ML20082L324
| ML20082L324 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/07/1995 |
| From: | Querio R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9504210106 | |
| Download: ML20082L324 (18) | |
Text
, ,, Commonwealth likson Osmpany Iasalle Generating Wtion
, 2M)I North 21st Roati Wrseilles. II,61.4119757 Tc! N1445N#7bi April 7,1995 United States Nuclear Regulatory Commission Washington, D.C. 20555 .
Attention: Document Control Desk
Subject:
LaSalle County Station Units 1 and 2 LaSalle County Station 4 Year Report NRC Docket Numbers 50-373 and 50-374.
Enclosed is Comed's submittal of the "4 Year Certification Report" for LaSalle County Nuclear Station Simulator Facility, in accordance with 10CFR55.45.
The enclosed report identifies uncorrected performance test failures, describes performance tests conducted from 1992 to 1995 and provides a Performance Test Schedule for 1996 to 1999. NRC Form 474's are enclosed due to changes in the Performance Test Schedule.
If there are any questions or comments concerning this letter, please refer them to me at (815) 357-6761, extension 3600.
Respectfully, Q N R. F.. Querio Site Vice President LaSalle County Station j l
l cc: J. B. Manin, Regional Administrator, Region III W. D. Reckley, Project Manager, NRR P. G. Brochman, Senior Resident Inspector, LaSalle D. L. Fanar, Nuclear Regulatory Senices Manager, NORS Central file r~ - .,
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i L_S-11e County Nuclear Station Units I and 2 D'ocket Numbers: 373 and 374 - .
LcSalle Simulator .4 Year Report j Director, Office of Nuclear _ Reactor Regulation ,
U.S. Nuclear Regulator Commission :
Document Control Desk !
- Washington, D.C. 20555 -l i
Gentlemen: i i
The purpose of this letter is to submit the "4 Year Certification Report" of Comed's LaSalle County Nuclear Station Simulator Facility, in accordance with 10CFR55.45. :
The enclosed report identifies uncorrected performance test failures, describes performance tests conducted from 1992-1995, and provides a Performance Test Schedule for 1996-1999. ;
i
- NRC Form 474's are enclosed due to changes in the Performance Test Schedule. !
Sincerely i
- h. j obert Querio Site Vice President i
cc: Administrator, Region 111, USNRC I Nuclear Licensing Adminstrator !
NRC Resident inspector-LaSalle Station Charlie Sargent t Sam Harmon !
Larry Blunk Ron Bell l'100 la 0 >
L:\BWR\MC\certsubm.wpf P.1 1/95 Rev. O b l l t ,
ffRC FORM 474 U.S. NUCLEAR LEcULATORY COMMISSION APPROVED SY OMS: NO. 3196438 EXPIRES: 1 *31/95 ESTIMATED BURDEN PER RESPONSE 10 COMPLY WITH TH48 INFORMATION COLLECTION REQUEST: 120 HOURS. FORWARD SIMULATION FACILITY CERTIFICATION ""'****^"'"
'u"'""""""',"."S. "^'*" ^"o RECORDS MANAGEMENT BRANCH (MNSS 7714) U NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 206054001,AND TO THE ,
PAPERWORK REDUCTION PROJECT 0150 0138), OFFCE OF MANAGEMENT AND BUDGET, WASHINGTON. DC 20S03.
gNTRUCTIOsst: The form a to be Iked for meter ce*tlecation, reconecaten {st requwod), and for any change to a simulaten facsilty performance testmg plan made after mitel submmal of such a penn. Prowde the fonoudng informaten and checa the approonste bow to ind<ste reason for submmal.
F ACEJTY - DOCKET NUMBER
- 373 LaSalle statinn - tin i +- 1 uCENsEE oArE Commonwealth Edison (Com Ed) 3/18/95 The eioce,inym.t
- i. The a e nam.d f==y acen e u..ng a .,muen facay conteng e.y of a piani.ree.r.nc.d .enuinio,ihai m.ei. tn. , equi,emenie of so CrA es..
- 3. D um.ntaien N a.a.eb e NRC r. wee m uco,s.nc. w.m to CrA ss.sn
& The annulanon facday meets the guieance contamed in ANSI /ANS 3 S,1965, as endorsed by NRC Regunetory Guide 1.140.
W there are any EXCEFT10NS to the consfication of this item, CHECK HERE { ] and desenbe fully on additenal pages as necemeary ,
NAME (or omer sde@4cason) AND LOCATION OF SIMULATION F ACIUTY.
Production Training Center 36400 S. Essex Rd.
Wilmington, IL 60481 giMULATION FAOluTY PERFORMANCE TEST ABSTRACTS ATTACHED. For penormance ress conducted a me pened ending we me date of mes cereocaoon)
DE SCRIPTION OF PERFORMANCE TESTING COMPLETED. (Afrece addeonaf pages as necessary and #dencry me Aem descrip6en besng conDnued.)
gaMULATION F ACIUTY PERFORMANCE TESTING SCHEDULE ATTACHED. For the conduct of apprommarely 25' of performance feats per year fbr me abur year pened commenceg we E me date of two ceescapon)
DESCRIPTION OF PERFONMANCE TESTING TO BE CONQUCTED. (Afrach addeons/ pages as necessary and spe@t Sie dem descapton bemg carenued)
See the attached, LaSalle Station Simulator Four Year . Report, Attachment 1.
x PERFORuANcE TrrNfG PLAN CHANGE. (For any mo** canon to e performance fosong plan submnrod on a prenous coeAespon)
DE 3CFgFTION OF PERFORMANCE TESTING PLAN CHANGE (Afrech acceDonW pages as necessmy and scenoy me nem descnpDon bomp conDnued)
The content of the performance test schedule for 1996-1999 is identical to the schedule in the initial certification report with the exception of malfunctions that were added or deleted. None of the deleted malfunctions were needed to meet the requirements of ANSI /ANS-3.5-1985, Section 3.1.2, Plant Malfunctions. See the attached 4 year report for details.
RECER'iFCATION (Desenbe correepwe accons ramen arrech residts of corrgoseded perrormance foreng en accordance we 10 CFR SS 4S(b)($)(v)
$Anach eddeord pages as necessary and ade@ry me Mers desenpban bemg corenued)
Any sease statement or omme,an m the sacument, menudmg anachments may ne sucrect to sw and enmmer sanct.ons. I certwy unoer penany of perjury that the wwormanon m the ensument and stischmente a true and correct siGNATVN AUTHoft2ED TPNSENTATWE TTTLE DATE A ,
~
3k.M44%s E ([ hb&GN /
'1n esis roance we 10 CFR 65 6. Communer.elens.1%e form snan be submitted to the NRC as faseme:
SY MAIL ADDRESSED TO- OfRECTOR, OPPICE OF NUCLf.AR Rt. ACTOR REGULAT10ei BY DELNERY IN PERSON ONE WHITY FLINT NORTH U.S. NUCLEAR REOULATORY COMMISSION TO THE NRC OFFCE AT: 11666 ROCKVILLE PIKE WASHINGTON, DC 706S6 4001 ROCKVILLE, MD peg; FCshi 474 OtH4 PRINTED ON RECYCLED PAPER l
l
l l
U.S. NUCLEAR REaULATORY COMMISSION APPROVED BY OesS: NO. stso41am NRC FORM 474 EXPIRSS: 10/31/06 ESTIMATED SU@EN PER RESPONSE WTTH THis wOauAe COu.ECTiON mOUEST: T,O
=0 C,OMPLY OuRS. FORWARD MMEMS REGAMM BU@EN ESDMATUO THE WNM A@
SIMULATION FACILITY CERTIFICATION RECORDS MANAGEMENT BRANCH (MNSS 7714), U.S. NUCLEAR REGIA.ATORY COMMISSION, WASHINGTON, DC 20586fs001, AND TO THE PAPERWORK REDUCTION PROJECT (3190 0138), OFFICE OF MANAGEMENT AND SUDGET. WASHINGTON. DC 20$03-N: The form o to be filed for massi certacaten, recefiscation lif required), and for any change to e simulation facnny performance testing pnen made afier ina.ai submmai of such a paan, provide the forto.ing informaterm and check tne appropnete bom to ma.cate reason for submmal. ,
FACgfry - DOCKET NUMBER
- 374 LaSalle Station - Unit 2 uCENoEE DArE Commonwealth Edison (Com Ed) 3/18/95 The le to com'y that;
- t. The aeove named facinny beeneee e verne a e mulaten facupy cons stmg sooty of a pani-referenced esmutator that meets the requiremente of to CFR $$.45.
S. oocumene.i.on m ww. sor NRC r.v,e. m .uo,danc. m so CrR ss 4sn
- 3. This emulanon facetsty meets the guidance contained in ANSI /ANS3 5.1965, as endorsed by NRC Regulatory Guede 1.149.
- there are any EXCEPTIONS to the certikaten of the item, CHECK HERE l ] and describe fully on addamnal pages as necessary fwsE (w oma ,denone. con; AND LocATm OF SiMULAToN F ACiUTY.
Production Training Center 36400 S. Essex Rd.
Wilmington, IL 60481 SlMULATION FACluTY PERFORMANCE TEST ASSTRACTS ATTACHED (For per%rmance fests conducted m me pened endmg wm me dars of rus coeAcaDort)
DESCRIPTION OF PERFOHMANCE TESDNQ COMPLETED. IAfreca addeonar peges as necesswy and sdenofy Pm nem essenpoon beeng eenonued.)
SIMULATION FACluTY PERFORMANCE TESTING SCHEDULE ATTACHED. (Fw me conduct of approsmeresy ss'etperformance sess per year er me Awyew pened commenc,ng wem X me due of Pn cesacanan)
DESCRIPTION OF PERFORMANCE TESTING TO BE CONDUCTED. (Attsch oddeonalpages as necessey and sdenery me nem descrqpoon bemy canonued.)
See the attached, LaSalle Station Simulator Four Year Report, attachment 1.
' PERFORuANCE TESTnNG PLAN CHANGE. (Fw any modunceoon e a owwmance n, song pran submmed on e provras cwencaem; DE.9CRF110N OF PERFORMANCE TESTING PLAN CHANGE #Afface adeponer pages as necessary wNT seenOff me Aem descapoon besng conDowed)
The content of the performance schedule for 1996-1999 is identical to the schedule in the initial certification report with the exception of malfunctions that were added or deleted. None of the deleted mal-functions were needed to meet the requirements of ANSI /ANS-3.5-1985, Section 3.1.2, Plant Malfunctions. See the attached 4 year report for details.
RECERTiFICATION (Desense conoceve oceans takers atraca resuRs of compiered perkomance neueng m accordance eve 10 CFR SS tS{b)(S)(v).
(Asoce eddeorW pages as necesswy and sdenet me som desonpean bemp conenwed)
Any tame statement or omesion m me sacument enceucing anachments, may be suplect to own and enmmal sanciens. I comty unoer penany of perputy that me erwormaton m me
_ .: and attachmente e true and correct.
BONAMIE = AUTHORJED MPHESENTADVE TITLE DATE
/ -
l [<. . ; . ;. .i INDEX J
- NRC Form 474 ;
1 LIndex I. : I n t rod u ct io n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ' 3
- II. - References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 III. Repo rtin g Req uirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 IV. I m ple m e n t a t io n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 ,
A. Performance Test Failures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 :
B. Performance Testing Completed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 C. Performance Test Schedule, if different . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 t
t Attachment 1 ..........................................................7 '
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5
- i LaSalle Nuclear Station Simulator j
. 1995 Certification Report l L INTRODUCTION s
This report is a supplemental to the 1995 Simulator Annual Certification Report. This report is ,
submitted in accordance with the requirements of 10 CFR 55.45 (b) (5), Certification of Simulator.
Facilities. It describes the simulator performance testing completed over the last 4 years, and the .
performance tests planned for the next 4 years. l 1
The Comed owned, General Electric BWR 5,1170 MWE power plant simulator is used for training and testing of LaSalle Unit 1 and 2 operators. Because of the near exact duplication between ,
the two units it is considered a plant specific simulator for both units, hereafter referred to as the LaSalle Simulator. Ilowever, since only one unit can be modeled, the simulator is modeled with LaSalle unit .
I as the reference plant. The simulator was constructed by electronics Associates, Inc. (EAl) in the early 1980's with the first training class conducted in the fall of 1983.
II. REFERENCES A. Title 10, Code of Federal Regulations, Part 55. Operator Licenses", Subpart E, Section 45.
B. U.S. Nuclear Regulatory Guide 1.149 Nuclear Power Plant Simulation Facilities for use in :
Operator License Examinations.
C. ANSI 3.5,1985, ' Nuclear Power Plant Simulators for use in Operator Training. r III. REPORTING REQUIREMENTS The requirements of this report as outlined in 10CFR55.45 are:
A.
Paragraph 55.45 (b) (5) (ii): Identify any uncorrected performance test failures, and submit a schedule for correction of such performance test failures. i B. Paragraph 55.45 (b)(5) (vi): A description of performance testing completed for the simulation >
facility.
C. Paragraph 55.45 (b) (5) (vi): A description of performance tests, if different, to be conducted '
on the simulation facility during the subsequent 4 year period.
D. Paragraph 55.45 (b) (5) (vi): A schedule for the conduct of approximately 25% of the performance tests per year for the subsequent 4 years.
i L:\BWR\MC\certsubm.wpf P.3 1/95 Rev. O
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- i i IV. IMPLEMENTATION A'. Identify any uncorrected performance test failures, and submit a schedule for correction of such performance test failures.
Shrink and Swell has been added to the LaSalle Simulator, but needs additional tuning at low powers. This will remain an exception until acceptable in all plant conditions. Our intention is to obtain the services of Prizm technologies to complete this project by June of 1995. ,
Work Requests have been written on 4 malfunctions to enhance their usability and will not be used for training until complete. None of these were needed to satisfy ANSI /ANS-3.5 1985, section 3.1.2, Plant Malfunctions.
B. A description of Performance Testing Completed for the Simulation Facility.
The LaSalle Simulator completed all annual and quadrennial performance tests for the years 1992 through 1995 as scheduled in the initial certification report. LaSalle procedures do not allow hot standby operation, so the normal operations tests that require hot standby conditions have been deleted from the new schedule. Due to numerous changes made to simulator software, the normal operations tests have all been done each year for the last 4 years. These normal operations tests will be placed on quadrennial schedule for the next 4 years.
- 1. Computer Real Time Testing is done annually, and has been satisfactory each year from 1992 through 1995.
- 2. Swady State Testing is done annually, and has been satisfactory each year from 1992 through 1995. Some parameters that were close to failure criteria have been tuned to more closely match the plant.
- 3. Normal Operations Testing has been done annually for the last 4 years, to more completely test changes to the simulator. For the next 4 yeus these tests will be run 25%
per year per the schedule in attachment 1. All normal operations tests done from 1992 through 1995 were satisfactory. The new shrink and swell modeling is causing some problems at low power levels. This problem should be corrected by June 1995.
- 4. Transient Testing is done annually, and has been satisfactory each year from 1992 through 1995. Some of the plots will be slightly different this year tban previous years due to the shrink and swell model changes.
- 5. Malfunction testing is done at a rate of 25% per year and has been satisfactory each year from 1992 through 1995, with a few minor exceptions that were corrected by the work request procedure. Work Requests are open on 4 mayunctions to enhance their usability, and will not be used for training until complete. None of these malfunctions are needed to satisfy the requirements of ANSI /ANS-3.51985, section 3.1.2, Plant Malfunctions.
L:\BWR\MC\certsubm.wpf P.4 1/95 Rev. O
C. A description of Performance Tests, if different, to be conducted on the simulation facility during the subsequent 4 year period.
The performance Test Schedule for 1996-1999 is identical to the initial certification report with the exception of malfunctions that have been added or deleted. See attachment 1 for a complete schedule.
The following malfunctions have been added since the 1991 certification report was issued:
- 1. Miscellaneous Auto Control Power Failure (MEE056) #324.
- 2. Reactor Recirc Flow Control Valve Failure (MRC039,40) # 325.
- 3. Recire Pump Suction Line Rupture inside the isolation valves (MRC041,42) # 326.
- 4. Main Steam Line Radiation Monitors fail to trip (NUMACS) (MRM038) # 327.
- 5. Steam Line Rupture in the Steam tunnel between the inboard and outboard MSIV's (MNB205)
- 328.
- 6. Degraded Scram Discharge Volume (MRD277,278) # 329.
- 7. Control Rod Drive Flow Control Valve Failure (MRD279) # 330.
- 8. Failure of the Feedwater Testable Check valves (MCF111) # 331.
- 9. Feed Flow transmitter (C34-N002A, B) fails low. (MNB1222 & MNB123 # 332.
- 10. Feed Flow Transmitter (C34-N002A, B) fails high. (MNB124 & MNB125) # 333.
- 11. Plugged Suction Strainers in the Suppression Pool (MRH014-16 & MES022-24) # 334.
12 . Scram Contactor Fails Closed. (MRP019-24) # 335.
- 14. Scram discharge volume rupture. (MRD337) # 337.
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L:\BWR\MC\certsubm.wpf P.5 1/95 Rev. O
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The following malfunctions have been deleted since the 1991 certification report. None of the deleted malfunctions are needed to satisfy the requirements of section 3.1.2 of ANSI /ANS 3.5 1985.
- 1. The IIPCS F001/F0015 transfer interlock failure malfunction was deleted because a plant modification deleted the interlock. (MES005) #53
- 2. The IIPCS starts at - 100 malfunction (MNB079) #88 was no longer needed because MNB078 was made a variable.
- 3. The RCIC starts at - 100 malfunction (MNB081) #90 was no longer needed because MNB080 was made a variable.
- 4. The Line Speed Matcher Fails Malfunction (MMS 022) #120 was deleted due to a plant modification that removed the Line Speed Matcher.
- 5. The Condensate Polisher under drain failure (MCF008) #136 deleted due to lack of Training Value and work needed to fix it.
- 6. The Reactor Water Cleanup (RT) Pump Seizure malfunction (MRW001) #187 deleted. No observable difference between it and the overload trip.
Normal operation should prevent failure at station.
- 9. The flux estimator fails high malfunction (MRC010) #200 deleted duel to Loop Manual operation at LaSalle.
- 10. The flux estimator fails low malfunction (MRC016) #201 deleted as above.
- 11. The flux demand fails malfunction (MRC016) #204 deleted as above.
- 12. The RR Flow decreases malfunction (MRC017) #205 deleted as above.
- 14. Several RWM failure malfunctions (MRD174-177) #263-265 deleted due to installation of a new RWM.
- 15. The blown scram fuse malfunctions (MRP008-015) #279 deleted. Remote functions to remove fuses look the same.
1
! L:\BWR\MC\certsubm.wpf P.6 1/95 Rev. 0 l
LASALLE SIMULATOR
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ANSI /ANS 3.5 CERTIFICATION REPORT ATTACHMENT 1 Description Last Test Next Test Real Time Test #1 12/94 1996 Real Time Test #2 12/94 1996 Steady State Test #1 12/94 1996 Steady State Test #2 12/94 1996 Steady State Test #3 12/94 1996 Manual Scram (TRANS1) 12/94 1996 Trip of all Feedwater (TRANS2) 12/94 1996 Closure of all MSIV's (TRANS3) 12/94 1996 Trip of all Recirc Pumps (TRANS4) 12/94- 1996 Trip of One Recire Pump (TRANS5) 12/94 1996 Main Turbine Trip < 25% (TRANS6) 12/94 1996 Ramp Power Down then Back Up (TRANS7) 12/94 1996 LOCA with Loss or Power (TRANS8) 12/94 1996 Main Steam Line rupture (TRANS9) 12/94 1996 MSIV closure and Stuck SRV (TRANS10) 12/94 1996 Normal Startup (NORM!) 12/94 1996 Turbine Startup (NORM 3) 12/94 1996 Reactor Trip and Recovery (NORM 4) 12/94 1997 Reduce and increase Power (NORM 6A,B) 12/94 1997 Startup and Shutdown 1 Loop (NORM 7A,B) 12/94 1998 Shutdown and Cooldown (NORM 8) 12/94 1996 IIeat Balance and Shutdown Margin Test (NORM 9A,B,C.D) 12/94 1999 ECCS Surveillance Tests (NORM 10A,B,C,) 12/94 1999 L:\BWR\MC\certsubm.wpf P.7 1/95 Rev. O
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LASALLE SIMULATOR ANSI /ANS 3.5 CERTIFICATION REPORT ATTACliMENT I Malfunction Description Malfunction No. ANS Last Next item Test Text MN1001 SRM OUT OF CALIBRATION lilGli 1 21 5/92 1997 MN1005 SRM OUT OF CALIBRATION LOW 2 21 5/92 1997 MN1009 SRM INOP ' MODULE UNPLUGGED 3 21 5/92 1997 MN1013 SRM STUCK DETECTOR 4 21 5/92 1997 MNIC17 SRM/lRM 9 RIVE PWR FAILURE 5 21 5/92 1997 MNI018 IRM OUT OF CALIBRATION 111G11 6 21 5/92 1997 MN1026 IRM OUT OF CALIBRATION LOW 7 21 5/92 1997 MN1034 1RM INOP ' MODULE UNPLUGGED 8 21 5/92 1997 MN1042 IRM STUCK DETECTOR 9 21 5/92 1997 MN1050 LPRM DRIFT UP 10 21 S/92 1997 MN1073 LPRM DRllT DOWN II 21 6/92 1997 MN1096 APRM OUT OF CAL lilGli 12 19 6/92 1997 21 21 MN1102 APRM OUT OF CAL LOW 13 6/92 1997 MN1008 STUCK TIP DETECTOR 14 6/92 1997 MN1109 TIP BALL VLV FAILS OPEN 15 6/92 1997 MNil10 TIP BALL VLV FAILS CLOSED 16 6/92 1997 MNill! TIP IN SillELD SWITC11 FAILUT 17 6/92 1997 MNill2 TIP FAST SPEED SWITCil FAIL 18 6/92 1997 MNill3 TIP SLOW SPEED SWITCil FAILUkE 19 6/92 1997 MRD001 RBM OUT OF C AL lilGil 20 6/92 1997 MRD003 RBM OUT OF CAL LOW 21 6/92 1997 MRD005 RBM INOP ' MODULE UNPLUGGED 22 6/92 1997 MRD007 RBM FAILS TO GO INTO SERVICE 23 6/92 1997 MRD009 RBM STAYS IN SERVICE 24 6/92 1997 MRM001 M.S. LINE RAD MOD FAILS lilGli 29 6/92 1997 MRM005 M.S. LINE RAD MON FAILS LOW 30 6/92 1997 MRM009 0.G. POST TREAT, MON FAILS lilGli 31 6/92 1997 MRM013 0.G. POST TREAT, MON FAILS LOW 32 6/92 1997 MRM015 O.G. POST TREAT MON INOP 33 6/92 1997 MN1013 FUEL POOL VENT FAILS UPSCALE 34 6/92 1997 MRM019 FUEL POOL VENT FAILS DOWN 35 6/92 1997 MRM023 R.B. VENT MON. FAILS UPSCALE 36 6/92 1997 MRM027 R.B. VENT MON. FAILS DOWN 37 6/92 1997 MEE001 LOSS 24/48 VDC PNL l A CB #4 38 3 6/92 1997 MEE002 LOSS 24/48 VDC PNL l A CB #6 39 3 6/92 1997 MEE003 LOSS 24/48 VDC PNL l A CB #4 40 3 6/92 1997 MEE004 LOSS 24/48 VDC PNL l A CB #6 41 3 6/92 1997 MEE005 LOSS OF 250 VDC PNL 121X 42 3 6/92 1997 MEE006 LOSS OF 250 VDC PNL 121Y 43 3 6/92 1997 MEE007 LOSS OF 125 VDC BUS IllX 44 3 6/92 1997 MEE008 LOSS OF 125 VDC BUS lily 45 3 6/92 1997 MEE009 LOSS OF 125 VDC BUS ll2X 46 3 6/92 1997 MEE010 LOSS OF 125 VDC BUS ll2Y 47 3 6/92 1997 MEE0ll LOSS OF 125 VDC BUS 113 48 3 6/92 1997 L:\BWR\MC\certsubm.wpf P.8 1/95 Rev. O
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LASALLE SIMULATOP.
ANSI /ANS 3.5 CERTIFICATION REPORT ATTACIIMENT 1 Malfunction Description Malfunction No. ANS Last Next item Iec.st Text MES001 IIPCS PUMP SEIZURE 49 3 10/92 1997
. MES002 IIPCS PIPE RUPTURE IN CONTAINMENT 50 10 10/92 1997 23 MES003 IIPCS PUMP REDUCED CAPACITY SI 10 10/92 1997 :
MES004 IIPCS lilGH LEVEL ISOLATION FAILS 52 10/92 1997 '
MES005 llPCS F001/F015 XFER FAILURE 53 10/92 1997 MES006 ADS TMR K5 FAILS TO COUNT DWN 54 Id 10/92 1997 MES008 SRV ADS SOLENOIDS Fall 55 Id 10/92 1997 MNB001 SRV PIPE SHEAR IN DW 56 20 10/92 1997 MNB020 SRV PIPE BREAK IN POOL AIR SPACE $7 20 10/92 1997 MNB021 SRV SET POINT DRIFT $8 Id 10/92 1997 MNB040 SRV VLV SEAT ERODED 59 Id 10/92 1997 MES015 LPCS PUMP SElZURE 60 10 10/92 1997 MES016 LPCS DISCII PIPE BREAK IN D.W. 61 10 10/92 1997 23 MES017 LPCS PUMP REDUCES CAPACITY 62 10 10/92 1997 MR11001 RIIR llX TUDE LEAK 63 11/92 1997 MRil003 RilR PUMP REDUCED CAPACITY 64 7 10/92 1997 MRH006 RiiR INJ LINE BREAK IN D.W. 65 10 10/92 1997 MR11009 RiiR S/L BREAK AFTER PRV 66 12/92 1997 MRil01i S/D COOLING LINE BRK OUTSIDE DW 67 7 10/92 1997 MES018 RCIC TURBINE TRIP 68 10 10/92 1997 MES019 RCIC STM. LINE RUPT-UPSTRM F045 69 23 MES020 RCIC TRIP COIL OPEN CIRCUIT 70 10/92 1997 MES02) RCIC PUMP REDUCED CAPACITY 71 12/92 1997 MCW001 RilR SW PUMP REDUCED CAPACITY 72 6 12/92 1997 MCWOO2 RilR SW PUMP TRIPS 73 6 12/92 1997 MNB059 RPV INST. LINE NBl2B BRK-A RWLC 74 22 12/92 1997 MNB060 RPV INST. LINE NBl5B BRK-WR, SDR 75 22 12/92 1997 MNB061 RPV INST. LINE NB10B BRK-LLS, ADS 76 22 12/92 1997 MNB062 RPV INST. LINE NB25B BRK 77 22 12/92 1997 MNB063 RPV INST. LINE NB23B 78 22 12/92 1997 MNB064 'A' SCRAM .AT 22.5"-N024A&C COC 111 79 12/92 1997 MNB065 'A' SCRAM AT 2.5"-N024A&C OOC LO 80 12/92 1997 MNB066 'B' SCRAM AT 22.5"-N024B&D OOC 111 81 12/92 1997 MNB067 'B' SCRAM AT 2.5"-N024B&D OOC LO 82 6/93 1998 MNB068 111 LVL TRIP AT 55" FAILS-k624 HI 83 6/93 1998 MNB069 111 LVL TRIP RESET TO 45"-k624 LO 84 6/93 1998 L MNB070 LVL 2 ISO & P. LOCA REC OOC 111 85 6/93 1998 MNB073 'D' LVL 2 ISO & P. LOCA REC OOC HIGH 85 6/93 1998 MNB074 LVL 2 ISO & P. LOCA REC OOC LO 86 6/93 1998 ;
MNB076 'C' LVL 2 ISO & P603 WR OOC LOW 86 6/93 1998 MNB077 'D' LVL 2 ISO & P001 WR OOC LOW 86 6/93 1998 MNB078 IIPCS & DG START AT +13"-NO31111 87 6/93 1998 MNB079 IIPCS & DG STARTR AT -100"-N031 88 6/93 1998 MNB080 RCIC STARTS AT -20" -NO37111 89 6/93 1998 MNB081 RCIC STARTS AT -130"-N037 LO 90 6/93 1998 MCA001 SGTS DISCil VLV IVG03 FAILS OPEN 91 6/93 1998 L:\BWR\MC\certsubm.wpf P.9 1/95 Rev. O
LASALLE SIMULATOR
. ANSI /ANS 3.5 CERTIFICATION REPORT ATTACl{ MENT I Malfunction Description Malfunction No. ANS Last Next item Test Text MCA002 SGTS DISCil VLV IVG02 FAILS CLOSED 92 6/93 1998 MCA003 SGTS DISCII VLV IVG03 FAILS AS IS 93 6/93 1998 MCA004 SGTS PRI FAN IVG01C SEIZURE 94 6/93 1998 MCA005 D W PRESS INST LINE NB27A BREAK 95 6/93 1998 MCA006 DW VAC BREAKER FAILS OPEN 96 6/93 1998 MCA010 D W BREAKER FAILS CLOSED 97 6/93 1998 MCF016 F W llEATER 16 TUBE RUPTURE 98 6/93 1998 MCF035 F W llTR 16 NORM DRN FAILS CLOSED 99 6/93 1998 MCF081 F W llEATER 151UBE RUPTURE 100 6/93 1998 MCF021 F W llEATER 14 TUBE RUPTURE 101 6/93 1998 MCF037 F W llTR 15 NORM DRN FAILS CLOSED 102 6/93 1998 MCF040 F W llEATER 14 NORM DRN FAILS CLOSED 103 6/93 1998 MCF024 F W llEATER 13 TUBE RUPTURE 104 6/93 1998 MCF043 F W I?<TR 13 EMER DRN FAILS OPEN 105 6/93 1998 MCF027 F W IIEATER 12 TUBE RUP1URE 106 9 6/93 1998 MCF046 F W llTR 12 NORM DRN FAILS CLOSED 107 6/93 1998 MCF030 F W llEATER 11 TUBE RUPTURE 108 6/93 1998 MCF049 F W llTR 11 NORM DRN FAILS CLOSED 109 6/93 1998 MCF052 11 D TANK NORM DRN FAILS CLOSED 110 6/93 1998 MCF053 IlEATER DRAIN PUMP SEI7URE 111 6/93 1998 MMS 001 MSR DRN TK NORM DRN Fall CLOSED 112 6/93 1998 '
MMS 003 IST STG RifTR DR TK NRM DRN FC 113 6/93 1998 MMS 005 2ND STG RilTR DR TK NRM DRN FC 114 6/93 1998 MMS 007 EllC llYDRAULIC SYSTEM RUPTURE 115 6/93 1998 MMS 008 ACCEL RATE CONTROL FAILS 111 116 6/93 1998 MMS 009 ACCEL RATE CONTROL FAILS LOW 117 6/93 1998 MMS 010 INTERCEPT VLV FAILS CLOSED 118 6/93 1998 i MCF016 INTERMED STOP FAILS CLOSED 119 6/93 1998 MCF022 LINE SPEED MATCilER FAILS INOP, 120 6/93 1998 MCF023 PWR/ LOAD UNBAl RPT & LOAD REJECTION 121 7/93 1998 ;
MCF024 PWR/ LOAD UNBAL CKT FAILS OFF 122 7/93 1998 MCF025 Cl!EST/SiiELL WARMING FAILURE 123 7/93 1998 MCF026 MECil TRIP VLV FAILS TO TRIP 124 7/93 1998 MCF027 TURBINE SPEED CONTROL FAILS 125 7/93 1998 MCF028 EllC PR REG FAILS - MAX COMB FLOW 126 25 7/93 1998 MMS 029 EllC PR REG FAILS-BACKUP WORKS 127 25 7/93 1998 MMS 030 EllC MS PR XMTR lil-MAX FLOW 128 25 7/93 1998 MMS 032 EllN MS PR XMTR LO-BACKUP OK 129 25 7/93 1998 MMS 034 EllC PUMP FAILS TO AUTO START 130 7/93 1998 MMS 036 MASTER TRIP SOL A OPEN COIL 131 15 7/93 1998 MMS 079 MASTER TRIP SOL B OPEN Colt 131 15 7/93 1998 MCF057 COND PUMP SilEARED SilAFT 132 9 7/93 1998 MCF061 COND PUMP SEIZURE 133 9 7/93 1998 ;
MCF065 BSTR PUMP SilEARED SilAFT 134 9 7/93 1998 MCF001 POLISilER RESIN DEPLETION 135 7/93 1998 MCF008 POLISilER UNDER DRAIN FAILURE 136 7/93 1998 MCN001 CONDENSER TUBE LEAK 137 7/93 1998 MCF015 POLISilER llIGli D/P 138 7/93 1998 L:\BWR\MC\certsubm.wpf P.10 1/95 Rev. 0
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LASALLE SIMULATOR ANSl/ANS 3.5 CERTIFICATION REPORT ATTACllMENT 1 Malfunction Description Malfunction No. ANS Last Next item Test Text MCF069 RFP FLOW XMTR FAILS HIGH 139 22 7/93 1998 MCF072 RFP FLOW XMTR FAILS LOW 140 22 7/93 1998 MNB082 M/S STA BMPLESS XFER FAILS 141 7/93 1998 MNB086 LVL SP REDUCED TO POST SCRAM LVL 142 7/93 1998 MNB087 POST SCRAM LVL SP NOT REDUCED 143 7/93 1998 MNB088 RWLC PDUS FAIL TO RAMP DEVIATION 144 7/93 1998 MNB089 MS FLO XMTR C34-N003 FAILS HI 145 22 7/93 1998 MNB093 MS FL.O XMTR C34-N004 FAILS LO 146 22 7/93 1998 MNB097 NR LVL XMTR C34-N004 FAILS HI 147 22 7/93 1998 MNB100 NR LVL XMTR C34-N004 FAILS LO 148 22 7/93 1998 MCF075 TDRFP SilEARED SilAIT 149 9 7/93 1998 MCF077 MDRFP SilEARED SilAFT 149 9 7/93 1998 MCF033 FEEDWATER RUPTURE OUTSIDE DW 150 10 7/93 1998 MCF034 FEEDWATER RUPTURE INSIDE DW 151 10 7/93 1998 MCF078 TDRFP TRIP 152 9 7/93 1998 ,
MCF080 TDRFP FAILS TO TRIP 153 9 7/93 1998 MCF082 TDRFP HP SV FAILS CLOSED 154 9 7/93 1998 MMS 037 TDRFP HP STEAM LINE RUPTURE 155 7/93 1998 MMS 039 TDRFP LP STEAM LINE RUPTURE 156 7/93 1998 MCF084 TDRFP SElZURE 157 9 7/93 1998 MCF086 FEED REG. VALVE FAILS OPEN 158 9 7/93 1998 MCF087 FEED REG. VALVE FAILS CLOSED 159 9 7/93 1998 MCF088 FEED REG. VALVE FAILS AS IS 160 9 7/93 1998 MCF089 MDRFP FAILS TO TROP 161 9 7/93 1998 MCF090 MDRFP LOCKED ROTOR 162 9 7/93 1998 MEE048 SYNC. CilECK RELAY FAILURE 163 3 7/93 1998 MEE049 GENERATOR TRIP 164 16 5/94 1999 MEE050 FAILURE OF GEN TO TRIP 165 5/94 1999 MMS 078 STATOR COOLING RU'NBACK FAILURE 166 5/94 1999 MEE051 AUTO VOLTAGE RET FAILS lilGH 167 5/94 1999 MEE052 AUTO VOLTAGE REG FAILS LOW 168 5/94 1999 MEE053 GRID TRANSIENT 169 3 5/94 1999 MEE054 GEN FIELD FLASli FAILURE 170 3 5/94 1999 MDG001 DG GOVERNOR FAILURE 171 3 5/94 1999 MDG004 DG LOSS OF FIELD 172 3 5/94 1999 MDG007 DG TRIPS & LOCKS OUT 173 3 5/94 1999 MDG010 DG SEQUENTIAL LOADING FAILURE 174 3 5/94 1999 MDG013 DG OUTPUT BREAKER TRIP 175 3 5/94 1999 MCN002 SJAE SUCTION LINE RUPTURE 176 5 5/94 1999 MCN003 SLOW BURN IN OFF-GAS PIPING 177 5/94 1999 MCN004 EXPLOSION IN OFF-GAS PIPING 178 5/94 1999 MCN005 CilARCOAL BED RUP1URE 179 5/94 1999 MCN006 IlOLD UP PIPE RUPTURE 180 5/94 1999 MCN007 PREFILTER RUPTURE 181 5/94 1999 MCN008 SJAE PRESS REG FAILS lilGli 182 $/94 1999 MCN009 SJAE PRESS REG FAILS LOW 183 5 5/94 1999 MMS 041 OG PREllEATER PRESS REG FAILS HIGH 184 5/94 1999 l MMS 042 OG PREllEATER PRESS RFG FAILS LOW 185 5/94 1999 i L:\BWR\MC\certsubm.wpf P.11 1/95 Rev. O
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LASALLE SIMULATOR ANSI /ANS 3.5 CERTIFICATION REPORT A7TACilMENT I Malfunction Description Malfunction No. ANS Last Next item Test Text MDL001 SBLC PUM RV SETPOINT DRIFT 186 5/94 1999 MRW001 RWCU PUMP SilAFT SECURE 187 5/94 1999 MRWOO4 RWCU FILTER lilGH DIFF PRES 188 5/94 1999 MRWOO7 FILT/DEMIN RESIN DEPLETION 189 7/94 1999 MRW010 RWCU SYSTEM LEAK AFTER F004 190 7/94 1999 MRW0ll FILT/DEMIN FAILS-RESIN INTRU 191 7/94 1999 MRW014 FILT/DEMIN FCV FAILS OPEN 192 7/94 1999 MRW017 FILT/DEMIN FCV FAILS CLOSED 193 7/94 1999 MCWOO9 RBCCW SYSTEM RUPTURE 194 8 7/94 1999 MRC001 RR PMP NO.1 SEAL FAILS 195 1C 7/94 1999 MRC003 RR PMP NO. 2 SEAL FAILS 196 IC 7/94 1999 MRC005 RECIRC PUMP SE!ZURE 197 4 7/94 1999
- MRC007 RR PMP TRIPS AFTER STARTING 198 17 7/94 1999 MRC009 JET PUMP FAILURE 199 17 7/94 1999 i MRC010 FLUX ESTIMATOR SIGNAL FAILS 111G11 200 7/94 1999 MRC0ll FLUX ESTIMATOR SIGNAL CYCLIC 201 7/94 1999 MRC012 RR PMP FAILS TO RPT 202 17 7/94 1999 MRC014 RR PMP XFER FAILS (GOES TO 0) 203 17 7/94 1999 MRC016 FLUX DEMAND III LMTR S.P. DECR 204 7/94 1999 MRC017 RR FLO DECR (LMTR K615 Fall LO) 205 7/94 1999 MRC018 RECIRC FCV ACTUATOR JAMMED 206 7/94 1999 MRC020 RUNBACK FAILURE < RFP & LO LVL 207 7/94 1999 MRC021 RECIRC FCV LOCKUP OCCURS 208 7/94 1999 MRC023 RECIRC FCV VELOCITY LIM FAILS 209 7/94 1999 MRC025 RECIRC FCV FLOW FB FAILS 111 210 17 7/94 1999 MRC027 RECIRC FCV FLOW FB BAILS LOW 211 17 7/94 1999 MRC029 RECIRC PUMP SilEARED SilAFT 212 4 7/94 1999 MRC031 RR PMP SPURIOUSLY DOWNSillFTS 213 17 7/94 1999 MRC033 RECIRC LOOP SUCTION RUPTURE 214 7/94 1999 MRC035 RECIRC LOOP DISCil RUPTURE 215 IB 7/94 1999 1C 7/94 1999 MRC037 RR PMP FAILS TO AUTO DOWNSHIFT 216 7/94 1999 MCN010 CIRC. PUMP SElZURE 217 5 7/94 1999 MRDl71 RSCS FAILURE TO LATC11 AT LPSP 218 7/94 1999 MRD172 RSCS FAILURE TO UNLATCil AT LPSP 219 7/94 1999 MRD173 RSCS FAILURE TO LATCil AT LPAP 220 7/94 1999 MRDl74 RSCS FAILURE TO UNLATCH AT LPAP 221 7/94 1999 MA1001 PLANT AIR SYSTEM RUPTURE 222 (2) 7/94 1999 MA1002 RUNNING DW AIR COMPRESSOR TRIP 223 (2) 7/94 1999 MA1003 FUEL ELEMENT FAILURE 224 (2) 7/94 1999 MNB103 FUEL ELEMENT FAILURE 225 14 7/94 1999 MRP001 RPS MG SET TRIP 226 (11) 7/94 1999 MEE012 LOSS OF TRil42 227 3 7/94 1999 MEE013 LOSS OF TR141 228 3 7/94 1999 MEE014 LOSS OF TRIE 229 3 7/94 1999 ,
MEE015 LOSS OF BUS 151 230 3 7/94 1999 MEE016 LOSS OF BUS 152 231 3 7/94 1999 MEE017 LOSS OF BUS 141X 232 3 7/94 1999 L:\BWR\MC\certsubm.wpf P.12 1/95 Rev. O
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LASALLE SIMULATOR ANSI /ANS 3.5 CERTIFICATION REPORT ATTACIlMENT I Malfunction Description Malfunction No. ANS Last Next Item Tnt Text MEE018 LOSS OF BUS 142X 233 3 7/94 1999 MEE019 LOSS OF BUS 141Y 234 3 7/94 1999 MEE020 LOSS OF BUS 142Y 235 3 7/94 1999 MEE021 LOSS OF BUS 143 236 3 7/94 1999 MEE022 LOSS OF SWGR 135X &l35Y (141Y) 237 3 7/94 1999 MEE023 UPS FAILURE TO XFER TO 235X-2 238 3 7/94 1999 MEE024 LOSS OF SWGR 136X & 136Y (142Y) 239 3 7/94 1999 MEE025 345 KV BUS 1 FAULT 240 3 8/94 1999 MEE026 LOSS OF MCC 135X-1 241 3 8/94 1999 MEE027 LOSS OF MCC 135X-2 242 3 8/94 1999 MEE028 LOSS OF MCC 135X-3 243 3 8/94 1999 MEE029 LOSS OF MCC 135Y-2 244 3 8/94 1999 MEE030 LOSS OF MCC 136X-1 245 3 8/94 1999 MRWO31 LOSS OF MCC 136X-2 246 3 8/94 1999 MEE032 LOSS OF MCC 136Y-1 247 3 8/94 1999 MEE033 LOSS OF MCC 136Y-2 248 3 8/94 1999 !
MEE034 LOSS OF MCC 136Y-3 249 3 8/94 1999 MEE035 LOSS OF MCC 143-1 250 3 8/94 1999 MEE036 LOSS OF MCC 135Y-1 251 3 5/91 1996 MEE037 LOSS OF MCC 136X-3 252 3 5/91 1996 MEE038 LOSS OF SWGR 13] A & 131B (8 5i) 253 3 6/91 1996 MEE039 LOSS OF SWGR 133A & 133B (151) 254 3 6/91 1996 MEE040 LOSS OF SWGR 131X & 131Y (141X) 255 3 6/91 1996 MEE041 345 KV 13US 13 FAULT 256 3 6/91 1996 MEE042 LOSS OF SWGR 132A & 132B (152) 257 3 6/91 1996 MEE043 LOSS OF SWGR 134A & 134B (152) 258 3 6/91 1996 MEE044 LOSS OF SWGR 132Y & 132Y (142X) 259 3 6/91 1996 MEE045 LOSS OF SWGR 134X & 134Y (42Y) 260 3 6/91 1996 MEE046 BUS 141Y LOAD SilED RELAY FAILS 261 3 6/91 1996 MEE047 BUS 143Y LOAD SilED RELAY FAILS 262 3 6/91 1996 MRD178 RWM FAILS DETECT INSERT ERROR 266 6/91 1996 MRDl79 RWM FAILS DETECT WTilDRW ERROR 267 6/91 1996 i MNB104 MSL BREAK IN DW BEFORE RES1RICTOR 268 20 6/91 1996 i MNil105 MSL BREAK IN DW AITER RESTRICT 269 20 6/91 1996 MNB106 MSL BREAK IN STEAM TUNNEL 270 20 6/91 1996 MNB107 LOW-LOW SETDOWN LOGIC FAILS 271 6/91 1996 MNB108 LOW-LOW SETDOWN LOGIC INITIATES 272 6/91 1996 MMSO43 IlYPASS MSBPV FAILS OPEN 273 25 6/91 1996 l MMS 048 BYPASS MSBPV FAILS CLOSED 274 25 6/91 1996 l MNB109 MSIV FAILS TO CLOSE 275 25 6/91 1996 MRP003 ROS SYS SCRAM BUTTONS FAILS 276 11 6/91 1996 MRP005 FAILURE OF AUTO SCRAM CIRCUIT 277 24 6/91 1996 MRP006 RPS MG SET VOLT REG FAILS 278 6/91 1996 MMS 053 IST STG PR.SV INILK ALLOWS SCRAM 280 6/91 1996 MMS 054 IST STG PR/SV INTLK SCRAM FAILS 281 6/91 1996 MRD180 ROD BLOCK FAILURE 282 6/91 1996 MMS 055 MAIN TURBINE AUTO TRIP LOGIC FAILS 283 6/91 1996 MMS 056 TURBINE SHAFT BOW 284 15 6/91 1996 L:\BWR\MC\certsubm.wpf P.13 1/95 Rev. O
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LASALLE SIMULATOR ANSI /ANS 3.5 CERTIFICATION REPORT ATTACllMENT I Malfunction Description Malfunction No. ANS Last Next item Teg Text MMS 057 IST STG RilTR TUBE LEAK 285 6/91 1996 MMS 059 2ND STG RilTR TUBE LEAK 286 6/91 1996 MSS 061 QUILL S11 AFT FAILURE 287 6/91 1996 MCN013 IlOTWELL MAKEUP VLV FAILS OPEN 288 5 6/91 1996 MCN014 IlOTWELL MAKEUP VLV FAILS CLOSED 289 5 6/91 1996 MCN015 IlOTWELL REJECT VLV FAILS OPEN 290 5 6/91 1996 MCN016 110TWELL REJECT VLV FAILS CLOSED 291 5 6/91 1996 MMS 062 TURB STOP VLV FAILS OPEN 292 7/91 1996 MMS 066 TURB STOP VLV FAILS CLOSED 293 7/91 1996 MMS 070 TURB CONT VLV FAILS OPEN 294 25 7/91 1996 MMS 074 11]RB CONT VLV FAILS CLOSED 295 25 7/91' 1996 MRD027 CRD PUMP REDUCED CAPACITY 296 13 7/91 1996 MRD029 02-27 STUCK ROD 297 12 7/91 1996 MRD049 02-27 UNCOUPLED ROD 298 12 7/91 1996 MRD069 CONTINUOUS ROD WITIIDRAWAL 299 12 7/91 1996 MRD070 02-23 ROD DRIFT IN 300 12 7/91 1996 MRD090 02-19 COLLET FINGER FAILURE 301 12 7/91 1996 MRDI10 02-35 tilGil NOTCil WORTil 302 7/91 1996 MRD130 ROD WITIIDRAWS BUT RE-INSERTS 303 7/91 1996 MRD131 REED SWITCil STUCK CLOSED 304 7/91 1996 MRD151 LOSS OF ROD POSITION INDICATION 305 7/91 1996 MRDl81 SDV DRAIN & VENT VLV Fall OPEN 306 7/91 1996 MCA014 SUPP. POOL WATER LEAK 307 23 7/91 1996 MDG016 DG ENGINE START FAILURE 308 3 7/91 1996 MDG019 DG SYNC. CilECK RELAY FAILURE 309 7/91 1996 MCF091 FW PUMP SUCT TRIP OUT OF CAL 310 9 7/91 1996 MCF092 FW PMP FUNCT GEN FAILURE DEC 311 9 7/91 1996 MCF094 FD REG VLV FUNCT GEN FAIL DEC 311 9 7/91 1996 MCF098 FW PMP FUNCT GEN FAILURE INC 312 9 7/91 1996 MCF100 FD REG VLV FUNCT GEN FAILURE INC 312 9 7/91 1996 MCF095 FW MIN FLOW VLV RANDOM CYCC 313 9 7/91 1996 MRD182 RMCS CONTROL FAILURE 314 7/91 1996 MRil012 RilR llX B/P VLV TIMER Fall 315 7/91 1996 MRP016 SCRAM AIR llEADER FAILURE 316 19 7/91 1996 MRP017 FAILURE OF RPS CilANNEL TO SCRAM 317 24 7/91 1996 MNBil7 REACTOR INSTABILITY EVENT 318 17 7/91 1996 MRWO20 RWCU NRi1X TUBE LEAK 319 7/91 1996 MW1001 SW PLUGGED STRAINER 320 6 7/91 1996 MWS002 SERVICE WATER PMP AUTO TRIP 321 7/91 1996 MCG001 STATOR COOLING WTR PMP TRIP 322 7/91 1996 MEE055 345 KV BUS 10 FAULT 323 7/91 1996 MEE056 MISC AU1D CONTROL POWER FAILURE 324 7/91 1996 MRC029 RR FCV FAILURE 325 7/91 1996 MRC041 RR RUPTURE INSIDE ISOLATIONS 326 7/91 1996
\MRM038 MSL NUMAC's Fall TO TRIP 327 7/91 1996 MNB205 MSL RUPFURE INSIDE MSIV's 328 7/91 1996 MRD277 DEGRADED SDV 329 7/91 1996 MRD279 CRD FCV FAILURE 330 7/91 1996 L:\BWR\MC\certsubm.wpf P.14 1/95 Rev. O
o l LASALLE SIMULATOR I
. ANSI /ANS 3.5 CERTIFICATION REPORT ATTACllMENT I Malfunction Description Malfunction No. ANS Last Next item Teg Text MCFill FW TESTABLE CliECK FAILS 331 8/93 1996 MNB122 FW FLOW FAILS LOW 332 1/93 1996 MNB124 FW FLOW FAILS 111 333 1/93 1996 MR11014 PLUGGED SUCTION STRAINERS IN SP 334 4/94 1997 MRP019 SCRAM CONTACTOR FAILS CLOSED 335 3/94 1997 MRP027 SCRAM CONTACTOR FAILS OPEN 336 3/94 1997 MRD337 SCRAM DISCilARGE VOLUME RUPTURE 337 6/94 1997 I
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