ML20087G102

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Submits 1995 Simulator Certification Rept & NRC Form 474, Simulation Facility Certification
ML20087G102
Person / Time
Site: Byron, Comanche Peak  Luminant icon.png
Issue date: 08/11/1995
From: Graesser K
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-95-0282, BYRON-95-282, NUDOCS 9508160231
Download: ML20087G102 (22)
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  • Q>mmonwealth IMison Osmpany
  • ll)ron Generatmg St.trion

. -1450 North German Church Road 11yron. I!. 61010 9'9 6 Tri HIS 23446 61 August 11, 1995 LTR: BYRON 95-0282 FILE: 1.10.0101 United States Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

Byron Nuclear Power Station Units 1 and 2 " Byron Simulation Facility" Certification Renewal of Simulator Facility NRC Docket Number 50-454 and 50-455

REFERENCE:

Title 10, Code of Federal Regulations, Part 55, Subpart E, Section 55.45, " Operating Tests" Gentlemen:

The purpose of this letter is to submit the 1995 Byron Station Simulator Certification Report and NRC Form 474, Simulation Facility Certification.

This report is being submitted as required by 10CFR55.45 on the fourth anniversary of the initial certification of the Byron Station Simulator. This submittal addresses both operating units at Byron Station with Byron Unit i serving as the reference plant.

The enclosed report describes performance tests conducted from 1991 to 1995 and provides a revised Ferformance Test Schedule for 1995 through 1999.

These documents certify the Byron Simulation Facility meets the Nuclear Regulatory Commission's regulations.

NRC Forms 474 are enclosed due to the changes in the Performance Test Schedule.

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4 Byron Ltr. 95-0282 Page 2 August 11, 1995 If you have any questions regarding this submittal, please contact Steve Pettinger, Operations Training Supervisor, at (015) 234-5441 ext. 3212 or Jeff Hamilton, Simulator Fidelity / Certification Coordinator, at (815) 234-5441 ext.

3221.

Respectfully,

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K.L. Graes er Site Vice President Byron Nuclear Power Station KLG/RC/rp Attachment (s)

't cc: H.J. Miller, NRC Regional Administrator - RIII G.F. Dick Jr., Byron Project Manager - NRR H. Peterson, Senior Resident Inspector - Byron Office of Nuclear Facility Safety - IDNS l

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l N f5AC FORM 474 U.S. NUC1. EAR REGut.ATORY COMMISSION AreRowen ev oses: No. at nesaa g EXPtRES: 19/31/99 ESTIMATED IEJFEN PER FESPONSE TO CXXAPLY ntTH ?>ss I PdCNATION rn i rf TION FEQUEST: 120 HOURL FCRWAFC l

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REGULATDFPf CDuMISSON, WASMNGTON, DC 205%0001, AND TO THE PAPERWORK REDUCnON PRCUECT Qt SO413ah OmCE OF WANAGEMENT AND ButXiET. WASHpsG'ON DC lNB03 INSTRUCTIONS: The form a to De fttee ke mdhed tenshr.anm, secenmcmmn (ff reggsareal, and tot any change to a L . lessfy peNormance tegeng plan meo# ARef eWims DJberuRal af I suca o n. Pr.na. m. vono mg eneorm==n ano caece me oproonee nos io no. cme f on ser suormnes 1 F Acn>TY occra HuueER Byron Station - Unit 1 50 - 454 l

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2. Documenigen a senDw for NRC rowe en occarone men to CFR $5.45(4 1
3. The .imusatson tacany moess P e g.mdance conte nod n ANSI /ANS 3 S.194$, as .ndorsed by NRC Reguissary Guise t 648. l s mee we any ExcErnONs so me cartrne .on or m . cNEcx HERE [ ] and ee.cnn. evey .a .ean.o,.s e.g no ee ty NAus (w eater .oerer.cuory ANo LoCAnow oF sJMULATON F ACiUTV l Byron Station Training Facility 4450 North German Church Road Byron, IL 61010 l l

SluVLAftON F ACAJTV PERFORuANCE TEST ABSTRACTS ATTACHED. F F or persormece essa consueved a rio penas enang een tw case et rus corese om; j DESCRPTION 05 &EMOAMANCE TESDNQ COMPLETED lAnca eaceans pages as neceuwy WW Wenot rw sem encgcen eeng canonued) )

See enclosure, four year Simulator Certification Renewal Repor*

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SluyLAfloN F ACTUTY PERFORMANCE TESDNG SCHEDULE AT' ACNED (For sie conchxf et w ', 25* siperswmance tests per peer for tw Anis-yw pense conwneneang ee X rw eere er rw ce*8canoro osmPnoN os +tnFc+a4ANCE TESTiNO 'O EiE CCNDUCTED 4Ar'eca ecotone peges as riecesswy aw soeret me sem oessnpean bemy cwamved)

See enclosure, four year Simulator Certification Renewal Report and attached Malfunction Testing Schedule.

i PtReopA4ANCE TE5tNG PLAN CHANGE (For er mooreceoen m e e twang gum 9 suersonse en a prewns seeeceron)

DEscarnos of PtRec*wNcs TEsnNG PLAN cxANGE sace noseen. e.ges a nee awy are menet r. ee eenvs.en een, carenuse; 1 See enclosure,Section IV.c of the four year Simulator Certification Renewal keport for Malfunctions added since the initial certification testing schedule.

s HECERnFICADON (Descnos correcewe acoww ranen streen resure of carnemeteo cedormwice sesong e accwoortes een 10 CIR Sid$(6y!M (Arrace semoorts pagee as necesswy ew were4 me een oescapoon peng cwenved)

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SJONAM)% e AL/THOWED f4EP [$EN1AINE *:'(E DATE g/ station Manager g9y m ac4ureence esm 10 Cf H */ A. comm rucwena u trus eorm . nam t.e ewommee to ine AMC as soucos gv MAA ADORESSEO 'I DIRECTOR. OmCE DF NUCLDR PUCTOR REQUULnON SY DEUVE1'Y IN PERSON ONE WHITE FUNT NORTH U S. NUCLEAR Af 0VuTORY CCWuisslON TO THE NEC OrtCE AT 11955 POCKvial Pia y so m q-  ; u. . nm r .-

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4 TTmC FORM 474 U.S. NUCLEAR REGULATORY COMMISSION APPRovro av ous: NO,315441M g ExPtRES: 10/31/99 r3TEAATED BUF0EN PER FESPONSE TO Cx)uPLY wtTH nas lHFe8AAT10N rnarrTON REQUEST: 120 HOURS. FORWAm SIMULATION FACllJTY CERTIFICATION WMMNTUGAN &#NSNATE T NE rMAfm Mc aEcoms - aEuEur s w a - me. us wuauR REGULATORY fmeteirus, WASHINGTON. DC 20$$$4001,AND TO THE PAMPWON REDUCDON PRCUECT Q00413al.OmCE OF MANAGEMO(T AND BUDGET. WASHINGTON. DC 20$03 pesTauenoNS: The wm a io se nee ter msuas cenacaten, recenmemen in seaweesi, ano sor any snange in a sommenon saceey penormance tesung pian maae one eeues suommai at euca e sun Promse tw soisamng e*.manan ena enece the amoeconaw bos to me. caw reason eat suommat FAcunt - DOCKET NUM8ER Byron Station - Unit 2 54- 455 uCENsEE DATE Com Ed Tn o to senny mar.

1. The abe>se named faci #y iscensee a useng a enmusaison teciley conssteg sone 8y of a pannidenced semuuser this meem sne eequnements of to CFR ES eS.
3. Docummahon a avenabe for NRC eeeen en accoreence men to CFR SS.aSfbt
3. The s,munauon facey meets tne guseence conta,ned m ANSI / ANS 3.S.1885, as ensorted by NRC Regdalery Gimme 1 lat.

s m-. we any ExCtPTIONS to the cenecean at me nom. CHECK HERE l ] and cescnbe M4 on oddanno pages as necenwy NAue tw een ow=aceaani ANO LOCADON OF EIMULADON F ACIUTY Dyron Station Training Facility 4450 North German Church Road Byron, IL 61010 sWLATcN F ACrJTY PERFORMANCE TEST ABSTRACTS ATTACHEO. (Fw pemwmwice run sensuetes a rw pened enawig aan rw ese W rw cwescaem)

DE5vrin>N OF PERFOHMANGE TE$itNQ COMA %fTED (Anace socoone pages as neceuwy and ederie8y Ine som aescrusan cong cenonuedJ See enclosure, four year Simulator Certification Renewal Report 1

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siuutATow F ACrtrTV etRFoRMANCE TES% SCMEDULI ATTACHED /For re eanswer or scoremmerse r & of performerce assa per yew for tw Awyer pense conwnenemg me l X re e eetru e-eace m s ocscumON os PtReoRuANcE TEST NG To bE CONOUCTED. sApoca ecceone peges a neceuwy ww merery tw awn oeunper cong cwonweaJ See enclosure, four year Simulator Certification Renewal Report and attached Malfunction Testing Schedule.

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oc.2-- os Ptyco-CE Ttsn~o ,uN C-E ,Annen a o.n. . , co y a,. ,.y ,. . - .em, ,_, l See enclosure,Section IV.c of the four year Simulator Certification Renewal Report for Malfunctions added since the initial certification testing schedule.

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BYRON STATION SIMULATOR FOUR YEAR CERTIFICATION REPORT AUGUST,1995 Simulator Certification Renewal Report Approval w ,}  ?~Y'?b Simulg(or elipf/ Certification CoorIlinator Date b/fru- 4ffjY-7, f-Y-95~

Operations Training Supervisor Date dm (7bfillt s-+-vs-Byron Statjo[ Training Supervisor Date 1

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BYRON STATION SIMULATOR FOUR YEAR CERTIFICATION REPORT 1 AUGUST,1995 l

TABLE OF CONTENTS f I

1. Int roduction . . . . . . . . . . . . . . . . . . .. .. . ......... ... ... ....... 3
11. References ....... ..... . .......... . ...... .................. 3 '

lit. Reporting Requirements ............... ... ....... . . . . . . 3 ,

r IV. Implementation ....... . .. . . ...... ....... .... ..... 4  !

A. Uncorrected performance tast failures . . . ................ . ....... 4 B. Description of periormance testing completed ......... ...... . . ..... 4 I C. Description of new performance tests . . .................. .... . ... 7 j D. Performance test schedules for the subsequent four years . . ..... . . ...... 8 .l I

Attachment:

Certified Malfunction Test Schedule.

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i BYRON STATION SIMULATOR FOUR YEAR CERTIFICATION REPORT AUGUST,1995

l. Introduction The Byron Station Simulator is used to conduct NRC License operating tests and is therefore required to meet the criteria established in 10 CFR 55.45. To comply with this criteria, a report I which identifies simulator testing status must be submitted every four years on the anniversary of the simulator certification. The Byron Station Simulator was originally certified on August 27, 1991.

The Commonwealth Edison owned Westinghouse PWR 4-loop, 3411 MW power plant simulator is used for training and testing the Byron Unit 1 and Unit 2 Operators. Because of the near exact duplication between the two units, it is considered a plant specific simulator for both Byron Unit 1 and Unit 2. The Byron Station Simulator is modeled after Byron Unit 1, with Byron Unit 1 being considered the referenced plant.

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For the purposes of this report a certification year starts August 26 of the first year and ends 1 August 25 of the next year.

II. References A. Title 10, Code of Federal Regulations, Part 55, Subpart E, Section 55.45, " Operating Tests". ,

B. NRC Regulatory Guide 1.149, " Nuclear Power Plant Simulation Facilities for use in ,

Operator License Examinations" >

C. ANSI /ANS-3.5-1985, " Nuclear Power Plant Simulators for Use in Operator Training".

111. Reporting hquirements The requirements of this report as outlined in 10 CFR 55.45 are :

A. Paragraph 55.45 (b)(5)(ii): Identify any urcorrected performance test failures, and submit a schedule for correction of such performance test failures,if any.

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 pcrformance tests, if different, to be i conducted on the smulation facility during the subsequent four year period.

D. Paragraph 55.45 (b)(5)(vi): A schedule for the conduct of approximately 25 percent of the performance tests per year for the subsequent four years.

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BYRON STATION SIMULATOR FOUR YEAR CERTIFICATION REPORT AUGUST,1995 IV. Implementation A. Identify any uncorrected performance test failures, and submit a schedule for correction of such performance test failures, if any.

1. All certified performance test failures have been corrected.

B. Description of performance testing completed for the simulation facility.

This section contains a description and the results of the performance testing completed during the last four year period.

1. Computer Real Time Test The Computer Real Time Test is conducted annually using the Byron Simulator Real Time Test Procedure. This procedure verifies that the simulsior complex operates in real time.

Certification year 1991/1992 Computer Real Time Test was satisfactory.

Certification year 1992/1993 Computer Real Time Test was satisfactory.

Certification year 1993/1994 Computer Real Time Test was satis. factory.

Certification year 1994/1995 Computer Real Time Test was satisfactory.

2. Steady State Tests The Steady State Tests are conducted annually using the Byron Simulator Acceptance Test Procedure (Section 7.1, Steady State Testing).

The Steady State heat balance tests were performed at 30%,90% and 100%

power. These power levels were chosen due to the availability of Byron Unit 1 plant data. The simulator parameters were compared with plant data and heat balance information, all parameters were within the tolerances for critical and non-critical parameters as established in ANSl/ANS-3.5-1985.

The 100% power 60 minute stability test was performed by recording data et 100% power and then running the simulator for 60 minutes. Following 60 minutes of operation, data was recorded again. The final values did not vary more than i 2% of the initial values. The test results are listed below:

Certification year 1991/1992 Steady State Tests were satisfactory.

Certification year 1992/1993 Steady State Tests were satisfactory.

Certification year 1993/1994 Steady State Tests were satisf actory.

Certification year 1994/1995 Steady State Tests were satisf actory.

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i BYRON STATION SIMULATOR FOUR YEAR CERTIFICATION REPORT AUGUST,1995 ,

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3. Normal Operations Tests Normal Operations Tests are conducted using the Byron Station General , '

Emergency Operating, and Operating Surveillance Procedures and using only operator actions normal to Byron Station. The Normal Operations Tests for certification year 1991/1992,* consisted of performing all of the Normal Plant Evc.utions listed in section 3.1.1 of ANSI /ANS-3.5-1985. The tests results are listed below; i

Certification year 1991/1992 Normal Plant Operations Tests were satisfactory. l Effective with the 1992/1993 certification year, approximately 25% of the Normal Plant Evolutions listed in section 3.1.1 of ANSI /ANS-3.5-1985 was performed every year. Below is the normal operations test schedule and test results for certification years 1992/1993 through 1994/1995: ,

Certification year 1992/1993 - Plant startup from cold shutdown to hot standby, nuclear startup from hot standby to rated power, turbine startup and generator synchronization.

Certification year 1992/1993 Normal Plant Operations Tests were satisfactory.

Certification year 1993/1994 - Reactor trip followed by recovery to rated power, operations at hot standby and load changes.

Certification year 1993/1994 Normal Plant Operations Tests were satisfactory. I l

1 Certification year 1994/1995 - Surveillance testing on safety related equipment or systems (Surveillance Tests).

Certification year 1994/1995 Normal Plant Operations Tests were satisfactory.

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FOUR YEAR CERTIFICATION REPORT i AUGUST,1995 l l

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4. Transient Tests i

Transient tests are conducted annually using the Byron Simulator Acceptance Test Procedure (Section 7.2, Transient Tests). '

The objective of the Byron Simulator Transient Tests is to verify the ability of the ,

simulator to reproduce a defined set of transients. All transients listed in ANSI /ANS-3.5-1985 Appendix B 2.2 were performed. No operator followup action was taken. Data was collected as prescribed in ANSl/ANS-3,5-1985 Appendix B 2.2 at 0.5 second intervals. Transients were run until stable conditions were reached. The simulator response was reviewed by the Byron l Simulator Transient Test Review Board. Where available, actual plant data was  :

used to evaluate the simulator response. The test results are listed below:

l Certification year 1991/1992 Transient Tests were satisf actory.

Certification year 1992/1993 Transient Tests were satisfactory.

Certification year 1993/1994 Transient Tests were satisf actory.

Certification year 1994/1995 Transient Tests were satisf actory.

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5. Malfunction Tests l l

Malfunctions are tested using the Byron Simulator Acceptance Test Procedure  !

(Section 4, Malfunction Testing). Approximately 25% of the certified malfunctions were tested each certification year in accordance with the test schedule submitted with the ori9inal certification report.

The test results are listed below:

Certification year 1991/1992 Certified Malfunction Tests were satisfactory.

Certification year 1992/1993 Certified Malfunction Tests were satisfactory Certification year 1993/1994 Certified Malfunction Tests were satisfactory Certification year 1994/1995 Certified Malfunction Tests were satisfactory l

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. i BYRON STATION SIMULATOR t FOUR YEAR CERTIFICATION REPORT l AUGUST,1995  !

C. Description of performance tests, if different, to be conducted on the simulation' facility f during the subsequent four year period. *

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1. The following malfunction tests have been added to the certified malfunction test i schedule: ,

CH05 ROD STUCK DURING HEAD REMOVAL l CH06 BREAK IN CONTAINMENT INTEGRITY i CH07 DROPPED FUEL BUNDLE DURING REFUELING l CH08 CONTAINMENT PRESSURE TRANSMITTER FAILURE {

CV29 CHARGING PP DEGRADED IMPELLER l CV30 EXCESS LETDOWN LINE LEAK i CWO4 NDC.T CLOGGED FLUME SCREENS i FP03 FIRE DETECTION CAUSING CO2/HALON ACTUATION l HV02 AUX BLDG CHAh00AL BOOSTER FAN FAILS TO START / TRIP MS11 LOW PRESS TURBINE INLET PRESS SWITCH FAILURE

)

RD14- CONTROL ROD SHEARED / UNCOUPLED SPIDER ASSEMBLY l RH11 RELIEF VALVE FAILURE '

RP24 INADVERTENT SAFETY INJECTION RP25 SSPS BLOWN GROUND RETURN FUSE RP26 TRN A SAFEGUARD SEQUENCER RELAY FAILED DEENERGlZED RP27 TRN A SAFEGUARD SEQUENCER RELAY FAILED ENERGlZED RP28 TRN B SAFEGUARD SEQUENCER RELAY FAILED DEENERGlZED RP29 TRN B SAFEGUARD SEQUENCER RELAY FAILED ENERGlZED RX29 S/G FW REG VALVE AUTO CONTROLLER FAILURE RX30 S/G FW REG BYPASS VALVE AUTO CONTROLLER FAILURE RX31 S/G LEVEL SETPOINT FAILURE 1Ll 505 Sl12 SI ACCUMULATOR INCORRECT RELIEF VLV SETPOINT TC18 INADVERTENT OTDT TURBINE RUNBACK TH19 REACTOR VESSEL BOTTOM CRACK TH2O PZR PORV ACCUMULATOR FAULTY RELIEF VLV SETPOINT 1 TH21 SAFETY VALVE SETPOINT FAILURE I TPO4 CLOGGED GC FILTER 1

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4 BYRON STATION SIMULATOR FOUR YEAR CERTIFICATION REPORT AUGUST,1995 D. Schedule for the conduct of approximately 25 percent of the performance tests per year for the subsequent four years.

1. The following tests will be performed annually:

Computer Real Time Test.

Steady State Heat Balance Tests at 30%,90% and 100% power.

100% Power 60 Minute Stability Test.

1 Manual Reactor Trip Transient Test. I 1

Simultaneous Trip of all Main Feedwater Pumps Transient Test.

Simultaneous Closure of all Main Steam isolation Valves Transient Test.

Simultaneous Trip of all Reactor Coolant Pumps Transient Test. ,

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Trip of any single Reactor Coolant Pump Transient Test. i Main Turbino Trip From Less Than 30% Power Transient Test. I Maximum Rate Power Ramp Transient Test.

Maximum Size LOCA with a Loss of all Offsite Power Transient Test.

Maximum Size Unisolable Main Steamline Rupture Transient Test.

Slow Primary System Depressurization to Saturation Condition Transient Test.

2. The following performance tests will be performed during Certification Year 1995/1996:

Plant shutdown from rated power to hot standby and cooldown to cold shutdown i cc,ditions. This will include cooldown operations with less than full reactor

coolant flow where applicable.

, Approximately 25 percent of the malfunctions will be tested in accordance with l the attached certified malfunction test schedule for the 1995/1996 annual testing l

period.

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BYRON STATION SIMULATOR FOUR YEAR CERTIFICATION REPORT ,

AUGUST,1995  ;

3. The following performance tests will be performed during Certification Year 1996/1997 Plant heatup from cold shutdown to hot standby, nuclear startup from hot standby to rated power, turbine startup and generator synchronization. This willinclude heatup operations with less than full reactor coolant flow where applicable.

Approximately 25 percent of the malfunctions will be tested in accordance with the attached certified malfunction test schedule for the 1996/1997 annual testing i period. l l

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4. The following performance tests will be performed during Certification Year 1997/1998 i l'

Reactor trip followed by recovery to rated power, operations at hot standby, and load changes.

Approximately 25 percent of the malfunctions will be tested in accordance with the attached certified malfunction test schedule for the 1997/1998 annual testing period.

5. The following performance tests will be performed during Certification Year 1998/1999: '

Calorimetric, Shutdown Margin, and Operator conducted surveillance testing on safety related equipment or systems (Surveillance Tests).

Approximately 25 percent of the malfunctions will be tested in accordance with the attached certified malfunction test schedule for the 1998/1999 annual testing period. ]

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BYRON SIMULATOR MALFUNCTION TESTING SCHEDULE MUMBEB IIILE TEST CYCLE (QUARTER-YEAR)

AN01 LOSS OF ANNUNCIATOR HORN 1st-1996 AN02 LOSS OF FUSE TO THE AN CABINET RACK 1st-1997 CC01 CCW PUMP FAILS TO STAR / TRIP 1st-1996 CCO2 CCW PUMP DISCH PRESS INDICATOR FAILURE 1st-1996 CC03 CCW SURGE TANK LEVEL INDICATOR FAILURE 1st-1997 EL 4 ESSENTIAL CCW TO RHR HX LEAK 1st-1996 CC0t CCW TO THE CCW HX PIPING DREAK 1st-1997 CC06 NON-ESSENTIAL CCW SYSTEM LEAK 1st-1998 CCO'. RCP THERMAL BARRIER LEAK 1st-1999 CC08 CC HX TUBE LEAK 1st-1999 CC09 THERMAL BARRIER CCW FLOW X-MITTER FAILURE 1st-1998 CH01 RCFC FAN FAILS TO START / TRIP, LOW SPEi.D 1st-1997 CH02 RCFC FAN FAILS TO START / TRIP, HIGH SPEED 1st-1998 CH03 CROM FAN FAILS TO START / TRIP 1st-1999 CH^4 REACTOR CAVITY BOOT FAILURE 1st-1998 CMOS ROD STUCK DURING HEAD REMOVAL 1st-1997 CHC3 BREAK IN CONTAINMENT INTEGRITY 2nd-1997 CH07 DROPPED FUEL BUNDLE DURING REFUELING 1st-1998 CH08 CONT AINMENT PRESSURE TRANSMITTER FAILURE 2nd-1998 CS01 CONTAINMENT SPRAY PUMP FAILS TO START / TRIP 1st-1999 CSO2 CONTAINMENT SPRAY PUMP SUCTION LINE BREAK 1st-1998 CV01 CHARGING PUMP FAILS TO START / TRIP 1st-1997 CV02 PRI WATER MAKE-UP PUMP FAILS TO START / TRIP 1st-1996 CV03 BORIC ACID XFER PUMP 1 AB03P FAILS TO START / TRIP 1st-1999 CV04 VCT DIVERT VALVE FAILURE (112A) 151-1996 CV05 PCV 131 AUTO CONTROL FAILURE 1st-1997 i CV06 CLOGGED RCS FILTER (1CV3CF) 1st 1996 CV07 CLOGGED SEAL INJ FILTER 1st-1997 l CV08 FAILURE OF PT-131 (LTDN PRESS) 1st 1996 CV09 FAILURE OF TE 130 (LTDN HX TEMP) 1st-1997 CV10 FLOW CONTROL VALVE 1CV121 FAILURE 1st-1998 CV11 CVCS UNBORATED MIXED BED DEMINERAltZER 1st-1996 CV12 LTDN RELIEF VALVE FAILS OPEN 151-1996 CV13 CHARGING LINE LEAK OUTSIDE CONTAINMENT 1st-1997 CV14 REGENERATIVE HX TUBE LEAK 1st-1996 CV15 SEALWATER HX TUBE LEAK 1st-1997 L . m . , , ,

BYRON SIMULATOR MALFUNCTION TESTING SCHEDULE NUMBER TITLE TEST CYCLE (QUARTER-YEAR)

CV16 VCT LEVEL MALFUNCTlON (112) ist-1998 CV17 VCT LEVEL MALFUNCTION (185) ist-1999 CV18 VCT PRESS MALFUNCTION 1st-1999 CV19 MAKE-UP CONTROL FAILURE 1st-1997 CV20 BORIC ACID FLOW TRANSMITTER (FT-110) FAILURE 1st-1998 CV21 CHARGING HEADER HCV-182 CONTROL FAILURE 1st 1999 CV22 LTDN LINE LEAK INSIDE CONTAINMENT 1st-1998 CV23 LTON HX TUBE LEAK 1st 1998 CV24 LTDN LINE LEAK OUTSIDE CONTAINMENT 1st-1999 CV25 CHARGING LINE LEAK INSIDE CONTAINMENT 1st-1999 CV26 SEAL INJ LINE LEAKS 1st-1996 CV27 RCP SEAL #1 I AILURE 1st-1998 CV28 RCP SEAL #2 i AILURE 1st 1999 CV29 CHARGING PliDEGRADED IMPELLER 4th-1996 CV30 EXCESS LETDOWN LINE LEAK 4th-1997 CWO1 C!RC WATER PUMP FAILS TO START / TRIP 1st-1997 CWO2 CIRC WATER PUMP DISCHARGE VALVE FAILURE 1st-1998 CWO3 NDCT LOSS OF EFFICIENCY 1st-1999 CWO4 NDCT CLOGGED FLUME SCREENS 1st-1999 ED01 345 KV SWITCHYARD BREAKER FAILS TO TRIP 1st-1996 ED02 345 KV SWITCHYARD BREAKER TRIP 1st 1997 ED03 FAILURE OF UNIT AUX TRANSFORMER (UAT) ist 1998 ED04 FAILURE OF SYJTEM AUX TRANSFORMER (SAT) 1st-1999 j i

EDOS LOSS OF 6 9KV BUS 1st-1996 1

ED06 FAILURE OF 6 9KV ABT 1st-1997 i ED07 LOSS OF 4160V BUS ist-19%

EDOS LOSS OF FEED TO 480V NON-ESF BUS OR MCC 1st-1997 E009 LOSS OF FEED TO 480V ESF BUS OR MCC 1st-1998 ED10 LOSS OF 120 VAC ESF CONSTANT VOLTAGE XFMR 1st-1996 ED11 120 VAC INSTRUMENT BUS INVERTER FAILURE 1st-1997 ED12 LOSS OF DC DISTRIBUTION BUS 1st-1999 ED13 DC CONTROL POWER FAILURE (4160V) 1st-1998 ED14 DC CONTROL POWER FAILURE (480V) 1st-1999 ED15 345 KV BUS FAULT 1st-1996 ED16 LOSS OF FEED TO 120V NON-ESF PANEL 1 st-1998 ED17 LOSS OF FEED TO 120V ESF PANEL 1st-1999 l

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BYRON SIMULATOR MALFUNCTION TESTING SCHEDULE ,

NUNIBEB IIILE TEST CYCLE (QUARTER-YEAR) .

EGOI MAIN GENERATOR AUTO VOLTAGE REGULATOR FAILURE 1st-1997 EG02 MAIN GENERATOR EXCITER FAILURE 1st-1998 EG03 MAIN GENERATOR FIELD FORCING 1st-1999 EG04 BASE FOLLOWER UNIT FAILS TO TRACK 1511996  :

EGOS MAIN POWER TRANSFORMER TRIP 1st-1997 5

EGC3 D/G FAILURE TO FLASH GENERATOR FIELD 1st 1998 EG07 D/G ELECTRIC SPEED CONTROL FAILURE 2nd-1997 EG08 D/G SElZURE 1st-1996 EG09 D/G DIFFERENTIAL OVERCURRENT TRIP 1st-1997 F P01 MANUAL FIRE SUPRESSION WATER SYSTEM ACTIVATION 2nd-1998 FP02 AUTO FIRE SUPRESSION WATER SYSTEM ACTIVATION 1st-1999 FP03 FIRE DETECTION CAUSING CO2/HALON ACTUATION 4th-1997 FWOI MAIN FW PUMP FAILS TO START / TRIP (MOTOR) 2nd-1996 FWO2 MAIN FW PUMP FAILS TO START / TRIP (TURBINE) 2nd-1997 FWO3 START-UP FEED PUMP FAILS TO START / TRIP 2nd-1998  !

FWO4 MAIN FW OIL PUMP FAILS TO START / TRIP 2nd-1999 FWOS TURBINE DRIVEN MFP CONTROL VALVE FAILURE 2nd-1996 FWO6 1URBINE DRIVEN FW PUMP SPEED CONTROL FAILURE 2nd-1997 FWO7 FW PUMP SPEED CONTROL OSCILLATES 2nd-1998 FWOB LOSS 'JF FW PUMP SPEED CONTROL 2nd-1999 FWO9 SK, FW CONTROL VALVE FAILURE 2nd-1996 FW10 f W REGULATION BYPASS VALVE FAILURE 2nd-1997 FW11 iW TEMPERING LiNE ISOLATION VALVE FAILURE 2nd-1998 FW12 /W PREHEATER BYPASS VALVE FAILURE 2nd-1999 FW13 FW ISOLATION VALVE FAILURE 2nd-1996 FWie FEED LINE BREAK BETWEEN FWD 09 & CONTA!NMENT 2nd-1997 YW15 MAIN FW PUMP SHAFT BREAK 2nd-1998 FW16 FW HEADER PRESS FAILURE 2nd-1999 ,

FW17 HEATER DRAIN TANK LEVEL CONTROLLER FAILURE 2nd-1996 FW18 FW HEATER T UBE LEAK (17) 2nd-1997 FW19 FW LINE BREAK INSIDE CONTAINMENT 2nd-1998  !

FW20 FW LINE BREAK OUTSIDE CONTAINMENT 2nd-1999 FW21 S/G TEMPERING LINE RUPTURE 2nd-1996 FW22 CONDENSATE PUMP FAILS TO START / TRIP 2nd-1997 FW23 FW HEATER BYPASS VALVE FAILURE (1CB025) 2nd-1998 '

FW24 CONDENSER EXHAUST HOOD PRESS XMITTER FAILURE 2nd-1999  !

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BYRON SIMULATOR

. MALFUNCTION TESTING SCHEDULE l l

MUMBER TITLE TEST CYCLE (QUARTER YEAB)

FW25 GLAND STEAM CONDENSER MALFUNCTION 2nd-1996 .;

FW26 MAIN FEED FsEGULATING VALVE SEAT LEAKAGE 2nd-1997 FW37 FW HEATER TUBE LEAK (11 DC) 2nd-1996 FW20 FW HEATER TUBE LEAK (11) 2nd-1997 l FW29 FW HEATER TUBE LEAK (12) 2nd-1998 .

t FW30 FW HEATER TUBE LEAK (13) 2nd-1999 FW31 FW HEATER TUBE LEAK (14) 2nd-1996 FW32 FW HEATER TUBE LEAK (15 DC) 2nd-1997  :

FW33 FW HEATER TUBE LEAK (15) 2nd-1998 FW34 FW HEATCR TUBE LEAK (16) 2nd-1999 ;

FW35 HEATER DRAIN PUMP FAILS TO START / TRIP 2nd-1998 i

FW36 LOSS OF CONDENSER VACUUM 2nd-1999 FW37 HOTWELL LEVEL CONTROLLER FAILURE 2nd-1996  :

FW38 HOTWELL LEVEL CONTROLLER FAILURE 2nd-1997

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FW39 HOTWELL LEVEL CONTROLLl R FAILURE 2nd-1998 FW40 HOTWELL LEVEL CONTROLLi R FAILURE 2nd-1999 ,

FWO1 FW ISOL AUX RELAY FAILURE (TRAIN A) 2nd-1996 FW42 FW ISOL AUX RELAY FAILURE (TRAIN B) 2nd-1997 t FW43 AUX FW PUMP FAILS TO STARTTTRIP (MO10R) 2nd-1998 FW44 AUX FW PUMP FAILS TO START / TRIP (TURBINE) 2nd-1999

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FW45 AUX FW VALVE FAILURE 2nd-1996 ,

FWC6 AUX FW LINE RUPTURE 2nd 1997 HV01 CONTROL ROOM MAKE-UP FAN FAILS TO START / TRIP 2nd-1998 HV02 AUX BLDG CHARCOAL BOOSTER FAN FAILS TO START / TRIP 2nd-1999 IA01 LOSS OF INSTRUMENT AIR 2r.d-1996 ,

IA02 LOSS OF SERVICE AIR 2nd-1997 ,

IA03 IA LEAK INSIDE OF CONTAINMENT 2nd-1998 I

IA04 IA LEAK ON THE TURBINE BLDG HEADER 2nd-1999 MOS SERVICE AIR COMPRESSOR FAILS TO START / TRIP 2nd-1996

)

MG3 MSIV ROOM HEADER LEAK 2nd-1997 M07 STEAM DUMP HEADER LEAK 2nd-1998 M08 AUX FEED VALVES HEADER LEAK 2nd-1999 )

l M09 PENETRATION AREA HEADER LEAK 2nd-1996 j MS01 FAILURE OF MAIN STEAM ISOLATION VALVE (S) 2nd-1997 MS02 MSIV BYPASS VALVE FAILURE 2nd-1998 MS03 S/G SAFETY VALVE FAILURE 2nd-1999 l

L l

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BYRON SIMULATOR

. MALFUNCTION TESTING SCHEDULE NUMBEB IIILE TEST CYCLE (QUARTER-YEAR)

MSO4 S/G PORV CONTROLLER FA; LURE 2nd-1996 MS05 STUCK STEAM DUMP 2nd-1997 MSC3 MSR FAILS TO ISOLATE 2nd-1998 MS07 STEAMLINE BREAK INSIDE CONTAINMENT 2nd-1999 MS08 STEAMLINE DREAK OUTSIDE CONTAINMENT 2nd-1996 MSO9 MAIN STEAM HEADER CROSS TIE RUPTURE 2nd-1997 MS10 HEATER 13 EXTRACTION STEAM LINE BREAK 2nd-1998 MS11 LOW PRESS TURBINE INLET PRESS SWITCH FAILURE 3rd-1997 N101 SR CHANNEL FAILURE 2nd-1999 M102 NOISY SR CHANNEL 2nd 19%

NIO3 SR CHANNEL HIGH VOLTAGE 2nd-1997 M104 FAILURE OF SR HIGH VOLTAGE TO DISCONNECT 2nd-1998 N105 SR DISCRIMINATOR FAILURE 2nd-1999 M106 IR CHANNEL FAILURE 2nd-1996 N107 INTER. RANGE CHANNEL GAMMA COMPENSATION FAILURE 2nd-1997

%I08 PR DETECTOR FAILURE 3rd 1998 N109 PR CHANNEL FA! LURE 2nd-1999 M110 INCORE MONITORING SYSTEM FAILURE 3rd-1996 Wl11 STUCK INCORE DETECTOR 3rd-1997 N112 LEAK INTO GUIDE TUBE FOR INCORE DETECTOR 3rd-1998 RD01 ROD DRIVE MG SET TRIP 3rd-1999 I RD02 DROPPED ROD 3rd-1996 RD03 DROPPING ROD 3rd-1997 RD04 ROD EJECTION 3rd-1998 RDOS STUCK ROD 3rd-1999 RD06 RODS Fall TO MOVE 3rd-1996 l RD07 UNCONTROLLED ROD MOVEMENT 3rd-1997 i

RDO8 DRPI- DATA CABINET FAILURE 3rd-1998 RD09 AUTO ROD SPEED CONTROLLER FA LURE 3rd-1999 RD10 FAILURE ON LOGIC CABINET 3rd-1996 RD11 POWER CABINET FAILURE 3rd-1997 RD12 ROD STOPS Fall 3rd-1998 RD13 DRPI OPEN OR SHORTED COIL 3rd-1999 RD14 CON ~1ROL ROD SHEARED / UNCOUPLED SPIDER ASSEMBLY 4th-1996 RH01 RHR PUMP FAILS TO START / TRIP 3rd-1996 RM02 RHR HX FLOW CONTROL VALVE FAILURE 3rd-1997

o. . . . - . .

,I BYRON SIMULATOR MALFUNCTION TESTING SCHEDULE I

NUMBEB IIILE TEST CYCLE (QUARTER-YEAR) >

RH03 RHR HX BYPASS VALVE CONTROL FAILURE 3rd-1998 RH04 RHR AUTO SWITCH-OVER MALFUNCTION 3rd-1999 RHOS RWST LEVEL TRANSMITTER MALFUNCTION 3rd-1996 RH06 RHR HX TUBE LEAK 3rd-1997  ;

RH07 RHR HX BYPASS LINE LEAK 3rd-1998  !

RH08 NST LEAK 3rd-1999  !

RH09 RHR PUMP SUCTION HEADER BREAK 3rd-1996 RH10 RHR PUMP DISCHARGE HEADER BREAK 3rd-1997 RH11 RELIEF VALVE FAILURE 3rd-1998 FtM01 AREA RADIATION MONITOR ACTUATION 3rd-1999 RM02 INOPERABLE RADIATION MONITOR 3rd-1996 l

RM03 INADVERTANT AUTO RADIATION MONITOR ACTUATION 3rd-1997 l i

RM04 PROCESS RADIATION MONITOR ACTUATION 3rd-1998  !

RM05 RADIATION MONITOR INTERLOCK ACTUATION FAILURE 3rd-1999 RM06 GASEOUS AIR MONITOR FAILURE  !

3rd-1996 RP01 REACTOR TRIP FAILURE 3rd-1997 RP02 REACTOR TRIP BREAKER FAILURE 3rd-1998 ,

RP03 REACTOR 1 RIP BYPASS BREAKER FAILURE 3rd-1999 .

RPO4 FAILURE OF PHASE A CNTMNT ISOL TO ACTUATE 3rd-1996 RPOS F ALLURE OF PHASE B CNTMNT ISOL TO ACTUATE 3rd-1997 RP06 TURBINE TRIP INTERLOCK C-8 FAILS 3rd-1998 RP07 UNDER-FREQUENCY ON RCP BUSES 3rd-1999 RP08 UNDER-VOLTAGE ON RCP BUS 3rd-1996 -

RP09 INADVERTANT FW ISOLATION 3rd-1997 RP10 INADVERTENT PHASE A CONTAINMENT ISOLATION 3rd-1998 RP11 INADVERTENT PHASE B CONTAINMENT ISOLATION 3rd-1999 RP12 INADVERTENT CONTROL ROOM VENT ISOLATION 3rd-1996 RP13 REACTOR 1R!p PERMISSIVE P-4 FAILS TO ACTUATE 3rd-1997 ,

RP14 FAILURE OF SAFE TY INJ TO ACTUATE 3rd-1998 RP15 SAFEGUARD SEQUEi9CING FAILURE 3rd-1999 RP16 POWER PERMISSIVE P-6 FAJLS TO ACTUATE 3rd-1996 RP17 POWER PERMISSIVE P 7 FAILS TO ACTUATE 3rd-1997 l

RP18 POWER PERMISSIVE P-8 FAILS TO ACTUATE 3rd-1998 ,

, I RP19 POWER PERMISSIVE P-10 FAILS TO ACTUATE 3rd-1999 RP20 PZR PRESS LOW PERMISSIVE P 11 FAILS TO ACTUATE 3rd-1996 RP21 LO-LO TAVG PERMISSIVE P-12 FAILS TO ACTUATE 3rd-1997

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i BYRON SIMULATOR  ;

1 MALFUNCTION TESTING SCHEDULE

  • MUMBE8 IIILE 1EST CYCLE (QUARTER-YEAR)

RP22 POWER PERMISSIVE P-13 FAILS TO ACTUATE 3rd-1998 RP23 Hi-HI S/G LEVEL PERMISSIVE P-14 FAILS TO ACTUATE 3rd-1999 RP20 INADVERTENT SAFETY INJECTION 2nd-1999 RP25 SSPS BLOWN GROUND RETURN FUSE 1st-1998  ;

RP26 TRN A SAFEGUARD SEQUENCER RELAY FAILED DEENERGlZED 4th-1995

'l RP27 TRN A SAFEGUARD SEQUENCER RELAY FAILED ENERGlZED 4th-1995 RP28 1RN B SAFEGUARD SEQUENCER RELAY FAILED DEENERGlZED 4th-1995 l l

RP29 TRN B SAFEGUARD SEQUENCER RELAY FAILED ENERGlZED 4th-1995 RX01 STEAM PRESS DETECTOR FAILURE 3rd-1996 RXO2 UNSTABLE S/G LEVEL CONTROLLER 3rd-1997 RXO3 STEAM FLOW DETECTOR FAILURE 3rd 1998 RXO4 FW FLOW TRANSMITTER FAILURE 3rd-1999 RX05 STEAM LINE PRESS DET ECTOR (PT-507) FAILURE 3rd-1996 RXC3 NARROW RANGE S/G LEVEL FAILURE 3rd-1997 RXO7 WIDE RANGE S/G LEVEL FAILURE 3rd-1998 RXO8 STEAM DUMP COOLDOWN VALVES CONTROL FAILURE 3rd-1999 RXD9 STEAM FLOW OSCILLATION - TIME 3rd-1996 RX10 FIRST STAGE PRESS TRANSMITTER FAILURE 3rd-1997 j RX11 STEAM FLOW OSCILLATION - MAGNITUDE 3rd-1998 RX12 TREF FAILURE 3rd-1999 RX13 PZR LEVEL CHANNEL FAILURE 3rd-1996 RX14 FW PUMP MASTER SPEED CONTROLLER FAILURE 3rd-1997 RX15 PZR PRESS MASTER CONTROLLER FAILURE 3rd-1998 RX16 PZR LEVEL MASTER CONTROLLER FAILURE 3rd-1999 RX17 ROD CONTROL SYSTEM FAILURE 3rd-1996 RX18 FAULTY PRIMARY RTD (NARROW RANGE)(TC&TH) 4th-1996 RX19 LOSS OF LOAD INTERLOCK C 7 FAILS 4th-1997 RX20 CONDENSER AVAILABLE INTERLOCK C-9 FAILS 3rd 1999 RX21 PZR PRESS CHANNEL FAILURE (455 & 456) 4th-1995 RX22 PZR PRESS CHANNEL FAILURE (457 & 458) 4tn-1996 RX23 OVERPOWER DELTA T SETPOINT FAILURE 4th-1997 RX24 OVERTEMPERATURE DELTA T SETPOINT FAILURE 4th-1998 RX25 RCS PRESS TRANSMITTER FAILURE (403 & 405) 4th-1995 RX26 RCS PRESS TRANSMITTER FAILURE (406 & 407) 4th-1996 RX27 RCS PRESS TRANSMITTER FAILURE (408 & 409) 4th-1997 RX28 RCS LOOP FLOW TRANSMITT ER FAILURE 4th-1998

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i i

BYRON SIMULATOR MALFUNCTION TESTING SCHEDULE 4

NUMBER IIILE IESI CYCLFdQUARTER-YEAR)

RX29. S/G FW REG VALVE AUTO CONTROLLER FAILURE 4th-1998 RX30 S/G FW REG BYPASS VALVE AUTO CONTROLLER FAILURE 3rd-1999 RX31 S/G LEVEL SETPOINT FAILURE 1Li-505 4th-1998 1 1

S10 1 SAFETY INJ PUMP FAILS TO START / TRIP 4th-1995

]

S40 2 SI ACCUMULATOR LEVEL XMITTER FAILURE 4th-19% j S10 3 COLD LEG INJ CHECK VALVE LEAKAGE (Sl8818) 4th-1997 S104 COLD LEG INJ CHECK VALVE LEAKAGE (Sl8819) 1st-1998 .

l S 10 5 COLD LEG INJ CHECK VALVE LEAKAGE (Sl8948) 4th-1995 l S10 6 COLD LEG INJ CHECK VALVE LEAKAGE (Sl8956) 1st-1999 S10 7 HOT LEG INJ CHECK VALVE LEAKAGE (S18905) 4th-1997 Sl08 HOT LEG INJ CHECK VALVE LEAKAGE (Sl8841) 4th-1998 l l

S10 9 HOT LEG INJ CHECK VALVE LEAKAGE (S18949) 4th-1995 S 11 0 HIGH HEAD St LEAK INSIDE CONTAINMENT 4th-1996 S 11 1 St ACCUMULATOR TANK RUPTURE 4th-1997 S 11 2 SI ACCUMULATCR INCORRECT RELIEF VLV SETPOINT 1st-1996 SWO1 SX PUMP FAILS TO START / TRIP 4th-1998 SWO2 SX BREAK INSIDE CONTAINMENT 4th-1995 SWO3 LOSS OF SX COOLING TO D/G 4th-19%  !

SWO4 SX DISCHARGE HEADER BREAK 4th-1997 SWOS WS HEADER BREAK 4th-1998 TC01 INADVERTENT TURBINE RUNBACK 4th-1995 TCO2 TURBINE TRIP ON LOW LOAD INDICATION (PDS-T0071) 4th-1996 1CO3 TURBINE AUTO TRIP FAILURE 4th-1997 TC04 TURBINE AUTO RUNBACK FAILURE - 4th-1998 TC05 OPC LP TURB INLET PRESS SENSOR (PT-MS003) FAILURE 4th-1995 TC06 DEHC - IMPULSE PRESS TRANSMITTER FAILURE (PT-MS002) 4th-1996 TC07 DEHC - MW TRANSDUCER FAILURE 4th-1997 TC08 DEHC - GV/TV OSCILLATION - TIME 4th-1998 TC09 DEHC - GV/TV OSCILLATION

' l BYRON SIMULATOR .

MALFUNCTION TESTING SCHEDULE <

! 1 l

i NMMBER IIILE IEST CYCLElQUARTf& YEAR)

TC17 EH PUMP FAILS TO START / TRIP 4th-1995 TC1B INADVERTENT OTDT TURBINE RUNBACK 4th 1998 TM01 PZR STEAM SPACE LEAK 4th-1996 -

TH02 PZR RELIEF TANK LEAK 4th-1997 YH03 S/G TUBE LEAK . 4th-1998 TH04 RCS LEAK. HOT LEG (HIGH) 4th-1995 THOS RCS LEAK, HOT LEG (MEDIUM) 4th-19%

l YH06 RCS LEAK, COLD LEG 4th-1997 I I

TH07 REACTOR VESSEL FLANGE LEAK 4th-1998 TH08 RCS FUEL ELEMENT FAILURE 4th-1995 TH09 RTD MANIFOLD FAULTY FLOW CONDITIONS 4th-1996 TH10 PZR SPRAY VALVE FAILURE 4th-1997 TH11 PZR POWER OPERATED RELIEF VALVE FAILURE 4th-1998 i

TH12 PZR SAFETY VALVE FAILURE 4th-1995 TH13 PZR LEVEL DETECTOR REF/ VARIABLE LEG LEAK 4th-1996 j TH14 PZR RELIEF LINE RTD FAILURE 4th-1997 THIS RCS WIDE RANGE RTD FAILURE 4th-1998 TH16 RCP FAILS TO START /TR P 4th-1995 TH17 RCP DEGRADED PERFORMANCE / LOCKED ROTOR 4th-1996 THI8 RCP SHAFT BREAK 4th-1997 TH19 REACTOR VESSEL BOTTOM CRACK 4th-1998 TH2O PZR PORV ACCUMULATOR FAULTY RELIEF VLV SETPOINT 3rd-1997 TH21 SAFETY VALVE SETPOINT FAILURE 2nd-1996 TP01 STATOR COOLING WATER PUMP FAILS TO START / TRIP 4th-1998 TP02 STATOR COOLING WATER HIGH CONDUCTIVITY 4th-1995 i TP03 SEAL OIL SYSTEM PUMP FAILS TO START / TRIP 4th-1996 l

TP00 CLOGGED GC FILTER 3rd-i398 TUO1 TURBINE VIBRATION 4th-1997 TUO2 TURBINE BEARING OIL PUMP FAILS TO START / TRIP 4th-199 l

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TUO3 TURBINE HP SEAL OIL B/U PUMP FAILS TO START / TRIP 4th-1995 TUO4 TURBINE DC EMER OIL PUMP FAILS TO START / TRIP 4th-1997 TUDS TURBINE Oil SYSTEM LEAK 4th 1996 i TUC3 BEARING LIFT PUMP SUCTION STRAINER CLOG 3rd-1996 1

WD01 GAS DECAY TANK RUPTURE 4th 1996 YR01 LOSS OF RM-11 COMMUNICATION LGOP 4th-1998

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