L-99-010, Forwards NRC 474 Forms, Simulation Facility Certification & Associated Attachments for Units 1 & 2.No NRC Commitments Associated with Submittal

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Forwards NRC 474 Forms, Simulation Facility Certification & Associated Attachments for Units 1 & 2.No NRC Commitments Associated with Submittal
ML20207L030
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 03/11/1999
From: Dennis Morey
SOUTHERN NUCLEAR OPERATING CO.
To:
NRC (Affiliation Not Assigned)
References
NEL-99-0103, NEL-99-103, NUDOCS 9903170338
Download: ML20207L030 (18)
v • d • e


Text

,, Orve Morey Southern Nuclear Vice President Op: rating Compa y Farley Project P0. Box 1295 Birmingham. Alabama 35201 Tel 205.992.5131 SOUTHERN March 11, 1999 Energy to Serve Your World" Docket Nos.: 50-348 NEL-99-0103 50-364 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C 20555 0001 Joseph M. Farley Nuclear Plant Simulation Facility Certification Reoort Ladies and Gentlemen:

This report is submitted pursuant to 10 CFR 55.45(bX5Xii) and 10 CFR 55.45(bX5Xvi).

Farley Nuclear Plant (FNP) has no uncorrected simulation facility performance test failures to report. Enclosed are NRC 474 Forms, " Simulation Facility Certification," and associated attachments for FNP Units I and 2.

There are no NRC commitments associated with this submittal.

If there are any questions, please advise.

Respectfully submitted,

[ A; A 7 Dave Morey  : DRC/maf: simre. doc Enclosures w/ Associated Attachments I 

                                                                                                                -o h

n\\ 1m-9903170338 990311 PDR ADOCK 05000348-P PDR __

J Page 2 

           . U. S. Nuclear Regulatory Commission ec:   Southern Nuclear Ooeratina Comoany Mr. L. M. Stinson, Gcneral Manager - Farley 1

U. S. Nuclear Renulatory Commission. Washington. D. C. I Mr. J. I. Zimmerman, Licensing Project Manager - Farley i I Documem Control Desk U. S. Nuclear Regulatory Commission. Region II Mr. L. A. Reyes, Regional Administrator Mr. T. P. Johnson, Senior Resident Inspector - Farley 1 I I 1 l i i i 1

l 

          .a hRC FORM 474                                                   U S. FCLEAR REGlMTORY COMMISSION                 APPROVED BY OMB; Na 316o41G                                     ERPIRE8; W31/J001 (8-1998)

Esnmated burden per response to compy with inis mandatory informanon conection request 12o nours This information is used to costdy a simulate faanty Forward comments regareng burden assimate to tne Recoros Management Branch (T-8F33L SIMULATION FACILITY CERTIFICATION U S NuceReduction Paperwork R@t1ropectComrnmon. (315c o138), Wamngton, DC 26W and Othce of Management andBudget. to me

  • Wastungion, DC 2o5o3 it an information collection does noi opolay a currensy vahd ,

OMB control numoar. the NRC may not ronduct or sponsor, and a person is not _reouired to resoond to me mtormation collection ANSTRUCTIONS: This form is to be filed for initial certification, recertificatiNi (it required). and for any change to the simulation facility performance testing plan made after initial submittal of such a plan. Provide the followMg information and check the appropnate box to indicate reason for submittal. FACluTY DOCKET NUMBER Joseph M. Farley Nuclear Plant, Unit 1 50- 348 UCENSEE DATE Southern Nuclear Operating Cor oany 3/10/99 Yks is to certify that:

1. The above named facility licensee is using a simulation facility consisting so6ely of a plant referenced simulator that meets the requirements of 10CFR 55 45.
2. Documentation is available for NRC review in accordance with 10 CFR 55.45(b).
3. This simulation facility meets the guidance contained in ANSVANS 3,5-1985 or ANSI /ANS 3 5-1993. as endorsed by NRC Regulatory Guide 1,149 If there are any EXCEPTIONS to the certification of this item. CHECK HERE and descrtbe fully on additional pages as necessary.

NAME (or other utentifscapon! AND LOCATlON OF SIMULATION FACluTY. Farley Nuclear Plant Training Center U.S. Hwy 95 S.,5 miles south of Columbia, AL h SIMULATION FACluTV PERFORMANCE TEST A8STRACTS ATTACHED. (Forpedarmance rests condbeted ni me pened encang we me care or mss ce DESCRIPTION OF PERFORMANCE TESTING COMPLETED. (Arracr> aceronar pages as necessary and conwy me tem oescrpre Dems canonued1 See Attachment 1 SIMULATION FACluTY PERFORMANCE TESTING SCHED*JLE ATTACHED. (For me condba or apprommatory 25 percent or performance tests peryear for me four yearpered commenong een me onre or m a cornreanon ) DESCRIPTION OF PERFORM ANCE TESTING TO BE CONOUr:TED. (Anacn adatenarpages as necussary and cenary me sem oesenpren osep coninued) See Attachment 2 PERFORM ANCE TESTIhG PLAN CHANGE. (For any modhcate to a pedormance lesteg pran sutrnsted on a preveus comfiarte J DESCRIPTION OF PERFORMANCE TESTING PLAN CHANGE. (Arracn aderenaipages as necessary and scendy me nem assenpron cong contnued1 See Attachment 3 i RECERTIFICAT)ON (Desonoe correctwo actens taken, arracr> resutt or canperedperrormance nesang e accaronna wsn to CFR ss es(0x5xv1. (AWaCri addnanat pages as necessary and Qantdy Ine Gem desCrGtion being Contmued) Any falso statement or omission in this document, including attachments. may be subject to civil and enminal sanctions. ! certify under penalty of par)ury that the information in I this document and attachments is true and correct, i SiONATURE AUTHORIZED REPRE ATlVE TITLE DATE . j Nuclear Plant General Manager gg' / I in accordera w:tn 10 CFr654 Communiennons. trus form snesi be suommed to the NRC ss tahows BY MAIL ADORESSED TO: DIRECTOR. OFFICE OF NUCLEAR REACTOR REGULATION BY DELIVERY IN PERSON ONE WHITE FUNT NORTH  ! U.S. MUCLEAR REGULATORY COuamSSION TO THE NRC OFFICE AT. tissa ROCKVtLLE PtKE WASHINGTON. DC 20:54 0001 ROCKVILLE. MD NRC FORM 47418-199s) PRINTED ON RECM1LD PAPt.R i 

                                                                                                                                                                                                     ~

[J 9& DRC FORM 474 U S. NUCLEAR REGUI.ATORY COMM:3S80N APPROVED BY 00R NO.3150413s ERPIRES: 53 MODI (8-1998) Esemated tiurden per response to comply we trus mandatory mtormate coHection re@est 120 hours. Trus enformanon is used to cedity a smul.acn faciaty Forwgrd Comments regarono curden esomate to Ine Records Management Branch (T-8F33L SIMULATION FACILITY CERTIFICATION L8e,"",*l%a,Tl,'abca=,"m,7g 

                                                                                                                          ,                      ec                go,Joi,5Po,           "*

s Pan'd La,*7 , Waarungton. DC 20503. 11an informanon collection does not onpay a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not recurred to resoond to the information collechon-INSTRUCTIONS: This form is to be filed for initial certification, recertification (it required). and for any change to the simulation facility performance testing plan maos after initial submittal of such a plan. Provide the followng information and check the appropriate box to indicate reason for submittal. FActuTY DOCKET NUMBER Joseph M. Farley Nuclear Plant, Unit 2 50 364 UCENSEE DATE Southern Nuclear Operating Company 3/10/99 This is to certify that: 1, The above named facility licensee is using a simulation facility consisting solely of a plant-referenced simulator that meets the requirements of 10CFR $5.45.

2. Documentation is available for NRC review in accordance wth 10 CFR 55.45(b).
3. This samulation facility meets the guidance contained in ANst/ANs 3 51985 or ANst/ANs 3 51993, as endorsed by NRC Regulatory Guide 1.149.

If there are any EXCEPTIONS to the Ceftification of this item, CHECK HERE and desenbe fully on additional pages as necessary. NAME (or other #dentehcation) AND LOCATION OF SIMULATIOh FACluTY. Farley Nuclear Plant Training Center U.S. Hwy 95 S.,5 miles soch of Columbia, AL g SIMULATION FACIUTY PERFORMANCE TEST A85 TRACTS ATTACHED. (Forperformana tests con &csod a me penod enclng win me ante of Ws artscaron j DESCRIPTION OF PERFORMANCE TESTING COMPLETED. (Attaat somreat pages as nomssary and eennry me nem aesenpren oeng connnusa) The Unit 1 Training Simulator is utilized for Unit 2 Simulator Training. Performance tests are those of Unit 1. SIMULATION FACIUTY PEhFORMANCE TESTING SCHEDULE ATTACHED. (For me condLa at approomaresy 25 percent of performance rests per year for m tour-yearpened commencre e tn me ante et en certurente.) DESCRIPTION OF PERFORMANCE TESTING TO BE CONDUCTED. (Attaen aoaire ialpages as necessary and osnnfy me nem oescqpron come annnved1 l The Unit 1 Training Simulator is utilized for Unit 2 Simulator Training. The schedule for annual performance testing is that of Unit 1. I l PERFORMANCE TESTING PLAN CHANGE. (For any mooficaten to e performance tesang pean suemirred on a prewous corritsaron ) DESCRIPTION OF PERFORMANCE TESTING P'.AN CHANGE. (Aliaai acceronalpages as nomssary and noenr#y me nem aescreen eems connnued) The Unit 1 Training Simulator is utilized for Unit 2 Simulator Training. The Changes to the performance testing plan ara those listed for Unit 1. RECERTIFICATION (Descnbe correctwo aceans tsuen. stracn results or compoered performance tesang e accordance no 10 CFR ss 4st0x5M (A tacn acetonar pages as necessary and onennty me nem oescnoten bemy connnved) Any false statement or omission in this document. Including attachments, may be cubject to civil and enminal sanctions. I certify under penalty of perjury that the information in this document and attachmonts is true and correct. 

    ~SeGe4ATURE-AUTHORIZED RE               ENTATIVE                                                          TITLE                                                        DATE Nuclear Plant General Manager                                  ggg in Acc6rdenom ecm to CFK66 s. Commurucates, trus term shall De subnutted to the NRC as knows.

BY Mall ADDRESSEC TO: DIRECTOR. OFFICE OF NUCLEAR REACTOR REOULATION BY DELfVERY IN PERSON ONE WHtTE FLINT NORTH U.S. NUCLEAR REOULATORY C0estnesa0N TO THE NRC OFFICE AT; 11655 ROCKylLLE PIKE WASMNIGTON. DC 206650001 ROCKVILLE. TID NRC FOAM 4741s.lets) PRIN T ED ON REW Lt.D Fart it

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ATTACHMENT 1 I DESCRIPTIONS OF TESTS COMPLETED I l l 4 l 

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!- Attachment 1 

                .            Description of Tests Completed - 1995 FNP-0-CTP-1.0    START UP FROM COLD SHUTDOWN TO IIOT STANDBY FNP-0-CTP-1.7    SIMULATOR REAL TIME TEST FNP-0-CTP-1.8    OPERATING LIMITS EXCEEDED TEST FNP-0-CTP-2.1    FAILURE OF INSTRUMENT AIR SYSTEM                i FNP-0-CTP-2.2    SERVICE WATER PUMP TRIP                        i FNP-0-CTP-2.3    CCW PUMP TRIP FNP-0-CTP-2.4    STEAM JET AIR EJECTOR FAILURE                   l FNP-0-CTP-2.5    HOTWELL FILL CONTROLLER CP-4055F FAILURE FNP-0-CTP-2.16   STARTUP TRANSFORMER FAILURE FNP-0-CTP-2.20    120V VITAL INSTRUMENTATION DISTRIBUTION PANEL ;

TRIP l FNP-0-CTP-2.21 120VAC DISTRIBUTION PANEL TRIP FNP-0-CTP-2.39 INADVERTANT REACTOR TRIP ] i FNP-0-CTP-2.44 PRESSURIZER SAFETY VALVE FAILURE J l FNP-0-CTP-2.48 REACTOR COOLANT SYSTEM LEAK FNP-0CTP-2.50 STEAM GENERATOR TUBE LEAK FNP-0-CTP-3.1 MANUAL REACTOR TRIP FNP-0-CTP-3.2 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS FNP-0-CTP-3.3 SIMULTANEOUS CLOSURE OF MAIN STEAM ISO. VALVES FNP-0-CTP-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS FNP-0-CTP-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PITMP ! FNP-0-CTP-3.6 MAIN TURBINE TRIP (LESS THAN P-9 SETPOINT) FNP-0-CTP-3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%) FNP-0-CTP-3.8 MAX SIZE RCS RUPTURE WITH LOSP FNP-0-CTP-3.9 MAX SIZE NON ISOLABLE MAIN STEAM LINE RUPTURE FNP-0-CTP-3.10 SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATED CONDITION USING PRESSURIZER REl.IEF SAFETY VALVE STUCK OPEN FNP-0-CTP-4.0 ONE HOUR STEADY STATE OPERATIONS TEST FNP-0-CTP-4.1 STEADY STATE COMPARISON TO REFERENCE PLANT ) FNP-0-CTP-5.7 REACTOR TRIP DUE TO SPURIOUS MSIV CLOSURE l l 1 i l L

Attachment i Continued 

             .              Description of Tests Completed - 1996 FNP-0-CTP-1.1      START UP FROM HOT STANDBY TO MINIMUM LOAD FNP-0-CTP 1.2      POWER OPERATIONS-MINIMUM LOAD TO 100% POWER FNP-0-CTP-1.7      SIMULATOR REAL TIME TEST FNP-0-CTP-1.8      OPERATING LIMITS EXCEEDED TEST FNP-0-CTP-2.12     DEGRADED GRID VOLTAGE-LOSP FNP-0-CTP-2.IS     DIESEL GENERATOR ESSENTIAL PROTECTION FAILURE FNP-0-CTP-2.19     120VAC VITAL INSTRUMENT INVERTER FAILURE        )

FNP-0-CTP-2.22 125VDC DISTRIBUTION PANEL TRIP  ! FNP-0-CTP-2.27 FEEDWATER HEADER PRESSURE TRANSMITTER FAILURE FNP-0-CTP-2.38 POWER RANGE CHANNEL FAILURE 1 FNP-0-CTP-2.3801 POWER RANGE CHANNEL DETECTOR FAILURE I FNP-0-CTP 2.3802 POWER RANGE BLOWN FUSE FNP-0-CTP-2.42 PRESSURIZER STEAM SPACE BREAK - FNP-0-CTP-2.43 PRESSURIZER RELIEF VALVE FAILURE FNP-0-CTP-2.49 LOSS OF COOLANT ACCIDENT FNP-0-CTP-2.53 RCS LOOP PRO'IECTION RTD FAILURE FNP-0-CTP-2.55 RHR PUMP TRIP , I FNP-0-CTP-2.56 RHR HEAT EXCHANGER BYPASS LINE BREAK FNP-0-CTP 2.57 TURBINE 1" STAGE PRESSURE TRANSMITTER FAILURE FNP-0-CTP-2.59 AUX FEEDWATER PUMP TRIP FNP-0-CTP-3.1 MANUAL REACTOR TRIP i FNP-0-CTP-3.2 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS I FNP-0-CTP-3.3 SIMULTANEOUS CLOSURE OF MAIN STFAM ISO. I VALVES I FNP-0-CTP-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS l FNP-0-CTP-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP FNP-0-CTP 3.6 MAIN TURBINE TRIP (LESS THAN P-9 SETPOINT) FNP-0-CTP-3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%) FNP-0-CTP-3.8 MAX SIZE RCS RUPTURE WITH LOSP FNP-0-CTP-3.9 MAX SIZE NON-ISOLABLE MAIN STEAM LINE RUPTURE FNP-0-CTP-3.10 SLOW PRMARY SYSTEM DEPRESSURIZATION TO SATURATED CONDITION USING PRESSURIZER RELIEF SAFETY VALVE STUCK OPEN FNP-0-CTP-4.0 ONE HOUR STEADY STATE OPERATIONS TEST FNP-0-CTP-4.1 STEADY STATE COMPARISON TO REFERENCE PLANT 4

8-Attachment 1 Continued Description of Tests Completed - 1997 l FNP-0-CTP-1.0 START UP FROM COLD SHUTDOWN TO HOT STANDBY

FNP-0-CTP-1.1 START UP FROM HOT STANDBY TO MINIMUM LOAD FNP-0-CTP-1.2 POWER OPERATIONS-MINIMUM LOAD TO 100% POWER FNP-0-CTP-l.3 RATED POWER TO HOT STANDBY FNP-0-CTP-1.301 SHUTDOWN FROM MINIMUM LOAD TO HOT STANDBY j FNP-0-CTP-1.4 SHUTDOWN FROM HOT STANDBY TO COLD SHUTDOWN FNP-0-CTP-1.5 START UP FOLLOWING A REACTOR TRIP FNP-0-CTP-1.6 CORE PHYSICS TESTING FNP-0-CTP-1.7 SIMUI ATOR REAL TIME TEST

{ FNP-0-CTP-1.8 OP'IRATING LIMITS EXCEEDED TEST FNP-0-CTP-1.9 O ERATOR CONDUCTED SURVEILLANCE TEST  ; FNP-0-CTP-2.1 FAILURE OF INSTRUMENT AIR SYSTEM l FNP-0-CTP 2.2 SERVICE WATER PUMP TRIP f FNP-0-CTP-2.3 CCW PUMP TRIP l FNP-0-CTP-2.4 STEAM JET AIR EJECTOR FAILURE l FNP-0-CTP-2.5 HOTWELL FILL CONTROLLER CP-4055F FAILURE FNP-0-CTP-2.7 RODS FAIL TO MOVE IN AUTO FNP-0-CTP-2.9 CONTROL ROD FAILURE-STUCK ROD FNP-0CTP-2,10 CONTROL ROD FAILURE-DROPPED ROD FNP-0-CTP-2.11 VCT LEVEL TRANSMITTER FAILURE FNP-0-CTP-2.12 DEGRADED GRID VOLTAGE-LOSP 4 FNP-0-CTP-2.13 4160V BUS TRIP FNP-0-CTP-2.14 EMERGENCY 4160V BUS TRIP FNP-0-CTP-2.15 DIESEL GENERATOR ESSENTIAL PROTECTION ' FAILURE FNP-0-CTP-2.16 STARTUP TRANSFORMER FAILURE FNP-0-CTP-2.17 600V LOAD CENTER TRIP FNP-0-CTP-2.18 600V MOTOR CONTROL CENTER TRIP FNP-0CTP-2.19 120VAC VITAL INSTRUMENT INVERTER FAILURE FNP-0-CTP-2.20 120V VITAL INSTRUMENTATION DISTRIBUTION PANEL TRIP FNP-0-CTP-2.21 120VAC DISTRIBUTION PANEL TRIP FNP-0-CTP-2.22 125VDC DISTRIBUTION PANEL TRIP FNP-0-CTP-2.23 MDAFW FLOW CONTROL VALVE FAILURE I FNP-0-CTP-2.24 STEAM GENERATOR FEEDPUMP TRIP FNP-0-CTP-2.25 STEAM GENERATOR FAILURE TO AUTO TRIP l FNP-0-CTP-2.26 STEAM GENERATOR TURBINE SPEED CONT. FAILURE I FNP-0-CTP-2.27 FEEDWATER HEADER PRESSURE TRANSMITTER FAILURE FNP-0-CTP-2.28 STEAM GENERATOR LEVEL CHANNEL FAILURE FNP-0-CTP-2.29 FEED LINE BREAK OUTSIDE CONTAINMENT DOWNSTREAM OF STOP CHECK VALVE FNP-0-CTP-2.30 FEED LINE BREAK INSIDE CONTAINMENT FNP-0-CTP-2.31 STEAM LINE BREAK INSIDE CONTAINMENT FNP-0-CTP-2.32 STEAM LINE BREAK OUTSIDE CTMT UPSTREAM OF MSIV FNP-0-CTP-2.33 STEAM l.INE FLOW TRANSMTITER FAILURE 

   .                                                                            l l

Attachment i Continued ) Description of Tests Completed - 1997 Continued FNP-0-CTP-2.34 STEAM DUMP VALVES FAIL TO OPERATE IN Tave MODE FNP-0-CTP-2.35 STEAM HEADER PRESS CONTROLLER PT464 FAILURE FNP-0-CTP-2.36 SOURCE RANGE CHANNEL FAILURE FNP-0-CTP-2.3601 FAILURE OF SOURCE RANGE CHANNEL HIGH VOLTAGE TO DISCONNECT FNP-0-CTP-2.3602 SOURCE RANGE CHANNEL HIGH VOLTAGE FAILURE FNP-0-CTP-2.3603 SOURCE RANGE BLOWN FUSE FNP-0-CTP-2.37 INTERMEDIATE RANGE CHANNEL FAILURE I FNP-0-CTP-2.3701 INTERMEDIATE RANGE CHANNEL GAMMA l COMPENSATION FAILURE FNP-0-CTP-2.3702 INTERMEDIATE RANGE CHANNEL BLOWN FUSE FNP-0-CTP-2.38 POWER RANGE CHANNEL FAILURE ' FNP-0-CTP-2.3801 POWER RANGE CHANNEL DETECTOR FAILURE FNP-0-CTP-2.3802 POWER RANGE BLOWN FUSE FNP-0-CTP 2.39 INADVERTANT REACTOR TRIP FNP-0-CTP-2.40 REACTOR TRIP BREAKER FAILS TO OPEN FNP-0-CTP-2.41 SAFEGUARD ACTUATION AND CTMT ISO. FAILURE FNP-0-CTP-2.42 PRESSURIZER STEAM SPACE BREAK FNP-0-CTP 2.43 PRESSURIZER RELIEF VALVE FAILURE FNP-0-CTP-2.44 PRESSURIZER SAFETY VALVE FAILURE FNP-0-CTP-2.45 PRESSURIZER PRESSURE CHANNEL FAILURE FNP-0-CTP-2.46 PRESSURIZER LEVEL MASTER CONTROLLER FAILURE FNP-0-CTP-2.47 PRESSURIZER LEVEL CHANNEL FAILURE FNP-0-CTP-2.48 REACTOR COOLANT SYSTEM LEAK FNP-0-CTP-2.49 LOSS OF COOLANT ACCIDENT FNP-0-CTP-2.50 STEAM GENERATOR TUBE LEAK FNP-0-CTP-2.51 REACTOR COOLANT PUMP TRIP FNP-0-CTP-2.52 FUEL CLADDING FAILURE FNP-0-CTP-2.53 RCS LOOP PROTECTION RTD FAILURE FNP-0-CTP-2.54 RCS LOOP COLD LEG RTD FAILURE FNP-0-CTP-2.55 RHR PUMP TRIP FNP-0-CTP-2.56 RHR HEAT EXCHANGER BYPASS LINE BREAK FNP-0-CTP-2.57 TURBINE I ST STAGE PRESSURE TRANSMITTER FAILURE FNP-0-CTP-2.58 GENERATOR AUTO VOLTAGE REGULATOR FAILURE 

         ~ FNP-0-CTP-2.59           AUX FEEDWATER PUMP TRIP FNP-0-CTP-3.1             MANUAL REACTOR TRIP FNP-0-CTP-3.2             SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS FNP-0-CTP-3.3             SIMULTANEOUS CLOSURE OF MAIN STEAM ISO.

VALVES FNP-0-CTP-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS FNP-0-CTP-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP FNP-0-CTP-3.6 MAIN TURBINE TRIP (LESS THAN P-9 SETPOINT) FNP-0-CTP-3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%) FNP-0-CTP-3.8 MAX SIZE RCS RUPTURE WITH LOSP

i Attachment 1 Continued Description of Tests Completed - 1997 Continued FNP-0-CTP-3.9 MAX SIZE NON ISOLABLE MAIN STEAM LINE RUPTURE -l FNP-0-CTP-3,10 SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATED CONDITION USING PRESSURIZER RELIEF SAFETY VALVE STUCK OPEN FNP-0-CTP-4.0 ONE HOUR STEADY STATE OPERATIONS TEST FNP-0-CTP-4,1 STEADY STATE COMPARISON TO REFERENCE PLANT i FNP-0-CTP 5.1 LOSS OF BOT.i SOURCE RANGES WHILE SIIUTDOWN FNP-0-CTP-5.3 LOSS OF INVERTER 1 A WHILE NI42 BEING TESTED FNP-0-CTP-5.4 RCP UNDER-FREQUENCY REACTOR TRIP  ; FNP-0-CTP-5.5 DEH PROBLEMS  ! FNP-0-CTP-5.6 DEH PROBLEMS FNP-0-CTP-5,7 REACTOR TRIP DUE TO SPURIOUS MSIV CLOSURE I lI i i

~ 1 

     .l                                                                      l 1-                                                                         ;

l Attachment ! Continued , 

        ,                    Description of Tests Completed - 1998

{ FNP-0-CTG-I.301 FNP-0-CTG-1.4 SHUTDOWN FROM MINIMUM LOAD TO HOT STANDBY ) SHUTDOWN FROM HOT STANDBY TO COLD 1 SHUTDOWN 

          - FNP-0-CTG-1.5. START UP FOLLOWING A REACTOR TRIP             i FNP-0-CTG-1.6      CORE PHYSICS TESTING FNP-0-CTG-1.7      SIMULATOR REAL TIME TEST                      i FNP-0-CTG 1.8      OPERATING LIMITS EXCEEDED TEST FNP-0-CTG-2.7      RODS FAIL TO MOVE IN AUTO / MANUAL FNP-0-CTG-2.9      CONTROL ROD FAILURE STUCK ROD FNP-0-CTG-2.10     CONTROL ROD FAILURE-DROPPED ROD FNP-0-CTG 2.24     STEAM GENERATOR FEEDPUMP TRIP l

FNP-0-CTG-2.25 STEAM GENERATOR FAILURE TO AUTO TRIP ' FNP-0-CTG-2.26 STEAM GENERATOR TURBINE SPEED CONT. FAILURE I FNP-0-CTG-2.28 STEAM GENERATOR LEVEL CHANNEL FAILURE ) FNP-0-CTG-2.29 FEED LINE BREAK OUTSIDE CONTAINMENT DOWNSTREAM OF STOP CHECK VALVE FNP-0-CTG-2.30 FEED LINE BREAK INSIDE CONTAINMENT FNP-0-CTG-2.33 STEAM LINE FLOW TRANSMrITER FAILURE FNP-0-CTG-2.36 SOURCE RANGE CHANNEL FAILURE FNP-0-CTG-2.3601 FAILURE OF SOURCE RANGE CHANNEL HIGH VOLTAGE TO DISCONNECT FNP-0-CTG-2.3602 SOURCE RANGE CHANNEL HIGH VOLTAGE FAILURE . FNP-0-CTG-2.3603 SOURCE RANGE BLOWN FUSE FNP-0-CTG-2.37 INTERMEDIATE RANGE CHANNEL FAILURE FNP-0-CTG-2.3701 INTERMEDIATE RANGE CHANNEL GAMMA COMPENSATION FAILURE FNP 0-CTG 2.M02 INTERMEDIATE RANGE CHANNEL BLOWN FUSE FNP-0-CTG-2.41 SAFEGUARD ACTUATION AND CTMT ISO. FAILURE FNP-0-CTG-2.51 REACTOR COOLANT PUMP TRIP FNP-0-CrG-3.1 MANUAL REACTOR TRIP FNP-0-CTG 3.2 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS FNP-0-CTG-3.3 SIMULTANEOUS CLOSURE OF MAIN STEAM ISO. VALVES FNP-0-CTG-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS FNP-0-CTG-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP FNP-0-CTG-3.6 MAIN TURBINE TRIP (LESS THAN P-9 SETPOINT) FNP-0-CTG 3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%) FNP-0-CTG-3.8 MAX SIZE RCS RUPTURE WITH LOSP FNP-0-CTG-3.9 MAX SIZE NON-!SOLABLE MAIN STEAM LINE RUPTURE FNP-0-CTG-3.10 SLOW PRIMAki SYSTEM DEPRESSURIZATION TO SATURATED CONDITION USING PRESSURIZER RELIFF SAFETY VALVE STUCK OPEN FNP-0-CTG-4.0 ONE HOUR STEADY STATE OPERATIONS TEST .. FNP-0-CTG-4.1 STEADY STATE COMPARISON TO REFERENCE PLANT l L

I e' 9 

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4 ATTACHMENT 2 l FOUR YEARS TEST SCHEDULE l e l l l l I l

r s 

       ~.

Attachment 2 Four Year Test Schedule- 1999 FNP-0-CTG-1.0 START UP FROM COLD SHUTDOWN TO HOT STANDBY FNP-0-CTG-1.7 SIMULATOR REAL TIME TEST FNP-0-CTG-1.8 OPERATING LIMITS EXCEEDED TEST FNP-0-CTG-2.1 FAILURE OF INSTRUMENT AIR SYSTEM FNP-0-CTG-2.2 SERVICE WATER PUMP TRIP FNP-0-CTG-2.3 CCW PUMP TRIP FNP-0-CTG-2.4 STEAM JET AIR EJECTOR FAILURE FNP-0-CTG 2.5 HOTWELL FILL CONTROLLER CP-4055F FAILURE FNP-0-CTG-2,16 STARTUP TRANSFORMER FAILURE FNP-0-CTG-2.20 120V VITAL INSTRUMENTATION DISTRIBUTION PANLL l TRIP FNP-0GG-2,21 120VAC DISTRIBUTION PANEL TRIP j l FNP-0-CTG 2.36 SOURCE RANGE CHANNEL FAILURE ' FNP-0-CTG 2.3601 FAILURE OF SOURCE RANGE CHANNEL HIGH VOLTAGE TO DISCONNECT FNP-0-CTG-2.360 SOURCE RANGE CHANNEL HIGH VOLTAGE FAILURE i FNP-0-CTG-2.3603 SOURCE RANGE BLOWN FUSE FNP-0-CTG 2.39 INADVERTANT REACTOR TRIP FNP-0-CTG-2.44 PRESSURIZER SAFETY VALVE FAILURE  ! FNP-0-CTG-2.48 REACTOR COOLANT SYSTEM LEAK I FNP-0-CTG 2.50 STEAM GENERATOR TUBE LEAK FNP-0-CTG-3.1 MANUAL REACTOR TRIP FNP-0-CTG-3.2 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS l FNP-0-CTG 3.3 SIMULTANEOUS CLOSURE OF MAIN STEAM ISO. VALVES FNP-0-CTG 3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS FNP-0-CTG-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP FNP-0-CTG 3.6 MAIN TURBINE TRIP (LESS THAN P-S SETPOINT) FNP-0-CTG 3.7 MAX RATE POWER RAMP (10T'o TO 75% TO 100%) FNP-0-CTG 3.8 MAX SIZE RCS RUPTURE WITH LOSP l FNP-0-CTG 3.9 MAX SIZE NON ISOLABLE MAIN ST' M LINE RUPTURE FNP-0-CTG-3.10 SLOW PRIMARY SYSTEM DEPRES' ' TION TO SATURATED CONDITION USING PL aZER RELIEF i SAFETY VALVE STUCK OPEN FNP-0-CTG-4.0 ONE HOUR STEADY STATE OPERATIONS TEST FNP-0-CTG-4.1 STEADY STATE COMPARISON TO REFERENCE PLANT l FNP-0-CTG 5.7 REACTOR TRIP DUE TO SPURIOUS MSIV CLOSURE l l l l 4

i: 4 Attachment 2 

          ,                  Four Year Test Schedule - 2000                 I FNP-0-CTG I.1    START UP FROM HOT STANDBY TO MINIMUM LOAD FNP-0-CTG-1.2    POWER OPERATIONS-MINIMUM LOAD TO 100% POWER FNP-0-CTG-1.6    CORE PHYSICS TESTING                            l FNP-0-CTG-1.7    SIMULATOR REAL TIME TEST FNP-0-CTG-1.8    OPERATING LIMITS EXCEEDED TEST FNP-0-CTG-2.12   DEGRADED GRID VOLTAGE-LOSP FNP-0-CTG-2.15   DIESEL GENERATOR ESSENTIAL PROTECTION FAILURE FNP-0-CTG 2.19   120VAC VITAL INSTRUMENT INVERTER FAILURE FNP-0-CTG 2.22   125VDC DISTRIBUTION PANEL TRIP FNP-0-CTG 2.27   FEEDWATER HEADER PRESSURE TRANSMITTER FAILURE                                       I FNP-0-CTG 2.38   POWER RANGE CHANNEL FAILURE                   I FNP-0-CTG-2.3801 POWER RANGE CHANNEL DETECTOR FAILURE FNP-0-CTG-2.3802 POWER RANGE BLOWN FUSE FNP-0-CTG-2,42   PRESSURIZER STEAM SPACE BREAK FNP-0-CTG-2.43   PRESSURIZER RELIEF VALVE FAILURE FNP-0-CTG-2.49   LOSS OF COOLANT ACCIDENT FNP-0-CTG-2.53   RCS LOOP PROTECTION RTD FAILURE FNP-0-CTG-2.55   RHR PUMP TRIP FNP-0-CTG-2.56   RHR HEAT EXCHANGER BYPASS LINE BREAK FNP-0-CTG-2.57   TURBINE 1" STAGE PRESSURE TRANSMTITER FAILURE FNP-0-CTG-2.59   AUX FEEDWATER PUMP TRIP FNP-0-CTG-3.1    MANUAL REACTOR TRIP FNP-0-CTG-3.2    SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS FNP-0-CrG-3.3    SIMULTANEOUS CLOSURE OF MAIN STEAM ISO.

VALVES FNP-0-CTG-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS FNP-0-CTG-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP i FNP-0-CTG-3.6 MAIN TURBINE TRIP (LESS TIIAN P4 SETPOINT) FNP-0-CTG-3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%) FNP-0-CTG-3.8 MAX SIZE RCS RUPTURE Wrill LOSP FNP-0-CTG-3,9 MAX SIZE NON-ISOLABLE MAIN STEAM LINE RUPTURE FNP-0-CTG-3.10 SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATED CONDITION USING PRESSURIZFR RELIEF SAFETY VALVE STUCK OPEN J FNP-0-CTG-4.0 ONE HOUR STEADY STATE OPERATIONS TEST l FNP-0-CTG-4.1 STEADY STATE COMPARISON TO REFERENCE PLANT ) 

                                                                            )

l 1 l i l

(. - L, # Attachment 2 Four Year Test Schedule-2001 FNP-0-CTG-1.3 RATED POWER TO HOT STANDBY FNP 0-CTG-1.7 SIMULATOR REAL TIME TEST FNP-0-CTG-1.8 OPERATING I.IMITS EXCEEDED TEST FNP-0-CTO-1.9 OPERATOR CONDUCTED SURVEILLANCE TEST l FNP-0-CTG-2.11 VCT LEVEL TRANSMITTER FAILURE i FNP-0-CTG-2.13 4160V BUS TRIP l FNP-0-CTG-2.14 EMERGENCY 4160V BUS TRIP - l- FNP-0-CTG-2.17 600V LOAD CENTER TRIP FNP-0-CTG-2.18 600V MOTOR CONTROL CENTER TRIP l FNP-0-CTG-2.23 - MDAFW FLOW CONTROL VALVE FAILURE t- FNP-0-CTG-2.31 STEAM LINE BREAK INSIDE CONTAINMENT l FNP-0-CTG-2.32 STEAM LINE BREAK OUTSIDE CTMT UPSTREAM OF MSIV FNP-0-CTG-2.34 STEAM DUMP VALVES FAIL TO OPERATE IN Tave MODE FNP-0-CTG-2.35 STEAM HEADER PRESS CONTROLLER PT464 FAILURE FNP-0-CTG-2.40 REACTOR TRIP BREAKER FAILS TO OPEN FNP-0-CTG-2,45 PRESSURIZER PRESSURE CHANNEL FAILURE FNP-0-CTG-2.46 PRESSURIZER LEVEL MASTER CONTROLLER FAILURE FNP-0-CTG-2.47 PRESSURIZER LEVEL CHANNEL FAILURE FNP-0-CTG-2.52 FUEL CLADDING FAILURE FNP-0-CTG-2.54 RCS LOOP COLD LEG RTD FAILURE' FNP-0-CTG-2.58 GENERATOR AUTO VOLTAGE REGULATOR FAILURE FNP-0-CTG-3.1 MANUAL REACTOR TRIP FNP-0-CTG-3.2 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS FNP-0-CTG-3.3 SIMULTANEOUS CLOSURE OF MAIN STEAM ISO. VALVES FNP-0-CTG-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS FNP-0-CTG-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP FNP-0-CTG-3.6 MAIN TURBINE TRIP (LESS THAN P-9 SETPOINT) FNP-0-CTG-3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%) FNP-0-CTG-3.8 MAX SIZE RCS RUPTURE WITH LOSP FNP-0-CTG 3.9 MAX SIZE NON-ISOLABLE MAIN STEAM LINE RUP'IURE FNP-0-CTG-3.10 SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATED CONDITION USING PRESSURIZER RELIEF SAFETY VALVE STUCK OPEN l FNP-0-CTG-4.0 ONE HOUR STEADY STATE OPERATIONS TEST FNP-0-CTG-4.1 STEADY STATE COMPARISON TO REFERENCE PLAhT l I l

Attachment 2 Four Year Test Schedule - 2002 FNP-0-CTG-1.301 SliUTDOWN FROM MINIMUM LOAD TO HOT STANDBY FNP-0-CTG-1.4 SHUTDOWN FROM HOT STANDBY TO COLD SHUTDOWN FNP-0-CTG-1.5 START UP FOLLOWING A REACTOR TRIP FNP-0-CTG-1.7 SIMULATOR REAL TIME TEST . FNP-0-CTG-1.8 OPERATING LIMITS EXCEEDED TEST FNP-0-CTG 2.7 ' RODS FAIL TO MOVE IN AUTO / MANUAL FNP-0-CTG-2.9 CONTROL ROD FAILURE-STUCK ROD FNP-0-CTG-2.10 CONTROL ROD FAILURE-DROPPED ROD FNP-0-CTG 2.24 STEAM GENERATOR FEEDPUMP TRIP FNP-0-CTO-2.25 STEAM GENERATOR FAILURE TO AUTO TRIP ' FNP-0-CTG-2.26 STEAM GENERATOR TURBINE SPEED CONT. FAILURE FNP-0-CTG-2.28 STEAM GENERATOR LEVEL CHANNEL FAILURE FNP-0-CTG-2.29 FEED LINE BREAK OUTSIDE CONTAINMENT DOWNSTREAM OF STOP CHECK VALVE FNP-0-CTG-2.30 FEED LINE BREAK INSIDE CONTAINMENT FNP-0-CTG-2.33 STEAM LINE FLOW TRANSMITTER FAILURE FNP-0-CTG-2.37 INTERMEDIATE RANGE CHANNEL FAILURE FNP-0-CTG-2.3701 INTERMEDIATE RANGE CHANNEL GAMMA COMPENSATION FAILURE l FNP 0-CTG-2.3702 INTERMEDIATE RANGE CHANNEL BLOWN FUSE FNP-0-CTG 2.41 - SAFEGUARD ACTUATION AND CTMT ISO. FAILURE FNP-0-CTG-2.S l REACTOR COOLANT PUMP TRIP FNP-0-CTG-3.1 MANUAL REACTOR TRIP FNP-0-CTG-3.2 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS FNP-0-CTG-3.3 SIMULTANEOUS CLOSURE OF MAIN STEAM ISO. l VALVES I FNP-0-CTG-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS l FNP-0-CTG-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP FNP-0-CTG-3.6 ' MAIN TURBINE TRIP (LESS THAN P-9 SETPOINT) FNP-0-CTG-3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%) FNP-0-CTG-3.8 MAX SIZE RCS RUPTURE WITH LOSP FNP-0-CTG-3.9 MAX SIZE NON-ISOLABLE MAIN STEAM LINE RUPTURE ' FNP-0-CTG-3.10 SLOW PRIMARY SYSTEM DEPRESSURIZATION TO ' SATURATED CONDITION USING PRESSURIZER RELIEF SAFETY VALVE STUCK OPEN FNP-0-CTG-4.0 ONE HOUR STEADY STATE OPERATIONS TEST FNP-0-CTG-4.1 STEADY STATE COMPARISON TO REFERENCE PLANT

9 e 4 e 0 ATTACHMENT 3 I CHANGES TO THE TESTING PLAN f I l 

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l l l l l l l l 2 l I

1 

    .                                                                                                       i

, O I Attachment 3 

          -                                    Changes To the Testing Plan Attachment 4 to the 1995 certification report listed the tests to be performed in each of four   .

test periods, 1995-1998. The following are changes made to those lists: 1995 (first year auadrennial tests)  ! FNP-0-CTP-2.6, HOTWELL DUMP CONTROLLER CP-4055G FAILURE, was not , performed due to the removal of the controller in the plant. The test procedure was deleted. FNP-0-CTP-5.7, REACTORTRIP DUE TO SPURIOUS MSIV CLOSURE, was performed. This procedure was added to test the simulator agamst an actual plant trip. l 1997 (third year auadrennial tests) In the spring of 1997, all the simulator software was ported to new computer systems. As a result, the entire complement of certification tests was run to validate the converted software running on the new computers. 4 1998 (fr ivear auadrennial tests) 

            "CTP" _. ach procedure number was changed to " CTG".

FNP-0-CTG-1.9, OPERATOR CONDUCTED SURVEILLANCE TEST, was deleted. The functionality of this procedure was incorporated into FNP-0-CTG-4.0, which was performed in 1998. ' FNP-0-CTG-2.8, RODS FAIL TO MOVE IN MANUAL, was deleted and incorporated into FNP-0-CTG-2.7, RODS FAIL TO MOVE IN AUTO / MANUAL. FNP 4-CTG-4.2, STEADY STATE THERMAL CALORIMETRIC COMPARISON, was , deleted and incorporated into FNP-0-CTG-4.1, STEADY STATE COMPARISON TO REFERENCE PLANT. FNP-0-CTG-2.48 was deleted from the list for 1998 because it was duplicated in the list for 1995. l}}

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