ML20081F105
| ML20081F105 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/14/1995 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9503210530 | |
| Download: ML20081F105 (14) | |
Text
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%i Southern Nuclear Opertting Company.
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Post Office Box 1295
. Birmingtt:.m. Alabama 35201 a.
Telephone (205) 868-5131.
Southern Nuclear Operating Company oey uorey fa$efp,*he*[
t the southem electnc system March 14,1995 Docket Nos.:50-348 10 CFR 55.45
.50-364 Director, Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission -
MS 12G 18 Room 12 D1 Washington, DC 20555-001 Joseph M. Farley Nuclear Plant t
Simulator Facility Re-Ceitification Gentlemen:
Southern Nuclear Operating Ccmpany submits Form-474, " Simulation Facility Certification," with attachments, in compliance with 10 CFR 55.45.b.5.ii and b.5.vi. The enclosed material provides you the information necessary for the re-certification of the Farley Nt.:ar Plant simulator as a plant-referenced simulation facility.
If there are any questions, please advise.
Respectfully submitted, tT) Mew Dave Morey EFB/ cit:simrecr. doc Enclosure
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cc: Mr. S. D. Ebneter i
Mr. B. L. Siegel Mr. T. M. Ross 210062 9503210530 950314 PDR ADOCK 05000348 8
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.l SIMULATION FACluTY CERTIFICATION
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INSTRUCT 100st. This form is to be filed for inetial omrtificateen, reesrtification (if required), and for any change to a simuistion festaity -.. c testing pian made after irutial sutmittal of sush a plan. Provide the feelewing information, and check the appropriate bom to indicate reason for outmuttal.
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>ACiUTY Joseph M. Farley Nuclear Plant, Unit.1 so. 34 ucENsEE l oats Southern Nuclear Operating Company 2/28/95 This is to certify thst:
1.
The above named fetillity licensee is using a simulation facility consisting solely of a pientoferenced simuister that meets the requerements of to CF M 56.46.
2, Doeunientasion is ave 6iende ser NRC review in assordenes with 10 CF A 84.46(t).
i 3.
This simuistion feeility meses the ondenes sentened in ANSI /ANS 3.5,1905, es endorsed by NRC Megaistory Guide 1.140.
if there are any emeeptions to the eartsfiestion of this 6terii, check here [ j and desordse fully on addetional pages as necessary NAME for sWearaAser/Meer/sp) Afs0 LOCATlON OF SleWULATION FActuTY Farley Nuclear Plant Trainino, Center US Hwy 95 S, 5 miles South of Columbia, A1.
SIMULATION F ACILITY PE R FORMANCE TEST A88 TRACTS ATTACHED, (forperfbrmance rests condurreur in the period ancfiny with the dure of this certification) 1 OESCRIPTION OF PER FORMANCE TESTING COMPLETED (Artsat andfraons/papp(s) se necessary, and tomrW the sren deserrardon bent cont /nuesf/
SIMULATION FAClu TY PERFORMANG TESTING SCHEDULE ATTACHE 0. Ify ene conduct of amoronsnarser 255 of partensnes reursper roer fbr rne Asur year perdad somnienetrqr adre see duse of ends care /Amerden.)
DESCRif' TION OF PERFORMANCE TESTING TO BE CON 00CTEO. (Arouse asMirdenstassse)as assssunry,and Ashmirt& the men desanistise 6eisp aantesued; y
PERFORMANCE TESTING PLAN r44 NGE. (For any mosWessefon to a persbanimise reurnir aden ment / trust on a prowdois cert / Amer 4on/
DESCRif' TION OF PER FORMANCE TESTING PLAN CHANGE (Artsch adsMrsonsiJespp(s/ as asesuury,andidesti$ ras Aron duurr$srion besip contenued).
j See Attachment 1 l
R ECE RTIFICATiON (Deertr6e corruer/se actsons seten, sesech resu43 of contodstadperfbrmance rearmy #t asterslence awth 70 CrA 5 56.45I41(51/rf.
X Arrasa adsursenet paesvos as nessemer, eid Amnswe ene seen dessrerw 6edny cont *=mu See Attachments 2,3 and 4 Any hies sessement or ommon m thes desumente$ciud.no atteerenems, mey tie eutiket to emi and crimenet sorcemes i eartify unser penesty of omrtury that the informetee7~
tM)" -, and setachments is true and correst" SiONATURE - A HOftl5EQ REPRESENTATIVE l TITLE lOATE
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sv MAIL AcontseEo To: onesaur,ofane se samasse mensmer nessammen av oEuvEnv NPEnsoN one undis Pum Mere UA sessemer messauery Censmetulos TO TNE NRC OFF8M AT:
11M Reshnes Feie WIssIIIngguai,oC 3M W Im Niec #cass 474 81agg
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appmovt3 ev osse: eso. 3teeketae oops esmw, M.e sus MA WTansATec suncea pen Reposes TO CoerLY WITH THee inspomasATI0ss COLLaCTI0er nGehdWT: tas Mat P053ssano 7 getAsse t W3, seuCLAAA meeutATOsty ensamanamanas, wrn_;7y,, of o"E.' o'p'InEoM Ass'O "o"uoET, usofIose ItC 30803.
IfSTRUCTIOGIS. The foren is to be filed for imtial eartifteetion, resortification Of requirass), and for any change to e sunulation faccity performenee testwas pian inade after initial summaw of such a ien. Provide ce fene. n. informaien, and che.m the a.oro.rme non to indiano,meon for sun tw.
FACluTY l DOCKET NVM5ER Tosenh M. Farlev Nuclear Plant. Unit 2 so. 364 P^
Southern Nuclear Operating Company 2/28/95 This is to eartify that:
1.
The above named facility licensee is ussag a simuletsen feedity conssting solely of a plant <eferenood simulator that enests the requirements of 10 CF R 56.46, 2.
Desumentation is osedemie for NRC rev6ew in esmordanos wah 10 CF M SSA6(t),
3.
This simulation famility meets the psidense contasnad in ANSt/ANS 3.5,1985, as endorsed by NRC Reedstory Guale 1.140.
If there are any==ava=*is to the eartsfleethan of this 6 tem, check here [ ] and deserthe fully on addetional pages as necessary NA44E forsener Admir/Meerden/ AND LOCAtlope OF SlMULATION FACIUTY Farley Nuclear Plant Training Center US Hwy 95 S, 5 miles South of Columbia, A1.
SIMULATlON F ACluTY PER FORMANCE TEST ASSTRACTS ATTACHEO. (Forperfbr6nence taurs conclueraf in the pened miding wrrh the clare of this cet/flearnm/
DESCRIFTION OF PE RFORMANCE TESTING COMPLETED (Arrace adw#ione/pegers) as neremory, wieidentify the hem senerrardon bana contmuerl SIMULATION FAClu TY FERPORMAfeCE TESTING SCHEDULE ATTACHEO. (for ets constser 9/ameremanerefy 265 etpartbanesses reurs per year sbr the /our year perdsW ammmeassy wdre the ahes e/ eAdr ser/fisarden./
DESCRIPTION OF PERFORMANCE TESTING TO BE CXh400CTEO. (Assume adeurdensipegedu/ as assamury, andistunrW *ne 4 eve ahuuresrden temy sontheueW) y PERFORMANCE TESTING PLAN CHANGE. (For any meswisseten to e perdsswiwee resreia pdwe makm# red on a prendous corrt/Iserten/
DESCRWTION OF PER FORMANCE TESTING PLAN CHANGE (Aesse4 adsurdenaf papods)se assamury,anafidearl$ the /ren dauertorien eesny continued)
The Unit 1 training simulator is utilized for Unit 2 simulator training.
The schedule for annual nerformance testin3 is that of Unit 1.
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R ECE RTlFICATION (Deserv6e cenart/ve artens seter, ersarA rear 4s of ciwnsederedperWominare toursrip at accorses' ice evern 70 CFA l 55.48db1(51/r).
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straer anwesenet pareta) a nessmery, e.d idmarw the non ammansrden sets centhmuod.)
l The Unit 1 training sinulator is utilized for Unit 2 simulator training.
1 Performance test results and corrective actions are those of Unit 1.
A.ny f
.ement - om.en.n n.s desum /.*"'.n. niee n, may. sweet io c d and crim.nm sena.ons. i c-tw und-senney of riury m me iMaTu~n in i e desumere end a _.s t~e end es,re SIGNAT
. AUTHONIZERMEPRESENT TIVE l TITLE lDATE I
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e t-Nuclear Plant General Manager J /g f(-~
f In aussesnee with 10 CPR l EEA. Cos$nuneauseenL tous form shaft to estenetted to spo NRC as tonome:
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SY MAIL ADOREMEO TO: Desesser Osame et semukse mensner negadmusma SY OEUVERY IN PER9080 One tuttens Ptst Itasch 5
UA Ieudmer needucary Osmumheten TO THE NRC OFFICE AT:
11M Resisses Pts I
Winshingssa,DC 3M Anakoes, RS SAC POW e7e (Im
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1 l
Changes To Testing Plan Section A.S.2 of the initial certification report of 1991 listed the tests to be performed in each of the following four years. In addition to those listed, the-following tests were added to the fourth year plan and run in 1994/95:
FNP-SIM-CTP-1.301 SHUTDOWN FROM MINIMUM LOAD TO HOT STANDBY FNP-SIM-CTP-1.4 SHUTDOWN FROM HOT STANDBY TO COLD SHUTDOWN FNP-SIM-CTP-1.5 START UP FOLLOWING A REACTOR TRIP FNP-SIM-CTP-1.6 CORE PHYSICS TESTING FNP-SIM-CTP-2.48 REACTOR COOLANT SYSTEM LEAK FNP-SIM-CTP-4.2 STEADY STATE THERMAL CALORIMETRIC COMPARISON l
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Failed Test Procedures There are no test' failures pending. All test failures have been corrected and retested satisfactorily. The following is a list of tests and simulator change requests (SCR's) that were written and worked during the past 4 yearc.
1991 FNP-SIM-CTP-2.1 SCR 91.064 Emergency breathing air valves did not fail due to loss of air. Corrected the logic for HV2935A and HV2935B to allow proper failure modes on loss of Aux Building air.
FNP-SIM-CTP-2.50 SCR 91.065 During a S/G tube rupture, while cooling by draining back to the RCS, S/G pressure increased when it should have decreased. Changed energy flow calculation to reflect S/G enthalpy flow is out when flow is out of the S/G.
FNP-SIM-CTP-4.1 SCR 91.067 Steady state values for steam flow and feed flow at low power (32%) were not within tolerance with plant expected values. Analysis of the plant indicated that the plant data were inaccurate at the low power level and the simulator was in fact correct. The SCR was cleared and no changes were made to the simulator 1992 FNP-SIM-CTP-3.1 SCR 93.004 S/G level response after a reactor trip was slightly different from the plant. Tuned S/G narrow range level response to more closely match the plant.
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, Attachment 2 Continued Failed Test. Procedures 1993 FNP-SIM-CTP-2.52
- SCR 93.023 -Gross ' failed' fuel detector ~did not-alarm. Added' Gross' failed' fuel' detector alarm logic to the RMS model.
FNP-SIM-CTP-2.18 SCR'93.029.MOV 8100 did not respond ~to loss of' power._ Valve was powered from;the wrong MCC.
FNP-SIM-CTP-3.2-SCR 93.045 S/G NR.did not seem 'o agrea=
t with WR level response. Further,
investigation'of ? plant _ data-revealed that the simulator was accurate and this SCR.was cleared without making'any_.
changes to the simulator.-
~
1994 FNP-SIM-CTP-2.3801 SCR 94.055 New digital NIS power range meters did not respond properly to failed detector malfunctions. Over range blanking corrected by rewiring meter inputs.
FNP-SIM-CTP-2.57-SCR~94.059 Turbine _first' stage. pressure meter was~ indicating psia values whenJpsig' values were entered-for the malfunction.
~
Corrected the' malfunction
-program.
FNP-SIM-CTP-2. 37 '
SCR 95.002 IR'HI FLUX' AUTO / MAN ROD STOP-alarm responded to one channel and not the other. Corrected alarm logic.
FNP-SIM-CTP-4.1 SCR 95.011 Tuned pressurizer pressure and intermediate range NIS to more closely match 1995 plant data.
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Description of Tests Completed - 1991 FNP-SIM-CTP-1.0 START UP FROM COLD SHUTDOWN TO HOT STANDBY FNP-SIM-CTP-1.7 SIMULATOR REAL TIME TEST FNP-SIM-CTP-1.8 OPERATING LIMITS EXCEEDED TEST FNP-SIM-CTP-2.1 FAILURE OF INSTRUMENT AIR SYSTEM FNP-SIM-CTP-2.2 SERVICE WATER PUMP TRIP FNP-SIM-CTP-2.3 CCW PUMP TRIP FNP-SIM-CTP-2.4 STEAM JET AIR EJECTOR FAILURE FNP-SIM-CTP-2.5 HOTWELL FILL CONTROLLER CP-4055F FAILURE FNP-SIM-CTP-2.6 HOTWELL DUMP CONTROLLER CP-4055G FAILURE FNP-SIM-CTP-2.16 STARTUP TRANSFORMER FAILURE FNP-SIM-CTP-2.20 120V VITAL INSTRUMENTATION DIST. PANEL TRIP FNP-SIM-CTP-2.21 120VAC DISTRIBUTION PANEL TRIP FNP-SIM-CTP-2.39 INADVERTENT REACTOR TRIP FNP-SIM-CTP-2.44 PRESSURIZER SAFETY VALVE FAILURE 4
FNP-SIM-CTP-2.48 REACTOR COOLANT SYSTEM LEAK FNP-SIM-CTP-2.50 STEAM GENERATOR TUBE LEAK FNP-SIM-CTP-3.1 MANUAL REACTOR TRIP FNP-SIM-CTP-3.2 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS FNP-SIM-CTP-3.3 SIMULTANEOUS CLOSURE OF MAIN STEAM ISO. VALVES FNP-SIM-CTP-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS FNP-SIM-CTP-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP FNP-SIM-CTP-3.6 MAIN TURBINE TRIP (LESS THAN P-9 SETPOINT)
FNP-SIM-CTP-3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%)
FNP-SIM-CTP-3.8 MAX SIZE RCS RUPTURE WITH LOSP FNP-SIM-CTP-3.9 MAX SIZE NON-ISOLABLE - MAIN STEAM LINE RUPTURE FNP-SIM-CTP-3.10 SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATED CONDITION USING PRESSURIZER RELIEF OF SAFETY VALVE STUCK OPEN FNP-SIM-CTP-4.0 ONE HOUR STEADY STATE OPERATIONS TEST FNP-SIM-CTP-4.1 STEADY STATE COMPARISON TO REFERENCE PLANT i
l
' Continued Description of Tests Completed - 1992 FNP-SIM-CTP-1.1 START UP FROM HOT STANDBY TO MINIMUM LOAD FNP-SIM-CTP-1.2 POWER OPERATIONS-MINIMUM LOAD TO 100% POWER FNP-SIM-CTP-1.7 SIMULATOR REAL TIME TEST FNP-SIM-CTP-1.8 OPERATING LIMITS EXCEEDED TEST FNP-SIM-CTP-2.12 DEGRADED GRID VOLTAGE-LOSP FNP-SIM-CTP-2.15 DIESEL GENERATOR FAILURE ESSENTIAL-PROTECTION FNP-SIM-CTP-2.19 120VAC VITAL INSTRUMENT INVERTER FAILURE FNP-SIM-CTP-2.22 125VDC DISTRIBUTION PANEL TRIP FNP-SIM-CTP-2.27 FEEDWATER HEADER PRESSURE TRANSMITTER FAILURE FNP-SIM-CTP-2.38 POWER RANGE CHANNEL FAILURE FNP-SIM-CTP-2.3801 POWER RANGE CHANNEL DETECTOR FAILURE FNP-SIM-CTP-2.3802 POWER RANGE BLOWN FUSE FNP-SIM-CTP-2.42 PRESSURIZER STEAM SPACE BREAK FNP-SIM-CTP-2.43 PRESSURIZER RELIEF VALVE FAILURE FNP-SIM-CTP-2.49 LOSS OF COOLANT ACCIDENT FNP-SIM-CTP-2.53 RCS LOOP PROTECTION RTD FAILURE FNP-SIM-CTP-2.55 RHR PUMP TRIP FNP-SIM-CTP-2.56 RHR HTX BYPASS LINE BREAK FNP-SIM-CTP-2.57 TURBINE 1ST STAGE PRESSURE TRANSMITTER FAILURE FNP-SIM-CTP-2.59 AUX FEEDWATER PUMP TRIP FNP-SIM-CTP-3.1 MANUAL REACTOR TRIP FNP-SIM-CTP-3.2 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS FNP-SIM-CTP-3.3 SIMULTANEOUS CLOSURE OF MAIN STEAM ISO. VALVES FNP-SIM-CTP-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS FNP-SIM-CTP-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP FNP-SIM-CTP-3.6 MAIN TURBINE TRIP (LESS THAN P-9 SETPOINT)
FNP-SIM-CTP-3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%)
FNP-SIM-CTP-3.8 MAX SIZE RCS RUPTURE WITH LOSP FNP-SIM-CTP-3.9 MAX SIZE NON-ISOLABLE MAIN STEAM LINE RUPTURE FNP-SIM-CTP-3.10 SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATED CONDITION USING' PRESSURIZER RELIEF OF SAFETY VALVE STUCK OPEN FNP-SIM-CTP-4.0 ONE HOUR STEADY STATE OPERATIONS TEST FNP-SIM-CTP-4.1 STEADY STATE COMPARISON TO REFERENCE PLANT i
l
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Attachment'3 continued'
-Description of. Tests Completed - 1993 FNP-SIM-CTP-1.3-RATED POWER TO HOT STANDBY FNP-SIM-CTP-1.7 SIMULATOR REAL TIME TEST FNP-SIM-CTP-1.8 OPERATING LIMITS EXCEEDED TEST FNP-SIM-CTP-2.11
~VCT LEVER TRANSMITTER FAILURE FNP-SIM-CTP-2.13 4160V BUS TRIP FNP-SIM-CTP-2.14'
. EMERGENCY 4160V BUS TRIP FNP-SIM-CTP-2.17 600V LOAD CENTER TRIP FNP-SIM-CTP-2.18 600V MOTOR CONTROL CENTER TRIP FNP-SIM-CTP-2.23 MDAFW FLOW CONTROL VALVE FAILURE FNP-SIM-CTP-2.31 STEAM LINE BREAK INSIDE CONTAINMENT-FNP-SIM-CTP-2.32 STEAM LINE BREAK.OUTSIDE CTMT UPSTREAM OF MSIV FNP-SIM-CTP-2.34 STEAM DUMP VALVES FAIL' TO OPERATE IN TAVE MODE FNP-SIM-CTP-2.35 STEAM HEADER PRESS CONTROLLER PT464 FAILURE FNP-SIM-CTP-2.40 REACTOR TRIP BREAKER FAILS TO OPEN FNP-SIM-CTP-2.45 PRESSURIZER PRESSURE CHANNEL FAILURE FNP-SIM-CTP-2.46 PRESSURIZER LEVEL MASTER CONTROLLER FAILURE FNP-SIM-CTP-2.47 PRESSURIZER LEVEL CHANNEL FAILURE FNP-SIM-CTP-2.52-FUEL CLADDING FAILURE FNP-SIM-CTP-2.54 RCS LOOP COLD LEG RTD FAILURE FNP-SIM-CTP-2.58 GENERATOR AUTO VOLTAGE REGULATOR FAILURE FNP-SIM-CTP-3.1 MANUAL REAC"9R TRIP FNP-SIM-CTP-3.2 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS FNP-SIM-CTP-3.3 SIMULTANEOUS CLOSURE OF MAIN STEAM ISO. VALVE 1 FNP-SIM-CTP-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS FNP-SIM-CTP-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP FNP-S1M-CTP-3.6 MAIN TURBINE TRIP (LESS THAN P-9 SETPOINT)
FNP-SIM-CTP-3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%)
Fl!P-SIM-CTP-3.8 MAX SIZE RCS RUPTURE WITH LOSP FNP-SIM-CTP-3.9 MAX SIZE NON-ISOLABLE MAIN STEAM LINE RUPTURE FNP-SIM-CTP-3.10 SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATED CONDITION USING PRESSURIZER RELIEF OF SAFETY VALVE STUCK OPEN 1
FNP-SIM-CTP-4.0 ONE HOUR STEADY STATE OPERATIONS TEST FNP-SIM-CTP-4.1' STEADY STATE COMPARISON TO REFERENc" PLANT 1
'j
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. continued Description of Test Completed - 1994/95 FNP-SIM-CTP-1.301 SHUTDOWN FROM MINIMUM LOAD TO HOT STANDBY FNP-SIM-CTP-1.4 SHUTDOWN FROM HOT STANDBY TO COLD SHUTDOWN FNP-SIM-CTP-1.5 START UP FOLLOWING A REACTOR TRIP FNP-SIM-CTP-1.6 CORE PHYSICS TESTING FNP-SIM-CTP-1.7 SIMULATOR REAL TIME TEST FNP-SIM-CTP-1.8 OPERATING LIMITS EXCEEDED TEST FNP-SIM-CTP-1.9 OPERATOR CONDUCTED SURVEILLANCE TEST FNP-SIM-CTP-2.7
. RODS FAIL TO MOVE IN AUTO FNP-SIM-CTP-2.8 RODS FAIL TO MOVE IN MANUAL FNP-SIM-CTP-2.9 CONTROL ROD FAILURE-STUCK ROD FNP-SIM-CTP-2.10 CONTROL ROD FAILURE-DROPPED ROD FNP-SIM-CTP-2.24 SGFP TRIP FNP-SIM-CTP-2.25 SGFP FAILURE TO AUTO TRIP FNP-SIM-CTP-2.26 SGFP TURBINE SPEED CONTROLLER FAILURE FNP-SIM-CTP-2.28 STEAM GENERATOR LEVEL CHANNEL FAILURE FNP-SIM-CTP-2.29 FEED LINE BREAK OUTSIDE CONTAINMENT DOWNSTREAM OF STOP CHECK VALVE FNP-SIM-CTP-2.30 FEED LINE BREAK INSIDE CONTAINMENT FNP-SIM-CTP-2.33 STEAM LINE FLOW TRANSMITTER FAILURE FNP-SIM-CTP-2.36 SOURCE RANGE CHANNEL FAILURE FNP-SIM-CTP-2.3601 FAILURE OF SOURCE RANGE CHANNEL HIGH VOLTAGE TO DISCONNECT FNP-SIM-CTP-2.3602 SOURCE RANGE CHANNEL HIGH VOLTAGE FAILURE FNP-SIM-CTP-2.3603 SOURCE RANGE BLOWN FUSE FNP-SIM-CTP-2.37 INTERMEDIATE RANGE CHANNEL FAILURE FNP-SIM-CTP-2.3701 I.R.
CHANNEL GAMMA COMPENSATION FAILURE FNP-SIM-CTP-2.3702 INTERMEDIATE RANGE BLOWN FUSE FNP-SIM-CTP-2.41 SAFEGUARD ACTUATION AND CTMT ISO FAILURE FNP-SIM-CTP-2.48 REACTOR COOLANT SYSTEM LEAK FNP-SIM-CTP-2.51 REACTOR COOLANT PUMP TRIP FNP-SIM-CTP-3.1 MANUAL REACTOR TRIP FNP-SIM-CTP-3.2 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS FNP-SIM-CTP-3.3 SIMULTANEOUS CLOSURE OF MAIN STEAM ISO. VALVES FNP-SIM-CTP-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS FNP-SIM-CTP-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP FNP-SIM-CTP-3.6 MAIN TURBINE TRIP (LESS THAN P-9 SETPOINT)
FNP-SIM-CTP-3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%)
FNP-SIM-CTP-3.8 MAX SIZE RCS RUPTURE WITH LOSP FNP-SIM-CTP-3.9 MAX SIZE NON-ISOLABLE MAIN STEAM LINE RUPTURE FNP-SIM-CTP-3.10 SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATED CONDITION USING PRESSURIZER RELIEF OF SAFETY VALVE STUCK OPEN FNP-SIM-CTP-4.0 ONE HOUR STEADY STATE OPERATIONS TEST l
FNP-SIM-CTP-4.1 STEADY STATE COMPARISON TO REFERENCE PLANT FNP-SIM-CTP-4.2 STEADY STATE THERMAL CALORIMETRIC COMPARISON
Four Year Test Schedule - 1995 FNP-SIM-CTP-1.0 START UP FROM COLD SHUTDOWN TO HOT STANDBY FNP-SIM-CTP-1.7 SIMULATOR REAL TIME TEST l
FNP-SIM-CTP-1.8 OPERATING LIMITS EXCEEDED TEST FNP-SIM-CTP-2.1 FAILURE OF INSTRUMENT AIR SYSTEM FNP-SIM-CTP-2.2 SERVICE WATER PUMP TRIP FNP-SIM-CTP-2.3 CCW PUMP TRIP FNP-SIM-CTP-2.4 STEAM JET AIR EJECTOR FAILURE FNP-SIM-CTP-2.5
'HOTWELL FILL CONTROLLER CP-4055F FA.. LURE FNP-SIM-CTP-2.6 HOTWELL DUMP CONTROLLER CP-4055G FAILURE FNP-SIM-CTP-2.16 STARTUP TRANSFORMER FAILURE FNP-SIM-CTP-2.20 120V VITAL INSTRUMENTATION DIST. PANEL TRIP FNP-SIM-CTP-2.21 120VAC DISTRIBUTION PANEL TRIP FNP-SIM-CTP-2.39 INADVERTENT REACTOR TRIP FNP-SIM-CTP-2.44 PRESSURIZER SAFETY VALVE. FAILURE FNP-SIM-CTP-2.48 REACTOR COOLANT SYSTEM LEAK FNP-SIM-CTP-2.50 STEAM GENERATOR TUBE LEAK FNP-SIM-CTP-3.1 MANUAL REACTOR TRIP FNP-SIM-CTP-3.2 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS FNP-SIM-CTP-3.3 SIMULTANEOUS CLOSURE OF MAIN STEAM ISO. VALVES FNP-SIM-CTP-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS i
FNP-SIM-CTP-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP FNP-SIM-CTP-3.6 MAIN TURBINE TRIP (LESS THAN P-9 SETPOINT)
FNP-SIM-CTP-3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%)
FNP-SIM-CTP-3.8 MAX SIZE RCS RUPTURE WITH LOSP FNP-SIM-CTP-3.9 MAX SIZE NON-ISOLABLE MAIN STEAM LINE RUPTURE-FNP-SIM-CTP-3.10 SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATED CONDITION USING PRESSURIZER RELIEF OF SAFETY VALVE STUCK OPEN FNP-SIM-CTP-4.0 ONE HOUR STEADY STATE OPERATIONS TEST.
FNP-SIM-CTP-4.1 STEADY STATE COMPARISON TO REFERENCE PLANT
- t
, - - - - w
' Continued Four Year Test Schedule - 1996 FNP-SIM-CTP-1.1 START UP FROM HOT STANDBY TO MINIMUM LOAD FNP-SIM-CTP-1.2 POWER OPERATIONS-MINIMUM LOAD TO 100% POWER FNP-SIM-CTP-1.7 SIMULATOR REAL TIME TEST FNP-SIM-CTP-1.8 OPERATING LIMITS EXCEEDED TEST FNP-SIM-CTP-2.12 DEGRADED GRID VOLTAGE-LOSP 1
FNP-SIM-CTP-2.15 DIESEL GENERATOR FAILURE ESSENTIAL-PROTECTION i
FNP-SIM-CTP-2.19 120VAC VITAL INSTRUMENT INVERTER FAILURE FNP-SIM-CTP-2.22 125VDC DISTRIBUTION PANEL TRIP L
FNP-SIM-CTP-2.27 FEEDWATER HEADER PRESSURE TRANSMITTER FAILURE FNP-SIM-CTP-2.38 POWER RANGE CHANNEL FAILURE FNP-SIM-CTP-2.3801 POWER RANGE CHANNEL DETECTOR FAILURE FNP-SIM-CTP-2.3802 POWER RANGE BLOWN FUSE j
-FNP-SIM-CTP-2.42 PRESSURIZER STEAM SPACE BREAK FNP-SIM-CTP-2.43 PRESSURIZER RELIEF VALVE FAILURE FNP-SIM-CTP-2.49 LOSS OF COOLANT ACCIDENT FNP-SIM-CTP-2.53 RCS LOOP PROTECTION RTD FAILURE FNP-SIM-CTP-2.55 RHR PUMP TRIP FNP-SIM-CTP-2.56 RHR HTX BYPASS LINE BREAK FNP-SIM-CTP-2.57 TURBINE IST STAGE PRESSURE TRANSMITTER FAILURE FNP-SIM-CTP-2.59 AUX FEEDWATER PUMP TRIP FNP-SIM-CTP-3.1 MANUAL REACTOR TRIP FNP-SIM-CTP-3.2 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS 4
FNP-SIM-CTP-3.3 SIMULTANEOUS CLOSURE OF MAIN STEAM ISO. VALVES FNP-SIM-CTP-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS FNP-SIM-CTP-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP FNP-SIM-CTP-3.6 MAIN TURBINE TRIP (LESS THAN P-9 SETPOINT)
FNP-SIM-CTP-3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%)
FNP-SIM-CTP-3.8 MAX SIZE RCS RUPTURE WITH LOSP FNP-SIM-CTP-3.9 MAX SIZE NON-ISOLABLE MAIN STEAM LINE RUPTURE I
FNP-SIM-CTP-3.10 SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATED CONDITION USING PRESSURIZER RELIEF OF SAFETY VALVE STUCK OPEN FNP-SIM-CTP-4.0 ONE HOUR STEADY STATE OPERATIONS TEST FNP-SIM-CTP-4.1 STEADY STATE COMPARISON TO REFERENCE PLANT
1 Attachment 4.ContinuedL
- Four Year Test Schedule.- 1997 FNP-SIM-CTP-1,3 RATED POWER'TO HOT STANDBY-FNP-SIM-CTP-1.7 SIMULATOR REAL TIME TEST
.FNP-SIM-CTP-1.8-OPERATING LIMITS-EXCEEDED TEST-FNP-SIM-CTP-2.11 VCT LEVER TRANSMITTER FAILURE FNP-SIP-CTP-2.13 4160V. BUS TRIP
-r FNP-SIM-CTP-2.14-EMERGENCY 4160V BUS TRIP FNP-SIM-CTP-2.17 600V LOAD CENTER TRIP:
FNP-SIM-CTP-2.18 600V MOTOR CONTROL CENTER TRIP FNP-SIM-CTP-2.23 MDAFW FLOW. CONTROL' VALVE FAILURE
'FNP-SIM-CTP-2.31 STEAM LINE BREAK INSIDE CONTAINMENT FNP-SIM-CTP-2.32 STEAM LINE BREAK OUTSIDE CTMT UPSTREAM OF MSIV.
I FNP-SIM-CTP-2.34 STEAM DUMP VALVES FAIL TO OPERATE IN TAVE MODE FNP-SIM-CTP-2.35-STEAM HEADER PRESS CONTROLLER PT464 FAILURE
-FNP-SIM-CTP-2.40 REACTOR TRIP BREAKER FAILS TO OPEN FNP-SIM-CTP-2.45-PRESSURIZER PRESSURE CHANNEL FAI LURE-FNP-SIM-CTP-2.46-PRESSURIZER LEVEL MASTER CONTROLLER FAILURE FNP-SIM-CTP-2.47 PRESSURIZER LEVEL CHANNEL FAILURE FNP-SIM-CTP-2.52 FUEL CLADDING FAILURE FNP-SIM-CTP-2.54-RCS LOOP COLD LEG RTD FAILURE, FNP-SIM-CTP-2.58 GENERATOR AUTO VOLTAGE REGULATOR FAILURE FNP-SIM-CTP-3.1 MANUAL REACTOR. TRIP FNP-SIM-CTP-3.2 SIMULTANEOUS TRIP-OF ALL FEEDWATER PUMPS FNP-SIM-CTP-3,3 SIMULTANEOUS CLOSURE OF MAIN STEAM ISO. VALVES FNP-SIM-CTP-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS FNP-SIM-CTP-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP FNP-SIM-CTP-3.6 MAIN TURBINE TRIP (LESS THAN P-9 SETPOINT)
FNP-SIM-CTP-3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%).
FNP-SIM-CTP-3.8 MAX SIZE RCS RUPTURE WITH LOSP FNP-SIM-CTP-3.9 MAX SIZE NON-ISOLABLE MAIN STEAM LINE RUPTURE FNP-SIM-CTP-3.10 SLOW PRIMARY SYSTEM DEPRESSURIZATION'TO SATURATED CONDITION USING PRESSURIZER RELIEF OF SAFETY VALVE STUCK OPEN FNP-SIM-CTP-4.0 ONE HOUR STEADY STATE OPERATIONS TEST FNP-SIM-CTP-4.1 STEADY STATE COMPARISON TO REFERENCE PLANT i
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. Continued Four Year Test Schedule - 1998 FNP-SIM-CTP-1.301 SHUTDOWN FROM MINIMUM LOAD TO HOT STANDBY FNP-SIM-CTP-1.4 SHUTDOWN FROM HOT STANDBY TO COLD SHUTDOWN FNP-SIM-CTP-1.5 START UP FOLLOWING A REACTOR TRIP FNP-SIM-CTP-1.6 CORE PHYSICS TESTING FNP-SIM-CTP-1.7 SIMULATOR REAL TIME TEST FNP-SIM-CTP-1.8 OPERATING LIMITS EXCEEDED TEST FNP-SIM-CTP-1.9 OPERATOR CONDUCTED SURVEILLANCE TEST FNP-SIM-CTP-2.7 RODS FAIL TO MOVE IN AUTO FNP-SIM-CTP-2.8 RODS FAIL TO MOVE IN MANUAL FNP-SIM-CTP-2.9 CONTROL ROD FAILURE-STUCK ROD FNP-SIM-CTP-2.10 CONTROL ROD FAILURE-DROPPED ROD FNP-SIM-CTP-2.24 SGFP TRIP FNP-SIM-CTP-2.25 SGFP FAILURE TO AUTO TRIP FNP-SIM-CTP-2.26 SGFP TURBINE SPEED CONTROLLER FAILURE FNP-SIM-CTP-2.28 STEAM GENERATOR LEVEL CHANNEL FAILURE FNP-SIM-CTP-2.29 FEED LINE BREAK OUTSIDE CONTAINMENT DOWNSTREAM OF STOP CHECK VALVE FNP-SIM-CTP-2.30 FEED LINE BREAK INSIDE CONTAINMENT FNP-SIM-CTP-2.33 STEAM LINE FLOW TRANSMITTER FAILURE FNP-SIM-CTP-2.36 SOURCE RANGE CHANNEL FAILURE FNP-SIM-CTP-2.3601 FAILURE OF SOURCE RANGE CHANNEL HIGH VOLTAGE TO DISCONNECT FNP-SIM-CTP-2.3602 SOURCE RANGE CHANNEL HIGH VOLTAGE FAILURE FNP-SIM-CTP-2.3603 SOURCE RANGE BLOWN FUSE FNP-SIM-CTP-2.37 INTERMEDIATE RANGE CHANNEL FAILURE FNP-SIM-CTP-2.3701 I.R.
CHANNEL GAMMA COMPENSATION FAILURE FNP-SIM-CTP-2.3702 INTERMEDIATE RANGE BLOWN FUSE FNP-SIM-CTP-2.41 SAFEGUARD ACTUATION AND CTMT ISO FAILURE FNP-SIM-CTP-2.48 REACTOR COOLANT SYSTEM LEAK FNP-SIM-CTP-2.51 REACTOR COOLANT PUMP TRIP FNP-SIM-CTP-3.1 MANUAL REACTOR TRIP FNP-SIM-CTP-3.2 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS FNP-SIM-CTP-3.3 SIMULTANEOUS CLOSURE OF MAIN STEAM ISO VALVES FNP-SIM-CTP-3.4 SIMULTANEOUS TRIP OF REACTOR COOLANT PUMPS FNP-SIM-CTP-3.5 TRIP OF ANY SINGLE REACTOR COOLANT PUMP FNP-SIM-CTP-3.6 MAIN TURBINE TRIP (LESS THAN P-9 SETPOINT)
FNP-SIM-CTP-3.7 MAX RATE POWER RAMP (100% TO 75% TO 100%)
FNP-SIM-CTP-3.8 MAX SIZE RCS RUPTURE WITH LOSP FNP-SIM-CTP-3.9 MAX SIZE NON-ISOLABLE MAIN STEAM LINE RUPTURE FNP-SIM-CTP-3.10 SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATED CONDITION USING PRESSURIZER RELIEF OF SAFETY VALVE STUCK OPEN FNP-SIM-CTP-4.0 ONE HOUR STEADY STATE OPERATIONS TEST FNP-SIM-CTP-4.1 STEADY STATE COMPARISON TO REFERENCE PLANT FNP-SIM-CTP-4.2 STEADY STATE THERMAL CALORIMETRIC COMPARISON
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