With Recovery to Rated Power (06-06).
The Vogtle simulator is initialized to 100% power. BOL, Equilibrius Xe. .A reactor trip is performed with a recovery to rated power. The exercise is conducted using controlled copies of the Vogtle plant procedures. If a step is performed and the response of the simulator does not meet the startup test criteria, or if a step can not be performed, or if an alarm annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
This scenario includes initiating a reactor trip 1 minute after the simulator is placed in run, stabilizing the plant at Hot Standby utilizing "Fast Time" to accelerate the Xe concentration at 60Xs normal for 20 minutes (equates to 20 Hrs real time), and commencing a power ascension to 100%. The exercise is terminated when the plant is stable at 100% powtr.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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J FORM 06-02 PLANT A.W. V0GTLE SINULATOR CERTIFICATION PLAN PAGE 7 0F 11 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 0 PREPARED BY: M. Pe11echi DATE: 9/22/88 REVIEWED BY: M. Gibson DATE: 9/22/88 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMUIATOR PERFORMANCE TEST ABSTRACT TITLE : Core Performance Tests (06-07)
The Vogtle simulator is initialized to 30% power. BOL. Equilibrius Xe. A core physics test at 30% power is performed to determine the power coefficient. The exercise is conducted using controlled copies of the Vogtle plant procedures.
If a step is performed and the response of the simulator does not meet the startup test criteria, or if a step can not be performed, or if an alars annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
The Vogtle simulator is initialized to IE-8% power. BOL. Xe free. Core physics tests are performed to determine the isothermal coefficient, boron coefficient.
and control rod worth. The exercise is conducted using controlled copies of the Vogtle plant procedures. If a step is performed 'and the response of the simulator does not meet the startup test criteria, or if a step can not be performed, or if an alors annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written. "
The simulator response is evaluated against the acceptance criteria specified in the plant procedures.
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FORM: 06-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 8 0F 11 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pellechi LATE: 9/22/88 REVIEWED BY: M. Gibson DATE: 9/22/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Surveillance Testing on Safety Equipment or Systems (06-08)
The Vogtle simulator is initialized to conditions required by the diesel generator operability test procedure. A diesel generator surveillance test Js performed to determine the availability of the el diesel generator. The exercise is conducted using controlled copies of the Vogtle plant procedures. If a step is performed and the response of the simulator does not meet the startup test criteria. or if a step can not be performed, or if an alars annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
The Vogtle simulator is initialized to conditions required by the source range NIS operability test procedure. A source range nuclear instrument surveillance test is pe rformed to dete rmine the availability of 1 of the source range channels. The exercise is conducted using controlled copies of the Vogtle plant procedures. If a step is performed and the response of the simulator does not meet the startup test criteria, or if a step can not be performed, or if an alarm annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
The Vogtle simulator is initialized to conditions required by the control room emergency filtration system operability test procedure. A surveillance test is performed to determine the availability of the CR emergency filtration system.
The exercise is conducted using controlled copies of the Vogtle plant procedures. If a step is performed and the response of the simulator does not meet the startup test criteria, or if a step can not be performed or if an alarm annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
The Vogtle timulator is initialized to conditions required by the boron injection flow rate verification test procedure. A surveillance test is performed to verify the boron injection flow rate. The exercise is conducted using controlled copies of the Vogtle plant procedures. If a step is performed and the responst of the simulator does not meet the startup test criteria, or if a step can not be performed, or if an alarm annunciates but shouldn't or doesn't annunciatt but should, then a discrepancy report is written.
The simulator response is evaluated against the acceptance criteria specified in the plant procedures.
F0Fet: 06-02 PLANT A.W. V0 GILE SIMUIATOR CERTIFICATION PLAN PAGE 9 0F 11 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/22/88 REVIEWED BY: M. Gibson DATE: 9/22/88 (
APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMUIATOR PERFORMANCE TEST ABSTRACT TITLE : Steady State Test 9 30% Pcwer (06-09)
The Vogtle simulator is initialized to 301 power. BOL, Equilibrius Xe. The simulator is placed in run and allowed to operate for 60 minutes. A heat balance calculation is performed 10 minutes after the simulator is placed in run. The calorimetric is conducted using controlled copies of the Vogtle plant procedures.
If a step is performed and the response of the simulator does not meet the startup test criteria, or if a step can not be performed, or if an alarm annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written. The exercise is terminated after 60 minutes.
The simulator response is evaluated against the acceptance criteria specified in
' the plant procedures and in Section 4.1, Steady State Operation, of ANSI /ANS-3.5-198S.
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FORM: 06-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 10 0F 11 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/22/88 REVIEWED BY: M. Gibson DATE: 9/22/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Steady State Test 9 75% Power (06-10)
The Vogtle simulator is initialized to 75% power. BOL Equilibrium Xe. The simulator is placed in run and allowed to operate for 60 minutes. A heat balance calculation is performed 10 minutes after the simulator is placed in run. The calorimetric is conducted using controlled copies of the Vogtle plant procedures.
If a step is performed and the response of the simulator does not meet the startup test criteria, or if a step can not be performed, or if an alarm
,~~
annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written. The exercise is terminated af ter 60 minutes.
l The simulator respon.e is evaluated against the acceptance criteria specified in the plant procedures and in Section 4.1 Steady State Operation, of ANSI /ANS-3.5-1985.
f FORM: 06-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 11 0F 11 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: M. Pe11echi DATE: 9/22/88 REVIEWED BY: M. Gibson DATE: 9/22/88 APPROVED BY: R. Do rman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT l
TITLE : Steady State Test 6 100% Power (06-11)
The Vogtle simulator is initialized to 100% power. BOL. Equilibrium Xe. The simulator is placed in run and allowed to operate for 60 minutes. A heat balance calculation is performed 10 minutes after the simulator is placed in run. The calorimetric is conducted using controlled copies of the Vogtle plant procedures.
If a step is performed and the response of the simulator does not meet '.he startup test criteria. or if a step can not be pe rformed, or if an alarm
- annunciates but shouldn't or doesn' t annunciate but should, then a discrepancy report is written. The exercise is terminated after 60 minutes.
The simulator response is evaluated against the acceptance criteria specified in the plant procedures and in Section 4.1. Steady State Operation. of ANSI /ANS-3.5-1985.
4 FORM: 07-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OI 10 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: V. MADISON DATE: 9/12/88 REVIEWED SY: M. GIBSON DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERTORMANCE TEST ABSTRACT TITLE : Manual Reactor Trip (07-01)
The Vogtle simulator is initialized to 100% power.BOL. Equilibrius Xe. A manual reactor trip is performed one minute af ter the simulator is placed in run. The simulator is allowed Feedwater flow.
to run with no operator actions except modulating Auxiliary The operator should control feedwater flow as necessary to stebilize SG 1evels above 5%.
place in run. The exercise is terminated 16 minutes after the simulator is The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
FORM: 0/-02 PLANT A.W. V0GTLE SIMULATOR r,ERTIFICATION PLAN PAGE 2 0F 10 FORM TITLE: PERFORMANCE TEST ABSTRACT _ REVISION O PREPARED BY: V. MADISON DATE: 9/12/88 REVIEWED BY: M. CIDSON ,,, DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINIM) DATE: 10/17/88 SIMUIATOR PERFORMANCE TEST ABSTRACT TITLE : Simultaneous Trip of All Feedwater Pumps (07-02)
The Vogtle simulator is initialized to 100% power.BOL, Equilibrius Xe. A trip of bcIh turbine driven Main Feedwater pumps (malfunctions 146A and 146D) is inserted one minute after the simulator is placed in run. The operator shall only perfors the following actions:
o Reduce TDAFW flow to minimum af ter AFW pumps start o Modulate the motor driven auxiliary feedwater pump throttle valves to stabilize SG levels above 5%
The axercise is terminated 11 minutes after the simulator is place in run.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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FORM: 07-02' PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 10 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: V. MADISON DATE: 9/12/88 REVIEWED BY: M. GIBSON DATE: 9/13I88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 i
SIMUIATOR PERFORMANCE TEST ABSTRACT TITLE : ,_ Simultaneous Closure of All Main Sta Isol Valves (07-03)
The Vogtle simulator is initialized to 100% power.BOL. Equilibrius Xe. A simultaneous closure of all aa'i D) is ir.serted onesteso inuteisolationafter thevalvessimulatormalfunction (malfunctions is placed in run. The179A. R. C. and operator shall perf^rs only the ; ,owing actions:
, o Reduce h I flow to miniaua after AFW starts o Modulate the motor iriven auxiliary feedwater pump throstle valves to stabilize SG levels above 5% ,
The exercise is ta:minated 11 minutes after the simulator is piece in run.
The simulator response is evaluated against best estisete judgement where Vogt.1e plant data is not available. ,
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i FORM: 07-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 4 0F f6 FORM TITLE: PERFORMANCE TEST ABSTRACT RESISION 0 PREPARED BY: V. MADISON DATE: 9/12/88 REVIEWED BY: M. GIESON DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) [' ATE : 10/17i88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Simultaneous Trip of All Reactor Coolant Pumps (07-06)
The Vogtle simulator is initialized to 100% power.EOL Equilibrina Xe. A simultaneous trip of all reactor coolant pumps malfunction (malfunctions 46A. B. C. and D) is inserted one minute after the simulator is placed in run. The operator shall perform only the following actions:
z o Reduce TDA)W flow to minimum after AFW starts o Modulate the motor driven auxiliary feedwater pump throttle valves to stabilize SG 1evels above 5%
The exercise is terminated 16 minutes after the simulater is place in run.
The simulator response is evaluated against best estimate judgement where Vogrie plant data is not available.
FORM: 07-02 PLANT A.W. V0 GILE SIMULATOR CERTIFICATION PLAN PAGE 5 0F 10 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: V. MADISON DATE: 9/12/88 REVIEWED BY: M. CIBSON DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
-t SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Single Reactor Coolant Pump Trip (07-05)
The Vogtle simulator is initialized to 30% power.BOL. Equilibrius Xe.
simulator in run and shift the rod control system to manual. A trip of Place the a single reactor coolant pump malfunction (salfunction 464) is inserted one minute after the simulator is placed in run.
The simulator is allowed to run with NO CPERATOR ACTION for the remainder of the exercise.
The exercise is terminated 11 minutes after the simulator is place in run.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available. '
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i FORM 07-02 PLANT A.W. V0GILS SIMULATOR CERTIFICATION PLAN PAGE 6 0F 10 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: V. MADISON _ DATE: 9/12/88 REVIEWED BY: M. GIBSON DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Main Turbine Trip w/o a Reactor Trip (07-06) i
-_9-g The Vogtle simulator is initialized to 30% power.BOL. Equilibrium Xe. A main turbipe trip w/o a reactor trip salfunction (malfunction 98) is inserted one minute after the simulator is placad in run. Once the simulator is placed in run, the rod control system is switched to manual.
The simulator is allowed to run with NO OPERATOR ACTION for the remainder of the exercise. The exercise is terminated 11 minutes af ter the simulator is place in run.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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e FORM: 07-02 PIANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 7 0F 10 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: V. MADISON DATE: 9/12/88 REVIEWED BY: M. CIBSON DATE: 9/13/88 9.PPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/89 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Maximus Rate Power Ramp (1001 to 75%.Back to 100%) 07-07 The Vogtle simulator is initialized to 100% power, EOL, Equilibrius Xe. The r5d control system is placed(verified) in automatic operation after the simulator is placed in run. After a one minute time delay, thw operator shall manually reduce turbine load to approxiiestely 75% (860 MW) over a5 minute period. Eleven minutes after the load reduction, the operator shall raise turbine load to 100% (1150 MW) over a 5 minute period.
The exercisa is terminated 21 minutes after the simulator is place in run.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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FURM: 07-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 8 OF 10 FOR>i TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: V. MADISON DATE: 9/12/88 REVIEWED BY: M. CIBSON DATE: 9/13/88 APPROVED BYt R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMt'I.ATOR PERFORMANCE TEST ABSTRACT TITLE : LOCA with Loss of Of fsite Power (07-08)
The Vogtle simulator is initialized to 100% power. EOL. Equilibrium Xe. A LOCA with.a loss of offsite power is initiated by insertfon of the following malfunctions o 35 (RCS Loop 3 Cold Les Rupture) o 126 and 127 (loss of reserve auxiliary transformers 1NXRAll)
- o 128 and 129 (loss of unit auxiliary transformers INXAA/B)
I The simulator is placed in run and allowed to operate with NO OPERATOR ACTION for 21 sinutes. The operator then places the ECCS in the recirculation mode. The exercise is terminated 26 minutes after the simulator is place in run.
The simulator response is evaluated against best estimate judsesent where Vogtle plant
- data is not available.
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FORM: 07-02 FLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 9 0F 10 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: V. MADISON DATE: 9/12/88 REVIEWED BY M. GIBSON DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT
[
TITLE : Unisolable Main Steam Line Rupture Inside Containment (07-09)
The Vogtle simulator is initialized to 0% power. EOL. Not zero power. A steam line rupture inside containment (salfunction 91) is inserted at 100% sev*rity one minute after the simulator is placed in run. The simulator is allowed to run with NO OPERATOR ACTION for the ' remainder of the exercise. The exercise is terminated 3 minutes after the simulator is pl. ace in run.
\
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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FOM: 07-02 Pl. ANT A.W. V0GTLE SIMULATOR CERTIFICATION PIAN PAGE 10 0F 10 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: V. MADISC'N DATE: 9/12/88 REVIEWED BY: M. GIBSON DATEt 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMU1ATOR PERFORMANCE TEST ABSTRACT TITLE : Slow Primary Sys Depressurization to Sat Cond w/ Stuck SV (07-10) '
The Vogtle simulator is initialized to 100% power. EOL, Equilibrius Xe. A$15w primary systes depressurization salfunction (salfunction 58) is inserted at 20% orie minute af ter the simulator is placed in run. The simulator is allowed to run with NO OPERATOR ACTION for the ressinder of the exercise. The exercise is terminated 21 3
minutes after the simulator is place in run.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
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I FURM: 08-02 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN
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PAGE 1 0F I TITLE: PERFORMANCE TEST ABSTRACT REVISION O PERPARED BY M. Pellechi DATE: 9/23/88 RIVIEWID BY: M. Gibson DATE: 9/23/88 APPROVED BY R . Do rman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Computer Real Time Test The Computer Real Time Test consists of 3 tests. -
In the first test the simulator is initialized to any full power initial condition (IC) and placed in run. The simulator is allowed to run for 30 minutes at steady state conditions. During the 30 minutes, the minisua spare time of the CPU and the l IPU are recorded. If either of the spare times is less than 10%, a discrepancy report is generated.
In the second test three as1 functions are seP.cted which will exercise the major models of the simulator (i.e.. LOCA. Reseter Trip and MSIV Closure). For each malfunction the simulator is initialized to the IC used in the first test and placed in run. The simulator is allowed to run for 10 minutes with the malfunction active.
During the 10 minutes, the minimum spare time of the CPU and the IPU are recorded. If either of the spare times is less t' tan 10%, a discrepancy report is generated.
In the third test 5 valves are selected for valve strokins. The valves selected are froe different systems and have a minimum of 15 second stroke time. The valves are stroked on the simulator and the times recorded. If any actual valve stroke time exceeds its calculated value by more than 1 2%, a discrepancy report is generated.
All of the above tests passed the acceptance criteria.
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- FORMt 08-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PACE 1 0F 1 TITLE: SIMULATORREALTIMkREPORT REVISION O PREFORMED BY: ASIF MEHMOOD DATE: 8/14/88 REVIEWED BY M. 01850N DATE: 8/14/88 SECTION A CPU IPU IC NLhBER SPARE TIME SPARE TIME DR NUMBER (PCFREE) (PCM0DIPU-100) 13 87.3 38.7 SECTION 5 CPU IPU
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MALFUNCTION NLMBER SPARE TIME SPARE TIME DR NUMBER (PCFREE) (PCMODIPU-100)
- 1. 35 85.6 36.7
- 2. 34 86.5 39.0
- 3. 91 86.5 38.7 SECTION C VALVE DATA POOL CALCULATED ACTUAL DR NAME VARIABLE NAME TIME TIME NLMBER
- 1. NV8812A RNV8812A 120 121.0
- 2. HV4084A CDV40884A 120 120.78
- 3. HV4248 COV4248D 50 50.9
- 4. HV7002A CSV9002A 60 60.35
- 5. HV7244 CWV7244 70 69.6
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FORM: 12-01 PLANT A.W. VoGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 uf 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: Rubin.Ciminel DATE: 6/6/88 REVIEWED BY: M. Pe11echt DATE: E13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-01 (LOCA Significant SG Leaks) f Interval: 2nd Rx trip to Termination DRW Number: 1 Comparison Comparison -
Parameter Measure Value
- Przr Level Channel 459A NA TABLE TOP
.i Przr Press 455A NA TABLE TOP Tav Channel 412 NA TABLE TOP '
Tav Channel 442 NA TABLE TOP IR SUR NI-35 NA TABLE TOP TI-413A Loop 1 T-hot NA TABLE TOP TI-4138 Loop 1 T-cold NA TABLE TOP TI-443A Loop 4 T-hot NA TABLE TOP
Probles
Description:
In less than 5 sec., prar level increases from 0% to approximately 90% and Tav soes froe 530 to 602 Des F (affected loop) and fros 530 to 568 Des F (unaffected loop). l Tav should not be off-scale low (< 530 Des F) in either case. Both temperature channels exhibit gyrations. IR SUR response indicates downconer voiding. Wide range temperatures gyrate also.
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FORM 12-01 PLANT A.W. V0GTLE SIMUIATOR CERTIFICATION PIAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: Rubin.Ciminel DATE: 6/6/88 REVIEWED BY M. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause RCS pressure decreases too much, placing the RCS in two-phase conditions. The RCS model cannot handle two-phase conditions realistically.
Corrective Action:
Implement two-phase RCS model.
Impact if not Corrected:
Significant response.
impact - simulator response is very unrepresentative of expected plant
FORMt 12-01 PLANT A.W. VOGTLE SIMULAIOR CERTIFICATION PLAN PAGE 3 OF 3 FORM TITLE:
DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED SY: Rubin.Ciminel DATE: 6/6/88 REVIEWED SY: M. Pellechi DATE: 9/13/88 APPROVED BY: R. Dorman
_ OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807026 was written.
GPC hss contracted to replace the simulator models (Core. Reactor Coolant System.
Steam Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of this discrepancy report by 1/30/90. ,
Results:
FORM 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: A. Guthrie DATE: _6/6/88 REVIEWED BY: M. Pe11echt DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-01 (LOCA significant SG Leaks)
Interval: 2nd Rx trip to Termination DRW Number 2 Comparison Comparison Parameter Measure Value LI-517 SG-1 KR Level NA TABLE TOP LI-501 SG-1 WR Level NA TABLE TOP PI-514A SG-1 Pressure NA TABLE TOP Probles Descriptioat About two minutes after Rx trip, step change of approximately 65% (o to 65%) on KR and of 12% (541 to 66%) on WR occurs for no spparent reason in the affected SG. Note that unaffected SG shows no increase in level. The pressure in the affected SG dropped to 480 psi with Rx trip, about a 600 lb drop.
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FORM: 12-01 PLANT A.W. V0GTLE SIMUIATOR CERTIFICATION PLAN PAGE 2 0F i FORM TITLE: DISCREPANCY RESOLUTION WORRSHEET REVISION O PERFORMED BY: A. Cuthrie DATE: 6/6/88 RTVTEWED BY: M. Pellechi DATE: 9/13/88 APPROVED BY: R . Do rman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
. Cause:
Inadequate SG model.
Corrective Actiont Implement correct 50 sodel.
- Impact if not Correctedt Significant impact - Level responds too quickly, leading trainee to take ingppropriate action. The pressure drop caused MSL isolation causing trainee to depressurize using ARV's.
l FokMr 12-01 PLANT A.W. V0 GILE SIMULATOR GERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BYr A. Cuthrie DATE: 6/6/88 REVIEWED BY: M. Pellechi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolutiont Discrepancy Report number 8807027 was written.
l GPC has contracted to replace the simulator models (Core. Reactor Coolant Systes.
Steam Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of this discrepancy report by 1/30/90.
A P
Resultst
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FORM 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGt: 1 0F 3 FORM TITLE: DISCREPANCY RESOLtTTION WORKSHEET REVISION O PEPFORMED BY: A. Guthrie DATE: 6/6/88 REVIEWED BY M. Pe11echt DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: _10/17/88 Performance Test Procedure: 05-01 (LO A Significant SG 1eaks)
Interval 2nd Reactor Trip to Ters. DRW Number 3 Comparison comparison Parameter Messure Value -
FI-5150 AFW Flow NA TABLE TOP to SG-1
)
Problem
Description:
AFW flow decreased as SG pressure decreases. Flow dropped by 200 sps as pressure 1
dropped 600 psi. The opposite effect is expected.
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FORM 12-01 PLANT A.W. V0GTLE SIMULATOR CERIIFICAll0N PLAN PAGE 2 0F i ORM TITLE: DISCREPANCY RESOLUTION WORK 5HEET REVISION O PERFORMED BY: A. Guthrie DATE: 6/6/88 REVIEWED BY: M. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorman ,_, OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause:
ATW model inadequacies.
Corrective Actions Correct AFW model.
Impact if not Corrected:
Significant impact - may lead trainee to misdiagnose transient.
FORM: 12-01 PLANT A.W. V0GTLE $1MULATOR CERTIFICATION PLAN PAGE 3 of 3 FORM TITLE: DISCREPANCYRESOLUTIONy0RKSHEET REVISION O PERFORMED BY: A. Guthrie DATE: 6/6/88 REVIEWED BY: M. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807028 was written. This DR is prioritized 28 and is scheduled to be repaired by 3/15/89.
a Results
f FOM: 12-01 PIMT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITL/ DISCREPANCY RESOLUTION WORKSHEET REVISION 0 PEkFOMED BY: A. Cuthrie DATE: 6/7/88 REVIEWED BY: M. Pe11echi DATE: 9/13/88 APPROVED BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-02 (LOCA: Inside containment)
Interval SI to Teretnation DRW Number 4 Compartson Comparison Parameter Measure Value .
TI-922 SI Trn B Pump Flow NA TABLE TOP PI-923 51 Pump B Discharge Pressure NA TABLE TOP PI-403 RCS WR Pressure NA TABLE TOP TI-422 Lp-2 T., NA TABLE TOP TI-433 tr-3 T., NA TABLE TOP LI-460 Prz Level NA TABLE TOP Probles Descriptices Major inexplicable changes in RCS terperature. and pressure and Par level are observed. SI parameters are consistent with RCS response.
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1 FOMt 12-01 PLANT A.W. VuGTLE 51MULAfok CERTIFICATION PLAN PAGE 2 of 3 FOM TITI.E DISCREPANCY RESOLUTION WORKSHEET REVISION 0 ;
PERFORMED SY A. Guthrie , DATE: 6/7/88 REVIEWED SY M. Pe11echi DATE: 9/13/88 ,
APPROVED BY: R. Dorean OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause: [
t The RCS model is unrealistic under two-phase conditions.
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Corrective Action: i, t
Implement two-phase RCS model. *
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L Impact if not Corrected: i l
Significant impact
(
t a) major loss of creditability b) will not alle+ proper implementation of E0P's.
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i FORM 12-01 PIANT A.W. V0GTLE SIMt/1ATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLEt DISCREPANCY RESOLUTION WORKSNEET REVISIOM 0 PERFORMED Bf: A. Guthrie DATE: 6/7/88 REVIEWED BY: M. Pe11echi DATE 9/13/88 APPROVED BY: R. Dorean OPERATIONS S!!PERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807029 was written. This malfunction has been removed from training until new models are incorporated.
GPC has contracted to replace the simulator models (Core, Reactor Coolant Systen.
$ team Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of this discrepancy report by 1/30/90. -
Results
FORM 12-01 PLANT A.W. V0GTLE $1MULATOR CERTIFICAIION PLAN PAGE 1 0F 3 FORM TIT 1.E DISCREPANCY RESOLUTION WORK $NEET REVISION O PERFORMED BY: A. Cuthrie DATE: 6/7/88 REVIEWED BY M. Pe11echi DATE: 9/13/88 APPROVED BY: R. t>orman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-08 (Loss of Offsite Power)
Interval: Malfunction to Termination DRW Numbert 5 Comparison Comparison Parameter Measure Value -
DG 1A Watt Meter NA TABLE TOP DG 1A Frequency Meter NA TABLE TOP Probles
Description:
With DC not running, meters read 60Hz. 5250 KV at zero volts. Should all read zero.
,a .
FORMt 12-01 PLANT A.W. V0GTLE SLWLATOR CEE'IFICATION PLAN PAGE 2 uf 3 FORM TITLE DISCREPANCY RESOLUTION WORKSNEET REVISION 0 PEPJORMED BY A. Guthrie DATE: 6/7/88 k'JVIEWED BY M. Pellechi DATE: 9/13/88 i APPROVED BY R. Dorman OPEAATIONS SUPERINTENDENT (TRAINING)
DATE: 10/17/88 Causet i Problem with DG sodel.
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Corrective Actiont !
Examine and fix DG sodel.
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,. Impact if not Correctedt l
Minimal impact on trainina - credibility issue r
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F0fet: 12-01 PLANI A.W. V0 GILE SIMULATOR CERTIFICATION PLAN PAGE 3 vf 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: A. Guthrie DATE: 6/7/88 REVIEWED BY M. Pellecht DATE: 9/13/88 APPROVED BYr R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807030 has written Results:
Discrepancy Report was tested satisfactorily and closed on 7/24/88
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i F0kMt 12-01 PLANT A.W. V0GTLE 51MULATOR CERTIFICATION PLAN ~
FORM TITLE: PAGE 1~uf 1 DISCREPANCY RESOLUTION WORKSNEET REVTSTON O PERFORMED BY: A. Guthrie DATE: _6/7/88 REVIEWED BY: M. Pe11echi DATE: 9/13/08 APPROVED BYt R. Dorman
_ OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 !
t Performance Test Proceduret I
- 05-10 (Loss of Emeraeney Generators)
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Intervalt Malfunction to Termination DRW Number: 6 t Compartson Parameter comparison Measure
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Value - '
DG 1A Frequency Meter ~
NA L TABLE TOP 1
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Description:
1)
With DG not runnlag frequency shows 60 Hz (should be offseale low) .
2)
Af ter salfunction removal DC starts and loads but o
o frequency seter shows large spikes (should be nearly constant) frequency decrease). increases every time load increases on the diesel (should
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FvRM: 12-01 PMNT A.W. V0GTLE 51MVLATOR CERTIFICATION PLAN PAGE 2 uF 3 FORM TITI.E DISCREPANCY RE50LlTTION WORK 5NEET REVISION 0 ,
PERFORMED SY: A. Cuthrie DATE: 6/7/84 REVIEWED BY: M. Pe11echi DATE: 9/13/88 !
APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/44 I
Cause:
Probles with DG model.
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i I I Corrective Action: '
Examine and fix DC model.
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I Impact if not Corrected:
Minimal impact on training - credibility issue.
4
e FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 uf 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 0 PIRFORMED BY: A. Guthrie DATE: 6/7/88 REVIEWED SY M. Pellecht DATE: 9/13/84 APFROVID BY: R. Dorman OFFRATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/as
. Resolution:
Discrepancy Report number 8408030 was written.
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Aesults:
J Discrepancy Report was tested satisfactorily and closed on 7/24/88 k
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f FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FOM TITLE: DISCREPANCY RESOLUTION WORFSHEET REVISION O PERFORMED BY: A. Guthrie DATE: 6/7/88 REVIEWED BY: M. Pellechi DATE: 9/13/88 APPROVCD BY: R. Dorman OPERATIONS S!IPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-10 (Loss of Emergency Generator)
Interval Malfunction to Tersiination DRW Number 7 Comparison Comparison -
Parameter Measure Value DG 1A Watt Meter NA TABLE TOP Problem
Description:
- 1) After malfunction removal. DG starts and loads but watt meter reads zero. It should respond .
- 2) Load 14 indicated even when diesel is not running.
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FORM: 12-01 PLANT A.W. VOGTLE SIMULAT0k tr.Alifluilun FL.AN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: A. Guthrie DATE: 6/7/88 REVIEWED BY: H. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 -
Cause:
Problem with DG model.
I Corrective Action:
Examine and fix DG model.
t Impact if not Corrected:
Minimal impact :.r training - credibility issue.
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PIAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORK 5HEET REVISION O PERFORMED BY: A. Guthrie DATE: 6/7/88 REVIEWED BY: M. Pellechi DATE: 9/13/88 APPROVED BY: R. Lorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807030 was written.
l Results:
Diccrepancy Report was tested satisfactorily and closed on 7/24/88
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-4, p l FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERT UICATION PLAW PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O FERFORMED BY: A. Guthrie DATE: 6/7/88 REVIEWED BY: M. Pe11echi DATE: 9/13/88 APPROVED BY: _R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-14B (Loss of Condenser Level Control)
Interval: Malfunction to Alara DRW Number: 8 Comparison Comparison Parameter Measure Value -
LI 4415 Hotwell Level NA TABLE TOP
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Problem
Description:
Hotwell level decreases, it should increase, t'
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s FORM 12 -O'I~ PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: A. Cuthrie DATE: 6/7/88 REVIEWED BY M. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause:
Problem in condensate model.
Corrective Action Fix cond, model. -
Impact if not Corrected Mittimal impact on training - credibility issue.
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4 FORM 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET RECSION O PERFORMED BY: A. Guthrie DATE: 6/7/88 REVIEWED BY: M. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8804047 was written. This DR is prioritized 38 and is scheduled to be repaired by 9/15/89.
a Results:
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FOR"' 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 0 ,
PERFORNED BY: P. Rubin DATE: 7/20/88 REVIEWED BY: M. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-24A (Par Press Trans. PT 455 Fails)
Interval: Malfunction to Rx Trip DRW Number: 9 Comparison Comparison Parameter Measure Value -
PZR Heaters Bank "D" NA TABLE TOP Problem
Description:
Heaters never turns off with controlling channel failure high (should have been off)
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 7/20/88 REVIEWED BY: M. Pe11echt DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause:
Logic error.
t Corrective Action:
Correct logic.
Impact if not Corrected Minor impact on sin. credibility, i
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE' DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORME0 BY: P. Rubin DATE: 7/20/88 REVIEWED BY: M. Pellechi _ DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 f
Resolution:
Discrepancy Report number 8804052 was written.
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Results:
Discrepancy Report was tested satisfactorily and closed on 6/5/88
FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CFFTIFICATIm or au pggg g 97 3 FORM TITLE:
DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pellechi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-21 (Fuel Cladding Failure)
Interval Identify Failed Fuel DRW Number: 10 Comparison comparison ~
Parameter Measure Value -
Gross Failed Fuel Det.
Alars NA q High rad monitor alaru TABLE TOP NA TABLE TOP Intermediate Rad. Monitor NA TABLE TOP Alarm Probles
Description:
Alams never actuated with a failed fuel element present (should have alarmed)
FORM 12-01 PLANT A.W. V0GTLE SIMULATOR c!.EI1FicAT1uN PIAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin -DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause:
Logic error.
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Corrective Action:
Fix logic.
Impact if not Corrected:
Significant impact - does not allow student to identify failed fuel.
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'l FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8804051 was written.
s Results:
Discrepancy Report was tested satisfactorily and closed on 6/5/88 t i
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FORM: 12-01 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/07/88 REVIEWED BY: M. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-138 (Loss of Instrument Bus IDD1)
Interval Identify Loss of SWGR IDD1 DRW Number: 11 Comparison Comparison Parameter Measure Value Invertor 1DD114 Trouble i Alarm NA TABLE TOP Probles
Description:
Alara never activated as it should have on a loss of IDD1.
, - - -, -------y 3- , - - - - - -- y , ..--,m----- - .-.--.----e,- -.w, e - - - - - -
1 4
FORM: 12-01 PLANT A.W. V0GTLE SIMULAIOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/07/88 REVIEWED BY M. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
, cause:
Logic error.
I.
Corrective Action:
Fix logic.
Impact if not Corrected:
f Minor impact on simulator credibility.
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FORM: 12-01 PLANT A.W. V0GTLE SINULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION W6kxsMEET REVISION O PERFORMED BY P. Rubin DATE: 6/07/88 REVIEWED BY: M. Pellechi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 880404? was written.
Results:
Discrepancy Report was tested satisfactorily and closed on 5/28/88 i
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t FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE:
DISCREPANCY RESOLUTION *'ORX5iiEET REVISION O PERFORMED BY: P. Rubin DATE: 6/07/88 REVIEWED BY: M. Pe11echi DATE: _9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-06A (Failure of Pzr SV/PORVs)
Interval: Rx Trip to ECCS Actuation DRW Number: 12 Comparison Comparison Parameter Measure Value -
PRT Pressure PI 469 NA TABLE TOP 1
Problem
Description:
PRT Pressure responded as if the rupture disc failed at 43 psig. Pressure dropped immediately to O pais. The rupture disc should fail around 100 psig.
10 FORM 12-01 PLANT A.W. V0GTLE SINULATOR CERTIFICATION PLAN PAGE 2 0F 1 FORM TITLE: DISCREPANCY RESOLUTIC" 'a*0RKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/07/88 REVIEWED BY: M. Pellechi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause Unknown Corrective Action:
Investigate and fix. -
Impact if not Corrected:
Moderate impact on simulator credibility.
O
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FORM: 12-01 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WOREANFFT REVISION O PERFORMED BY: E Rubin DATE: 6/07/88 REVIEWED BY: M. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8804037 was written.
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Results:
Discrepancy Report was tested satisfactorily and closed on 5/8/88
i FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLEt DISCREPANCY RESOLUTION WORKSREET REVISION O PERFORMED BY: A. Guthrie DATE: 7/14/88 REVIEWED BY: M. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 06-07A (Power Coefficient)
Interval: Entire test DRW Number: 13 Comparison Comparison Parameter Measure Value .,
P0wer coefficient NA TABLE TOP i
Problem
Description:
The power coefficient measurement did not meet the acceptance criterion for VEGP Procedure 1-6SC-01, ,
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- . , , - - -- ~,--- -r,,- - . - , ,
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7 FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 4 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: A. Guthrie DATE: 7/14/88 REVIEWED BY M. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE _10/17/88 a
Cause Inaccurate constants in core physics routines for cycle 1.
Corrective Action:
4 Reinitialize and recompute physics constants for cycle 2.
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f Impact if not Corrected:
Negligible.
FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSKEET REVISION O PERFORMED BY: A. Guthrie DATE: 7/14/88 REVIEWED BYt M. Pe11echi DATE: 9/13/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807031 was written.
Results:
Discrepancy Report was tested satisfactorily and closed on 9/30/88.
FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTIO" 'JOR.iO"EET REVISION O PERFORMED BY: P. Rubin DATE: 6/6/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: _10/17/88 t
Performance Test Procedure: 05-01 (SCTR)
Interval Rx Trip to Termination DRW Number 14 Comparison Comparison Parameter Measure Value _
SG Blowdown rad monitor NA TABLE TOP Air Ejector rad monitor NA TABLE TOP Main Steam Line rad monitor NA TABLE TOP Probles
Description:
SG Rad monitors increased rapidly causing high rad alaras. SG #1 main stesa line rad son on ERF computer read less than SG 2. 3 and 4. The above responses are Senerally unrealistic as a gradual increase in activity levels is expected.
g *e FORM 12-01 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTTOW WOPTSMEET REVICION O PERFORMED BY: P. Rubin DATE: 6/6/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Causes Model of radiation transport is not high fidelity.
Corrective Action:
Improve fidelity of model.
- Impact if not Corrected:
Significant impact as unrealistic response gives students immediate notification of malfunction insertion.
1 FORM 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE:
DISCREPANCY RESOLUT10W WORKSHEET REVISION O PERTORMED BY: P. Rubin DATE: 6/6/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: _10/17/88 Resolution:
Discrepancy prioritized 2E.
Report numbers 8804033 and 88Cs038 were written. DR 8804035 is GPC has contracted to replace the simulator models (Core. Reactor Coolant System.
Steam Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of discrepancy report 8804035 by 1/30/90. -
Results:
Discrepancy report 8805038 was tested satisfactorily and closed on 8/11/88.
5 FORM: 12-01 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLITTION WORKSHEET REVISION O PERFORMED BY: P. Rubia DATE: 6/7/s8 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-11C (Loss of Electrical Dist. Bus 1NB03)
Interval: Malfunction to Termination DRW Number: 15 Comparison Comparison Parameter Measure Value Rx Trip NA TABLE TOP Problem
Description:
Rx trip occurred on high MSR Drain task levels.
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FORM: 12-01 PLANT A.W. V0GTLE SIMUI.ATOR CERTIFICATION PIAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTTOW WORFSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/7/88 REVIEWED BY M. Pe11echi DATE: _9/15/88 APPROVED BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) OATE: 10/17/88 Cause:
Unknown.
1 Corrective Action:
I Investigate cause of MSR high tank levels.
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i Impact if not Corrected:
Significant impact.
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLEr DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/7/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8804042 was written. This DR is prioritized 2A and is scheduled to be repaired by 6/15/89.
e Results:
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: _6/07/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-13A (Loss of InstnamenLBus 1AD1)
Interval: Identify Loss of SWG 1AD1 DhW Number: 16 Comparison Comparison Parameter Measure Value -
Seq. A Trouble Alara NA TABLE TOP Probles
Description:
Seq. A trouble alara did not activate as it should have on a loss of 1AD1.
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8 FORMt 12-01 PLANT A .k . V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERF0AMED BY: P. Rubin DATE: 6/07/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. borsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 ,
. Cause:
Logic error.
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. Corrective Actions t
Fix logic.
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i Impact if not Corrected:
Minor impact on simulator credibility.
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l FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 ;
FORM TITLE: _ DISCRIPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/07/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 l
Resolutiont s Discrepancy Report number 8807056 was written.
h Resultst Discrepancy Report was testen satisfactorily and closed on 7/31/88.
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FORM: 12-01 Pl. ANT A.W. V0GTLE SIHUI.ATOR CERTIFICATION PLAN PAGE L OF i FORM TITLE: DISCREPANCY RESOLUTION WORKSNEET REVISION O PERFORMED BY: P. Rubin DATE: _7/06/88 REV12WED BY M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 06-09 (Steady State S 30%)
Interval: Entire Test DRW Number 17 Compartson Comparison Parameter Measure Value t Mn. Generator Megawatts NA TABLE TOP Probles Descriptica Megawatts read approximately 240 but should read about 340.
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j FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PIAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 7/06/88 REVIEWED SY: M. Pe11echt DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Ji
, cause Unknown.
Corrective Action:
Investigate Impact if not Corrected:
Significant impact - students see a large power aisaatch.
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FokM: 12-01 PLANT A.W. V0GTLE SIML'LATOR GERIIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTIOl4 WORKSHEET REVISION O PERTORMED BY: P. Rubin DATE: 7/06/98 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution Discrepancy Report number 8807032 was written.
Results:
Discrepancy Report was tested satisfactorily and closed on 9/28/88.
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FORM: 12-01 PLANT A.W. V0GTLE SINULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-23A (Spurious Train T SI Sisnal)
Interval: Malfunction to Termination DRW Number: 18 Comparison Comparison Parameter Measure Value PI-919 SI Pump A Pressure NA TABLE TOP i
i Problea
Description:
$1 Pump A did not actuate (salfunction was spurious B train actuation) but did show diucharge pressure. Pressure should be at ambient pressure.
O
l Fu.u t 12-01 PLANT A.W. VOGTLE 51ML'IATOR LER11FICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORRSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Causet
$1 dynamics program inadequacy.
Is Corrective Action: .
Fix SI dynamics program.
Impact if not Correctedt Moderate impact - compromises simulator creditability.
i FORM: 12-01' PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: _6/08/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATI0h5 SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807033 was written.
4 i
Results:
Discrepancy Report was tested satisfactorily and closed on 8/7/88.
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FORM 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORK 5HEET REVISION 0 PERFORMED BY: P. Rubin DATE: 6/07/88 REVIEWED BY: M. Pe11echt DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/p Performance Test Procedure: 05-07 (Loss of Instrument Air)
Interval: Alarm to 10 psis DRW Number 19 Comparison Comparison Parameter Measure Value ~
TV 110B NA TABLE TOP
~
FV 111A NA TABLE TOP FV 1118 NA TABLE TOP l
I Probles
Description:
These valves remained open on a loss of IA with pressure as low as 10 psig (valves !
should fail closed).
1
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y FORM 12-01 PLANT A.W. VOGTLE SIMULAIOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSREET REVISION O PERFORMED BY: P. Rubin DATE: 6/07/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Causes simulator modeling.
~
s Corrective Actions l'.orrect model.
Impact if not Corrected:
Minor ereining impact since these valves are only for VCT sakeup.
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/07/88 REVIEWED SY M. Pellechi DATE: 9/15/88 APPROVED BY: R. Do,rman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 880403? was written.
Results:
Discrepancy Report tsas tested satisfactorily and closed on 6/26/88.
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FORM 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Frocedure: 05-25B (MS Bypass Valve Header Rupture)
Interval: Malfunction to Termination DRW Number 20 Comparison comparison -
Parameter Measure Value LI-501 SG 1 WR Level NA TABLE TOP LI-504 SG 4 WR Level NA TABLE TOP Problem Descriptiosa I SG WR level responda in same direction as NR due to shrink and swell. (SG WR level should not see aspects of shrink and swell as NR does).
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I FORM: 12-01 PLANT A.W. V0GTLE SIMUI.ATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLEr DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 l l
APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 ,
Cause:
Inadequacies in steam generator dynamics model.
Corrective Action:
Fix SG dynamics program. '
l Impact if not Corrected:
Significant impact - improper training on steam generator dynamics. -
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4 FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807034 was written.
GPC has contracted to replace the simulater models (Core, Reactor Coolant System.
Stesa Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of this discrepancy report by 1/30/90.
i Results:
FORM: 12-01 PL. ANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY R. Ciminel DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-255 (MS Bypass Valve Header Rupture)
Interval: Malfunction to Termination DRW Number 21 Comparison Comparison -
Parameter Measure Value
-- LI-459 Prz Level NA TABLE TOP NI-35D SUR NA TABLE TOP Problee DescriPtical Indication of RCS flashing. (RCS did not and should not flash)
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l FOM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FOM TITLE: DISCRIPANCY RESOLUTION WORKSHEET REVISION 0__
PERFORMED BY: R. Ciminel DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause:
Inadequacies in RCS dynamics model.
l t Corrective Action:
l l Correct RCS dynamics model, i
Impact if not Corricted:
Significant impact - possible misdiagnosis as LOCA.
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION Pl.AN PAGE 3 0F 3 F0kM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: R. Ciminel DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATE: ,9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
. Resolution:
Discrepancy Report number 8807035 was written.
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GPC has contracted to replace the simulator models (Core. Reactor Coolant System. '
Steam Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of this discrepancy report by 1/30/90. -
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i Results: .
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c FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATL: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: Op255(MSBypassValveHeaderRupture)
Interval: St Isol, to Termination DRW Numbert 22 Comparison Comparison Parameter Measure Value PI-514A SG-1 Pressure NA TABLE TOP
, PI-544A SG-4 Pressure NA TABLE TOP Probles
Description:
SG-1 pressure is inconsistent with SG-4 pressure. This pressure abnormality is similar to that seen on SGTR (05-01). (SG #1 and #4 should have similar traces).
FORM: 12-01 PLANT A.W. V0GTLE SIMUI.ATOR CERTIFICATION PLAN PAGE 2 0F 3 l FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pe11echt DATE: 9/15/88 APPROVED BY: R. Dorman !
OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
. Cause:
Inadequacies in sain steam dynamics program.
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Corrective Action:
Fix saia steam dynamics program. i t
i Impact if not Corrected:
Significant impact - may lead to sisdiagnosis (i.e.. it is a SV leak). '
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITi.E DISCREPANCY RESOLUTION WORKSHEET REVISION 0 PERFORMED BY: P. Rubin DATE: 6/08/84 REVIEWED BY M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807027 was written.
GPC has contracted to replace the simulator models (Core, Reactor Coolant System.
Stena Generator and containment) with never "state of the art" models. Model replacement will result in elimination of this discrepancy report by 1/30/90.
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Results:
r FORM 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 UF 3 FORM TITLE: DISCKIPANCY RESOLUTION WORKSHiET REVISION O PERFORMED BYi P. Rubin DATE: 6/07/88 REVIEWED BY: M. Pellecht DATE: 9/15/48 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE 10/17/88 Performance Test Procedure: 05-11F (Loss of Elect. Dist. Bus 18B06) _
Intervalt Malfunction to Termination DRW Number 23 coepa 1 son Cooparison -
Parameter Measure Value CTB C13. Unit Fans 3.4 I 7&8 NA TABLE TOP l
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l Problea Description l All loads continued to operate on loss of Bus 18506 (they shouldn't).
g FORM: 12-01 PLANT A.W. V0GT1.E SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 F0EM TITLEr DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/07/88 REVIEWED BY M. Pe11echt DATE: 9/15/88 APPROVED BY R. borman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
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Cause:
Logic errors.
k Corrective Action Fix logic.
Impact if not Corrected Unrealistic model impacts sisuistor credibility.
t FuM: 12-01 PLANT A.W. V0GTLE SIMUIATOR CERilFICATION PIAN PAGE 3 0F 3 F0f3 TITLE: DISCREPANCY RESOLUTION WORKSREET REVISION O PERFORNED BY P. Rubin DATE: 6/07/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: _10/17/88 Resolution:
Discrepancy Report number 8804044 was written.
Results:
Discrepancy Report was tested satisfactorily and closed on 5/29/88.
FuRM: 12-01 PLANT A.W. V0GTLE SIMbu TOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORK $NEET REVISION O PERFORMED BY: S. Dodds DATE: 6/04/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-288 (PR NI-44 Hi Voltage Failure)
Intervalt Malfunction to Termination DRW Number 24 Comparison Comparison Parameter Measure Value -
NI-44C Flux NA TABLE TOP NI-44C delta Flux NA TABLE TOP s
Probles Descript',on Loss of high voltase to channel should cause delta flux to so to "0". Delta flux doesn't change initially then drifts down as N64 drifts down.
i FukMt 12-01 PLANT A.W. V0GTLE $1MULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLEt DISCREPANCY RESOLUTION WORK $REET REVISION 0 PERFORMED BY: S. Dodds DATE: 6/08/88 REVIEWED BY M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Causes Possible loss of only one (upper / lower) detector, but should not stay the same value.
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Corrective Action:
.: Investigate model and malfunction guide to determine what has failed and whether delta flux should be zero.
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Impact if not Correctedt Minor confusion on channel failure evaluation by students I
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FORMr 12-01 PLANT A.W. V0GTLE $1ML1.ATOR CERTIFICATION PLAN PAGE 3 or 3 FORM TITLEt DISCREPANCY RESOLUTION WORKSNEET REVISION 0 1
PERFORMED 8Y: S. Dodds DATE: 6/08/88 REVIEWED BY M. Pellechi DATE: 9/15/88 l APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/86 i
Resolution:
Discrepancy Report number 8807036 was written.
I Results:
Discrepancy Report was tested satisfactorily and closed on 7/24/88.
t FORM: 12-01 PLANT A.W. V0GTLE $IMtTLATOR CERTIFICATION PLAN PAGE 1 of f FOPM TITLEr DISCREPANCY RESOLL' TION WORKSNEET REVISION O PERTORMED BY: P. Rubin DATE: 6/07/44 REVIEWED Bf M. Pe11echi DATE: 9/15/8e APPROVED BY: R. Dorman OPERATIONS SL*PERINTENDENT (TRAINING) DATE: 10/17/44 Performance Test Procedure: 05-11E (Loss of Elec. Dist. Sua 1N809)
Interval Malfunction to Termination DRW Number 25 Cospartson Coopar1 son Parameter Measure Value
, MS 2621
( (CB Preaccess Fan 2) NA TARLE TOP Problee
Description:
CE treaccess Fan 2 starts (it shouldn't): however it is lost when tua 19806 is lost (it shouldn't).
FORM; 12-01 PLANT A.W. V0GTLE SIMt1Af0R CERTIFICAtluN PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORK $NEET REVISION 0 TERF0AMID BY P. Rubin DATE: 6/07/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88
, APPROVED BY: R. Dorsan OPERATIONS SI/PERINTENDENT (TRAINING) DATE: 10/17/88 Cause !
Logic error. '
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Corrective Action:
Fix logic.
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!spect if not Corrected l'nrealistic model impacts simulator credibility.
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/07/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPEsINTENDENT (TRAINING) DATE: 10/17/88
, Resolutions i Discrepancy Report number 8804044 was written.
Results'. ;
Discrepancy Report was tested satisfactorily and closed on 5/29/88.
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FURM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN FORM TITLE: PAGE 1 0F i DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAININO) DATE: 10/17/88
. Performance Test Procedure:
05-29A (Loop Press Transmitter PT 438 Fails Hish)
Interval: sialfunction to Termination DRW Number 26 Compartson Parameter Comparison Measure
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Value PI-438 WR Press (Lp 4) NA TABLE TOP Problem Description Meter fails high, out SPDS shows PI-438 and PI-408 as the same failed high). .
(SPDS should show one
_ _ _ , _ _ - _ , , - - - ' ' ~ ~ ' ' ' ' ' ' ~
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FORM 12-01 PLANT A.W. VOGTLE SIMULAT0h CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATE: 9/1S/88 APPROVED BY: R. Do rman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
. Cause:
SPDS looks at wrong input.
Corrective Action:
Fix SPDS input.
sect if not Corrected:
mate impac. - may cause operator confusion.
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FORM: 12-01 PLANT A.W. VOGTLE SINULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPRG~iED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807037 was written.
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Results:
Discrepancy Report was tested satisfactorily and closed on 7/31/88.
FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-29A (Loop Press Transmitter PT 438 Fails High)
Interval: Malfunction to Termination DRW Number: 27 Comparison Comparison Parameter Measure Value -
PI-614 RHR Pump A Discharge Press NA TABLE TOP l
i Problem
Description:
With RNR pump secured and suction valve closed, discharge pressure reads constant 350 psi (should decrease and/or follow RCS pressure).
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 !
APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
. Causes Deficiency in RHR dynamics model. >
Corrective Action:
Fix RHR dynamics model.
Impact if not Corrected:
Minimus - simulator credibility issue.
FORM: 12-01 PLANT A.W. V0 GILE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATE: E15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 4
Resolution:
Discrepancy Report number 8807038 was written.
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Results:
Discrepancy Report was tested satisfactorily and closed on 7/31/88.
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FORM: 12-01 PLANT A. W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 10F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED.BY: R. Ciminel DATE: 6/08/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-29A (Loop Press Transmitter PT 438 Fails High)
Interval Malfunction to Termination DRW Number 28 Comparison Comparison -
Parameter Measure Value TI-413B Loop 1 Tc NA TABLE TOP Probles Description With loss of shutdown coolins, temperature goes down (should ineresse).
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I FORM: 12-01 PLANT A.W. V0GTLE SLMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O _
PERFORMED BY: R. Ctainel DATE: 6/08/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY:.'*. Dorman OPERATIONS SUPERINIENDENT (TRAINING) DATE: 10/17/88 Cause RCS dynamics problem.
Corrective Action:
Fix RCS dynamics model.
Impact if not Corrected:
Significant impact - does not properly portray RCS dynamics.
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l FORM: 12-01 PLANT A.W. V0GU.E SIMJI.AIOR CERTIFICAIION PLAN PAGE 3 UF i FORM TITLE: DISCREPANCi' RESQLUTION WORKSHEET REVISION O PERFORMED BY: R. Ciminel DATE: Q08/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807041 was written.
GPC has contracted to replace the simulator models (Core. Reactor Coolant System.
Steam Generator and Containment) with newer "state of the art" models. Model replicement will result in elimination of this discrepancy report by 1/30/90.
Results:
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLLTTION WORKSHEET REVISION O PERFORMED BY P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17I88 Performance Test Procedure: 05-29F (SG Level Transmitter LT 519 Fails)
Interval: Malfunction to RX Trip DRW Number 29 Comparison Comparison Parameter Measure Value LI-519 NA TABLE TOP i
Probles
Description:
Parameter remained at 501 level and decreased when reactor tripped. (Should have failed high)
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FORM: 12-01 PLANT A.W. VOGTLE SLMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVTSION O PERFORMED BY: P. Rubin DATE: 0/08/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause:
Unknown.
Corrective Action:
None.
Impact if not Corrected:
Minimal - Control board indication and level control systes respond correctly.
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4 FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/08/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APEROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807039 was written.
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Results:
Discrepancy Report was tested satisfactorily and closed on 8/07/88.
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i FORM: 12-01 PLANT A.W. V0 GILE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/15/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 _
APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-118 (Loss of Elect. Dist. Bus 1BA03)
Interval: Malfunction to Termination DRW Number 30 Comparison Comparison _
Parameter Measure Value
.- HS 1BA0306 Brk NA TABLE TOP
Description:
Breakers ressined closed (should have tripped).
. FORM: 12-01 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITL,E: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/15/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Causes Logic error.
Corrective Action:
Fix logic.
Impact if not Corrected:
Unrealistic model impacts simulator credibility.
9 FORM: 12-01 PIANT A.W. V0GTLE SIMULATOR CERTIFICATION PIAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLlrTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/15/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman ,. OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807055 was written.
Resultst Discrepancy Report toss tested satisfactorily and closed on 7/24/88.
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: S. Dodds DA E: 6/09/88 REVIEWED BY: H. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-26 (FW Line 2 Rupture Inside Containment)
Interval: SI to Termination DRW Number: 31 Comparison Comparison Parameter Hessure Value -
LI-502 SG 82 WR Level NA TABLE TOP Probles
Description:
Following feedline isolation #2 SG WR level began increasing and eventually passed the level in the unaffected SG. (Should have decreased to zero) 8
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FORM: 12-01 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 !
FORM TITLE:
DISCREPANCY RESOLUTION WORKSHFET REVISION O PERFORMED BY: S. Dodds DATE: 6/09/88 REVIEWED BY: M. Pellechi DATE: _9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: _10/17/88 Cause:
Modeling of FW rupture selfunction.
Corrective Action:
Fix modeling.
l Impact if not Corrected: '
Significant impact. t l
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i FORM: 12-01 PIANT A.W. V0GTLE SIMULATOR CERTIFICATION PIAN PAGE 3 0F 3 FORM TITLE: DTSCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: S. Dodds DATE: 6/09/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resoluti.on:
Discrepancy Report number 8807040 was written.
GPC has contracted to replace the simulator models (Core. Reactor Coolant System.
Steam Generator and Containment) with newer "state of the area models. Model replacement will result in elimination of this discrepancy report by 1/30/90.
Results:
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g FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/15/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-118 (Loss of Elec. Dist. Bus 1BA03)
Interval Malfunction to Termination DRW Number 32 Comparison Comparison -
Parameter Measure Value
Description:
CCP 18 could be manually started (it shouldn't be).
FORM: 12-01 PLANT A.W. VOGTLE SIMULAIOR CERIIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/15/88 REVIEWED BY M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause:
Logic error.
Corrective Action:
Fix logic.
Impact if not Corrected:
Unrealistic model impacts simulator credibility.
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fukM: 12-01 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/15/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERAT'ONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8804041 was written.
1 Results:
Discrepancy Report was tested satisfactorily and closed on 5/29/88.
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g FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLITTION WORKSHEET REVISION O PERFORMED BY: S. Dodds DATE: 6/09/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R . Do rman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure Generic Interval: Malfunction to Termination DRW Number 33 Comparison Comparison -
Parameter Measure Value MS-FR-4347 NA TABLE TOP Throttle Steam Flow i
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t Probles Descriptions i Parameter reads 16 MPPH at all reactor power levels. (Should vary with power) l e
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i FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FOP.M TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: S. Dodds DATE: 6/09/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAININC) DATE: 10/17/88 Cause Unknown.
T Corrective Action:
Check IV Point.
l Impact if not Corrected:
Minimal - CB recorder responde correctly, t
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FORM; 12-01 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: S. Dodds DATE: 6/09/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
, Resolution:
Discrepancy Report number 8807042 was written.
Resultst Discrepancy Report was tested satisfactorily and closed on 7/24/88.
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FORMS 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED Ba's S. Dodds DATE: 6/09/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-308 (Train A Cont Spray Auto Actuation Failure Interval RX Trip to Termination DAW Number: 34 Comparison Comparison Parameter Measure Value .
PI-514 SG #1 Press. NA ANSI 3.5 1
Probles
Description:
50 #1 pressure decreased to O psis following Rx trip and SI. This test was initiated by inserting a cold les rupture on Loop 3. (Should have followed SG pressure for unaffected SG's). i I
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70RMs 12-01 PLANT A.W. V0GTLE SIMULATUR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WOPKSHEET REVISION O PERFORMED SY: S. Dodds DATE: 6/09/88 REVIEWED BY: M. Pe11echi _ DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 3 Cause:
Unknown.
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Corrective Action:
Investigate and fix.
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Impact if not Corrected:
t Significant impact - could lead operators to misdiagnose a loca.
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FURM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCRIPANCY RESOLUTION WORKSHEET REVTSION O PERFORMED BY: S. Dodds DATE: 6/09/88 REVTEWED BY: M. Pe11echt DATE: 9/15/88 APPROVED BY: R. Dorman _ OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 l
Resolution:
Discrepancy Report number 8807016 was written. This TIR was closed oc 9/26/88 due to its similarity to DR 8709003. DR 8709003 is now linked to this DRW.
GPC has contracted to replace the simulator models (Core, Reactor Cocle.nt Systes.
Steam Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of discrepancy report 8709003 by 1/30/90.
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Results:
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FORM 12-01 PLANT A.W. VOCTLE LIMULAIOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE:
DISCREPANCY RESOLUTION WORK 3HEET REVil PION O PERFORMED BY: S. Dodds DATE: 6109/88 RIVIEWID BY: M. Pellechi DNIE: 9/15/88 APPkOVED BY: R. D,orman OPERAIIONS SUPL dNTENDENT (TRAINING) DATE: 10/17/88 4
Performance Test *rocedure g -30C (Train A SI Manual Actuation Failure)
Interval: Malfunction to Termination DRW Number 35 Cooparison Cosparison Parameter Measure Value
. PI-923 SI Pump 18 NA TABLE TOP Disc. Press.
Problem
Description:
Indicates discha. <toure with pump not running. (Should read zero).
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FORM 12 P1 ANT A.W. YOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: S; _Dodds DATE: 6/09/88 REVIEWED BY M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
. Cause Modeling error.
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Corrective Action:
Correct model.
Impect if not Corrected:
Moderate.
f FORM 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: S. Dodds DATE: 6/09/88 REVIEWED BY M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
4 Discrepancy Report number 8807033 was written.
d Results:
Discrepancy Report was tested satisfactorily and closed on 8/7/88.
FOM: 12-01 FLANT A.W. V0 GILE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 6/15/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorean OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-118 ( Loss of, Elect. Dist. Bus. IRA 03)
Interval Malfunction to Termination DRW Number: 36 Comparison Comparison -
Parameter Measure Value NSCW Pump 46 NA TABLE TOP Problem Descriptiva:
Pump 6 started and would not trip (it should not restart).
F UR.w : 12-01 Pl. ANT A.W. V0GTLE 51MUI.ATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLEr DISCREPANCY RESOLUTION WORJtSNEET REVISION 0 PERTORMED BY: P. Rubin DATE: 6/15/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause Logic error.
Corrective Action:
Fix logic.
Impact if not Corrected:
Minor impact - simulator credibility.
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f uM: 12-01 FLANT A.W. V0GTLE SIMULATOR CERIIFICATION PLAN PAGE 3 UF 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSNEET REVISION O PERFORMED BY: P. Rubin DATE: _6/15/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8804041 was written.
t Results:
Discrepancy Report taas tested satisfactorily and closed en 5/29/88.
t FORM 12-01" PLANT A.W. V0GTLE SIMllLATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: S. Dean DATE: 7/20/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BYt R. Dorean OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-24A (Par Press Transeitter PT 455 Fails)
Interval Malf Removal to Termination DRW Number: 37 Cosparison Cooparison -
Parameter Measure Value Prtr Press NA TABLE TOP e PI-456 I
Problee
Description:
With SI filling the pressuriser and PORV's and sprays closed the pressure should recover rapidly even though the water in the par is subcooled. It remained stable.
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLLTION WORKSHEET REVISION O PERTORMED BY: S. Dean DATE: 7/20/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SLTPERINTENDENT (TRAINING) DATE: 10/17/88 Cause:
Poor pressuriter model when being refilled.
Corrective Action:
Correct modeling. '
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Impact if not Corrected:
Sisnificant impact - will teach students that a fast refill of the pressuriter will have little effect on pressure and could result in causing overpressure protection to actuate.
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FORMt 12-01 PLAMI A.W. VOGTLE SIMULATOR CERTIFICATION PIAN PAGE 3 0F 3 FORM TITLEr DISCRIPANCY RESOLUTION WORKSMRET REVISION O PERTORMED BY: S. Dean DATE: 7/20/88 REVIEWID BY: M. Pe11echi DATE: 9/15/88 APPROVED BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
, Resolution Discrepancy Report number 8807043 was written.
GPC has contracted to replace the simulator models (Core. Reactor Coolant System.
Steam Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of this discrepancy report by 1/30/?0.
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r FORM 12-01 PLANT A.W. VOCTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE DISCREPANCY RESOLUTION WORK $NEET REVISION O PERFORMED BY: S. Dean DATE: 7/20/48 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 m
Performance Test Procedure: 05-18 (I.oss of all Feedwater)
Interval: Malfunction to Rx Trip DRW Number 38 r
Comparison Comparison '
Parameter Measure Value i
s Problee Descriptions On loss of FW 'o a SG at 100% load a significant swell in NR level should occur.
Level decreases during the trustent. '
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x TORM 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BYt S. Dean DATE: 7/20/88 REVIEWED BY M. Pellechi DATE: _9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
, Cause:
SG medel.
1 Corrective Action Correct model for shrink / swell effects.
Impact if not Corrected:
Significant impact - Rx trips may occur in the plant due to students not practicitig control of SG 1evels with shrinkiswell.
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: S. Dean DATE: _7/20/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807044 was written.
GPC has contracted to replace the simulator models (Core. Reactor Coolant System.
Steam Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of this discrepancy report by 1/30/90. -
Results;
FORM 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE! DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFukMED BY: S. Dean DATE: _6/29/88 _ REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERA 1 IONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 07-01 (Manual Rx Trip)
Interval: Malfunction to Tereination DRW Number: 39 Comparison Comparison -
Parameter Measure Value Przr Level NA TABLE TOP Przr Pressure NA TABLE TOP Przr Temperature NA TABLE TOP r
Probles Descriptioot i Safety Injection actuated on 14w Pressure approximately 25 seconds after a manual reactor trip. (81 should not actuate on normal trips). Pressuriser filled to 100%
due to Safety Injection Flow. Pressuriter pressure decreased to (17004. Decreased to 610*F due to pressuriser pressure response to trip.
FORM: 12-01 PLANT A.W. V0GTLE SIMULATUR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O ,
P PERFORMED BY: S. Dean DATE: 6/29/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 l APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 l
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. Cause: ,
Pressurizer Model.
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i Corrective Actions Correct pressurizer pressure response to reactor trip.
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Impact if not Corrected:
Significant impact - say cause incorrect response by operators to an uncomplicated :
reactor trip. '
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i FukM 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 uf 3 ;
FORM TITLE: DISCT.EPANCY RESOLUTION WORKSHEET REVISION 0 PERFORMED BY S. Dean DATE: 6/29/88 REVIEWED BY M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 !
Resolution:
Discrepancy Report number 8805009 was written.
GPC has contracted to replace the simulator models (Core. Reactor loolant h : tem. l Steam Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of this discrepancy report by 1/39/90.
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Results:
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g FuM 12-01 PLANT A.W. V0GTLE SIl W TOR CERTIFICATION PLAN PAGE 1 0F 3 FOM TITLE: DISCREPANCY Tr30LUTION WORKSHEET REVISION O PERF0MED BY: 5. Dean DATE: 6/29/88 REVIEWED BY: M. Pe11echt DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: Jo/17/88
. Performance Test Procedure: 07-01 (Manual Rx Trip)
Interval Malfunction to Termination DRW Number 40
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Comparison Comparison .
Parameter Measure Value Stena Flow NA TABLE TOP
?
Probles
Description:
Steam Flow Channel 512A spiked upward when reactor tripped. (should just decrease).
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I FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F J F0kM TITLE: DISCREPANCY RESOLUTION WORRSHEET REVISION 0 PERFORMED BY: S. Dean DATE: 6/29/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause Unknown - any be caused by steam dumps, i
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Corrective Action:
Correct reason for steam flow exceeding 100% value on Rx trip.
Impact if not Corrected:
Insignificant impact on training.
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3 FORM 12-01 PIANT A.W. V0GTLE SI.WLATOR CERTIFICATION PLAN PAGE 3 0F 3 l l
FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 0 PERFORMED BY: 5. Dean DATE: 6/29/88 RFVIEWED BY: M. Pe11echt DATE: 9/15/88 i APPROVED BY: R. Dorman '
OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
No corrective action necessary. ,
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FokM 12-01 PLANT A.W. V0GTLE 51MULA10k' CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORR$HEET REVISION O PERFORMED BY: S. Dodds _ DATE: 7/20/88 REVIEWED BY: M. Fellechi DATE: _9/15/88 <
APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/68 6
Performance Test Procedure: 05-18 (Loss of All Feedwater)
Interval: Malfunction to Rx Trip DRW Number 41 P
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j Comparason Comparison Parameter Measure Value 4
Stese Flow NA TABLE TOP e
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Probles
Description:
on Rx Trip. Steam Flow spikes up some when it should not increase at all.
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i FOM: 12-01 PLANT A.W. V0GTLE SINULATOR CERTIFICATION PLAN PAGE 2 of 3 F0kM IITLEt DISCREPANCY RESOLUTION WORKSNEET REVISION O PERF0MED BY: L_(odds DATE: 7/20/88 REVIEWED BY M. Pellechi DATE: 9/15/68 APPR(WID BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause Unknown.
Corrective Action: .
Determine reason for increase and correct.
Impact if not Corrected:
Minimal impact - not noticeable to students.
FORM: 12-01 PLANT A.W. VoGTLE SIMULATOR CERTIFICATION Pl.AN PAGE 3 of 3 ,
FORM TITLE: DISCREPANCY RESOLUTION WORKSNEET REVISION O PERFORMED BY: S. Dodds DATE: 7/20/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 !
APPROVED BY R. Dorman CPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/8s i
. Resolution Corrective action is not necessary.
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Results: ,
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70 $ 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERTORMED BY: S. Dodds DATE: 7/20/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAININO) DATE: 10/17/88 Performance Test Procedure: 05-18 (Loss of All Feedwater)
Interval: Rx Trip To Termination DRW Number: _42 i comparison comparison Parameter Measure Value
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PRT Temp NA TABLE TOP PRT Press NA I TABLE TOP PRT Level NA TABLE TOP PORV Temp NA TABLE TOP SV Temp NA TABLE TOP t
Probles Description Loss of FW Transient should heat up the RCS causing Przr level and press to increase and PORV's open. Prar pressure hardly went up prior to trip then went down and slowly returned to normal (w/ no opening PORv's). Above listed parameters did not change as the PORVs didn't open.
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERaIFICATION PLAN PAGE 2 or 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O t PERFORMED BY: S. Dodds ., DATE: 7/20/08 REVIEWED BY: M. Pe11echt DATE: 9/15/88 APPROVED BY: h_Doriaan _ OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 ,
a Cause: '
Large cooldown en RCS trip with SG 1evels seeming to decrease too slowly.
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j Corrective Action:
L Review Przr model and SG model. '
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l Impact if not Corrected i
Significant impact - loss of TW transient on simulator would confuse students for ene !
in the plant. (
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q-4 FORM: 12-01 PLANT A.W. VOGTLE SIMULAIOR CERTIFICATION PLAN PAGE 3 0F 3 FOPM TITLE: DISCREPANCY RE50Ltff10N WORKSHEET REVISION O PERFORMED BY: S. Dodds DATE: 7/20/48 REVIEWED BY: M. Pellecht DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
. Resolution:
Discrepancy Repc7t number 8805004 was written.
GPC has contracted to replace the simulator acdels (Core. Reactor Coolant System.
Steam Generator and Containment) with newer "state cif the art" models. Model replacement will result in clinination of this discrepant:y report by 1/30/90.
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Results l
i FokM: 12-01 PLANT A.W. V0GTLE SIMUI.ATOR CERTIFICATION PIAN z ,. PAGE 4 0F 3 FORM TITLEr DISCREPANCY RESOLUTION WORKSHEET REVISION O [
PERFORMED BY: S. Dodds DATE: 7/20/88 REVIEWED BY: M. Pe11echi DATE: _9/15/98 APPROVEL LY: R._ Dorsan
_ OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 k 4
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'i FvM: 12-01 PLANT A'.W. V0GTLE SIMUI.ATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O ;
PERT 0MED BY: S. Dodds DATE: 7/20/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman ,.
OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 F
. Performance Test Procedure: 05-18 (Loss of All Feedwater)
, Interval: Rx Trip to Termination DRW Number 43 l
Compar19on Comparison Parameter Measure Value SG WR Level NA TABLE TOP i
,* robles Descriptions in total loss of /W the WR SG 1evels seem to decrease so slowly af ter the trip that SG dry out would take over one hour. (Should rapidly decrease to zero).
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A FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: S. Dodds DATE: 7/20/88 REVIEWID BY: M. Pellecht DATE: 9/15/88 APPROVED BY: R. Dornan OPERATIONS SUPERINTENDENT (TRAINING) DATF.: 10/17/88
. Cause:
SG Model may not count the reduction of mass in SG vice level (secendary side) when level is low enough to uncover the tubes.
Correctivo Actiont Correct modeling of SG.
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Impact if not Corrected:
Significant impact -
Allows too such operator time prior to plant (RCS) heat up/repressuritation and feed / bled method of cooling.
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(9 FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN
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PAGL ) 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: S. Dodds DATE: 7/20/88 REVIEWED SY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
. Resolution:
Discrepancy Report number 8807057 was written.
GPC has contracted to replace the simulator models (Core. Reactor Coolant System.
Steam Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of this discrepancy report by 1/30/90.
4 Results:
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FORM 12-01 PLANT A.W. V0GTLE SIMULAloR CERTIFICATION PLAN PAGE 1 0F 3 '
FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: s. Dean DATE: 6/29/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 h
i Performance Test Procedure: 07-02 (Simultaneous Trip of All Feedwater Pumps)
Interval: Modiffeation to Termination DRW Number 44 )
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compartson Comparison -
Parameter Measure Value ;
Przr Pressure NA TABLE TOP i
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Przt Temp j NA TABLE TOP ;
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i Probles
Description:
Pressurizer pressure did not respond to 101 insurge due to RCS heatup. Pressure held at approximately 2228 psts during insurge. Also pressurizer vapor temperature did not respond to insurge. (Press should increase with insurse).
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PA,GE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED SY: S. Dean DATE: 6/29/88 REVIEWED 2Y: M. Pe11echi DATE: 9/15/88 APPROVED SY: R. Dorsan CPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause Pressurizer model.
Corrective Action:
Correct modeling to respond properly to insurges into pressurizer.
Impact if not Corrected:
Significant impact - say cause inadequate operator response to pressurizer level transient in plant.
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FORM: 12-01 PLANT A.W. VUGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLEr DISCREPANCY RESOLUTION WORKSHEET REVISION 0 PERFORMED BY: S. Dean DATE: 6/29/88 !
REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. borman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/58 ,
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Resolution: t
- Discrepancy Report number 8807045 was written.
4 GPC has contracted to replace the simulator models (Core Reactor Coolant Systes. !
Steam Generator and Containment) with aewer "state of the art" models. Model i replacement will result in elimination of this discrepancy report by 1/30/90.
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I FORM: 12-01 PLANT A.W. V0GTLE SIMU1.ATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: S. Dodds DATE: 7/20/08 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPT.RINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-20 (Rods fail to move on A/M Desand)
Interval Verify Rx Trip DRW Number: 45 Comparison Comparison Parameter Measure Value -
Teed Flow NA TABLE TOP Steam flow NA Tall.E TOP Probles
Description:
Reactor is annually tripped during test. Both steam and feed flows spike up prior to decreasing on trip.
FORM 12-01 PLANT A.W. V0GTLE SIMVLATOR CERTIFICATION PLAN PAGE 2~0F 3 TORM TITLEr DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: S. Do6ds DATE: 7/20/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APEROVED BY: R. borman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Causet SG/FW Model Corrective Action:
Correct ):odel.
Impact if not Corrected:
Minimal impact - Short ters and not very lerse in magnitude.
FORM: 12-01 PLANT A.W. V0GTLE $1MUIATOR CERTIFICAfl0N PLAN PAGE 3 0F 3 i FORM TITLE! DISCREPANCY RESOLUTION WORK $NEET REVISION O PERFORMED BY: S. Dodds DATE: 7/20/44 REVIEWED BY: M. Pe11echi DATE: 9/15/88 ;
APPROVID BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/48 i
Resolution:
No corrective action is necessary as it is not noticeable to students. I i
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FORM 12-01 PLANT A.W. V0GTLE SIMUIATOR CERTIFICATION PIAN PAGE 1 0F !
FORM TITLE: DISCREPANCY RES0ttTTION WORKSHEET '
REVISION 0 PERFORMED BY: S. Dean DATE: 6/30/88 REVIEWED BY: M. Po11echt DATE: 9/15/98 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 -
I Performance Test Procedure: 07-04 (Simultaneous Trip of All RCPs) '-
Interval: Malfunction to Termination DRW Number: 46
, Comparison Comparison -
Parameter Measure Value 1
i Loop 1 Flow NA TABLE TOP Loop 2 Flow l NA TABLE TOP !
Power Range Flux NA TABLE TOP !
IR SUR NA TABLE TOP -
SG 1 Steam Flow NA TABLE TOP SG 4 Steam Flow NA TABLE TOP i r
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Probles Descriptiost l 3 All parameters listed above spiked up at time of RCPs trip /RX trip. Power Ranae i spiked from 99.6% to 102.51. RCS loop flow spiked to 1011. IR SUR spiked to +0.3 DPM. Cteam flows spiked from 3.4E6 8/hr. to 3.9E6 8/hr. I r
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FORM: 12-01 PLANT A.W. V0GTLf SINCLATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLEr DISCREPANCY RESOLUTION WORK $NEET REVISION O PERF0MID BY: S. Dean DATEt 6/30/08 REVIEWED BY: M. Pellechi DATE: 9/15/98 APPROVED BY: R. Dorman OPERATIONC SUPERINTENDENT (TRAINING) DATE: 10/17/88 s'auset Unknown.
Corrective Action:
Correct probles that causes parameters to spike at time of RX Trip.
Impact if not Corrected:
Insignificant to Simulator Training since spike it, short in time duration.
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i ERM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PIAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERTORMED BY: 5. Dean DATE: 6/30/88 REVIEWED BY: M. Pe11echt DATE: 9/15/48 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807046 was written.
GPC has contracted to replace the staulat, models (Core. Reactor Coolant System.
Steam Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of this discrepancy report by 1/30/90.
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Results:
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TOM: 12-01 Pl. ANT A.W. V0GTLE SIMUI.ATOR CERTIFICATION PLAN PAGE 1 OF 3 F0M TITLE: DISCRIPANCY RESOLUTION WORKSHEET REVISION O PERF0MED BY: L._Guthrie DATE: 7/13/88 REVIEWED BY M. Pe11echt DATE: 9/15/88 i
APPROVED BY: R. Dcrean OPERATIONS SUPERINTENDENT (TRAINING) DATE: g17/88 l
i Performance Test Procedure: 06-078 (Rod Worth Measurement)
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Interval: Rod Worth Determination DRH Number: 47 l
Coepar1 son Coopartson Parameter Measure Value -
Differential loron Worth -10.09 + 1 peelppe -0.02 pee /ppe 1
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Problee Descriptions ,
Differential boron worth does not meet acceptance criterion for cycle 1. '
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FORM 12-01 PLANT A.W. V0GTLE SIM5At0R CERTIFICATIdil PLAN PAGE 2 UF 3 f FORM TITLE: DISCREPANCY RESOLUTION WORKSNEET REVISION O f PERFORMED BY: A. Cuthrte DATEt 7/13/88 REVICVED BY: M. Pellechi DATE: 9/15/a8 l t
APPROVED BY: R. Dorman CPEPATIONS SL'?tRINTENDENT (TRAINING) DATE: 10/17/84 i f
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, cause: i Inaccurate physics constants in core physics routines. +
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Re-initialize core programs for cycle 2.
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h Nesligible, f
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I FORM: 12-01 PLANT A.W. V0GTLE SINtl1.Af0R CERTIFICATION PIAN PAGE 3 0F 3 FORM TITLEr DISCREPANCY RES01.t' TION WORKSHEET REVISION 0 [
FERFORMED BY: A. Cuthrie DATE: 7/13/84 REVIEWED BY M. Pe11echi _
DATE: 9/15/88 l APPROVED BY: R. Dorman
. OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/84 Resolution: '
Discrepancy Report number 4807054 was written. !
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FOR.1: 12-01 P! ANT A.W. V0GTLE SIMUL.ATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCRIPANCY RESOLUTION WORK $NEET REVISION 0 j PERFORMF.D BYt 5. Dodds DATE: 7/20/88 REVIEWED BY: M. Pe11echi DATE: _9/15/98 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 06-01 (Plant Startup to Not Standby)
Interval: Plant Heatup to NOT. NOP DK4 Number: 48 Comparison Comparison Parameter Measure Value -
Prtr Level NA Tall.E TOP !
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Probles .,escriptions Charging / letdown doesn't seem to match up when CCP is used vice PDP. Charging control i valve does not seem to respond. Operator must periodically adjust Seal Injection to control charging flow and Prar level, s
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FuRM: 12-01 F1. ANT A.W. V0GTLE SIMt'LATOR CERTIFICATION PLAN PAGE 2 of 3 l FORM TITLE DISCREPANCY RESOLL* TION WORKSHEET REVISION O PERT 0hMED BY: 5. Dodds DATE: 7/20/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BYr R. Dorsan OPERATIO%'$ $UPERINTENDENT (TRAINING) DATE: 10/17/88
. Cause Charginc flow control valve model.
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Corrective Action:
Correct model on FV-121.
Impact if not Corrected:
l Moderate impact - Students learn to control przr level using the sesi injection flow l control valve instead of the proper control valve.
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s t' 10R.1: 12-01 PLANT A.W. V0 GILE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCRIFANCY RESOLUTION WORKSHEE? REVISION O FERTORMED BY: S. Dodds DATE: 7/20/88 RIVIEVED E( M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorrman OPERATIONS SUPERINTENDENT (TMINING) DATE: 10/17/88
. Resolution:
E Discrepancy Report number 8807047 was written.
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Results:
Discrepancy Report was tested satists torily and closed on 8/21/88.
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F0kM 12-01 P1 ANT A.W. V0GT1.E $LW1.ATOR CERT 121 CATION PLAN PAGE 1 or )
FORM TITLEt DISCRIPANCY RESOLtl TION WORKSHEET REVISION O PERFORMED BY: $. Dodds DATE: 7/20/88 REVIEWED BY: M. Pe11echt DATE: 9/1$/88 APPROVID BY: R . Do rman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 l
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Performance Test Procedure: 06-01 (Plant Startup to Not Standby) l Interval Plant Heatup to NOT NOP DRW Number 69 1
Comparison Comparison Parameter Measure Value
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1 Problee
Description:
SG pressure oscillates sipificantly more than it should when compared to SG toeperature and ACS toeperature.
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t FukMt 12-01 PLANT A.W. V0G7LE SIMU1.ATOR CEATIFICAf10N PLAN PAGE 2 0F 3 QRM TITLE: 3 DISCRIPANCY RESOLtt!!ON WORK $NEET i REVISION 0 PERFORMED BY: S. Dodds DATE: 7/20/48 REVIEWED BY: M. Pe11echt DATE: 9/15/44 APPROVED BY R. Dorean ,
OPERATIONS SUPERINTENDENT (TRAINING) DATE: _10/17/84
, cause i*
SG Modeling incorrect.
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- Corrective Actions j Correct modeling, t j !
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tapact if not Corrected:
1 Significant impact - Very hard to ,
j cre so unstable. A majority of plantteach plant control at low power levels n. hen $G's trips occur due to SG 1evel problems and !
1 simulator should prepare students to effectively handle the SG's. i i
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i 4 w F0M: 12-01 PLANT A.W. V0GTLE SINVI.ATOR CERTIFICATION PLAN PAGE 3 UF j TORM TITI.Er DISCREPANCY RIS01.UTION WORK 5NEET REVI510N 0 '
PERf0RMED BYt S. Dodds DATE: 7/20/88 REVIEWED BY: M. pellechi DATE: 9/15/64 !
APPROVED BY: R. Dorman T OPERATIONS SUPERINTENDENT (TRAININC) DATE: 10/17/44 i,
. Resoluttent Discrepancy Report number 4407064 was written. i I
GPC has contracted to replace the simulator models (Core. Reactor Coolant Systee. [
Steam Generator and Containment) tith newer "state of the art" models. Model !
replacement will result in elimination of this discrepancy report by 1/30/90. !
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FokM 12-01 PLANT A.W. V0GTLE $1MULATOR CERTIf1CAf!ON PLAN PAGE 1 0F 3 7 FORM TITLE: !
DISCREPANCY RESOLUTION WORKSNEET REVI$t0N 0 !
PERFORMED BY: 5. Dean Daft 7/1/88 REVItWED BY: M. Pe11echi Daft: 9/15/48 j APPROVED BY: R. Dorean OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/48 i I
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- Performance Test Procedure: 07-06 (Turbine Trip w/c, Rm Trip 6 305) !
Interval: Malfunction to Termination DRW Number: 50 l
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I Parameter Measure Value l
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PZR Pressure NA TABLE TOP l
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Probles
Description:
Pressuriser pressure decreased during turbine trip withou' reactor trip. Pressure should have increased with RCS heatup and pressuriser level insurse.
FORM 12-01 PLANT A.W. VoGTLE $1NVLAfoR CERTIFICAfloN PLAN PAGE 2 of )
TORM TITtt: DISCREPANCY RESOLUTION WORK $NEET REVISION O PERTORMED BY: S. Dean DATE: 7/1/88 REVIEWED BY: M. pellechi DATE: 9/15/84 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/44
. Causer Pressuriter W el.
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Corrective Action:
Correct pressurizer model to respond properly to insurges.
Impact if not Corrected:
Significant impact -
taproper training of operators on pressuriser response to insurses and outsurges, t
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FuRM: 12-01 PLANT A.W. V0GTLE SIMt1ATOR CERTIFICATION PLAN PAGE 3 uf 3 FORM TITLE: DISCRIPANCY RESOLUTION WORKSMEET REVISION 0 .
PERFORMED BYt S. Dean DATE: 7/1/88 REVIEWED BYt M. Pe11echi , DATE: 9/15/48 !
APPROVED BY: R. Dorean t
OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 l I
Resolution: t I
Discrepancy Report number 8807058 was written, GPC has contracted to replace the simulator models (Core. Reactor Coolant System. !
Steam Generator and containment) with newer "state of the art" models. Model '
replacement will result in elimination of this discrepancy report by 1/30/90. !
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P FORM: 12-01 PLANT A.W. VOCTLE SINtuf0R CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLEt DISCREPANCY REsotrTION WORK $NtET REVISION 0 PERFORMED BY: $. Dean DATE: 7/1/44 REVIEWED SY: M. Pellecht DATE: _9/15/04 AFPROVED BYt R. Dorsan OPERATIONS $lTPERINTENDENT (TRAININC) DATE: 10/17/44 Performance Test Proceduce: 07-06 (Turbine Trip w/o Rx Trip $ 305)
Interval Malfunction to Termination DRW Numbert $1 Coepartson Cooperison -
Parameter Measure Value Steam Flow
{ NA TABLE TOP Problee Descripties:
s
' Af ter turbine trip stees flow escillated excessively.
r-______-.__-.________.----_.__________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ _ _ .._
FORM 12-01 PIANT A.W. VQGTLE $1MULATOR CERTIFICATION PIAN PAGE 2 uf 3 FOM ?!fltt DISCREPANCY RESOLUTION WORK $NEET REVISIOW 0 PERTOMED SY: 5. Dean DATE: 7/1/44 REVIEWED BY: M. Pellecht DATE: 9/15/84 APPROVED SY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/44 cause:
SG Model.
i Corrective Actions correct modeling to handle turbine trip without reactor trip. i.e.. smoother transition to steam dumps.
Tapact if not Corrected:
Moderate tapact.
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FvRM 12-01 PLANT A.W. V0GTLE $1MUI.ATOR CERTIFIcAY10N PLAN PAGE 3 Of )
F0kM TITLtr DISCRIPANCY RESOLUTION WORK $NEET REVISION 0 1
l PEMORMED BY: $. Dean Daft: 7/1/44 REV!!wtD BY: M. Pe11echt DATE: 9/15/s4 APPROVID BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/11/88 l .
Resolution:
Discrepancy Report number 4407049 was written.
1 GPC has contracted to replace the aisulator models (Core. Reactor Coolant System.
j Steam Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of this discrepancy report by 1/30/90.
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O g FORM: 12-01 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 3 FORM TITLE: DISCREPANCY RESOLL'i10N WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 7/5/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 i Performance Test Procedure: 07-09 (Unisolable Main Steam Line Rupture IC)
Interval: Malfunction to Termination DRW Number: 52 Comparison Comparison -
Parameter Measure Value
, TI-413A (WR Tn..) NA TABLE TOP t
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Problem Description Loop 1 cm.. should respond independently of loop 3 tw.. since loop 3 is the loop with the steaa line break and will continue to blowdown after MS isolation.
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i FORM: 12-01 PLANT A.W.
VOGILE SIMULATOR CERTIFICATION PLAN FORM TITLE: PAGE 2 0F 3 DISCRIPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 7/5/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R._Dorman
_ OPERATIONS SUPERINTENDENT (TRAINING) DATE: y/17/83 Caus'e:
SG Models.
Corrective Action:
Correct Sim, model.
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Impact if not Corrected:
Significant impact - Student cannot properly identify the affected .
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 7/5/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPEkINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8805011 was written.
GPC has contracted to replace the simulator models (Core. Reactor Coolant System, Steam Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of this discrepancy report by 1/30/90.
e Results:
FORM: 12-01 PLANT A.W. V0GTLE SIMLI.AIOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 0 FERFORNED BY: A. Guthrie DATE: 7/13/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 06-078 (Rod Worth Measurement)
Interval: Rod Worth Determination DRW Number: 53 Comparison Comparison Parameter Measure Value .
Control Bank 1240 + 124 pcs 1107 pcs C Integral Worth Control Bank 960 + 96 pcm 857 pen B Integral Worth Control Bank 690 + 69 pcm 597 pca A Integral Worth l
l Problem
Description:
Integral Bank worth are too low.
Note that these values are for cycle 1.
6 FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATI.'N PLAN . PAGE 2 0F 3 . t FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET AEVISION o.
PERFORMED BY: A. Guthrie DATE: _7/13/88 REVIEWED BY: M. Pellechi DATE: 9/15/.18-APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DA7E: _10/1188 Cause Inaccurate constants in core physics routines.
Corrective Action:
Re-calculate constants for Unit 1. Cycle 2 Impact if not Corrected:
Negligible
FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PIAN PAGE T OF 3 FORM TITLE: DISCREPANCY RES0ttTTION WOPJSHEET REVISION O PERFORMED BY: A. Guthrie DATE: 7/13/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
. Resolution:
Discrepancy Report number 8807053 was written.
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Results:
Discrepancy Report was tested satisfactorily and closed on 9/30/88.
9
I, FORM: 12-01 PLANT A.W. V0GTLE SIMULAIOR CERTIFICATION PLAN PAGE 1 OF 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 0 PERFORMED BY: P. Rubin DATE: 7/5/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 06-06 (Rx Trip W/ Recovery To Rated Power)
Interval: Rx Trip to NOT STANDBY DRW Number 54 Comparison Comparison Parameter Measure Value Manual Rx Trip Annunciator NA TABLE TOP i
. Probles
Description:
1 l Annunciator did not alam; it should.
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FORM: 12-01 PLANT A.W. VoGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 7/5/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVID BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
. Cause:
Simulator logic wrong.
Corrective Action:
Fix simulator logic.
Impact if not Correctedt Significant impacti operator will not be able to validate the "first-out".
r0RM; 12-01 ~
PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 7/5/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED B'.': R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8807050 was written.
Results:
Discrepancy Report was tested satisfactorily and closed on 7/24/88.
FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 Of 3 FORM TITLE: DISCREPANCY RTSOLUTION WORKSHEET REVISJON O PERFORMED BY: P. Rubin DATE: _7/6/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OP:JATIONS SUPERINTENDENT (TRA).NING) DATE: 10/17/88 Performance Test Procedure: 06-10 (Steady State $ 75% Power)
Interval: Entire Test DRW Number: 55 Comparison Comparison Parameter Measure Value -
3 SG 1 Feed flow 510 2.5 MPPH + .08 MPPH L.85 MPPM
-' SG 1 Steam flow 512 2.6 MPPH ~+ .08 MPPH !!.85 MPPH SG 4 Feed flow $40 2.72 MPPR + .08 MPPH !!.85 MPPM SG 4 Steam flow 542 2.72 MPPH _I .08 MPPH :2.85 MPPH Problem
Description:
Parameters exceeded ANS 3.5 acceptance criteria.
f FORM: 12-01' PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 2 UF 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMfD BY: P. Rubin DATE: 7/6/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
, cause:
SG sodel made to look like plant over full power range. Possible bad reference data.
w corrective Action:
Investigate.
Impact if not Corrected:
None.
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FORM 12-01 PLANT A.W. VOGILE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: P. Rubin DATE: 7/6/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolutions Discrepancy Report number 8807051 was written.
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Results:
Discrepancy :teport was tested satisfactorily and closed on 7/26/88.
FORM: 12-01 PLANT A.W. V0 GILE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PEPFORMED BY: R. Ciminel DATE: 6/07/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-11A (Loss of Elec. Dist. Bus 1NAA)
Interval: Malfunction to Termination DRW Number: 56 ._
Comparison Comparison -
Parameter Measure Value
$. HS INA0508 BRK NA TABLE TOP Froblem Description Breaker did not trip (should have).
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l FORM: 12-01 PLANT A.W. V0 GILE SIMULATOR CER21FICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLlTTION WORKSHEET REVISION O PERFORMED BY: R. Ciminel _ DATE: 6/07/88 REVIEWED BY: M. Pellechi , DATE: 9/15/88 APPROVED BY: R . Do rmat. , OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause Logic error.
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Corrective Action:
Fix logic error.
Impact if not Corrected:
Unrealistic model impacts simulator credibility.
FORM: 12-01 PLANT A.W. V0GTLE SLMUI.ATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHE'.T REVISION O PERFORMED sY: R. Ciminel DATE: 6/07/88 REVIEWED BY: M. Pellechi LATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAININC) DATE: 10/17/88 c:
. Resolution:
Discrepancy Report number 8807052 was written.
Results:
Discrepaney Report was tested satisfactorily and closed en 8/14/88.
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FORM 12-01 PLANT A.W. VOGTLE SIML'I.ATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O_
PERFORMED BY: R. Ciminel DATE: 6/07/88 REVIEWED BY M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dormar. OPERATION.9 ,'UTZRINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-09 (Loss of Emergency Power)
Interval: Malfuaction to Termination DRW Number: 57 Comparison Compartson Parameter Measure Value .
Probles
Description:
NSCW Pump 5 started manually (should not have) and would not trip (should have).
-___m___ _____._ _ _ _ _ _ _
FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET 1
REVISION 0 ;
PERFORMED BY: R. Ciminel DATE: 6/07/88 REVIEWED BY M. Pellechi DATE: 9/15/88 APPROVED BY R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 cause: I Logic incorrect in model.
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Fix logic.
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FORM: 12-01 PLANT A.W. V0GTLE 5IMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET RIVISION O PERFORMED BY: R. Ciminel DATE: 6/07/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
. Resolution:
Discrepancy Report number 8804040 was written.
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Results:
Discrepancy Report was tested satistsetorily and closed on 5/29/84.
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 F0PM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: R. Ciminel DATE: 6/07/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-09 (Loss of Emersency Power) 1 Interval: Malfunction to Termination DRW Number: 58 Comparison Comparison -
Parameter Measure Value CCP 1A NA TABLE TOP a
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Description:
CCP 1A started manually (should not have).
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FuRM: 12-01 FLANI A.W. V0GTLF. SIMUIATOR CERTIFICATION PIAN PAGE 2 0F 3 F0kM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: R. Ciminel DATE: 6/07/88 REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman
_ OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
. Cause Logic incorrect in model.
Corrective Action:
Tix logic.
Impact if not Corrected:
Unrealistic model which decreases simulator credibility.
O
- FORM: 12-b1 PLANT A.W. V0GTLE SIMULATOR CERTIFICATIUN PLAN PAGE 3 UF i FORM TITLE:
DISCREPANCY RESOLUTION WORKSHEET RIVISION O PERf0MED BY: R. Ciminel DATE: 6/07/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APFROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolutions Discrepancy Report number 8804040 was written.
t Results:
Discrepancy Report was tested satisfactorily and closed on $/29/88.
FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCRIPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: R. Ctainel DATE: 6/07/88 REVIEWED BY M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: _10/17/88 l Performance Test Procedure: 05-02 (LOCA: Inside Containment) i Interval: SI Actuation to Termination DRW Number: 59 f i
Parameter coeparison Measure Coopertson Value CNMT PRESSURE PI 934 NA TABLE TOP i CNMT SUMP LEVEL ILR 764 NA TABLE TOP L
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Problee
Description:
i Containment pressure never exceeded 6 psig throughout this scenario, nor did containment sump level increase such. As this is a 5000 spe leak from the RCS one would expect a large rise in containment pressure and spray actuation causing sump [
level to increase.
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FORM: 12-01 PIANT A.W. YOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F'l ,
4 FORM TITLE: DISCREPANCY RESOLUTION WORKSMkET REVISION O PERFORMED BY: R. Ciminel DATE: 6/07/88 REVIEWED BY: M. Pellechi DATE: 9/15/S8 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 i
i Cause l
improper containment pressure dynamics being modelled.
t Corrective Action:
Investigate and fix dynamics.
Impact if not Corrected:
Significant impact - Unrealistic model which decresses simulator credibility. :
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FURM 12-01 PLANT A.W. VOGILE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERTORMED BY: R. Ciminel DATE: 6/07/88 REVIEWED BY: M. Pe11echi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 8804036 was written.
GPC has contracted to replace the simulator models (Core, Reactor Coolant System.
- Steam Generator and Containment) with newer "state of the art" models. Model replacement will result in eliminatiori of this discrepancy report by 1/30/90.
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Results:
FOM: 12-01 PLANT A.W. V0GTLE 51MUI.ATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM IITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION O PERFORMED BY: R. Ciminel DATE: 6/08/88 DATE: 9/15/88 REVIEWED BY: K. Pe11echi AFFROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Test Procedure: 05-17C (ACCW PLMP #1 LOCKED ROTOR)
Interval: PLHP TRIP TO TERMINATION DRW Number: 60 Coopsrtson Coeparison -
Parameter Measure Value
Description:
Breaker did not reclose and trip when attempting to restart pump. It should close and trip.
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE:
DISCRIPANCY RESOLUTION WORKSNEET REVISION O PERFORMED BY: R. Ciminel DATE: _6/08/88 _ REVIEWED BY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
. Cause:
Improper pump logic.
Corrective Action:
Investigate and fix logic.
Impact if not Corrected:
Unrealistic model which decreases simulator credibility.
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FORM: 12-01 FLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 UF 3 FORM ~ TITLE: DISCREPANCY RESOLUTION WORKSNEET REVISION O PERFORMED SY: R. Ciminel DATE: 6/08/88 REVIEWED SY: M. Pellechi DATE: 9/15/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88
, Resolution:
Discrepancy Report number 8804050 was written.
Results:
Discrepancy deport was tested satisfactorily and closed on 8/4/88.
O FuRM: 12-01 PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLEt DISCREPANCY RESOLUTION WORKSNEET REVISION O PERFORMED BY: M. PELLECHI DATE: 9/28/88 REVIEWED BY: M. CIBSON DATE: _9/28/88 i APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 j
, I Performance Test Procedure: 05-30B (TRAIN A CONT SPRAY AUTO ACTUATION FAILURE)
Interval: MALFUNCTION TO TERMINATION DRW Numbers 61 i
Comparison compartson Parameter Measure _
Value ;
. CNMT SPRAY EDUCTOR FLOW NA TABLE TOP FI-930 i
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Probles Description i EDUCTOR INCRfASED.
FLOW DID NOT CHANGE WEEN THE SLCOND SPRAY PLMP WAS STARTED. IT SHOULD RAVE ;
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FORM: 12-01 PLANT A.W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 3 FORM TITLE.' DISCREPANCY RESOLUTION WORRSHEET REVISION O P
PERFORMED BY: M. PELLECNI DATE: $28/88 REVIEWED BY: M. GISSON DATE: 9/28/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause:
Improper pump dynanics, i
Corrective Action:
Investigate and fix dynamics.
Ispact if not Corrected:
Unrealis:ic model which decreases simulator credibility.
1 FOPR: 12-01 PLANT A.W. V0GTLE 51MUIAIOR CERTIFICATION PLAN PAGE 3 0F 3 -i FORM TITLE: DISCREPANCY RESOLUTION WORKSHEET ,
REVISION O PERFORMED BY: M. PELLECHI DATE: 9/28/88 REVIEWED SY: H. CIBSON DATE: 9/28/88 APPROVED BYr R. Dorsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolutiont Discrepancy Report number 8804053 was written.
i Results:
Discrepancy Report was tested natisfactorily and closed on 4/26/84.
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b FORM 12-01 ' PLANT A.W. VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 0F 3 FORM TITLE: DISCREPANCY RESOLLTION WORKSHEET REVISION O PERFORMED BYt M. PELLECHI DATE: 9/28/88 REVIEWED BY M. GIBSON DATE: 9/28/88 APPROVED BY: R. borman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Perforleance Test Procedure: 05-308 (TRAIN A CONT SPRAY AUTO ACTUATION FAILURI) i Interval: MALFUNCTION TO TERMINATION DRW Number: 62 t
compartson Comparison -
Parameter Measure Value '
. CNMT SPRAY ACTUATION NA TABLE TOP i
Probles
Description:
Could not get cast spray actuation w/ main steaaline break inside containment.
Containment pressure stabilized at approx. 20 psis even w/ continous AfW flow to the effected SG.
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FORM: 12-01 PIANT A.W. VOCTLE SIMUIATOR CERTIFICAT70N PLAN PAGE 2 uF 3 I FORM TITLE: DISCREPASOY RESOLUTION WORKSHEET REVISION O PERFORMED BY: M._PELLECHI DATE: 9/28/88 REVIEWED BY: M. CIS$0N DATE: 9/28/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Cause l
Improper containment model dynamics.
Corrective A. tion:
Investigate and fix dynamics. l 4
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I Impact if not Corrected:
Moderate impact - Unrealistic model which decreases simulator credibility.
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FukM: 12-01 PLANT A.W. VOCTLE SIMULAIOR CERTIFICATION PLAN 3
PAGE 3 or 3 FORM TITLE: DISCREPAACY RESOLUTION WORK $NEET REVISION O PERFORMED BYt M. PELLECHI DATE: 9/28/88 REVIEWED BY: M. CIBSON DATE: 9/28/88 APPROVED BY: R. Dorman CPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Resolution:
Discrepancy Report number 4404054 was written.
GPC has contracted to replace the simulator models (Core. Reactor Coolant System.
Steam Generator and Containment) with newer "state of the art" models. Model replacement will result in elimination of this discrepancy report by 1/30/90.
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Results:
r Atta t ent 3 PDFC?.'"AC 7ST SOEDUIE 10/31/88 .
Plant A.W. Vogtle, Unit 1 Docket #50-424 '
Gecrgia Power Ccrpany -
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_ _ _ _ _ - _ _- -_______ _ _ ~
FORMt 17-02 PLANT A. W. V0GTLE SIMULATOR CERIIFICAT10N PLAN PAGE 1 of 5 FORM TITLE: PERFORMANCE TEST SCHEDL1E REVISION O PERFORMED BY: M. Pellechi DATE: 9/21/88 REVIEWED BY: M. Gibson DATE: 9/21/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: g/17/88 Aantal Operability Tev,
, The followins operability tests will be conducted annually (Computer Real Time Test and Appendix B - Steady State and Transient Performance Tests):
o COMPUTER REAL TIME TEST o STEADY STATE PERFORMANCE AT 30% POWER FOR 60 MINUTES (06-09) o STEADY STATE PERFORMANCE AT 75% FOR 60 MINUTES (06-10) o STEADY STATE PERFORMANCE AT 100% POWER FOR 60 MINUTES (06-11) o MANUAL REACTOR TRIP (07-01) o SIML1TANOEUS TRIP OF ALL FEEDWATER PlWPS (07-02) o SIMULTANEOUS CLOSURE OF ALL MAIN STEAM ISOL VALVES (07-03) o SIMULTANEOUS TRIP OF ALL REACTOR COOLANT PLMPS (07-04) o SINGLE REACTOR COLIANT PUMP TRIP (07-05) o MAIN TURBINE TRIP W/0 REACTOR TRIP (07-06) o MAXIMLH RATE POWER RAMP (07-07) o MAXIMLH SIZE RCS RUPTURE W/ LOSS OF OFFSITE POWER (07-08) o MAXIMtM SIZE UNISOLABLE MAIN STEAM LINE RUPTURE (07-09) o SLOW PRIMARY SYS DEPRESSURIZATION TO SATURATED CONDITION (07-10)
i FORMt 17-02 PLANT A. W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 2 0F 5 FORM TITLE: PERFORMANCE TEST SCHEDULE REVISION 0 i PERFORMED BY: M. Pe11echt DATE: 9/21/88 REVIEE D BY: M. Gibson DATE: 9/21/88 ,
APPROVED BY: R. borsan OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 r
Perforanoce Tests
- The following performance tests will be conducted (in addition to the annual operability tests) in the first year following certification (Normal Operation Tests.
Malfunction Tests, and Transient Tests not tested as Annual Operability Tests): '
o LOSS OF COOLANT- SIGNIFICANT PWR STAEM CENERATOR LEAKS (05-01) o LOSS OF COOLANT- SMALL RCS BRIAKS (05-05) o LOSS OF EMERGENCY PohTR (05-09) o
^ LOSS OF POWER TO INDIVIDUAL INSTRLMENT DC BUSES (05-13) r o
. LOSS OF COMPONENT COOLING SYS OR COLLING TO INDIVIUAL COMPONENTS (05-17) L o FUEL CLADDING FAILURE (05-21) I
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o MAIN STEAM LINE BREAK OUTSIDE CONTAINMENT (05-25) o PROCESS YNSTRlHENT, ALARMS. AND CONTROL SYSTEM FAILURES (05-29) o PLANT STARTUP FROM COLD TO HOT STANDBY (06-01) ,
o C001.DOWN FROM HOT STANDBY TO COLD SNUTDOWN CONDITIONS (06-05) '
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i FORM: 17-02 PLANT A. W. V0GTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F $
FORM TITLE: PERFORMANCE TEST SCHEDULE ___ REVISION O PERFORMED BY: M. Pellechi DATE: 9/21/88 REVIEWF.D BY M. Gibson DATE: 9/21/88 APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAININ0) DATE: 10/17/88 !
Performance Tests i
The following performance tests will be conducted (in addition to the annual operability tests) in the second year following certification (Normal Operation Tests.
Malianction Tests, and Transient Tests not tested as Annual Operability Tests):
l o LOSS OF COOLANT- INSIDE PRIMARY CONTAIhMENT (05-02) r o FAILURE OF SAFETY AND RELIEF VALVES (05-06) o LOSS OF EMERGENCY CENERATORS (05-10) I i
o LOSS OF CONDENSER VACULH INCLUDING LOSS OF CONDENSER LEVEL CONTR(..,(05-14) o LOSS OF ALL FEEDWATER- NORMAL AND EMERGENCY (05-18) o GENERATOR TRIP (05-22) o MAIN FEED LINE RREAK INSIDE CONTAINMENT (05-26) ,
o PASSIVE MALFUNCTIONS 14 SYSTEMS (05-30) l o '
NUCLEAR STARTUP FROM NOT STANDBY TO RATED POWER (06-02) o REACTOR TRIP FOLLOWED BY RECOVERY TO RATED POWEt (06-06)
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O FuRM 17-02 PLANT A. W. V0G1LE SIMUI.ATOR CERTIFICATION PLAN PAGE 4 0F 5 FORM TITLE: PERFORMANCE TEST SCHEDL1.E REVISION O PERFORMED BY: M. Pe11echi DATE: 9/21/88 REVIEWED BY M. Gibson DATE: 9/21/88 APPROVED SY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 i
Performance Tests !
o The following performance tests will be conducted (in addition to the annual [
operability tests) in the third year following certification (Normal Operation Tests.
- Malfunctior. Tests, and Transient Tests not tested as Annual Operability Tests):
o
. LOSS OF C001 ANT- OUTSIDE PRIMARY CONTAINMENT (05-03) i o LOSS OF INSTRLMENT AIR (05-07) o 1.05S OF POWER TO THE Pt. ANT'S ELECTRICAL BUSES (05-11)
, o LOSS OF SEF.VICE WATER OR COOLING TO INDIVIDUAL COMPONENTS (05-15) c o CONTROL ROD FAILURES (05-19) l 1 o FAILURE IN AUTOMATIC CONTROL SYSTEMS (05-23)
- o MAIF FEED LINE BREAK OITISIDE CONTAINMENT (05-27) !
i o FAILURE OF AUTOMATIC REACTOR TRIP SYSTEM (05-31) o LOAD CHANCES (06-03) i o CORE PERFORMANCE TESTING (06-07)
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FORM 17-C2 PLANT A. W. V0G1LE SIMULATOR CERTIFICATION PLAN PAGE 5 UF 5 FORM TITLE: PERFORMANCE TEST SCHEDULE REVISION O PERFORMED BY: M. Pe11echi DATE: 9/21/88 REVTEWED BY: M. Gibson DATE: 9/21/88 t
APPROVED BY: R. Dorman OPERATIONS SUPERINTENDENT (TRAINING) DATE: 10/17/88 Performance Tests l
The following performance tests will be cor. ducted (in addition to the annual !
operability tests) in the fourth year following eartification (Normal Operation Tests.
- 4altunction Tests. and Transient Tests not tested as Annual Operability Tests)
o LOSS OF COOLANT- 1ARGE RCS BREAKS (05-04) o LOSS OF OFFSITE POWER (05-08) o LOSS OF POWER TO INSTRUMENT AC BUSES (05-12) o LOSS OF SHUIDOWN COOLING (05-16)
I o INABILITY TO DRIVE CONTROL RODS (05-20) l o FAILURE OFRCS PRESSURI & VOLUME CONTROL SYSTEMS (05-24) f o NUCLEAR INSTRUMENTAPION FAILURES (05-28) o PIANT SHUTDOWN FROM RATED POWER TO HOT STANDBY (06-04)
I o OPERATOR CONDUCTED SURVEILLANCE TESTING ON SAFETY RELATED SYSTEMS (06-08)
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=a ve ,. ...e e .., e., ano toca tio oe s.=v6a rc= e aCitir, A.W. Vogtle Simulator, River Rd.. Approx. 5 mi. NE. Hwv. 23. Waynesboto. CA 308)0 x llawvLaf c.s 8 aCitii* Pt A80 awes.Ct ttIT aes7aaCT3 aft.c.t0 # ar # poew w. some seeme,et m ano sees essay va ree are et one see,aseceas C4 SCai** a04 08 *4 aeoawae.C4 Itifi=Q Com.e4if ao 4ame assemio a.gsras a - .. ese aseme4 ene own sur.:.we.ee om, ewww=mes Plant A.W. Vogtle. Unit 2 Simulator Training vill be performed using the Unit 1 Training simulator. The performance tests were run per the Unit 1 certification.
Operational characteristics of Unit 2 were considered and differences which may result in negative training are identffied as exceptions in Attachment 1 to this form.
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Plant A.W. Vogtle Unit 2 Simulator Training will be perfcrued using the Unit 1 Trainini simulator. The performance tests will be run per the Unit 1 certification. The operational characteristics of Unit 2 will be considered and differences which may result in neg.tive training identified and resolved.
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A::ac. h nt i DCPTICtIS 10/31/88 Plant A.W. Vogtle, Unit 2 Docke # 50-425 Georgia Pcver Ccrinny
A.W. TUJC VOCI, LUIT 2 #50-425 ATTAOCC C 1 10/31/88 Exceptiens to RJSI/R;S3.5-1955 for thit 2 are the sa, e as those specified fer Unit 1.
Gecrgia Pmr Ccrpany has researched the differences between Lhit 1 and Lhit 2 for Plant A.W. Vogtle for Lhit 2's initial license. mis report is rade a part of this attac,5 ent and serves to cLet explit .:e with Pegulatory Guide 1.149.
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