ML17348A801

Simulator Initial Certification, Vol 1

ML17348A801
Person / Time
Site:	Turkey Point
Issue date:	01/02/1991
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17348A800	List: L-90-461, Forwards Turkey Point Simulator Initial Certification, Vol 1 & Turkey Point Simulator Initial Certification, Vol 2 ML17348A801 ML17348A802
References
NUDOCS 9101080142
Download: ML17348A801 (177)

Text

FLORIDA POWER L LIGHTCOMPANY TURKEY POINT SIMULATOR INITIALCERTIFICATION VOLUME I SECTION I TURKEY POINT UNIT 3 SECTION II TURKEY POINT UNIT 4

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NRC FORM 474 (1401 10 CFA 55.45(b),

56.4 sne ESCA U.S. NUCLEAR REGULATORYCOMMISSION SIMULATION FACILITY CERTIFICATION APPAOVE 0 SY 0 MS: NO. 31500138 EXPIRES.'0042 ESTIMATED SUAOEN PER

RESPONSE

TO COMPLY WITH THIS INFORMATION COLLECTION AEQUESTI 120 HRS. FORWARO COMMENTS REGARDING BURDEN ESTIMATE TO THE INFOR.

MATION ANO RECOAOS MANAGEMENT BRANCH (MN88 7714),

U.S.

NUCLEAA REGULATORY COMMISSION, WASHINGTON, OC 20555, ANO TO THE PAPERWORK AEOUCTION PROJECT (3150 0138), OFFICE OF MANAGEMENT ANO BUDGET, WASHINGTON, OC 20503.

INSTRUCTIONS. This form is to be tiled for Initialcert(fiation, reccrtilicat ion (ilrequired), and for any change to a simulation facilityperformance testing plan made atter initial submittal of such a plan. Provide the following information, and check the appropriate box to indicate reason for submittal.

TURKEY POINT NUCLEAR GENERATING UNIT NUMBER 3 LICENSEE FLORIDA POl"ER AND LIGHT COMPANY DOCKET NUMBER EO. 250 DATE 12/31/90 This is to artifythat:

1.

The above named facility licensee is using 4 simulation facilityconsisting solely of a plant referenced simulator that meets the requirements of 10 CFR 55.45.

2.

Documentation is available for NRC review in accordance with 10 CFR 55.45(bi.

3.

This simulation facilitymeets the guidance contained in ANsl/ANs3,5, $955, as endorsed by NRc Regulatory Guide 1.149.

Ifthere are any exceptions to the certification of this item, check here I

1 and describe fullyon additional pages as necessary.

NAME(or orheridenr/frbarion/ AND LOCATIONOF SIMULATIONFACILITY TURKEY POINT SIMULATOR 92 MILES EAST OF FLORIDA CITY ON PALM DRIVE FLORIDA CITY, FI ORIDA 33034 SIMULATIONFACILITYPERFORMANCE TEST ABSTRACTS ATTACHED. (Forperfonnance tests conducted in the period ending with the date ofthis carr//ication/

DESCRIPTION OF PERFORMANCE TESTING COMPLETED (Arrach additions/ page(s/ as necessary, and idenrify the hem descr/prion being conrlnuedl SEE ATTACHED DOCUMENT y

SIMULATIONFACILITYPERFORMANCE TESTING SCHEDULE ATTACHED. (For the conduct ofapproximarefy 2575of pcrfonnance rerrs pcr yesr for rhe four yasr per/od commencing with rhe dare of this cert/iieet/on./

DEscR(pTIDN OF pERFDRMANGE TESTING TO BE CONDUCTEO. (Attach addi(/onaf pape(sias necessary, andidenrifythe /rem descrfprion beinpoonrlnued/

SEE ATTACHED DOCUMENT PERFORMANCE TESTING PLAN CHANGE. (For any modlfkarlon to a perfonnance rearing plan submirred on a previous certffkation/

DESCRIPT(ON OF PERFORMANCE TESTING PLAN CHANGE (A(tech edd/rlonel page(s) as necessary, and identify theirem darer/pr/on being cont/nued/

INITIALCERTIFICATION NOT APPLICABLE R EGERTIFIcAT(ON (Describe correct/reactions ra/ren, attach results ofcomp/ared perfbrrnence tearing /n ecconfence wirh f(7 cFR (I ss gs(b/(S/(v/.

Attach add/fiona/ page(s/as necessary, and /dent(fythe irem description belnp continued /

'INITIALCERTIFICATION NOT APPLICABLE Any faire statement or omission In this document, Including attachments, may be subject to c(viland criminal canc((onL I cert(fy under penalty of perjury that the Information In thh document and attachments is true and correct.

SIGNATURE AUTHORIZED REPRESENTATNE TITLE VICE PRESIDENT TURKEY POII'lT DATE In accordance with 10 CFR (I 55$, Commun(cations, this form shell be submitted to the NRC as follows:

BY MAILADDRESSED TO:

Dhector, OfRoeof Nsadeer Reactor Regu(ation BYDELIVERYIN PERSON One Wh(te Flint North Ug. Nusgeer Regulatory Commlssksn TO THE NRC OFFICE AT:

11555 Rudra(Ae Pike Wargdngon, DC 26%5 RochvIBa, IN)

NAC FORM 474 (140)

FLORIDA POWER ANDLIGHTCOMPANY TURKEYPOINT UNIT3 INlllALSIMULATORCERTIFICA17ON REPORT TABLEOF CON7ENTS VOLUMEI Infroductlon General Information Excepfions to ANSI/ANS3.5 Standard 1.0 Simulator Informafion

1. 7 General Informafion 1.2 Confrol Room Informafion 1.2. 7 Physical Arrangement 1.2.2 Panels/Equipmenf 1.2.3 Simulated Sysfems 7.2.4 Control Room Environmenf 1.3 Insfructor Interface 1.3.1 Initial Condifions 1.3.2 Malfunctions 7.3.3 Local Operafor Controls 7.3 4 Insfrucfor Sfafion Feafures 1 4 Operafing Procedures 1.5 Changes Since Last Report 2.0 Simulafor Design Dafa Base 3.0 Simulafor Tests 3.1 Certification Tesf Development and Format 3.2 Fufure Year Test Plans 4.0 Simulator Discrepancy and Upgrade Program 4.1 Simulafor Configurafion Management Sysfem 4.2 Simulafor Discrepancy Reporting Instructions 4.3 Planf Design Change Tracking 4.3 Simulafor Work Order Sfafus Appendix A: Qualifications of fhe Certificafion Team, SCRB, and SCRB Alfernates

Lisf of Figures 0-1 Simulator Configuration Review Board 0-2 InifialCertification Organization 1-1 Planf and Simulafor Confro/ Room Floor Plan 1-2 Developmenf of Simulator Initial Conditions 3-1 Certificafion Tesf Process 3-2 Simulafor Test Data Documenfafion System 4-1 Simulator Configurafion Management Information Flow Diagram 4-2 Outsfanding Discrepancies by Priority 4-3 Outstanding PCM Updates by Priorify 4-4 Assignment of Discrepancy Operational Priority List of Tables 0-1 1-1 1-2 1-3 3-1 3-2 3-3 3-4 3-5 3-6 3-7 3-8 3-9 ANSI/ANS 3.5 Cross-Reference Summary of InifialConditions 1-15 Summary of Malfunctions Insfrucfor Stations Main Keypad Funcfions Turkey Point Certificatio Tesf MafrixProfile ANSI/ANS 3.5 Certificatio Test Mafrix Certification Test Mafrix Annual Tesfs 1991 Test Plan 1992 Tesf Plan 1993 Test Plan 1994 Test Plan Tesf Accepfance Criferia

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VOLUMEII - TEST ABSTRACTS lntroducfion 1.0 Compufer Real Time Test (R1T) 2.0 Steady Stafe Tesfs (SST) 3.0 Normal Planf Evolufions (NPE) 4.0 Surveillances (SUR) 5.0 Malfunctions 5.1 Containment (MCN) 5.2 Common Services (MCS) 5.3'hemical & Volume Control Sysfem (MCV) 5A Feedwater (MFA 5.5 Generator & Grid (MGG) 5.6 Main Power Disfribufion (MMP) 5.7 Reactor Coolanf Sysfem (MRC) 5.8 Reacfor (MR)()

5.9 Sfeam Generator & Main Sfeam (MSG)

5. 10 Sfandby Power &Synchronization (MSP) 5.11 Safety Systems (MSS)

5. 12 Turbine (MTU)

Appendix A - Sample Complefe Cerfi%cation Tesf Procedure Lisf of Tables 0-1 Summary of Cerfi%cation Testing Discrepancies

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT INTRODUC17ON GENERAL INFORMATION The enclosed information supporting the Certification of the Turkey Point Unif 3 Simulatoris an absfracf ofthe information developed to demonsfrafe compliance wifh ANSI/ANS 3.5 and Regulafory Guide

1. 149. Backup references are included in each Secfion.

The Cerfilicafion submiftal is organized info two volumes.

Volume I confains fhe Cerfificafion submiffals for Turkey Poinf Unifs 3 and 4. The Unit 3 section of Volume I is organized in a manner similar to ANSI/ANS 3.5 Appendix A, Guide for Documenfing Simulator Performance.

The Unit4 secfion ofVolume Ireferences the Unif3 Cerff%cafion submiffal and analyzes fhe differences between fhe two unifs.

Volume II confains the absfracfs of fhe Simulator Cerfi%cation Tesfs which were performed to verifythaf the Turkey Point Simulator operatesin accordance wifhthe above references.

Table 0-1 provides a cross-reference befween ANSI/ANS3.5 secfions and fhe sections of this documenf.

This submiffal willreference the Simulator Configuration Review Board (SCRB). The Turkey Poinf SCRB was esfablished by adminisfrafive procedure O-ADM-305, Simulator Configuration Management (Reference 0-1).

The SCRB provides overall confrol and direcfion wifh respect to changes to fhe Simulator.

If also provided overall review and approval ofthe Cerfilicafion tesf program and fesf results.

The membership on fhe SCRB was selecfed per the guidelines ofthe Instifute ofNuclear Power Operations, "Simulafor Configuration Managemenf Sysfem," INPO 87-016, Augusf 1987 (Reference 0-2).

The SCRB comprises individuals with significant experience in Turkey Point operafions, simulator engineering, and simulator fraining.

The current SCRB includes the Plant Operations Supervisor, Simulator Engineering Coordinafor, and Simulafor License Training Coordinafor. Afleast one alfernafe wifhequivalent capabilifyis provided foreach SCRB member. Figure 0-1 identi%es the line organizafion responsible forthe Simulafor, the relationship offhe SCRB to that organizafion, and the present composition of fhe SCRB.

The preparafion of certilicafion test procedures, performance of the tests, and documenfafion of the resulfs were performed by an independent, dedicafed certificafion feam.

Each fesf procedure was approved by the Simulator Page 0.-1

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Engineering Coordinafor.

Addifional staf from the planf were used to support specific fesfs.

For example, current licensed operators were used in many ofthe normal startup and shutdown evolufions, and reacfor engineering staff were used during fhe staifup physics fesfs. Figure D-2idenfifies this secfion ofthe organization and the composifion of the Cerfi%cation feam.

Fufure tesfing will be the responsibi%ty of permanent Turkey Poinf Simulafor engineering staff. Appendix A ofthe Unif3 submiffal confains abstracts ofthe resumes forfhe Certificafion team, the SCRB, and fhe SCRB alfernates.

EXCEPTIONS TO ANSI ANS 3.5 STANDARD The Turkey Point Slmulafor meefs all of the requirements of ANSI/ANS 3.5.

The followingexceptions to ANSI/ANS3.5 are faken.

NON-APPLICABLEREQUIREMENTS The ifems in this section are identified as exceptions based on their applicabilify to this faci%fy.

ANSI ANS 3.5 Secfion 3.1.1 7

" 3.1 Simulator Capabilifies, 3.1.1 Normal Plant Evolufions, (7) Sfartup, shutdown, and power operations with less than fullreacfor coolant flow" Technical Specifications afthe Turkey Poinf Planf preclude normal power operafion unless all three reacfor coolanf pumps are operating.

Therefore, none of fhe simulator certification festsinvolving power operafion were performed wifhpartial RCP operating conditions.

Transienf fests involved tripping one, two, and three RC pumps and the fill and venf, heatup and cooldown operations fests were Performed with partial flow operafions in accordance wifh the applicable planf procedures.

There are no limifafionsin the Turkey Poinf Simulator regarding the number of RC pumps thaf can be operating or disabled at any plant operafing mode or during any malfunction.

ANSI ANS3.5 Secfion 3.1.2 12 "3.1 Simulator Capabilities, 3.1.2 Plant Malfunctions, (12) Confrol rod failure including sfuck rods, uncoupled rods, driffing rods, rod drops, and misaligned rods" Page 0.-2

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT DriffingRod malfunctions are not relevanf to the Turkey Poinf Confrol Rod Drive design. Allthe other listed rod malfunctions were included in the tesf program.

ANSI ANS3.5 Secfion 3. 1.2 25 "3.1 Simulafor Capabilifies, 3. 1.2 Plant Malfunctions, (25) Reactor pressure confrolsystem failureincluding turbine bypass failure (BWR)"

This item is speci%cally relafed to BWRs.

ANSI ANS 3.5 A endix B Secfion B2.1 2 "B2 PWR Simulator Operabi%fy Tesf, B2.1 Steady Sfafe Performance, (2) Secondary Planf, Sfeam Generafor Secondary side temperafure."

This femperafure is not monitored in Westinghouse vertical Sfeam Generators.

OTHER EXCEPTIONS The ifems in this section are Identi%ed as exceptions for reasons ofher fhan their applicabilify to this facilify. The specific reasons are Identified in the justification for each exception.

ANSI ANS 3.5 Section 4.1 3

" 4. Performance Criteria, 4.1 Steady Sfafe Operafion, (3) The simulafor computed values ofcrificalparamefers shall agree wifhin+2%of the reference plant parameters and shall not detracf from training."

The Turkey PolnfSimulator Sfeady Sfafe certi%cation tesfs used+2% ofthe reference insfrument loop range as the accepfance criteria forcriticalparameters and+ 10%

of the insfrumenf loop range as the accepfance criteria for non-critical parameters.

This criferia is based on the operator's abilify to observe such differences on the confrol room indicafors and realistically meefs the training requirements for paramefer accuracy.

This approach is consistenf wifh thaf of other facilities in the industry and was reviewed and approved by the SCRB.

For the acfual performance and analysis of the Sfeady Sfafe Tesfs, data was taken from planf control room logs and compared to the same log readings in the simulator.

To obtain the mafching sef of condi%ons, the simulator was operated

',using approved plant procedures unfilit was in fhe same condition as the planf.

The data from the two sets of logs was inpuf to a series of calculations which compared the difference befween the simulafor and plant readings to the 2%

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TURKEYPOINT UNIT3 INITIALSIMULATOR CERTIFICATION REPORT (10%) of the loop range criteria.

In addifion, instrumenf accuracies, where available, were taken into accounf by adding them to fhe computed values. All parameters were examined forerrors which could defracf from trainingin addifion to the 2% (10%) criferia. No errors were found which would detracf from training, however, if fhe simulafor was in error by more than the 2% (10%) criferia, a Discrepancy Report was wriffen.

ANSI ANS 3.5 Secfion 5.3 "5. Simulator Design Confrol, 5.3 Simulafor Modificafions.

The simulafor shall be modified as required wifhin 12 monfhs followingthe annual establishmenf ofthe simulafor updafe design data referenced in 5.2.

The following Planf Change/Modifications (PCM) have been identified as having simulator impact and have been completed in the planf formore than 12 months:

The systems affected by the followingPCM's are expecfed to be impacted by a major confrolroom re-configuration scheduled for 1991. The SCRB has deferred implementafion on the simulafor until the new configuration is finalized.

PCM 84-026, SWRN 8800276, Confrol Room Ventilation Emergency FilferSysfem Modi%cafion.

PCM 85-001, SWRN 8800405, Confrol Room DC LighfingModification.

PCM 88-587, SWRN 8900072, Temperature Confroller (TC-6548)

Manual Override.

Implemenfation of the following PCM is not yef complete due to delays encounfered in identification and procuremenf of the required hardware.

This change is scheduled fo be completed on the simulator in early 1991.

In fhe inferim, activities have been inifiated to implement a subsef of the funcfions associafed wifh fhis change, using currenflyinsfalled equipmenf.

PCM 87-3 10, SWRN 8800343, Emergency Response Dafa Acquisition and Display Upgrade.

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT ANSI ANS 3.5 A endix B Section B2.2 6 "B2 PWR Simulafor Operabilify Tesf, B2.2 Transienf Performance, (6) Main Turbine Trip (maximum power level which does nof result in immediate reacfor trip)"

At Turkey Poinf, the power level below which a turbine trip does nof resulf in a direcf reactor frip is l0%.

A turbine trip from l0% power level would be an extremely small transienf and would add very liffleto fhe simulator certification process.

Therefore, this fesf was run from a power leveljust below that for which rod control and sfeam dumps are designed fo provide a controlled sfabi%'zafion for the plant.

This was done by disabling the reactor trip by turbine trip.

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT TABLE0-1 ANSI/ANS3.5 CROSS-REFERENCE ANSI ANS 3.5 SECTION REPORT SECTION General Requirements 1.2.3 Table 3-9 3.1 Simulafor Capabilities Table 3-9 3.1. 7 Normal Planf Evolutions 7.2.2 1.2.3 Table 3-2 Table 3-9 3.7.2 Planf Malfuncfions 1.3.2 7.4 Table 1-2 Table 3-1 Table 3-2 Table 3-9 3.2.1 Degree of Panel Simulation 1.2. 7 1.2.2 3.2.2 Confrol on Panels 7.2.1 1.2.2 3.2.3 Confrol Room Environment 7.2.4 3.3.1 Systems Confrolled from the Confrol Room 1.2.3 3.3.2 Sysfems Operation of Funcfions Confrolled from Oufside of fhe Confrol Room 1.2.3 1.3.3 Page 0.-6

ANSI ANS 3.5 SECTION TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT REPORT SECTION 3.4.1 Initial Conditions 1.3.1 3.4.2 Malfunctions 1.3.2 1.3A Table 1-2 Table 3-9 3.4.3 Other Confrol Features 3.4.4 Instrucfor Interface 1.3.4 1.3.3 1.3A 4.1 Sfeady State Operafion Table 3-9 4.2 Transient Operation Table 3-9 4.3 Simulafor Operafing Limits 1.3A 4.4 Moniforing Capabilities 3.1 5.1 Simulafor Design Data 2.0 4.0 5.2 Simulafor Updafe Design Data 2.0 4.0 5.3 Simulafor Modi%cations 2.0 4.0 5.4.1 Simulator Performance Tesfing 3.1 5.4.2 Simulator Operability Tesfing 3.2 A1.1 General Page 0.-7

ANSI ANS 3.5 SECTION TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT REPORT SECTION A1.2 Confrol Room 7.2 A1.3 Instrucfor Interface 7.3 A1.4 Operafing Procedures for Reference Plant 7.4 A1.5 Changes Since Lasf Report 1.5 A2 Simulator Design Data 2.0 A3.7 Computer Real Time Test Table 3-1 Volume II, section 7

A3.2 Steady State and Normal Operations Tests Table 3-1 Volume II, section 2 Volume II, section 3 Volume II, section 4 A3.3 Transient Tesfs Table 3-1 Volume II, section 5 A3.4 Malfunction Tests Table 3-1 Volume II, secfion 5 A4 Simulator Discrepancy Resolufion and Upgrade Program 4.0 B2.1 Sfeady Sfafe Performance Table 3-1 Volume II, secfion 2 B2.2 Transient Performance Table 3-1 Volume II, secfion 5 Page 0.-8

TAFFY PO/% giVIT9 wmxz, sruuzaroe oFarrscArronr a+oar F/8'VPF 0- 1 SIMULATOR CONFIGURATION REVIEN BOARD VICE PRESIDENT TURKEY POINT PLANT MANAGER OPERATIONS SU P ERINTENDENT TRAINING SU P ERINTENDENT OPERATIONS SUPERVISOR OPERATIONS TRNG SUPERVISOR LICENSEO OPERATIONS STAFF PRI RICHARD G. MENDE ALT JOHN E. CROCKFORD ALT HUGH H. JOHNSON S IMULATOR ENGINEERING STAFF PRI ROBERT E. DODSON II ALT KAY A. LOVELL SI MULATQR INSTRUCTOR STAFF PRI LEO GOEBEL ALT CHARLES A. CCKER SI MULATOR CON FIGURATION REVIEW BOARD REV 12/07/90 PA6F 0.-9

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TVRKFYPO/!VT ghee/T g IIVITIAIS!)VV'OR CFRTIF/CATIOIVRFPORT F7GC/RF 0-Z INITIAL CE RTIF ICATI0 N ORGANIZATION SI MULATOR ENGINEERING COORDINATOR PERMANENT ENGINEERING STAFF I

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ASSISTANCE INITIAL CERTIFI CATION TEAM CERT ENGINEER JAMES F. HARRISON CERT TEST TEAM ROBCRT J. GINSBCRG JERRY W. JOHNSON KENNETH D. WHITE OTHER ORGANIZATIONS (OPERATIONS) RX ENGR, ETC.)

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rr rr ASSISTANCE INITIAL CE RTIFIGATION SUBMITTAL INITIALSUBMITTAL WAS DEVELOPED BY A DEDICATED CERTIFICATION TcAM FUTURE CERTIFICATION REAUIREMENTS WILL St THE RESPONSIBILITY OF THE PERMANENT ENGINEERING STAFF REV 10/26/90 PAGE 0-10

REFERENCES TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT 0-1 Turkey Point Adminisfrative Procedure O-ADM-305, Simulafor Configurafion Managemenf, November 1, 1990.

0-2 Insfitute of Nuclear Power Operations, "Simulafor Configurafion Management Sysfem," INPO 87-016, Augusf 1987.

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPOR1'IMULATOR

/NFORMATION GENERAL INFORMATION Owner: Florida Power and Light Co. (FPV, Turkey Point Plant.

~Oerator:

The conduct ot training programs is the responsibility of the Nuclear Training Departmenf's Training Program Coordinafors and their staff.

Simulator maintenance is the responsibi%fy of fhe Training Deparfmenf's Simulafor Engineering Coordinafor and his staff.

Manufacturer: CAE Electronics of Montreal, Quebec.

Reference Plant e Rafin: Turkey Poinf Unit3, is a three loop Westinghouse PWR licensed for 2200 Mwt.

The planf began commercial operafion in 1972 under Dockef 50-250 License DPR-31.

The NSSS and Turbogenerafor were supplied by Westinghouse, wifh Bechfe/ as the A/E.

Dafe Available for Trainin: Training ofsfudents began in May 19BB.

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CONTROL ROOM INFORMATION PHYSICAL ARRANGEMEN1'LOOR PLAN COMPARISON The Simulafor control room panels are orienfed and arranged to duplicafe the Planf control room panels.

Figure 1-1, Planf and Simulafor Confro/Room Floor Plan, provides a top view wifh dimensions of the Simulafor and Planf confrol room panels.

Small dimensional differences befween the Simulafor and Plant control rooms exisf due to the building arrangement and the omission of Unit 4 in the Simulator control room.

These differences in room dimensions cause slighf variances in panel layout distances.

The maximum deviafion in layout dimensions in the confro/ room surveillance area is 0.5 inches.

The fypical deviafion is s/gnlficanfly less. (References 1-1 8r 1-2)

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT The heavy metal outer enfry door is not included in fhe Simulator confrol room, however the inner entry door is duplicafed.

The Unif 4 side of fhe Planf control room is simulafed by fhe Insertion of a one-way-glass wall behind which resides the insfructor facility.

All main control room panels within the surveillance area are functionally simulafed.

Panels outside the surveillance area are functionally simulafed where operator lnferaction is required.

The followingpanels are included:

Flux Mapping Panels, Loose Parts MoniforingSysfem, Rod Position Cabinef, Rod Deviafion and AxialFlux Monitoring System, Containmenf Isolafion Cabinefs, Protecfion Rack Bisfable Trip Swifches, associated lights, and door alarm swifches, (remainder ofprofection racks are cosmetic)

Safeguards Logic Test Racks, Rod Disconnecf Panel, Spare Annunciator Power Supply Swifch Panel, Page Emergency Power Supply Swifch, Reacfivity Compufer, Remofe Llghfing Confro! Panels, Control Room Area Radiation Moniforlocal readout, AllConfrol Racks are cosmefically simulated.

The verfical panel's common section locafed above the opening in the vertical panels befween Units 3 and 4 is functionally simulated along wifh the sysfem and Quartz clocks.

A small portion of the Unif 4 vertical panel to the right of this openingis simulafed.

This parfialpanel houses the "B"Emergency Diesel waff-hour meter and common confainment level recorder.

The barometer and vacuum indicator on the end of the verfical panel are functionally simulafed with digital indicators.

Withinfhe Simulator, the office area designafedin the planf forthe ShiffTechnicians is used for replicafion of some equipment not locafed in the reference planf control room.

This equipmenf includes Reactor Coolant Pump Vibration insfrumenfafion, the Alternafe Shutdown Control Panel, and the Control Room Page 1.-2

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Ventilafion Confrols. In addi%'on, the Reactor Profecfion Test Panels are simulated within Miscellaneous Relay Racks.

The simulator confrol room includes the Shift Supervisor's office, Communications Booth, and the Wafch Engineer's office. The Simulator does notinclude the kitchen or restrooms locafed on Unif4 side of Pianf confrol room.

PANELS EQUIPMENT Simulafor control room panels were originallyfabricated to duplicate the existing Plant control room drawings as of Augusf 19B4.

Phofographs of all simulated control room equipmenf were taken at the planf in July 1990, in order fo establish the currenf stafus of the control room panels and equipment.

The planf confrol room photographs have been compared with the Simulator control room using Simulator Engineering Insfruction Number 9, Simulator Physical Fidelity Validation (Reference 1-3).

The resulfs ofthis review are documented In the Physical Fidelity Validafion Report (Reference 1-4). Discrepancies resulfing from the review were enfered into the Simulator Configuration Management Sysfem and Work Orders issued for their correcfion.

Those discrepancies not corrected as of the 474 form submiftal dafe are included in Figure 4-2.

All fidelity discrepancies will be correcfed In a timely manner in accordance wifh their assigned priorify.

SIMULATEDSYSTEMS The Turkey Poinf Planf Simulaforincludes the simuiafion ofallsysfems necessary for training in planf normal, off normal, and emergency modes of operafion.

The simulation accommodates allrelafed panel confrols, indicafions and alarms found in the confrol room.

Provisions for inferacfions between systems and sysfem remote functions are included.

The Simulafor Procurement Speci%cation (Reference 1-5) provided the initial definition ofthe scope ofsysfems to be simulafed. During simulafor developmenf, a color coded set of planf drawings was prepared thaf shows the scope of slmulafion foreach system.

(Reference 1-6). These drawings are archived with the Simulafor drawings.

The finaldefinition ofthe scope ofsimulafion for each sysfem Is included in the "Scope ofSimulafion" section ofeach model reporf. A compiefe lisfing of the model reporfs is included in Reference 1-7.

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT CONTROL ROOM ENVIRONMENT The Simulator environment comprises five systems:

lighting, sound,

audio, telephone, and furnishings.

Each system and fhe differences between the Plant and Simulator confro/ rooms willbe brief/y discussed.

Soffware documenfation on these sysfems includes a complefe description of the simulafed scope.

LIGHTINGSYSTEM - Every effort has been made to exactly duplicafe the locafion and type oflighfs available within the confro/ room surveillance area.

Replicafion ofone row of fluorescent /ighfing is nof currently possible in fhe Simulafor confro/

room due to the location ofventilation ductwork.

The missing row oflighfingdoes nof have any visible impacf on the lighting levels in fhe Simulafor surveillance area.

In addition lighfinginthe confro/ and profecfion rack areas behind the main confro/panels Is fluorescenfin the Simulafor control room andincandescentin the planf confro/ room.

The Simulator lighfingsystem is programmed to swap normal 1luorescenf lighting to emergency incandescenf lighting upon simulafed loss of volfage to confro/ room lighfingbusses.

The simulator also duplicafes the dimming ofcontrol room fluorescent lightingduring voltage transienfs on the lighfing busses, such as during fhe startup oflarge mofors.

SOUND SYSTEM - The Simulator sound sysfem consisfs ofreplication ofthe Source Range Audio Counf Rafe and unique sfeam sounds for operating and accidenf environments.

Each sound is driven by ifs inifiating model soffware with the capability to disable individual sounds or the enfire sound system from the insfrucfor faci%fy.

Simulafed sfeam sounds include sfeam line break, moisfure separator/reheater relief lifting, main sfeam safety valves lifting, and operafion of atmospheric steam dump valves.

Sound replicafion of sfep counters is not necessary since the mechanical step counfers utilized in the Simulafor are idenfical fo those used ln the Plant control room.

ALARMSYSTEM - The alarm sysfem consists ofthe sife evacuation alarm and the fire alarm. Each alarm is activated fromits respective push buffon located on the confrol room operafors desk.

The page sysfem alarm power switch is also functionally simulated.

Either or both of the alarms may be disabled from the insfructor facilify.

AUDIO SYSTEM - The audio sysfem consists of three componenfs: the Gaifronics Page l.-4

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT page sysfem, the Local Government Radio (GE Deskon I/), and the mainfenance jack/headset sysfem. Allofthese componenfs duplicate their planf control room counferparts in appearance and operafion.

The sysfem dispafcher radio is nof includedin fhe simulation sinceif is physically locafed on the Unit4 operafor desk.

TELEPHONE SYSTEM - Al/telephone communications available /n the control room at the Unif3 Operator's desk, Wafch Engineer's desk, Shiit Supervisor's desk, and Communicafions booth are funcfiona//y replicafed in the Simulafor confro/ room.

I Numbers dialed, other than those replicafed, ring in the insfrucfor facility.

The telephone system is capable ofproducing a dead line or a busy signal through local programming. Allcommunications from the simulafor confro/ room go to the instrucfor facilityand adequate indication is provided fo the instructor to role play the proper response.

FURNISHINGS - Major plant control room furnish/ngs such as desks, chairs, and carpeting have been duplicafed in the Simulator in both model and color.

The chairs in the plant confro/ room have been updated; therefore, presently the Simulator chairs are different.

The impact of the different chairs is minimal and following the planned re-configuration of the confro/ room, mafching furnishings willbe ordered.

Small furnishings such as sfafionary supplies, wasfe baskets, etc.,

are supplied, although no affempf has been made to duplicafe planf maferials.

The planf work order tracking system and the compuferized clearance sysfems located in the Wafch Engineer's office have not been replicafed.

INSTRUCTOR INTERFACE INITIALCONDITIONS The Turkey Point Simulafor has the sforage capacily for 60 initializafion condition

(/C) poinfs.

The number containing valid active conditions at any given time depends upon training needs.

IC points 1 through 15 are protected and are the basis for development ofall ofher points.

Poinfs 16 through 30 are also password profected and are under the confro/ ofthe Simulator Training Coordinafor.

These are generally poinfs creafed forspecific training scenarios which have confinuing use.

IC poinfs 31 fhrough 60 are unprotecfed and are used for speci%c training Page 1.-5

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT needs or forthe storage ofconditions for use in discrepancy clearance.

Table 7-7 presents a summary of the first 15 IC's.

AllIC points are created from a Full Power Steady State Middle of Life condition.

This plant condition is stored in Initial Condition

1. Initial Conditions 6 and 7 7 are fullpower steady state conditions for beginning of core life and end of core life.

These points are created using uti%ties to modifycore life dependent constants to produce the proper operating characteristics.

Each ofthe three hot fullpower conditions are maneuvered using plant operating procedures to produce four other operating conditions for each point in core life:

50% Power Steady State Hot Standby Cold Shutdown or Heatup/Cooldown Startup Conditions Figure 1-2 graphically presents the approach described above.

MALFUNCTIONS The Turkey Point Simulator is capable ofperforming all required Malfunctions for PWR's as specified in ANSI/ANS-3.5, 7985.

The malfunctions which the Simulatoris capable of producing are all based on speci%c component failures.

Specific failure mechanisms are represented for each component.

Hence, a particular failure to a specific component affects the interfacing components and systems in the same manner as it would in the plant.

In other words, there are no programmed "causes and effects."

This approach provides many thousands of failures and allows fora wide range ofcombinations offailures without the danger of violating pre-conceivedideas ofhow failures proceed.

Where the operator actions are a function ofthe degree ofseverity ofmalfunction (eg., loss ofcondenser vacuum, steam line break, loss ofcoolant, degraded feed water flow, etc.) the simulator has variable severity capability forthe malfunction ofsuch range to represent plant capabi%%es.

Malfunctioninsertion and termination are easily controlled through the instructor facility.

The simulator can be programmed for 130 active malfunctions/failures.

The introduction ofa malfunction does not alert the operator in any manner other than that which would occur in the Plant control room.

Page 1.-6

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Table 1-2illustrates the component specific failure approach and summarizes most ofthe major malfunctions. A complete list offailures that may be Imposed on the Simulator by the instructor is included in Reference 1-9.

The failures are also addressed in each applicable software model report.

Reference 1-7 provides a complete list ofthe simulator software model reports.

1.3.3 LOCAL OPERATOR CONTROLS Local Operator Actions (LOA's) are provided to allow the instructor to simulate actions which would be performed by field equipment operators in the Plant.

Simulation isincluded forsystems that are operated outside the control room, that provide input to the simulation models, or are necessary forthe performance ofthe plant normal and off-normal evolutions and plant malfunctions.

These actions are controlled from the Instructor Facility and the trainee interfaces with the instructor in the same manner as he would address the field operators within the Plant.

A number of LOA's are modelled via generic modules called "handlers."

Using handlers provides a standardized approach forallsimilar hardware.

The following listincludes the LOA's that are accessed via the Valve and Breaker handlers.

BREAKERS - LOCAL OPERATOR ACTIONS-Local close/trip mechanical, local close/norm/trip electrical, rackout, alarm reset, breaker position, manual spring charging, isolate switch (isolate/normal), selector switch (remote/local), transfer switch (normal/isolate).

VALVES-LOCAL OPERATOR ACTION-Local Handswitch/Local Pushbuffon Position BREAKER LOCAL OPERATOR ACTIONS - Local Close/Trip (Mechanical),

Rackout, Isolation Switch MANUALVALVEPOSITION Note: Not all Failures or LOA's are applicable to all breakers or valves.

The complete list of available LOA's is included in reference 1-9.

They are also addressed in each applicable software model report.

Reference 1-7 provides a complete list ofthe Simulator software model reports.

Page 1.-7

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT 1.3.4 INSTRUCTOR STATION FEATURES The instrucfor facility (I/F) controls, monitors, and presenfs Information abouf the sfafus of the simulafor, ifs simulafed planf sysfems and equipment.

The instrucfor sfafion has three displays (CRT's) with fouch sensifive screens and associated keyboards, three keypads, and communications equipment.

The complete descripfion of insfructor sfation features and ifs operafion can be found in Reference 1-B.

The touch screen CRT's are fhe primary vehicle the insfrucfor uses to monitor and confrol the simulafor training activi%es.

The CRT's display the following:

1) 2)

3) g)

5) 6)

Menus ofifems for selecfion via the touch screen.

Piping and insfrumenfafion diagrams (P&ID'S) ofsimulafed systems, showing status and key parameter values.

These include electrical wiring diagrams.

Plofs of up to eighf variables at a time.

Text or numerical data pages.

Bar chart diagrams.

Stylized insfrumenf pages.

These are diagrams of control panels which dynamicaliy display device stafus and provide the insfructor with access to main control panel Interface overrides, described later in this section.

Many of the features of the Simulafor are acfivafed from the keypads af the I/F.

Table 1-3 summarizes mosf of the insfructor stafion funcfions thaf are activated from these keypads.

There are three video cameras hanging from the overhead inside the Simulafor.

These provide inpuf to three television screens in the I/F.

The instrucfor has the abilify to move the cameras and zoom in for a closeup look af an individual insfrument or confrol. The cameras can provide an overview ofthe control room or an Individual instrumenf can be read when a camera is zoomed in. Also, a training session can be video recorded forplayback.

Page 1.-8

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Fore round Real Time Feafures.

The insfrucfor is responsible for the operafion and confrol of the simulafor during training sessionsin such a way thafifprovides adequate and complefe training for confrol room personnel.

The insfrucfor confrols the operafion of the training activifies via the following foreground features:

1) 2)

3) rf) 5)

6) 7)

8)

Inifialconditions, snapshots, and backfrack poinfs Performance moniforing, review and replay Failure acfivafion Task speed up or slow down Sound effects Parameter controller Main control panel interface overrides Simulator stafus alarms The insfrucfor may also develop a scenario thaf willdrive the training sessions with a pre-programmed sequence ofevenfs. Individual evenfs may be set to actuate by the instructor, at a given fimein the scenario, or be conditional on other evenfs or operator actions.

InifialCondifions Sna shots and Backfrack Points Inifial conditions (IC's) and backfrack poinfs are recordings of the simulafor common dafa base sfored on disc.

The instrucfor has the capabilify ofinitializing the simulator to any of60 ICpoints. Backtrack poinfs are made at presef intervals and can be recalled during a fraining session forreview or to re-perform a portion ofthe scenario.

An ICcan be saved af any time by utilizing the SNAP key on the instructor's keypad.

Performance Monitorin Review and Re la There are five feafures which allow the insfrucfor to review dafa which has been sfored during an exercise:

~Re ~(a allows fhe insfructor to play back a training exercise.

It sfarts from a backfrack point and willreplay allinpufs made from the time the poinf Page 1.-9

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT was stored until the present.

It is also possible to replay an earlier training session saved to tape.

It should be emphasized that this function records Inputs rather than outputs and is actually a re-run of the simulation.

This capability makes the function a valuable tool for testing the simulator in addition to its training uses.

Performance Review allows the instructor to enter data about a lesson (students'ames, date, etc.) and have this data, along with allinputs made during an exercise, stored on tape for later review or printed on the line printer.

ih i

t t

t i

dt hihh b

t d

on a Performance Review tape.

Monitored Parameters allows the user to monitor the values of up to twenty variables.

The Gra hic Recorder allows the instructor to create scenario specific ploffing menus.

There can be a total of twelve menus of four parameters each plotted against time.

Failure Activation Failures may be set up from any workstation ofthe I/Fbyselecting the P&IDdisplay with the target component and then selecting the failure from the menu for the particular device (e.g. valve, pump, etc.).

Failures can also be setup via a Scenario and be activated via the Control Parameters page.

TaskS eed U orSlow Down The simulation may be slowed or speeded ifnecessary for training on certain transients.

Speed up ls possible only for certain systems, and by a factor of up to 10 maximum.

The speedup factors cause the simulation to appear to be running faster than real time. Speedup factors are included for the followingsystems:

1)

Reactor system 2)

Boration and dilution Page l.-l0

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TURKEYPOINT UNIT3 IN/T/ALSIMULATORCERTIFICATION REPORT 3)

Condenser vacuum 4)

Conducfivify 5)

Main steam line metal temperature.

Time can also be slowed by any factor from 1 to 10.

In this case all simulafed sysfems are slowed.

Sound Effects Certa/n sounds thaf impart a degree of realism fo the confro/ room environmenf are available.

Any or all of these may be enabled or disabled by the insfructor.

Paramefer Confroller The paramefer controller permifs theinstrucfor fo manipulafe any parameferin the common data base.

The paramefer controller works via SINGLE and COMPOSITE EVENT enfries.

An EVENT consisfs of a parameter, a trigger and possibly a ramp time or delay time. A TRIGGER is the criteria for an EVENTto be /nserfed into the sysfem.

The insfrucfor can TRIGGER the evenf himself or have the sysfem doif via an expression.

A COMPOSITE is a single event which can consist of up to ten paramefer changes.

Each paramefer change in furn has ifs own TRIGGER.

Main Control Panel Interface Overrides The stylized insfrumenf feature provides CRT displays of all the confro/ and alarm panels.

A feature of the sfylized insfrument displays is thaf they permif the insfrucfor fo override the status of any panel componenf, alarm, swifch, mefer, fuse, efc., Iffhis is done, that componenf wil/show the value or stafus entered by the instructor ifit is an output device; i.e., one thaf supplies information to the operafors.

If the device overridden is an input device such as a switch or controller, the simulation willrespond asif the device werein the posi%on to which itis overridden.

Simulator Stafus Alarms The purpose of the simulator stafus monifor is to satisfy the requirements of ANSI/ANS3.5 Section 4.3 by defecfing when modules are operafing at or beyond Page 1.-11

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT physical or simulation limifs, and to signal the discrepancy to the instructor.

Paramefers were evaluafed and, where appropriafe, assigned a minimum and maximum value.

There are 153 active values fhaf when exceeded willcause an ouf of limits alarm.

1Vhen an out of limifs condifion is defecfed, an audible alarm is sounded in the Insfructor Faci%fy and the SOS buffon on the keypad willbe lif.

Pressing the keypad bufton willsilence the instrucfor faci%fy alarm and willdisplay the STATUS page.

Training may continue or be terminafed af the insfrucfor's discretion..

If the simulafor is nof operafing in real time, simulafion will stop and give the instrucfor an appropriafe abort message.

Certification tesfs were performed to demonstrafe that the simulafor willoperafein real time under conceivable loading condifions and fhat if would abort ifsimulation did not remain in real time.

The absfracfs of these

tesfs, RTT-001 and RTT-002, are in included Volume II of this submiffal.

Back round Features Scenario Develo menf This ufilifyallows the instrucfor fo develop a scenario for use in a future training session.

The instrucfor may inpuf some or all of the followinginformation:

1) 2)

3) 4)

5)

InifialCondifions, and modi%cafions on a label by label basis.

Speed-up or slow-down of Time.

Paramefer confroller.

Monifored parameters and performance indicafors.

Graphic recorder parameters.

Insfrucfor Dafa Book The Instructor Data Book (/DB) provides on-line access to documents and utilifies which willaid an instrucfor in preparing a lesson or scenario.

IDB willallow the insfrucfor to list files, prinf files and locafe variables required for scenarios.

1)

Disk file menus 2)

Longword/short word dictionary Page 1.-12

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT 3) g)

5) 6)

Absfracts menu Dafa base manager Scrafch pad Scenario abstracfs Of these features, the longword/shortword dictionary ls the primary feature used by Instructors in the developmenf of scenarios or lessons.

It will search for common dafa base labels given a

longword description (maximum 45 characters).

When prompted for a longword, enter parts of a longword or the whole longword and the dictionary willbe searched.

Ifany ofthe words entered appear in valid longwords, fhe associafed labels willbe returned.

The scenario absfracts option permits any abstract to be read but not modified.

1A OPERATING PROCEDURES Allcertificaflon tesfing and alltraining utilizes the actual currenf planf procedures.

A controlled sef of all normal, off-normal, and emergency procedures is mainfained in the simulafor confro! room.

1.5 CHANGES SINCE LASTREPORT This is the initial Simulafor certificatio report; therefore there are no changes fo report.

Page 1.-13

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT TABLE 1-1

SUMMARY

OF INITlALCONDI11ONS 1 - 15 IC CORE RCS REACTOR AGE TEMP POWER %

DEG F RCS XENON DESCRIPTION PRESSURE WORTH PSIG PCM 1

2 3

5 6

7 8

9 10 11 12 13 14 15 MOL 574 MOL 560 MOL 547 MOL 118 MOL 547 EOL 574 EOL 561 EOL 547 EOL 135 EOL 547 BOL 574 BOL 560 BOL 547 BOL 265 BOL 547 100 55 0

0 0

100 55 0

0 0

100 53 0

0 0

2235 2235 2235 322 2235 2235 2235 2235 365 2235 2235 2235 2235 377 2235

-28 18

-2248 0

0 0

-2929

-2446

-0 0

-4890

-2794

-2285 0

0 0

100% STEADYSTATE 50% STEADY STATE HOTSTANDBY COLD SHUTDOWN S/U, S/D RODS OUT 100% STEADYSTATE 50% STEADYSTATE HOT STANDBY COLD SHUTDOWN S/U, PEAK XENON 100% STEADYSTATE 50% STEADY STATE HOTSTANDBY HEATUP AND COOLDOWN S/U, POSITIVE MTC NOTE: Values forthe lisfed parameters may vary slighflyfrom the sfafed values when the IC's are re-established as a result of normal simulator maintenance.

Page 1.-14

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT TABLE 1-2

SUMMARY

OF MALFUNC11ONS SYSTEM LEAKS - Variable to Double Ended Guillofine RCS - Cold Legs, Hof Legs, Pump Sucfion Legs, RTD Bypass Loops CVCS - Charging and Lefdown Line - Multiple Locafions RHR - Sucfion and Discharge Line - Inside & Oufside Containmenf PRESSURIZER - Spray and Surge Line COMPONENT COOLING - Header Leaks, Heaf Exchanger Leaks MAINSTEAM - Main Sfeam Line - Inside Confainment Main Sfeam Line - Outside Confainmenf/Upsfream of MSIV Main Steam Line - Befween MSIV& NRV Main Steam Header Downsfream ofMSIV CONDENSER - Vacuum Leak and Tube Leak CONDENSATE - Pump Seal Leaks, Header Leak FEEDWATER - Header, Individual Lines Inside & Outside Containmenf AUXILIARYFEEDWATER - Pump Discharge, Each Header STEAM GENERATOR TUBE LEAKS - Variable Single to Multi-Tube ACCUMULATORCHECK VALVELEAKAGE-Variable to 100%

HEATEXCHANGER TUBE LEAKS - Variable to Multi-Tube RCP Thermal Barrier CVCS Non-Regenerative Heaf Exchanger CVCS Seal Water Heater Exchanger REACTOR COOLANTPUMP SEAL FAILURES - Variable fo 100%, Seals 1/2/3 TANKLEAKS - AllSimulated Tanks FUEL FAILURE/RCS ACTIVITYINCREASE - Variable FILTER BLOCKAGE-Variable to 100%, Filfers, Strainers, and Screens NUCLEAR INSTRUMENTATIONFAILURES Power Range - Detecfor Failures - High & Low Page 1.-15

Bistable Failures TURKEYPOINT UNIT3 INITIALSIMULATORCERT/FICATION REPORT Infermediate Range - Defecfor Failures - High &Low Incorrect Compensafion - Variable Over & Under Bisfable Failures Source Range - Detecfor Failures - High &Low Incorrecf Discrimination - Variable High &Low Excessive Noise Bisfable Failures TURBINE RUNBACKFAILURES - Fail to Actuate, Spurious Acfuation ROD STOP FAILURES - Fail to Acfuate, Spurious Actuation REACTOR TRIP RELAYFAILURES - Fail to Actuate, Spurious Actuafion PROTECTION RELAY-Fail to Actuate, Delayed or Spurious Acfuafion Sl RELAYFAILURES - Train A/Train B - Manual/Auto Fail to Acfuafe, Spurious Actuation REACTOR TRIP BREAKERS FAILURES - Fail Open, Fail Closed, Fail As-Is CONTROL ROD FAILURES - i'AllRods) Ejection, Slip to Any Posifion - Variable to Fully Inserted, Dropped

Rod, Dropped Group Mechanically Stuck, Blown Fuses, Sfafionary Gripper, Movable Gripper, LiftCoil, Uncoupled Rod, Rods Fail to Move or Confinuous Motion-Auto or Manual TURBINE FAILS TO TRIP GENERATOR VOLTAGEREGULATOR FAILURE DIESEL GENERATOR FAIL TO START - A and/or B ELECTRICAL BUS FAILURES - Ground Fault, Phase to Phase Shod - Variable Page l.-l6

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BREAKERS TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT GENERIC FAILURES - Fail Close, Fail Open, Fail As Is, Fail to Reset, Ground Fault (Load Side)

Note: Not all Failures are applicable to all breakers.

VALVES GENERIC FAILURES-Fail Open, Fail Closed, Fail As Is, Leak By, Mechanical Overload, Loss of Electric Power, Loss of Pneumatic

Power, Loss of Control or Conditioning Signal BREAKER FAILURES - Fail Closed, Fail Open, Fail As Is, Ground Fault Note: Not all Failures are applicable to all valves.

INSTRUMENTATIONGENERIC FAILURES INDICATOR-Power Loss, Signal Loss, Fail High, Fail Low, Fail As ls, Drift ALARMRELAY-Energized, De-energized, As Is B/S TRIP UNIT-Loss of Power, Loss ofSignal, Alarm Relay Fail Energized, De-energized, As ls DIFFERENTIAL COMP-Loss of Power, Loss ofSignal 1, 2, or Both, Alarm 0 1/ff2 Relay Fail Energized, De-energized, As Is, Spurious On SIGNAL CONDITIONER - Power Loss TRANSMITTERS - Loss of Power, Loss of Air, Fail High, Fail Low, Fail As Is, DriftCoefficient, Lag Coefficient SENSORS - Noise Amplitude, Fail Coefficient Multiplier, Offset in Output Page 1.-17

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT CONTROLLERS - Fail High, Low, or As Is, Loss of Power, Loss ofAir, Loss of Input Signal Note: Not all Failures are applicable to allinstrumentaf ion.

Page 1.-18

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT TABLE 1-3 INSTRUCTOR STATIONS MAINKEYPADFUNCllONS PUSHBUTTON FUNCllON F/R ANN DIS RESET STEP PG PRT COPY SNAP OVR CHX DEA SCE REC PWR MASTFAIL GLB CLR SYS MAT BAKTRK INISCE IC SEL TEST SOS Freeze/run.

This swifch resumes simulafion soff war, ififis pressed when the switch is LIT. IfLITno real fime simulafion soffware is acfive.

To disable/re-enable the audible alarms. Ifdepressed while the simulation is frozen, flashing annunciator windows willbe lif.

Causes the simulafor to be restored to the selecfed inifialcondifion.

When the operation is in sfep mode, pressing this key causes the simulafion soffware to cycle through one "sfep Page Forward/Page Backward Schemafics are displayed successively in numerical order oftheir occurrence.

In dafa book mode, fhese keys scroll through the documenf being displayed Print currenf confenfs ofthe CRTscreen at the line prinfer. The key remains lifand the CRT locked during fhe memory read cycle.

The lightgoes off when the CRT unlocks again.

Calls up the page which allows for the creation of initialconditions.

Override switch check. Permits the instrucfor fo accept any mispositioned device on the menu during swifch check.

Places all parameter controls which are not yef active on hold and sfops any controls fhaf are ramping or in time delays.

Power shutdown of all confrol room chart recorders.

Acfivates all armed failures.

Global clear of all acfive failures.

To call up fhe overall Master System Matrix.

Calls up a menu page thaf enables the insfructor fo: a) Sef backfrack time (interval between backfrack points), b) Inifialize the simulafor fo any backfrack poinf, c) Initiate replay from any backfrack point, d) Restore to the autosfore poinf.

Brings up a menu of scenarios on to the CRT. Instrucfor then makes a selection using the touch sensifive screen.

Brings up a summary of exisfing initial condifions.

The insfrucfor can resfore the simulator to any point.

Brings up a menu of simulation tests including: a)

Daily readiness b)

Simulator diagnostics Iflifdisplays the simulafor sysfem sfatus ofall ouf oftolerance paramefers.

Ifnot lif, there is nothing fo display. Must be depressed to silence IF alarm Page 1.-19

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT MON PAR CON PAR SIM CTRL REPLAY NOOP PERF REV SOUND STYL INST IDB DEV SCE TIME GRAF PERF IND ANNACK BYP CHX when out of bounds status alarm occurs.

Parameters being monitored are displayed on the screen.

The instructor can add and delete parameters being monitored to a maximum of 20.

Brings up the control parameter page onto the screen.

Parameter controller values may be entered.

Calls up the Level 0 simulator control menu. Functions include level 1

pages:

a) Armed failure summary, b) Environmental effects, c) Switch check messages, d) Local Operator Actions Index e) Plant performance factors, 0 Environmental factors, g) Timed failure, h) Part task, J) Function Keyboard Control.

Brings up a menu from which to start a replay.

Brings up a menu so that the instructor may disable one or more real time soffware modules.

Brings up a menu ofperformance review function so that the instructor can make a selection, using the touch sensitive screen.

Brings up the tableau allowing the instructor to enable/disable sound effects.

Stylized Instruments. Brings up the index, so that selected panel sections can be displayed on the touch sensitive screen.

The status ofalldevices, or the indicated reading of an instrument can be read, or overridden.

Sets CRT to Instructor Data Book mode. Instructor data book files are only open lfthis button Is lit.

Enter scenario development mode.

This enables the instructor to build scenarios for use in future training sessions.

Time control mode. Brings up a menu ofmodules that can be sped up by a factor of between 1 and 10.

The menu includes the possibility of the initiation of the step mode or of slowing the simulation down by a factor of between 1 and 10.

Brings up an index of control room ERDADS graphic displays.

One selection from the index is made by means ofthe touch sensitive screen.

Brings up a display of Performance indicators. Selections are made by means of the touch sensitive screen.

Acknowledges annunciators as iffrom the control room.

Bypasses Switch Check mode followingIC reset.

Page 1.-20

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P 56.0 S 55.5 P 39.5 S 40.0 22.0 S 23.2 TVR/CFYPO!AIT'iVIT8 liVIT/ALSIAfVCATOR CFRTII"ICATIOJI RFPORT P 39.2 F78URF 1-1 S 40.2 P 388 S 39.5 P 50.7 S 49.8 P 38.1 S 36.5 P 38.1 S 36.3 P 73.0 S 72.0 dP/ARPit!ASYidPA~d//AS///

1ItI III(IUIIIIIIIIillIIIIRIIISIIIIIIIIIIIIIIIIII(B(SNIIIIIIIJIIIIIIIIIIJIIII P 38.4 S 38.9 P 121.0 S 120.5 IIIIIIIIUIIIIIIINIIII4&

P 42.0 S 42.5 P 36.8 S 38.8 P 46.8 S 4C.7 P 45.7 S 45.8 P 33.8 S 55.8 P 50.6 S 51.0 P 43.6 S 43.5 P 43.2 S 43.5 P 41.0 S 41.0I P 37.4 S 39.2 P 46.4 S 46.7

%%b%%%%%RK%%Rb%%%%M%RK%

////~~i~i>$5lg SURVEILLANC E AREA WITHIN LINE IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII

'I ONE WAY GLASS PA8F

1. -Z1 AÃr'r'/A'g CONTROL ROOM FLOOR P LAN P = PlANT DIMENSION S

SIMUlATOR DIMENSION

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INITIAL CON DITION8 1

FPSS MOL CREATED AND VALIDATED USING PLANT DATA FIBULAE 1-Z rumaki pornrr user z liVmAC $(Alum TOR'ERjIFICA7IW RFPOR7 6

FPSS EOL 7

50'OL 8

HOT STANDBY EOL 2

50'OL 3

HOT STANDBY MOL FPSS BOL

't 2 50i BOL 13 HOT STANDBY BOL CORE LIFE COEFFICIENT CHANGES REDUCE POWER USING PLANT PROCEDURES AND HOLD UNTIL STEADY STATE IS ACHIEVED

.............. SHUTDOWN USING PLANT PROCEDURES AND HOLD UNTIL STEADY STATE IS ACHIEVED 9

COO LDOWN EOL 4

COOLDOWN MOL 14 COOLDOWN EOL COOLDOWN USING PLANT PROCEDURES AND HOLD UNTIL STEADY STATE IS ACHIEVED 10 STARTUP CONDITION EOL 5

STARTUP CONDITION MOL 15 STARTUP CONDITION BOL MANEUVER USING PLANT PROCEDURES UNTIL DESIRED CONDITION IS ACHIEVED REV 1002/'90 PALATE 1 -ZZ

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REFERENCES TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT 1-1 Planf and Simulator Control Room Floor Plan Drawing.

1-2 CAE Drawing UD139985.01.7.879, Turkey Poinf Control Room Complex Sife Layouf.

1-3 Simulator Physical Fidelity Validation, Simulafor Engineering Insfruction 9, Augusf 1, 1990.

1-4 1990 Simulafor Physical Fidelify Validation Report 1-5 Simulator Procurement Speci%cation.

I 1-6 Color Coded Simulator Scope Drawings.

1-7 Index of Process Model Documenfafion.

1-8 Insfructor Sfafion Manual.

1-9 Lisfing of Common Dafa Base Globa/ Partitions for Insfructor Confrols Including GLOBTA, GLOBTC, GLOBTF1, GLOBTF2, GLOBTF3, GLOBTF4, and GLOBTV.

Page 1.-23

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT 2.0 SIMULATORDESIGN DATA BASE Each module offhe Turkey Poinf Simulafor is fullydescribedin its associafed model repoit published by the simulafor vendor.

The model reporfs describe the mefhodology used to develop fhe individual module and explain the FORTRAN code used to implemenf this methodology.

These model reports are kept in fhe Turkey Point simulafor libraiy.

One complete sef is maintained as a library reference documenf and one sef is kept for a working reference.

The model reports list 1373 separate references from which Turkey Point specific technical Information was obfained.

These references include technical manuals, drawings, planf operafing dafa, and other relevanf material.

Over 90% of the references listed in fhe model reports are also available for use in fhe simulafor library or are obtainable from the FP&L documenf cenfers.

The remaining references are planf specific informafion provided to the vendor, which is described in the associafed model report.

Simulator Engineering Insfrucfion Number 10, Plant Design Change

Tracking, requires design changes to be downloaded once per quarter from the Florida Power & Light corporafe Information sysfem (Reference 2-1).

These changes are reviewed forimpacf on fhe Simulator and when a change impacfs the Simulafor, if is scheduled for implementation by the Simulafor Engineering Coordinator and entered info the Simulafor configuration managemenf sysfem.

The SCRB meefs af least once per quarter.

This board reviews all Simulafor modification packages, including those thaf have been authorized by the Slmulafor Engineering Coordinafor forimmediafe implementation (Reference 2-2).

REFERENCES 2-1 Planf Design Change Tracking, Simulafor Engineering lnstrucfion Number 10, Sepfember 12, 1990.

2-2 Simulafor Configuration Management, Turkey Point Planf Procedure O-ADM-305, Revision Date November 1, 1990.

Page 2.-1

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT 3.0 SIMULATORTESTS

3. I CERTIFICATION TEST DEVELOPMENTAND FORMAT Atthe initiation ofthe Simulafor Certi%cation project a reference test program was designed to meef the requiremenfs of ANSI/ANS 3.5.

This program was then approved bythe Simulafor Configuration Review Board (SCRB). The testing process involved the following elemenfs:

Preparafion of a tesf procedure, Ifs review and approval for use by the Simulator Engineering Coordinafor, Performance of the tesf by the test team and supporting staff from the plant, Ifnecessary, Evaluafion ofthe tesf results and preparation ofthe complefed tesf report, Review of the test report by the review team and ofher planf sfaff as necessary, and Presentafion ofthe test report fo the Simulafor Configuration Review Board for approval.

Figure 3-1 is a flowchad showing the process used in the Certification tesf process.

Simulafor Certification tesfing was conducfed by an experienced team of Individuals wifh diverse and complementary talenfs.

Sfaff from plant operations and engineering were utilized where particular special expertise or plant specific knowledge was desired to improve fhe experience base applied to the tesf.

Examples ofthese sifuafions include normal operafions, where current confrolroom operafors were used, and startup physics tests where planf reactor engineering staff were used.

This process applied the proper expertise to each tesf and provided a mulfi-level review culminating In a commiftee style review and approval by the SCRB.

For the purposes ofthe Certification effor, dafa recording and processing sysfems were developed forthe Simulafor, fhe plant ERDADS systems, and to Interface with RETRAN best esfimafe information. In order to compare fhe Simulator resulfs with plant data via the ERDADS archive sysfem and wifh RETRAN best esfimate Information, a PC based dafa processing and plofting sysfem was developed to allow the producfion of high qualify plofs on a volume basis.

(Reference 3-1).

Figure 3-2illustrates fhe various pafhs from the three inpufs to the fesf document.

Page 3.-1

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT The recording system on the Simulafor provides the facility to record up to 100 variables at a frequency as small as 0.2 seconds.

Up to four differen recording frequencies may be speci%ed over the durafion ofa tesf, such thaf the frequency may be changed consistenf wifh transient phenomena occurring.

Per ANSI/ANS-3.5, the Appendix B transienf dafa was recorded af a 0.4 second frequency.

The other tests were recorded at frequencies appropriafe for the transient.

The evaluation basis for the tesfs follows the followingorder ofpreference:

1) Plant Data

2) AnalyficalData (RETRAN)

3) Data from similar planf

4) Expert Examination The Evaluafion Team consisfed ofaf leasf one member ofthe Tesf Team and such additional expertise as was judged appropriate for the test.

In some cases no addifional expertise was necessary and the evaluafion was performed by the Test Team. The responsibility ofthe Evaluation Team was to review data collecfed from the fesf fo defermine accepfabilify of fhe test resulfs.

The test feam performed 106 tests.

Thirteen used plant data, eighf used analytical data (RETRAN), none used dafa from similar planfs, and eighfy two used expert examinafion.

Additionally, three of the tests had special quali%cations; RTT-001, Simulator Real Time Test - simulafor does nof abort on overruns, RTT-002, Simulafor Real Time Test Validation Tesf - slmulafor responds correctly to forced overruns, and SST-004, 100% Power 60 Minute NullTransient - sfable and parameters vary less than 2% from their original values.

RETRAN comparisons were used forsome of the major accidenfs not likelyto be encountered in planf operafions.

Planf data was used when available.

In the future, more tesfs willbe run using planf dafa as our PC based data processing system is used to analyze future planf transients.

Ofthe sixfynine tests using experf examination, fwenfy three were in the operafor conducted surveillance tesfing (SUR) category.

The SUR'S were conducfed by using confrolled planf procedures and in addifion to expert examination the procedure had to be able fo be performed on the slmuiafor and any acceptance criferia fhaf could be observed from the control room had to be met.

Three of the SUR's used plant data from a Page 3.-2

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIF/CATION REPORT past performance of the surveillance in fhe planf.

The norma/ planf evolufions (NPE's) were performed using confro/led procedures.

In three non-continuous tests the simulafor was taken from a parfial draindown condition to l00% power. In anofher two tesfs the planf was taken from fullpower to cold shutdown with the pressurizer water solid.

The sixth tesf was a trip and recovery back to fullrated power.

The SUR's were selecfed based upon the likelihoodthaf the surveillance would be used in training and how well the surveillance would tesf different aspecfs of the simulafor.

Alfhough nof all safety related surveillances were tested in the Ceiti%cafion program, all of them can be performed on the simulafor.

The malfunctions were selected to be inclusive of all ANSI/ANS3.5 requiremenfs and to further tesf all simulafor systems thoroughly.

As Table 3-2 iliusfrafes, requiremenfs for Certification tesfing were more than satisfied. Although in a few insfances ifrequires more than one Certification fesf to meet an ANSI/ANS3.5 tesf requiremenf, frequently the requiremenf was meet more than once.

Test Accepfance Criferia is established in accordance with the requirements of ANSI/ANS3.5, and is listed in Table 3-9.

The absfracts for each of the tesfs are in Volume IIof this submiffa/.

The absfracf comprises two pages thaf contain the followinginformation:

Description of the Test, Options Relevant to the Tesf, Inifial&Final Condifions, Basis for Evaluation, Discussion of the Tesfs Resulfs, Ouf of Bounds Conditions Encountered, Deficiencies Nofed During the Tesf, and Exceptions to ANS 3.5 One complete test procedure is also Included as Appendix Ain Volume II.

This test procedure is provided as an example of the test formaf and content.

When the fest documenfafion was complefe and had been reviewed by the certi%cation staff, each tesf was presenfed to the SCRB. The SCRB reviewed the fest Page 3.-3

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT results and disposed of each tesf in one of fhe followingcafegories:

l. Approved the test wifhoufdiscrepancies,

2. Approved fhe test wifhdiscrepancies, iffhey were judged not to be significant and nof to detracf from training,

3. Refurned the tesf with a requesf for additional information, or

4. Rejected the test and returned if for resolufion of software or hardware discrepancies.

A tesf had to be included in the firsf two cafegories, either approved wifh no discrepancies or approved with discrepancies thaf do not impacf fraining, before receiving final approval.

All questions were resolved and the SCRB members reached unanimify before a test was approved.

Meefing minufes were prepared for each SCRB meefing, and were reviewed and signed by the participants.

If should be nofed thaf some of fhe tesfs were approved by the SCRB wifhouf meeting all of the acceptance criteria in Table 3-9.

In fhese cases the SCRB concluded that the discrepancies were sufficiently understood and they did not have a signi%cant impacf on training.

These deficiencies were assigned the appropriafe priorify and entered info the Configuration Management Sysfem.

(Reference 3-2).

Table O-l in Volume IIcontains a mafrix of all Certification tests with deficiencies writfen against the test and the currenf sfafus of those deficiencies.

Signafures on each tesf report are as follows:

Approved for Use by the Simulafor Engineering Coordinafor Performed by fhe Test Team Evaluated by the Evaluafion Team Approved by the Simulafor Configurafion Review Board Table 3-1 presents a profile ofthe Turkey Poinf certification tesf program bygeneral type oftesf. Table 3-2 provides a cross-reference between each ANSI/ANS3.5 tesf requirement and the associafed Turkey Point Certification test(s).

Table 3.3 provides a similar Cerfi%cafion Tesf Mafrixin tesf Identification order. This table also includes the evaluafion basis for each tesf.

3.2 FUTURE YEAR TEST PLANS Per the requirements of Regulatory Guide

1. i@9, the Simulator Ceiti%cation test Page 3.-4

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT program willbe conductedin its entirety on a fouryear cycle. Allofthe ANSI/ANS 3.5 Appendix B tests will be performed annually.

Approximately 25% of the remaining tests in the Certification program willbe performed each year.

Table 3-4 presents the ANSI/ANS3.5 tests that willbe performed annually.

Tables 3-5 through 3-8 present the preliminary test plan forthe next four years.

The tests planned each year represent a cross section of the various types of tests.

In addition, the firstyear testsinclude several that were selected specifically because of planned model enhancements and anticipated Simulator changes for plant modifications.

This type ofsubstitution/prioritization can be expected to occurin the future.

Furthermore, additions of tests to meet new needs and requirements, or the availability of additional plant data from the ERDADS system can also be expected.

Some tests may also be deleted ifthey prove not to be valuable in exercising the Simulator processes or verifying training capabilities.

All changes to the annual test program will be approved by the Simulator Configuration Review Board before being submiffed to the Nuclear Regulatory Commission forifs approval.

Page 3.-5

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT TABLE3-1 TURKEYPOINT CER77FICA77ON TEST MATRIXPROFILE CATEGORY NUMBER OF TESTS COMPUTER REAL TIME TEST (RTT)

STEADYSTATE TESTS (SST)

NORMALPLANTEVOLUTIONS (NPE)

OPERATOR CONDUCTED SURVEILLANCE TESTING (SUR) 26 SUBTOTAL PLANTMALFUNCTIONS(MII)

CONTAINMENT(MCN)

COMMON SERVICES (MCS)

CHEMICAL& VOLUMECONTROL SYSTEM (MCV)

FEEDWATER (MFW)

GENERATOR & GRID (MGG)

MAINPOWER DISTRIBUTION (MMP)

REACTOR COOLANTSYSTEM (MRC)

REACTOR (MRX)

STEAM GENERATOR &MAINSTEAM (MSG)

STANDBYPOWER &SYNCHRONIZATION(MSP)

SAFETY SYSTEMS (MSS)

TURBINE (MTU)

SUBTOTAL 10 6B TOTAL Page 3.-6

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT ANSI ANS 3.5 TEST TABLE 3-2 ANSI/ANS 3.5 CERTIFICATION TEST MATRIX CERTIFICATION TEST 3.1.1(1) 3.1.1(2)

3. 1.1(3) 3.1.1(4) 3.1.1(5) 3.1.1(6) 3.1.1(7) 3.F 1(8) 3.1.1(9) 3.1.1(10)

Plant Fill and Vent from a Partial Drain Down to a Solid Pressurizer Plant Startup from Cold Shutdown to Hot Standby Plant Startup from Hot Standby to Rated Power Reactor Trip Followed By Recovery to Rated Power Plant Startup from Hot Standby to Rated Power Reactor Trip Followed By Recovery to Rated Power Reactor Trip Followed By Recovery to Rated Power Plant Startup from Cold Shutdown to Hot Standby Plant Startup from Hot Standby to Rated Power Reactor Trip Followed By Recovery to Rated Power Plant Shutdown from Rated Power to Hot Standby Cooldown from Hot Standby to Cold Shutdown Plant Startup from Hot Standby to Rated Power Reactor Trip Followed By Recovery to Rated Power Plant Shutdown from Rated Power to Hot Standby NPE-001 NPE-002 NPE-003 NPE-004 NPE-003 NPE-004 NPE-004 NPE-002 NPE-003 NPE-004 NPE-005 NPE-K5 NPE-003 NPE-004 NPE-005 NOT APP NPE-005 NPE-K5 SUR-001 SUR402 LICABLE SUR-032 NPE-002 NPE-003 NPE-K5 SUR-003 SUR404 SUR-005 SURM7 SUR408 SUR409 SUR410 SUR-011 SUR412 SUR414 Plant Shutdown from Rated Power to Hot Standby Cooldown from Hot Standby to Cold Shutdown Initial CriticalityAfter Refueling, OP-0204.3 Nuclear Design Check Tests During Startup Sequence After Refueling, OP%204.5 Normal Operation of Incore Moveable Detector System and Power Distribution Surveillance, OP-12404.1 Plant Startup from Cold Shutdown to Hot Standby Plant Startup from Hot Standby to Rated Power Cooldown from Hot Standby to Cold Shutdown EDG 8 Hour Load Test and Load Rejection Test. OP-4304.3 Component Cooling Water Pumps LowHeader Pressure Start Test. 3-OSP-030.5 Reactor Coolant System Leak Rate Calculations,3-OSP441.

1 CVCS Boric Acid Transfer Flow Test, 3-OSP-046.2 Boric Acid Transfer Pump 3-B Transfer and Control Switch Test, 3-OSP-046,5 Reactor Protection System Logic Test, 3-OSP-049.1 RHR MOV's/System Pressure Interlock Test, 3-OSP-050.7 RHR MOV's 750, 751, 862, 863 Interlock Test, 3-OSP-050.8 Emergency Containment Filter Fans Operating Test.

3-OSP-056.1 Source Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.1 Page 3.-7

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3.1.2(l)(a) 3.1.2(1)(b) 3.1.2(l)(c) 3.1.2(1)(d) 3.1.2(2) 3.1.2(3) 3.1.2(4)

SUR-015 SUR416 SUR-017 SUR-018 SUR419 SUR420 SUR421 SUR-022 SUR424 SUR426 SUR429 SUM)30 SUR-031 SUR432 MRC-001 MRC-002 MCV403 MRC-003 MCV405 MSS-001 MRC-002 MRC-003 MRC-004 MCS-004 MGG-002 MGG-003 MGG-004 MMP-001 MMP-002 MMP-003 MMP-004 MMP-005 MMP-006 MMP-007 MMP-008 MSP-001 MRC-005 TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Intermediate Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.2 Intermediate Range NIS Setpoint Verification, 3-OSP459.3 Power Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.4 Power Range Nuclear Instrumentation Shift Checks and Daily Calibration, 3-OSP-059.5 Process Radiation Monitoring Operability Test, 3-OSP-067.1 Main Steam Isolation Valve Closure Test Standby Steam Generator Feedwater Pumps/Cranking Diesels Test, 3-OSP474.4 AuxiliaryFeedwater Train 1 Operability Verification, 3-OSP-075.1 Main Turbine Valves Operability Test, 3-OSP-089 Engineered Safeguards Integrated Test, 3-OSP-203 Operational Test of MOV-535. 536 and PORV-455C, 456, OP-1300.2 Full Length RCC - Periodic Exercise, OP-1604.1 Inducing Xenon Oscillations to Produce Various Incore Axial Offsets, OP-12304.8 Normal Operation of Incore Moveable Detector System and Power Distribution Surveillance, OP 12404.1 Steam Generator Tube Rupture Large Break LOCA Inside Containment With Loss Of Offsite Power Charging Line Break Outside Containment Small Break LOCA Inside Containment Non-Regenerative Heat Exchanger Tube Leak Small Leak in Safety Injection Piping Outside Containment Large Break LOCA Inside Containment With Loss Of Offsite Power Small Break LOCA Inside Containment PORV Failure (Open) Without High Pressure Injection Instrument AirSystem Operation and Malfunctions Loss of 4kV Bus 3A Loss of 4kV Bus 3B Loss of AllAC Power Loss of Vital Bus 3P06 Loss of Vital Bus 3P07 Loss of Vital Bus 3P08 Loss of Vital Bus 3P09 Loss of DC Bus 3A (3D01)

Loss of DC Bus 3B (3D23)

Loss of DC Bus 4A (4D01)

Loss of DC Bus 4B (4D23)

Bus Stripping and Load Sequencing Tests Loss of Forced Reactor Coolant Flow Page 3.-B

3.1.2(5) 3.1.2(6) 3.1.2(7) 3.1.2(8) 3.1.2(9) 3.1.2(10) 3.1.2(11) 3.1.2(12) 3.1.2(13) 3.1.2(14) 3.1.2(15) 3.1.2(16) 3.1.2(17) 3.1.2(18) 3.1.2(19) 3.1.2(20) 3.1.2(21) 3.1.2(22)

MRC-K5 MRC-008 MFW-001 MCS-002 MCS-003 MSS-003 MSS-004 MCS-001 MFWM2 MFW-55 MFW-007 MFW-008 MFW-003 MRX-002 MRX-004 MRX-005 MRX-006 MRX-007 MRX-007 MRX-008 MTU401 MllJ402 MGG-001 MCV401 MRC-007 MCV402 MCV403 MCV404 MCV405 MRX-009 MSG401 MSG402 MSG404 MFW-004 MFW-005 MRX-003 MRX-001 MSG404 TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Loss ofa Single Reactor Coolant Pump With Power Below P-8 Loss of B and C Reactor Coolant Pumps at 1KP%%d Power Loss of Condenser Vacuum, Including Loss of Condenser Level Control Intake Cooling Water System Operations and Malfunctions Turbine Plant Cooling Water Operation and Malfunctions Loss of RHR While ln Cold Shutdown Loss of Inventory During a Shutdown and Partial Draindown Condition Component Cooling Water Operations and Malfunctions up to and Including Total Loss of CCW Loss of Normal Feedwater Failure ofSteam Generator Level Channel Providing Input to the Feedwater Controller Equivalent TMI-2 Scenario Loss of Feedwater/ATWS Loss of Normal and Emergency Feedwater Loss of Protection System Channel Stuck Control Rod Uncoupled Control Rod Test Dropped Control Rod Dropped Rod With Inabilityto Drive Control Rods Dropped Rod With Inabilityto Drive Control Rods Fuel Cladding Failure Resulting in High Reactor Coolant Activity Turbine Trip Which Does Not Cause Automatic Reactor Trip Turbine Trip from 100% Power Generator Trip Uncontrolled Maximum Rate Boron Dilution Stuck Open Spray Valve Charging System Failures Charging Line Break Outside Containment Letdown and VCT System Operations and Malfunctions Non-Regenerative Heat Exchanger Tube Leak Manual Reactor Trip from 100% Power Main Steam Line Break Inside Containment Main Steam Line Break Outside Containment Transmitter Failure Resulting In Maximum Atmospheric Dump Demand Feedwater Line Break Inside Containment Main Feedwater une Break Outside Containment Nuclear Instrumentatlon Failure During Startup Spurious Rod Position Indication Resulting in Maximum Rate Runback To 70% Power and Maximum Rate Return To Full Power Transmitter Failure Resulting In Maximum Atmospheric Dump Demand page 3.-9

3.1.2(23) 3.1.2(24)

A3.1 B2.1 100% Steady State 75% Steady State 25% Steady State 100% Stability Test B2.2(1)

B2.2(2)

B2,2(3)

B2.2(4)

B2.2(5)

B2.2(6)

B2.2(7)

B2.2(8)

B2.2(9)

B2.2(10)

MSG%05 MSG406 MTV%06 MTU408 MTU409 MTV%10 MTU-011 MFW-006 MSS-001 MSS-002 MCN-001 MFW-007 MFW-008 RTT-001 RTT-002 SST403 SST402 SST%01 SST404 MRX-009 MFW-003 MSG403 MRC-005 MRC-005 MTU401 MRX-001 MRC-002 MSG401 MRC-004 TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Failure of Reference Temperature to Steam Dumps Closure of a Single MSIV at Several Different Power Levels Hydrogen Seal Oil Hydrogen Cooling Turbine Lube Oil Control and Auto-Stop Oil Turbine Lube Oil Pump and Motor Failure of Turbine Control Valve Spring Failure ofSteam Generator Level Channel Providing Input to the Feedwater Controller Small Leak fn Safety Injection Piping Outside Containment Accumulator Operations and Malfunctions Containment Spray System Operations and Malfunctions Equivalent TMI-2 Scenario Loss of Feedwater/ATWS Simulator Real Time Test Simulator Real Time Test Validation Test Steady State 100% Power Heat Balance Steady State 75% Power Heat Balance Steady State 45% Power Heat Balance 100% Power 60 min Null Transient Manual Reactor Trip from 100% Power Loss of Normal and Emergency Feedwater Simultaneous Closure of All MSIV's Loss of Forced Reactor Coolant Flow Loss of Forced Reactor Coolant Flow Turbine Trip Which Does Not Cause Automatic Reactor Trip Spurious Rod Position Indication Resulting in Maximum Rate Runback To 70% Power and Maximum Rate Return To Full Power Large Break LOCA Inside Containment With Loss Of Offsite Power Main Steam Line Break Inside Containment PORV Failure (Open) Without High Pressure Injection Page 3.- l0

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT TABLE3-3 CERTIFICATION TEST MATRIX TEST ID DESCRIPTION OF TEST COMPUTER REAL TIME TEST (RTT)

RTT~1 Smulator Real Time Test ANS 3.5 REFERENCE SECTIONS 3.1.1 Normal Plant Evolutions 3.1.2 Plant Malfunctions A3.1 Computer Real Time Test EVALUATIONBASIS Smulator does not abort on overruns.

RTT-002 Smulator Real Time Test Validation Test 3.1.1 Normal Plant Evolutions 3.1.2 Plant Malfunctions A3.1 Computer Real Time Test Smulator responds correctly to forced overruns.

STEADY STA1'E TESTS (SST)

SST-9)1 Steady State 45% Power Heat Balance 4.1 Smulator Capabilities A3.2 Steady State and Normal Tests 82.

Smulator Operability Test Comparison of simulator to plant data.

SST-002 Steady State 75% Power Heat Balance 4.1 Smulator Capabilities A3.2 Steady State and Normal Tests B2.

Simulator Operability Test Comparison of simulator to plant data.

SST-003 Steady State 100X Power Heat Balance 4.1 Smulator Capabilities A3.2 Steady State and Normal Tests B2.

Simulator Operability Test Comparison of simulator to plant data.

SST-004 lKP%%d Power 60 min Null Transient 4.1.2 Steady State Operation B.2.1 Steady State Performance Stable and parameters vap less than 2X from their Initial values.

l

TURKEYPOINT UNIT3 INITIALSIMUIATORCERTIFICATIONREPORT NORMALPLANT EVOLUTIONS (NPE)

NPE-001 Plant filland Vent from a Partial 3.1.1(1)

Drain Down to a Solid Pressurizer Plant Startup - Cold to Hot Standby Plant Data Expert Examination NPE-002 Plant Startup from Cold Shutdown to Hot Standby 3.1.1(1) 3.1.1(5) 3.1.1(10)

Plant Startup - Cold to Hot Standby Operations at Hot Standby Operator Conducted Surveillance Testing on Safety Related Equipment Plant Data Expert Examination NPE403 Plant Startup from Hot Standby to Rated Power 3.1.1(2) 3.1.1(3) 3.1.1(5) 3.1.1(6) 3.1.1(10)

Nuc Startup-Hot Standby to Rated Power Plant Data Turbine Startup &Gen Synchronlzatton Expert Examination Operations at Hot Standby Load Changes Operator Conducted Surveillance Testing on Safety Related EquIpment NPE-004 Reactor Trip Foltowed By Recovery to Rated Power 3.1.1(4) 3.1.1(3) 3.1.1(5) 3.1.1(6) 3.1.1(2)

Reactor Trip W/Recovery To Rated Power Expert Examination Turbine Startup and Generator Synch Operations at Hot Standby Load Changes Nuclear Startup from Hot Standby to Rated Power NPE405 Plant Shutdown from Rated Power to Hot Standby NPE406 Cooldown from Hot Standby to Cold Shutdown 3.1.1(8) 3.1.1(6) 3.1.1(5) 3.1.1(8) 3.1.1(5) 3.1.1(10)

Plant Data Expert Examination Plant Data Expert Examination Plant Shutdown From Rated Power To Hot Standby Load Changes Operations at Hot Standby Plant Cooldown From Hot Standby to Cold Shutdown Operations at Hot Standby Operator Conducted Suwetttance Testtng on Safety Related Equipment Page 3.-12

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M W W W W W W W W W W W W W W W W W W TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT OPERATOR CONDUCTED SURVEILLANCETESTING (SUR)

SUR401 Initial CriticalityAfter Refueling, OP~04.3 3.1.1(9) Core Performance Testing Test Acceptance Criteria Expert Examination SUR402 Nuclear Design Check Tests During Startup Sequence After Refueling, OP%204.5 3.1.1(9) Core Performance Testing Test Acceptance Criteria Expert Examination SUR403 EDG 8 Hour Load Test and Load ReJection Test, OP-4304.3 1

SUR404 Component Cooling Water Pumps Low Header Pressure Start Test.

3-OSP-030.5 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Plant Data Expert Examination Test Acceptance Criteria Expert Examination SURES Reactor Coolant System Leak Rate 3.1.1(10) Operator Conducted Surveillance Calculations, 3-OS'.l Testing On Safety Related EquIpment or Systems 3.1.2 Plant Malfunctions Test Acceptance Criteria Expert Examination SUR407 CVCS Boric Acid Transfer Flow Test. 3-OSP446.2 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination SUR408 Boric Acid Transfer Pump 3B Transfer and Control Switch Test, 3-OSP446.5 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination SUR409 Reactor Protection ~tern Logic Test, 3-OSP449.1 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination SUR%10 RHR MOV's/System Pressure Interlock Test, 3-OSP-050.7 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related EquIpment or Systems Test Acceptance Criteria Expert Examination Page 3.-13

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT SUR411 RHR MOV's 750, 751, e62, e63, Interlock Test, 3-OSP-050.8 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination SUR412 Emergency ContaInment Filter Fans Operating Test, 3-OSP456.1 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination SUR414 Source Range Nuclear Instru-mentation Analog Channel Operational Test, 3-OSP459.1 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination SUR415 Intermediate Range Nuclear Instrumentatlon Analog Channel Operational Test, 3-OSP459.2 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination SUR416 Intermediate Range NIS Setpolnt Verification, 3-OSP459.3 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination SUR417 Power Range Nuclear Instrumen-tatlon Analog Channel Operational Test, 3-OSP459.4 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination SUR418 Power Range Nuclear Instrumen-tation Shift Checks and Dally Calibration, 3-OSP459.5 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination SUR419 Process Radiation Monitoring Operability Test, 3-OSP467.1 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination SUR420 Main Steam isolation Valve Test 3.1.1(10) Operator Conducted Surveillance Test Acceptance Criteria Testing On Safety Related Equipment or Systems Plant Data Expert Examination Page 3.- 14

W W W W W W W W W W. W W TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT SUR421 Standby Steam Generator Feed-water Pumps/Cranking Dleseh Test, O-OSPC74.4 3.1.1(10) Operator Conducted Surveillance Test Acceptance Criteria Testing On Safety Related Equipment or Systems Expert Examination SUR-022 AuxiliaryFeedwater Train 1

3.1.1(10) Operator Conducted Sutveillance Operability Verification, 3-OSP%75.1 Testing on Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination SU&324 Main Turbine Valves Operablliiy Test. 3-OSP489 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination SURM6 Engineered Safeguards Integrated Test. 3-OSP-203 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or ~tems Test Acceptance Criteria Expert Examination SUR429 Operational Test of MOV-535, 536, and PORV 455C, 456, OP-1300.2 3.1.1(10) Operator Conducted Sunfelllance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination SUMO Full Length RCC - Periodic Exercise, OP-1 604.1 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems Test Acceptance Criteria Expert Examination/Plant Data SURO31 Inducing Xenon Osclllations to Produce Various Axial Offsets, OP-12304.8 3.1.1(10) Operator Conducted Surveillance Test Acceptance Criteria Testing On Safety Related Equipment or Systems Expert Examination SURM2 Normal Operation of Incore Moveable Detector System and Power Dhtrlbution Surveillance, OP-12404.1 3.1.1(10) Operator Conducted Surveillance Testing On Safety Related Equipment or Systems 3.1.1(9) Core Performance Testing K

Test Acceptance Criteria Expert Examination Page 3.- 15

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT PLANT MALFUNCTIONS(Mll)

CONTAINMENT(MCN)

MCN~T Containment Spray System Operations and Malfunctions 3.1.2(23) Passive Malfunctions in Engineered Safety Expert Examination Features Systems COMMON SERVICES (MCS)

MCS401 Component Cooling Water 3.1.2(8) Loss of Component Cooling System Operations and Malfunctions up to and Including Total Loss of CCW Expert Examination MCS402 Intake Cooling Water System Operations and Malfunctions 3.1.2(6) Loss of Service Water or Cooling To Individual Components Expert ExamInation MCS-003 Turbine Plant Cooling Water Operation and Malfunctions 3.1.2(6) Loss of Component Cooling System or Cooling to Individual Components Expert Examination MCS404 Instrument Air Operation and Malfunctions 3.1.2(2) Loss of Instrument Air Expert Examination CHEMICAL& VOLUMECONTROL SYSTEM (MCV)

MCV401 Uncontrolled Maximum Rate Boron Dilution 3.1.2(17) Failure in Automatic Control Systems That Expert Examination Affect Reactivity and Core Heat Removal MCV402 Charging System Failures 3.1.2(18) Failure of Reactor Coolant System Pressure Expert Examination and Volume Control Systems MCV~ Charging Line Break Outside Containment 3.1.2(l,b) Loss of Coolant Outside Containment Expert Examination 3.1.2(18) Failure of Volume Control System Page 3.- 16

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT MCV404 Letdown and Volume Control Tank 3.1.2(18) Failure of Reactor Coolant System System Operations and Pressure and Volume Control Systems Malfunctions Expert Examination MCV405 Non-Regenerative Heat Exchanger 3.1.2(l,b) Loss of Coolant Outside Containment Expert Examination Tube Leak 3.1.2(18) Failure of Volume Control System FEEDWATER (MFW)

MFW-001 Loss of Vacuum Tests, Including 3.1.2(5) Loss of Condenser Vacuum Including Loss of Condenser Level Control Loss of Condenser Level Control Expert Examination MFW-002 Loss of Normal Feedwater 3.1.2(9) Loss of Normal Feedwater or Feedwater System Fa!lure Best Estimate Analysis Expert Examination MFW-003 Loss of Normal and Emergency Feedwater 3.1.2(10) Loss of AllFeedwater (Normal and Emergency)

B2.2(2) Smultaneous Trip of AllFeedwater Pumps Best Estimate Analysis Expert Examination MFW-004 Feedwater Une Break Inside Containment 3.1.2(20) Main Steam Une As Well As Main Feed Best Estimate Analysis Une Breaks (Both inside and Outside Containment)

Expert Examination MFW-005 Main Feedwater Une Break Outside Containment 3.1.2(20) Main Steam Une As Well As MaIn Feed Expert Examination Une Breaks (Both Inside and Outside Containment)

MFW-006 Failure of Steam Generator Level Channel Providing Input to the Feedwater Controller 3.1.2(9) Loss of Normal Feedwater Expert Examination 3.1.2(22) Process Instrumentation. Alarm, and Control System Failures MFW-007 Equivalent TMI-2 Scenario 3.1.2(9)

Loss of Normal Feedwater 3.1.2(24) Failure of Automatic Reactor Trip Expert Examination MFW-008 Loss of Feedwater/ATWS 3.1.2(9)

Loss of Normal Feedwater 3.1.2(24) Failure of Automatic Reactor Trip Best Estimate Analysis Expert Examination Page 3.-17

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT GENERATOR & GRID (MGG)

MGG401 Generator Trip MGG402 Loss of 4KV Bus 3A MGG403 Loss of 4KV Bus 3B MGG404 Loss of AllAC Power 3.1.2(16) Generator Trip 3.1.2(3) Loss of Electrical Power 3.1.2(3) Loss of Electrical Power Expert Examination Expert Examination Expert Examination 3.1.2(3) Loss or Degraded Electrical Power to the Expert Examination Station Including Loss of Offslte Power MAIN POWER DISTRIBUTION (MMP)

MMP401 Loss of Vital Bus 3P06 3.1.2(3) Loss or Degraded Electrical Power to the Station Including Loss of AC Inst Buses Expert Examination MMP402 Loss of Vital Bus 3P07 3.1.2(3) Loss or Degraded Electrical Power to the Station Including Loss of AC Inst Buses Expert Examination MMP403 Loss of Vital Bus 3POS MMP404 Loss of Vital Bus 3P09 3.1.2(3) Loss or Degraded Electrical Power to the Station Including Loss of AC Inst Buses 3.1.2(3) Loss or Degraded Electrical Power to the Station Including Loss of AC Inst Buses Expert Examination Expert Examination MMP405 Loss of DC Bus 3A (3D01) 3.1.2(3) Loss or Degraded Electrical Power to the Station Including Loss of AC Inst Buses Expert Examination MMP406 Loss of DC Bus 3B (3D23) 3.1.2(3) Loss or Degraded Electrical Power to the Station Including Loss of AC inst Buses Expert Examination MMP407 Loss of DC Bus 4A (4D01) 3.1.2(3) Loss or Degraded Electrical Power to the Station Including Loss of AC Inst Buses Expert Examination Page 3.- 18

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT MMP408 Loss of DC Bus 4B (4D23) 3.1.2(3) Loss or Degraded Electrical Power to the Expert Examination Station Including Loss of AC Inst Buses REACTOR COOLANT SYSTEM (MRC)

MRC-001 Steam Generator Tube Rupture 3.1.2(l,a) Significant PWR Steam Generator Leaks Best Estimate Analysis Expert Examinatfon MRC-002 Large Break LOCA Inside Containment With Loss Of Offslte Power 3.1.2(l.b and c) Loss of Coolant: Large and Small Expert Examination Breaks, Inside and Outside Containment B.2.2(8) Maximum Sze Reactor Coolant System Rupture Combined With Loss of Offsite Power MRC-003 Small Break LOCA Inside Containment 3.1.2(l.b and c) Loss of Coolant: Large and Small Breaks, Inside and Outside Containment Best Estfmate Analysis Expert Examination MRC-004 PORV Failure (Open) Without High Pressure Injection 3.1.2(l.d) Failure of Safety & Relief Valves Best Estimate Analysis B.2.2(10) Slow Prfmary Depressurlzation To Saturated Expert Examination Conditions Using A Pressurizer Relief or Safety Stuck Open Without Activation of ECCS MRC-005 Loss of Forced Reactor Coolant Flow 3.1.2(4) Loss of Forced Core Coolant Row Due to Single or Multiple Pump Failure B2.2(4) Simultaneous Trip of All Reactor Coolant Pumps B2.2(5) Trip of any Single Reactor Coolant Pump Plant Data Expert Examination MRC-006 Loss of a Single Reactor Coolant Pump With Power Below P4 3.1.2(4) Loss of Forced Core Coolant Flow Due to Single or Multiple Pump Failure Expert Examination MRC-007 Stuck Open Spray Valve 3.1.2(18) Failure of Reactor Coolant System Pressure Expert Examination and Volume Control Systems MRC-008 Loss of B and C Reactor Coolant Pumps at 1K% Power 3.1.2(4) Loss of Forced Core Coolant Flow Due to Single or MuNple Pump Failure Plant Data Expert Examination Page 3.-19

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT REACTOR (MRX)

MRX401 Spurious Rod Position Indication B2.2(7), Maximum Rate Power Ramp (10'own to Expert Examination Resulting In Maximum Rate Run-Approximately 75L and Back to 1$% Power) back to 7VL Power and Maximum 3.1.2(22) Process Instrumentatlon, Alarm, and Rate Return to Full Power Control System Failures MRX~

Loss of Protection System Channel 3.1.2(11) Loss of Protection System Channel Expert Examination MRX403 Nuclear Instrumentation Failure During Startup 3.1.2(21) Nuclear Instrumentatlon Failures Expert Examination MRX404 Stuck Control Rod 3.1.2(12) Control Rod Failures Including Stuck, Uncoupled, Mlsallgned, and Dropped Rods Expert Examination MRX405 Uncoupled Control Rod Test 3.1.2(12) Control Rod Failures Including Stuck, Uncoupled, Mlsaligned, and Dropped Rods Expert Examination MRX406 Dropped Control Rod 3.1.2(12) Control Rod Failures Including Stuck, Uncoupled, Mlsatlgned, and Dropped Rods Expert Examination MRX407 Dropped Rod with Inability to Drive Control Rods 3.1.2(12) Control Rod Failures Including Stuck, Uncoupled, Misallgned, and Dropped Rods 3.1.2(13) Inability To Drive Control Rods Expert Examination Plant Data MRX408 Fuel Cladding Failure Resulting In High Reactor Coolant Activity 3.1.2(14) Fuel Cladding Failure Resulting In High ActivityIn the Reactor Coolant Expert Examination MRS%

Manual Reactor Trip from 1$%

Power 3.1.2.(19) Reactor Trip B2.2(l) Manual Reactor Trip Expert Examination Page 3.-20

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT STEAM GENERATOR & MAINSTEAM (MSG)

MSG401 MaIn Steam Une Break inside Containment 3.1.2(20) Main Steam Une As Well As Main Feed Une Best Estimate Analysis Breaks (Both Inside and Outside Containment)

Expert Examination B2.2 (9) Maximum Unlsolable Main Steam Une Rupture MSG402 Main Steam Une Break Outside Containment 3.1.2(20) Main Steam Une As Well As Main Feed Une Expert Examination Breaks (Both Inside and Outside Containment)

MSG403 Simultaneous Closure of All MSIV's 82.2(3), Smultaneous Closure of AllMSIVs Expert Examination MSG404 Transmitter Failure Resulting In Maximum Atmospheric Dump Demand 3.1.2(22) Process Instrumentatlon, Alarms, and Expert Examination Control System Failures 3.1.2(20) Main Steam Une as well as Main Feed Une Breaks (Both Inside and outside ContaInment)

MSG405 Failure of Reference Temp-erature to Steam Dumps 3.1.2(22) Process Instrumentatlon, Alarms, and Control System Failures Expert Examination MSG406 Closure of a Sngle MSIVat Several Different Power Levels 3.1.2(22) Process Instrumentatlon. Alarms, and Control System Failures Expert Examination STANDBY POWER & SYNCHRONIZATION (MSP)

MSP-001 Bus Stripping and Load Sequencing Tests 3.1.2(3) Loss or Degraded Electrical Power to the Expert Examination Station Including Loss Emergency Power SAFHY SYSTEM (MSS)

MSSO01 Small Leak In Safety Infection Piping Outside ContaInment 3.1.2(23) Passive Malfunctions In Systems, Such As Expert Examination Engineered Safety Features &Aux Feedwater 3.1.2(l,b) Loss of Coolant Outside Primary Containment

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TURKEYPOINT UNIT3 INITIALSIMUlATORCERTIFICATIONREPORT MSS402 Accumulator Operations and Malfunctions 3.1.2(23) Passive Malfunctions In Systems, Such As Expert Examination Engineered Safety Features &Aux Feedwater MSS404 Loss of Inventory During a Shutdown and Partial Dralndown Condition 3.1.2(7) Loss of Shutdown Cooling MSS403 Loss of RHR While tn Cold Shutdown 3.1.2(7) Loss of Shutdown Cooling Expert Examination Expert Examination TURBINE (MTU)

MTU401 Turbine Trip Which Does Not 3.1.2(15) Turbine Trip Not Cause Automatic Reactor Trip B2.2(6). Main Turbine Trip From Power Level That Does Not Cause a Reactor Trip Expert Examination MTU402 Turbine Trtp from l(OX Power MTU403 Turbine Lube Oil System (Bearings) 3.1.2(15) Turbine Trip 3.1.1 Normal Plant Evolutions 3.1.2 Plant Malfuncttons Expert Examination Expert Examination MTU404 Turbine Gland Seal ~tern 3.1.1 Normal Plant Evolutions 3.1.2 Plant Malfunctions Expert Examination MTU~

Turbine Turning Gear Operation 3.1.1 Normal Plant Evolutions 3.1.2 Plant Malfunctions Expert Examination MTU-006 Hydrogen Seal Oil 3.1.2(22) Process lnstrumentatlon, Alarms, Controls Expert Examlnatton and Control System Failures MTU408 Hydrogen Cooling 3.1.2(22) Process Instrumentation, Alarms, Controls Expert ExamInation and Control System Failures MTU~

TurbIne Lube Oil Control and Auto-Stop Oil 3.1.2(22) Process Instrumentation, Atarms, Controls Expert Examinatton and Control System Failures Page 3.-22

TURKEYPOINT UNIT3 INITIALSIMULATORCER77FICATION REPORT MTUO10 Turbine Lube Oil Pump and Motor 3.1.2(22) Process Instrumentation, Alarms, Controls and Control System Failures Expert Examination MTUO11 Failure of Turbine Control Valve Spring 3.1.2(22) Process Instrumentation, Alarms, Controls and Control System Failures Expert Examination Page 3.-23

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Table 3-4 Annual Tests MFW403 MPC%02 MPC%04 MPC%05 MPX-001 MPX-ON MSG-001 MSG-003 MTU-001 SST%01 SST%02 SSTM3 SST%04 Loss of Normal and Emergency Feedwater Large Break LOCA Inside Containment With Loss Of Offslte Power PORV Failure (Open) Without High Pressure Injection Loss of Forced Reactor Coolant Flow Spurious Pod Position Indication Resulting in Maximum Pate Runback To 7C% Power and Maximum Rate Return To Full Power Manual Reactor Trip from lOPX Power Main Steam Line Break Inside Containment Simultaneous Closure of All MSIV's Turbine Trip Which Does Not Cause Automatic Reactor Trip Steady State 45L Power Heat Balance Steady State 75% Power Heat Balance Steady State 10'ower Heat Balance lOVÃ Power 60 min Null Transient Page 3.-24

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Table 3-5 1991 Test Plan MFW~

MFW~7 MGG-002 MGG-003 MGG-004 MMP-001 MMP-002 MMP-003 MMP-004 MMP-005 MMP-006 MMP-007 MMP-008 MRC406 MRC~7 MSP~l NPE-002 NPE-003 SUR-001 SUR-002 SUR-026 SUR-030 SUR-031 SUR-032 Loss of Normal Feedwater Equivalent TMI-2 Scenario Loss of 4KV Bus 3A Loss of 4KV Bus 3B Loss of AllAC Loss of Vital AC Bus 3P06 Loss of Vital AC Bus 3P07 Loss of Vital AC Bus 3P08 Loss of Vital AC Bus 3P09 Loss of DC Bus 3A (3D01)

Loss of DC Bus 3B (3D23)

Loss of DC Bus 4A (4D01)

Loss of DC Bus 4B (4D23)

Loss of a Sngte Reactor Coolant Pump WIth Power Below P-8 Stuck Open Spray Valve Bus Stripping and Load Sequencing Tests Plant Startup Cold Shutdown to Hot Standby Plant Startup from Hot Standby to Rated Power Initial Criticalityafter Refueling, OPM04.3 Nuclear Design Check Tests During Startup Sequence after Refueling, OP-0204.5 EngIneered Safeguards Integrated Test, 3-OSP-203 Full Length RCC - Periodic Exercise, OP-1604.1 Inducing Xenon Osclllatlons to Produce Various lncore Axial Offsets, OP-12304.8 Normal Operation of Incore Moveable Detector System and Power DIstribution Surveillance, OP-12404.1 Page 3.-25

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Table 3-6 1992 Test Plan MCV401 MCV~

MCV~

MFW404 MFW406 MRC403 MSG406 MTU-003 MTU-004 MTU-005 MTU-ON MTU-010 MTU-011 NPE-005 NPE-006 SUR-004 SUR-007 SUR-008 SUR-ON SUR-012 SUR-015 SUR-017 SUR-020 Uncontrolled Maximum Rate Boron Dilution Charging System Failures Letdown and Volume Ccontrol Tank System Operations and Malfunctions Feedwater Une Break Inside Containment Failure of Steam Generator Level Channel Providing Input to the Feedwater Controller Small Break LOCA Inside Containment Closure of a Single MSIVAt Several Different Power Levels Turbine Lube Oil System (Bearings)

Turbine Gland Seal System Turbine Turning Gear Operation Turbine Lube Oil Control 5 Auto-Stop Oil Turbine Lube Oil Pump 8. Motor Failure of Turbine Control Valve Spring Plant Shutdown from Rated Power to Hot Standby Cooldown from Hot Standby to Cold Shutdown Component Cooling Water Pumps Low Header Pressure Start Test, 3-OSP430.5 CVCS Boric Acid Transfer Flow Test, 3-OSP-046.2 Boric Acid Transfer Pump 3B Transfer and Control Switch Test, 3-OSP-046.5 Reactor Protection System Logic Test, 3-OSPM9.1 Emergency Containment Filter Fans Operating Test, 3-OSP456.1 Intermediate Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-O59.2 Power Range Nuclear lnstrumentatlon Analog Channel Operational Test, 3-OSP-O59,4 Main Steam Isolation Valve Closure Test Page 3.-26

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Table 3-7 1993 Test Plan MCS401 MFW401 MGG-001 MRC~1 MRC499 MRX-003 MRX-006 MRX-007 MSG-004 MSG-005 MTU-002 NPE-001 SUR-003 SUR-005 SUR-010 SUR-011 SUR-021 SUR-022 SUR-024 Component Cooling Water Operations and Malfunctions Up To and Including Total Loss of CCW Loss of Vacuum Tests, Including Loss of Condenser Level Control Generator Trip Steam Generator Tube Rupture Loss of B and C Reactor Coolant Pumps at 100% Power Nuclear Instrumentatlon Failure During Startup Dropped Control Rod Dropped With Inability to Drive Control Rods Transmitter Failure Resulting In Maximum Atmospheric Dump Demand Failure of Reference Temperature to Steam Dumps Turbine Trip from 10'ower Plant Rll and Vent from a Partial Drain Down to a Solid Pressurizer EDG 8 Hour Load Test and Load ReJectlon Test, OP-4304.3 Reactor Coolant System Leak Rate Calculations, 3-OSP-041.1 RHR MOV's/System Pressure Interlock Test, 3-OSP450.7 RHR MOV's 750, 751, 862, 863, Interlock Test, 3-OSP~.8 Standby Steam Generator Feedwater Pumps/Cranking Dleseis Test, O-OSP%74,4 AuxiliaryFeedwater Train 1 Operability Verification, 3-OSP475.1 Main Turbine Valves Operability Test, 3-OSP4S9 Page 3.-27

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Table 3-8 1994 Test Plan MCN401 MCS402 MCS403 MCS4N MCV~

MCV~

MFW405 MFW408 MRX-002 MRX-004 MRX-005 MRX-008 MSG-002 MSS-001 MSS-002 MSS-003 MSS-004 MTU-K5 MTU-008 NPE-004 RTT401 RTT4K?

SUR-014 SUR-Olb SUR-018 SUR-019 SUR-029 Containment Spray System Operations and Malfunctions Intake Cooling Water System Operations and Malfunctions Turbine Plant Cooling Water Operation and Malfunctions Instrument AirSystem Operation and Malfunctions Charging Une Break Outside Containment Non-Regenerative Heat Exchanger Tube Leak Main Feedwater Line Break Outside Containment Loss of Normal Feedwater/ATWS Loss of Protection System Channel Stuck Control Rod Uncoupled Control Rod Test Fuel Cladding Failure Resulting In High Reactor Coolant Activity Main Steam Line Break Outside Containment Small Leak In Safety InJectlon Piping Outside Containment Accumulator Operations and Malfunctions Loss of RHR While In Cold Shutdown Loss of Inventory During A Shutdown and Partial Dralndown Hydrogen Seal Oil Hydrogen Cooling Reactor Trip Followed By Recovery to Rated Power SImulator Real lime Test Simulator Real Time Test Validation Test Source Range Nuclear instrumentation Analog Channel Operational Test, 3-OSP-059.1 Intermediate Range NIS Setpoint Verification, 3-OSP459.3 Power Range Nuclear Instrumentatlon ShIft Checks and Daily Calibration, 3-OSP-059.5 Process Radiation Monitoring Operability Test, 3-OSP467.1 Operational Test of MOV-535, 536, and PORV 455C, 456, OP-1300.2 Condition Page 3.-28

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT TABLE3-9 TEST ACCEPTANCE CRITERIA COMPUTER REAL TIME TESTS 1 - Simulafion does nof half during execution of tesf transients.

2 - Simulafion halfs when forced to run ouf of real time.

STEADYSTATE TESTS 1 - Simulator instrument error shall be no greafer than that of fhe comparable planf instrument. (ANSI/ANS3.5, Secfion 4. 1) 2 - Simulafor values for criticalparameters shall not deviate from planf values by more than+/- 2% ofthe equivalent planfinsfrument range. (ANSI/ANS3.5, Secfion 4. 1, note excepfion) 3 - Simulafor values for noncrifical parameters shall nof deviate from plant values by more than 10% ofthe equivalent planf insfrumenf range. (ANSI/ANS3.5, Section 4. 1, nofe excepfion) 4 - Simulator values for critical and noncritical paramefers shall respond such thaf they do nof detracf from training. (ANSI!ANS3.5, Section 4. 1) 5 - Simulator compufed values for steady sfafe, full power operafion wifh the plant confrol system configuration shall be sfable and not vary more than 2% oftheirinifial values over a 60 minufe period. (ANSI/ANS3.5, Section 4. 1)

TRANSIENT TESTS Includes:

Normal Plant Evolution Tesfs Surveillance Tesfs Malfunction Tests 1 -

The observable changein fhe monitored parameters shall correspondin direction to those expecfed based on available validafion dafa and fhe assessment of fhe Tesf Team or Evaluafion Team. (ANSI/ANS 3.5, Section 4.2. 1)

Page 3.-29

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATIONREPORT 2 -

The observable response of fhe monitored paramefers shall nof violafe the physical laws of nafure. (ANSI/ANS3.5, Secfion 4.2. 1) 3 -

The simulafor shall respond wifh all alarms and automafic acfions which would result from the same conditions in fhe plant, and shall produce no alarms or automatic action which would not result from the same condifions in the planf. (ANSI/ANS3.5, Section 4.2. 1) 0 4 -

The response ofthe simulafor fo control manipulations and automafic confrolsystems shall be such that the operafor shall nof observe differences befween simulafor and plant response which would detract from fraining. (ANSI/ANS 3.5, Section 3. 1) 5 -

The simulator controls forsysfems which are confrolled outside the confrol room shall allow performance of those functions which direcfly or indirectly inferacf wifh observable indicafions in the confrol room. (ANSI/ANS3.5, Secfion 3.3.2) 6 -

The response of the simulafor shall be such thaf the operafor is required to take fhe same actions as those taken in the planf using similar procedures.

(ANSI/ANS 3.5, Section 3) 7 - For Surveillance Tesfs, the simulafor shall satisfy the accepfance criferia sfafed in the applicable planf procedure.

(ANSI/ANS3.5, Section 3.1. 1)

I'I 8 - For Malfunction Tesfs, fhe infroducfion ofa malfunction shall not alert the operafor to the impending malfunction in any manner other than would occur in the plant.

(ANSI/ANS 3.5, Section 3.4.2)

Page 3.-30

START CE RTIF ICATION TEST PROCESS TURKFYPOIA7 ViVI7 3

//II/j/A/ S/AKUL47VR CERT/FICA77OA'EPOR7 FIGURE 3-1 PREPARE TEST PROCEDURE PREPARE TEST REPORT REVIEW BY SIMULATOR ENGINEERING COO R DINATOR GENERATE DISCREPANCY REPORT REVIEW TEST REPORT APPROVm YES WITHOUT DISCIIEPANCIIIS APPROVED FOR USE

?

MAKE REQUIRED CHANGES REPORT ACCEPTABLE

?

NO GENERATE DISCREPANCY REPORT YES TEST TEAM PERFORMS TEST EVALUATION TEAM REVIEWS RESULTS PRESENT REPORT TO SIMULATOR CONFIGURATION REVIEW BOARD MAKE REQUIRED CHANGES (SEE FIGURE 4-1)

YES PERPORMANCC ACCEPTABLE

?

RESULTS YES ACCEPTABLE

?

APPROVIID BY SCRB

?

YES NO COMPLETE REV 1 1 /30/90 PAGE 3-3f DISCREPANCY ADDITIONALINFO

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SlMULATOR TEST DATA DDCUMENTATION SYSTEM TURKFYPOIAIT'IIIIT3 li/IT/A/. Slk/VL4TOR CFRTIFICATIO)V RFPORT FlGVRF'-P SIMULATOR TEST DATA PROCESSING EST DATA SCII DEPOT TAPE UTIUTY PC SYSTEM TEST DATA

~DAT TEST DOCT SIMULATOR JIMULATQR ERDADS DATA CONVERSION RPRE CUPPER C

ERDADS PT DEF

.DBFANTX EST DATA HEADER

.HDR DAD A CHIV INARY DAD DATA SCII GETDATA INPUT

.TST 0 CZDATA DOWOO8 YAOO C

DOWS OS C

RAPHE RAPHE PLOT RAPHE ERDADS SIMULATOR ERDADS DOWNLOAD

.TST RETRAN RUN FUEL RESOURCES RETRAN RAW DATA

.PRN DEPOT TAPE UTIUTY RTWWK RTSTRIP AWK C

RETRAN DOWNLOAD

.TST GRAPH DEFINITION

.GRF PLOT XPRESSION

.XPR GRAPHER PLOT COM

.PLT PAGF 3-H'

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT REFERENCES 3-1 Turkey Poinf Simulafor Test Documentation Sysfem User's Guide.

3-2 Turkey Poinf Simulator Engineering Instrucfion 5, Operation of the Configuration Managemenf Sysfem, January 31, 1H'0.

Page 3.-33

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT SIMULATORDISCREPANCYAND UPGRADE PROGRAM SIMULATORCONFIGURATIONMANAGEMENTSYSTEM The Simulafor Configurafion Management System is defined and controlled by Admlnisfrative Procedure O-ADM-305, Simulafor Configuration Managemenf (Reference 4-1). This procedure describes simulafor configurafion management and further details the sfeps and procedures fo be used for identification and collection ofpofenfial modifications; evaluafion ofpossible simulafor modificafions; implementation,

tesfing, and doc umenfafion of simulator modifications; certi%cation testing and documentation; simulator records managemenf; and simulafor sfatus moniforing.

Figure 4-1 is a flow charf illustrafing the process lmplemenfed by this procedure.

Defails forthe implemenfafion of0-ADM-305can also be found in the appropriafe Simulafor Engineering Instruction (SEI).

Identification and Collection of Potenfial Modificafions This secfion defines how potenfial modi%cafions will enfer the Simulafor Configurafion Management process.

The sfeps cover all pofenfial modifications, including simulator discrepancies, plant changes or modifications, and changes ln training requirements.

Evaluation of Possible Simulator Modifications This secfion defines the mannerin which allpotenfial modifications to the simulafor are evaluafed, the change disposition specified, and the priorifyformodifications established.

Im lemenfation Tesfin and Documentation ofSimulator Modificafions This secfion establishes the requirements for the management of changes to the simulafor hardware, software, test plans, and documentation.

Certification Testin and Documenfation The requirements for conducfing certification testing and preparing the required NRC documentation are defined in this section.

Page 4.-1

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Simulator Records Mana emenf This secfion defines the requirements and functions of simulator records management.

This includes fhe storage and control ofSimulafor documentafion, and the mainfenance of the computerized records sysfem.

Simulafor Stafus Moniforin This secfion defines the requiremenfs for moniforing the sfafus of simulafor modi%cafions from Identification through complefion.

4.2 SIMULATORDISCREPANCY REPORTING INSTRUCTIONS The procedure thaf describes the complete handling of a deficiency report (DR) is 0-ADM-305 and is described above in Secfion 4.1.

Simulafor Engineering Instrucfion 4 Simulafor Discrepancy Reporting (Reference 4-2), provides detailed instruction to the originator ofa possible discrepancy.

Ifexplains how to fillout a DR and what informafion to provide.

4.3 PLANTDESIGN CHANGE TRACKING Simulafor Engineering Insfrucfion 10, Plant Design Change Tracking (Reference 4-3),

defails the process used forplanf design change tracking. Basically, pianf design changes are received by fwo pafhs, (1) PC/M and DEEP distribufion by document confrol and (2) PNSC meefing materials. Simulator Engineering Insfrucfion 10 describes how material is received from each source, reviewed for applicabi%fy fo the simulator, filed, and scheduled for implemenfafion.

4.4 SIMULATORWORK ORDER STATUS Figures 4-2 and 4-3 presenf a snapshof of the simulafor work order stafus as of December 7, 1990.

The summary was prepared from the Simulafor Configuration Management System, a PC based dafabase sysfem that serves as a repository for informafion on all requesfs for modification to the Simulafor. (Reference 4-4).

ASimulafor Work Request Number (SWRN) is a unique work order number assigned to a

simulator discrepancy or ofher potential modification.

A Planf Page 4.-2

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Change/Modification (PCM) is a planf change document.

Some PCM's require a simulator modification and are enfered info the Simulafor Configuration Management System.

Figures 4-2 and 4-3 display fhe number of oufstanding simulafor work items in each prioritylevel for both discrepancies and PCM's.

The sysfem used to priorifize the various work orders is described in Simulator Engineering Insfruction 6,

Priorify and Disposition of Pofenfial Simulator Modi%'cafions. (Reference 4-5).

The sysfem forpriorifizingdiscrepancies is based on an adaptafion ofapproach developed by the Eiecfric Power Research Instifute and documenfed in NP-5746, Evaluation ofSimulator Discrepancies on the Basis of Operational Impact, April l988 (Reference 4-6).

Figure 4-4, Assignmenf of Discrepancy Operational Priorify, illustrafes the decision hierarchy leading fo the prioritydesignation.

The priorifization ofplanf changes is performed as described in SEI-6.

There are four categories:

A = Signiiicanf training impacf, including

hardware, B = Significant training impact, no hardware, C = Minimal training impact, and D = No direct training impact, sources of pofenfial validation data.

Figure 4-2 includes onlySimulafor discrepancies (priorifies 1-8). Figure 4-3includes only training impact ifems (priorifies A-C).

Page 4.-3

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/IVll7A/ SIAIUL4TOR CFRj//=/CAT/WRFPOR7 F7CPUiVF W-1 POTENTIAL MODIFICATION IDENTIFIED S IMULATOR CON F I0 0 RATION MANAGE ME NT I N FOR M ATION FLOW DIAGRAM INPUT TO CONFIGURATION MANAGEMENT SYSTEM REVIEW 8 REJECTED SIMULATOR ENQINEERINQ COORDINATOR UPDATE CONFIGURATION MANAGEMENT SYSTEM FILE PERFORM CERTIFICATION TESTING INWORK PLANNED DEFERRED NO IMPLEMENTATION PREPARE CERTIFICATION DOCUMENTATION UPDATE CONFIGURATION MANAGEMENT SYSTEM DEFERRED REVIEW B SIMULATOR CONFIGURATION REVIEW BOARD SUBMIT CERTIFICATION DOCUMENTATION IMPLEMENT INWORK PLANNED GENERATE SIMULATOR WORK REQUEST IMPLEMENT TEST AND DOCUMENT UPDATE CONFIGURATION MANAGEMENT SYSTEM FILE REV 10/26/90 PAGF 4-4

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rumor /arm ver s I/VIT/A/ S/AfVL4TH CFRJIF)CAT/W REPORT

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OUTSTANDING DISCREPANCIES BY PRIORITY 0

PRIORITY REV 12/07/90 PAGE 4-5

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ruWZr/ aWr u~rr S liVIT/A/ SIAfUZATOR CER'7IFICATINREPORT

~BVA'E 4-D OUTSTANDlNG PC/Ms BY PRIORITY t6 PRIORITY REV 1 2/07/'90 PAgZ 4-g

W W W I

ASSIGNMENT OF DISCREPANCY OPERATIONAL P RIOR ITY DISGACPANCY REPORT TgRAFY POIJV7 ViVl73 llIVIVAlSlitlVL4jOR CFRTIF/CATIW RFPOR?

~GVRF O' W IMPCDCS CREW PERFORMANCE OF ACQUIRCO FUNCTIONS PHYSICAL DIFFERENCE FROM PLANT CONTROL ROOM

?

IMPCDCS IN STAUCTOR PERFORMANCE OF RCQUIRCO FUNCTIONS

?

YCS YCS CRmCAL TO SAFETY CAN HE LEA YCS CXPCAICNCCD CREW MEMBER SCC IT

'?

YES INVOLVE CREW TASKS ASSOCIATCO WITH ACCIDENT MITIGATION, RESTORING PLANT TO SAFE CONDITION, MINIMIEING INJURY OR DAMAGE NOT CRITICAL TO SAFETY CAN NO E LEA YCS EXPERIENCED CREW MEMBER SCP IT

?

NQ OPERATIONAL IMPACT S IMVIATOR UPDATE REQUEST NOT A DISCREPANCY NO IF ERROR IS MADCo CAN IT BE RCCOVCACD

'?

YES NO IF ERROR IS MADE, CAN IT BE RCCOVCRCD

'?

YES NO IF ERROR IS MADE.

CAN IT BE RCCOVCRCO

'?

YES NO IF ERROR IS MADE, CAN IT BE ACCOVCRCD

'?

NO YES HARDCOPY OCUMENTATIO ONLY 10 REV 10/26/90 PAGF4-P'BASED ON EPAI NP-6T48)

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT REFERENCES 4-1 Simulator Configurafion Management, Turkey Poinf Planf Procedure O-ADM-305, November 1, 1988.

4-2 Simulafor Discrepancy Reporfing, Simulator Engineering Insfrucfion Number 4, January 31, 1990.

4-3 Plant Design Change Tracking, Simulafor Engineering Instruction Number 10, Sepfember 12, 1990.

4-4 Turkey Point Simulafor Engineering Instrucfion Number 5, Operation of the Configurafion Managemenf System, January 31, 1990 4-5 Turkey Point Simulafor Engineering Insfrucfion 6, Priorifyand Disposition ofPotential Simulafor Modi%cations, July 26, 1990.

4-6 Electric Power Research Institute NP-5746, Evaluation ofSimulafor Discrepancies on the Basis of Operational Impacf, April, 1988.

Page 4.-8

TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT APPENDIXA: QUAVFICATIONSOFTHECERTIFICATIONTEAM SCRB ANDSCRBALTERNATES This Appendix consists of abstracts from the resumes of the members of the Certi%cat/on team, the SCRB, and the SCRB alternates.

CERTIFICATION TEAM James F. Harrison - Simulator Certification Engineer Has nineteen years of experience in various water reactor areas including software development, safety analysis, coordination of licensing activities, and fluidsystems engineering.

Planned and directed the Florida Power & Light Turkey Point Simulator Certi%cation Test Program and conducted a number of the tests.

He provided a technical evaluation ofsimulator process models forthe Florida Power & Light, St. Lucie and Turkey Point plants and the Rochester Gas &

Electric, Ginna plant. He was a principal in the development ofmodels for the nuclear boiler for several BWR plants. He has part/c/pated in a project sponsored by Electric Power Research Institute (EPRI) to develop methods to qualify simulator models using RETRAN.

In the area ofsystem transient model development and safety analysis, Mr Hanison has participated In the development ofmodels fora wide variety ofplants, Including Westinghouse, three & four loop plants, Babcock and Wilcox raised & lowered loop plants, Genera/ Electricjet pump & non-jet pump plants, and the Combustion Engineering System 80.

These activities included preparation ofmodels forthe RCS, steam generators, emergency

systems, control systems, trip systems, and the balance of plant.

Mr.

Harrison has been Involved in an equally broad spectrum of analysis activities ranging from safety analysis to plant operational improvement studies.

Mr. Harrison coordinated the preparation ofthe EPRI PWR Transient Analysis Guidelines for the Reactor Analysis Support Package (RASP) and has performed independent analyses and assessments of the RETRAN03 code for the Electric Power Research Institute.

Mr. Harrison has a BS in Mechanical Engineering and is a Registered Professional Engineer in Virginia.

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Robert J. Ginsberg - Simulator Ceiti%cation Test Team Member Nuclear Training Instructor at Suriy Power Plant.

Senior Reactor Operator License.

Developed material for and conducted Licensed Operator Requali%cation Program for9 months, developed and taught Surry Technical Staff and Manager training program for 3 years.

US Navy Nuclear Officer on two submarines for 5 years.

Qualified as Engineer Officer of navy nuclear propulsion units.

BS in Engineering, US Naval Academy, 1979.

Jeny W. Johnson - Simulator Certification Test Team Member Two years experience as Simulator Validation Engineer responsible for 10CFR55A5/ANSI/ANS 3.5 compliance. Developed a UNIXcomputerbased validation database using plant modification documentation. Developed software in C to handle PC to UNIX data transfer. Performed soffware modifications to the Browns Feny Simulator in SEL assembler under MPX2.0.

Compiled preliminary requirements for annual testing per ANSI/ANS3.5.

Two years as Computer Applications Engineer. at the South Texas Nuclear Project.

Responsible for vendor interface of Emergency Response Facility

'omputersystems during acceptance testing, supervision ofinstallation and tech staff representation during start-up. Performed analysis and critique of ERF and SPDS displays.

Developed dBASE III soffware procedures for automated production of I/O point verification documents and configuration management.

Four years experience responsible forimplementation, maintenance and testing ofsoftware executin g on a SEL 32/77 under MPX2.0 at the Waterford 3 nuclear plant. Performed software development and modification in FORTRAN 77. Responsible formodifications to the Safety Parameter Display System per NRC commitments prior to full power operation. Performed testing of software during pre-operational testing of the Plant Computer.

Successfully completed a seven month Shift Technical Advisor training program.

Served as Staff Test Engineer during ANO-2 Cycle 2 reload physics tests and Waterford 3 precore hot functional testing.

B.S. Nuclear Engineering, Mississippi State University Page 2

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Kennefh D. White - Simulafor Certification Test Team Member Nuclear Training Insfructor for 2 years af Rancho Seco Power Plant.

Developed sysfem manuals and conducfed operator training classes.

Nuclear Power Plant Reacfor Operator for 2 years at the Koeberg Nuclear Power Station In South Africa.

Nuclear Power Planf Operafor for 7 years af Arkansas Nuclear One, Unif One.

Acted as all levels of plant operator up to and including Shiff Supervisor.

Senior Reacfor Operafor license.

US Navy submarine nuclear machinist's mafe for 6 years.

BA Economics, University ot Soufh Florida, 1974.

SIMULATORCONFIGURATION REVIEW BOARD Richard G. Mende - Operations SCRB Member Operafions Supervisor (Department Head) for lasf 3 1/2 years.

Supervises 160 operators and a budgef of $9 million. SRO license since July 1984.

Reacfor Engineering Supervisor (Department Head) for 1

1/2 years.

Supervised engineering personnel performing core physics moniforing, planf process and safety compufer sysfems, and Emergency Planning.

Also acted as license class and licensed operator requalificafion instructor.

Reactor and Plant Engineer for 8 years, including 7 years as Reacfor Engineer.

Performed core physics monitoring calculations, core reload work, and plant performance calculafions.

BS in Biologyfrom UniversifyofMiami wifhminorin Chemisfry. Senior status in Mechanical Engineering af University of Miami.

John E. Crockford - Operations Alfernafe SCRB Member Assisfant Operafions Superintendent forlast 2 years and forthree years from 1984 to 1986.

Responsible for review of changes and modificafions to the planf, plant Surveillance, and other dufies as assigned.

Licensed Senior Reactor Operafor.

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTIFICATION REPORT Nuclear Operations Training Supervisor for 2 years from 1987 to 1989.

Responsible forlicensed operator training and requalification programs and for Shift Technical Advisor training.

Plant Supervisor, Nuclear for five years.

Responsible for day-to-day operation of the nuclear units.

Nuclear Watch Engineer for 6 years and plant operator (unlicensed) for 2 more years.

7 years ofNavy nuclear experience.

r Hugh H. Johnson Jr. - Operations Alternate SCRB Member Assistant Operations Supervisor for last 18 months.

Responsible for various operations tasks associated with outage support.

Participated in SRO license class and received SRO license.

Unit One Operations Managerat South Texas Project forHouston Power and Light for 4 and 1/2 years from 1985 to 1989.

Responsible for overall unit operations during preoperafion, startup and commercial operations.

SRO licensed on units One and Two.

Assistant Nuclear Plant Supervisor at Florida Power and Light's St. Lucie Plant for 5 years from 1981 to 1985.

RO and SRO licensed on units 1 and 2 at St.

Lucie Plant.

Robert E. Dodson II - Simulator Engineering SCRB Member, SCRB Chairman Simulator Engineering Coordinator for last 4 years.

Responsible for all hardware and software changes and maintenance as well as certi%cation and budget activities.

Simulator Procurement Engineer for 3 years.

Participated in development of procurement specifications, design reviews, acceptance testing and other tasks associated with procurement of the Turkey Point Simulator.

Three years oflicensed nuclear power plant operations.

Held RO and SRO licenses at Turkey Point.

Seven years of Nuclear Training Instructor experience, five of which are at Turkey Point, including licensed operator training and requalification training.

BS in Industrial Technology, Florida International University, 1979.

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TURKEYPOINT UNIT3 INITIALSIMULATORCERTII-ICATIONREPORT Kay A. Lovell - Simulafor Engineering Alfernafe SCRB Member Simulafor Process Engineer forlast 5 years.

Responsible fordeveloping the procuremenf specifications for and maintaining the ffdelifyof fhe Turkey Poinf Simulafor.

Tesfs soffware and hardware changes and clears discrepancies.

Reviews planf changes for simulafor impacf.

Controls the software configuration.

Shift Technical Advisor and Planf Sysfems Engineer for four years af Turkey Point. Licensed as Senior Reacfor Operafor af Turkey Point.

BS in Mechanical Engineering with a minorin Power Production at Universify of Tennessee, Knoxville, 1981.

Leo Goebel - Simulafor Training SCRB Member Simulafor Training Coordinafor for last 4 1/2 years.

Responsible for total implemenfation ofall simulafor training activi%es, including training needs

analysis, maferial development, procedure validafions, and INPO accreditafion.

Licensed Operafor Requalificafion Program Supervisor for 2 years.

Inifial license class insfrucfor for2 years.

Plant licensed operator and Senior Reactor Operator for 2 years af Turkey Poinf.

Charles A. Coker - Simulator Training Alfernafe SCRB Member Simulafor Training Insfrucfor for last 3 years.

Responsible for fraining of licensed operafors and license candidates.

Planf Supervisor, Nuclear and Licensed Senior Reacfor Operafor for 12 years at Turkey Point. Responsible forall operations shiit acfivifies, mainfenance planning and scheduling, procedure writing.

Also served as oufage coordinator for several outages.

Nuclear Watch Engineer and Licensed Senior Reactor Operafor for5 years.

Twelve additional years as power plant operator at convenfional plants.

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NRC FORM 474 1140) 10 CFR 55.45(bl, 55.4 snd 555 U.S. NUCLEAR REGULATORYCOMMISSION SIMULATION FACILITY CERTIFICATION APPROVED BY OMB: NO. 31500135 EXPIRES: BQ042 ESTIMATED BURDEN PER

RESPONSE

TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST:

120 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFOR.

MATION AND RECORDS MANAGEMENT BRANCH (MNBB 771 ~I, U.S.

NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT 13150 0138), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503, INSTRUCTIONS. This form lito be filed for initialceitiiiation, rscertIIication Iilrequired), and Ior any change to a simulation facility performance testing plan made aher initial submittal of such a plan. Provide the followinginlormation, and check the appropriate box to indicate reason Ior iubniittal.

FACILITY TURKEY PO I NT NUCLEAR GENERAT I iVG UN I T I'lUMBER LICENSEE FLORIDA POWER AND LIGHT COMPAI'lY DOCKET NUMBER so-251 DATE 12/31/90 This isto cenify that:

1.

The above named facility licensee is using a simulation Iacilltyconsisting solely of a plant referenced simulator that mse<< the reuuirements of 10 CFR 55.45.

2.

Documentation 4 available for NRC review in accordance with 10 CFR 55.45(bl.

3.

This simulation facility meets the guidance contained in ANSI(ANS3.5, !rI85, as endorsed by NRC Regulatory Guide 1.149.

Ifthere are anyexceptions to the certiiiatlonof thh item, check here I

j and describe fullyon additional pages as nsce<<ary.

NAME (or otheridrnrlf(carionJ AND LOCATIONOF SIMULATIONFACILITY TURKEY POINT SIMULATOR 9E MILES EAST OF FLORIDA CITY ON PALM DRIVE FLORIDA CITY, FLORIDA 33034 X

SIMULATIONFACILITYPERFORMANCE TEST ABSTRACTS ATTACHED.(ForPerformance tests conduard in rhe Period ending with rhe dae of rhis ceni iicerioni OESCRIpTION OF pERFORMANCE TESTING COMPLETED (Arrrchafditioneipape(sJ es necessary, end idenriiythr!rrmdrscriprion beinp continua(i

'EE ATTACHED DOCUMENT SIMULATIONFACILITYPERFORMANCE TESTING SCHEDULE ATTACHED. (For the conduct ofeppmximereiy 25% ofperformance rests prr yrer for rhe four year period commencinp wirh thr dar ofthis certification.J DESCRIPTION OF PERFORMANCE TESTING TO BE CONDUCTED. (Arrech edditionei page(sJ as necessary, rnd Jdrnr Jfy the nan dacriprion brinp continued J SEE ATTACHED DOCUMENT PER FOR MANCE TESTING PLAN CHANGE. (For any modJficet Jon to 4 performance tesrinp plan submirraf on 4 previous cenificsrionJ DESCRIPTION OF PERFORMANCE TESTING PLAN CHANGE (Attach edditionripage fsi es necessary, rnd (dent Jfy the iran descriprion bring conrinuedJ-INITIALCERTIFICATION NOT APPLICABLE RECERTIF ICATION (Describrconectlve action ts(rrn, attach resuksof compirred perfonnrnce tatinp in rccordsncr wkh 10 CFR g 5545ibi(5(JYJ.

Arrsch edd/rIona( pepr(sJ es necessary, end identify the /tan drscripr(on beinp continuedJ INITIALCERTIFICATION - NOT APPLICABLE Any false statement or omission In this document, including attachments, may be subject to dvil and aimlnal sanctionL I certify under penahy of perjury that the Information in this document and attachments is true and correct.

SIGNATURE-AUTHORIZED REPRESENTATIVE TITLE DATE VICE PRESIDENT TURKEY POIiIT In accordance with 10 CF R jj 55$, Communications, this form shall be submitted to the NRC as follows:

BY MAILADDRESSED TO:

Director, Dfoce of Nudeer Reactor Regulation BY DELIVERYIN PERSON One White Flint North UA. Nudeer Regulatory Commlsdon TO THE NRC OFFICE AT:

11555 Rodrvllte Pike Weddngton, DC Ztm55 Rodtvioe, IC)

WIC FORM 41411401

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FLORIDA POWER AND OGHT COMPANY lUJKEYPOINT UNIT4 INmALSIMULATORCENlFICAllONREPORT TABLEOF CON1EN1S 1.0 Introducfion 2.0 Unit 3 vs Unit 4 Differences 2.1 Exceptions to ANSI/ANS3.5 Sfandard 2.2 Operator Training 2.3 Facility Design &Sysfems Relevanf to Control Room Personnel 24 Technical Specifications 2.5 Operating, OffNormal, and Emergency Procedures 2.6 Confrol Room Design and Insfrumentation Locations 2.7 Operafional Characterisfics

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1.0 INTRODUC11ON TURKEYPOINT UNIT4 INITIALSIMULATORCERTIFICATION REPORT Turkey Poinf Unit 4, Dockef 50-251, License DPR-41, simulafor training willbe performed using the Unif3 training simulafor.

The performance tesfs were run for Unit 3 certification.

The differences between the two unifs were evaluafed and differences which could have training impacf are identified in Secfion 2.

2.0 UNIT3 VERSUS UNIT4 DIFFERENCES 2.1 EXCEPTIONS TO ANSI ANS 3.5 STANDARD The exceptions to ANSI/ANS 3.5 noted for Unif 3 were evaluated and are considered applicable fo Unit 4.

2.2 OPERATOR TRAINING Operafor training for initiallicense classes and operafor requalification classes include differences training as part ofthe normal classroom, simulafor, and on-the-Job training. In addition, the above training segments include segments and practice on common sysfem failures and appropriafe operafor actions.

2.3 FACILITYDESIGN & SYSTEMS RELEVANTTO CONTROL ROOM PERSONNEL The Facilify Design Control Process, under which planf modifications are performed, includes reviews by several organizations within FPL. Ifis FPL policy wherever possible to confrol planf modi%cations such thaf the design similarify of Turkey Poinf Units 3 and 4 is mainfained.

The followingifems lisfthe differences identifie between Units 3 and 4 forfacility design and sysfems.

Allfhe differences were reviewed by the SCRB and it was defermined thaf none are signi%cant enough to have a negafive effect on operafor fraining or examinations.

2.3.1 ROD POSITION INDICATIONS The power supplies to the rod posifion indications are differenf between Unif 3 and Unit 4 as Unif3 uses a DC power supply and a mofor confrol cenfer where Unit4 uses a DC power supply, a motor confrol center and a lighting panel.

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TURKEYPOINT UNIT4 INITIALSIMULATORCERTIFICATION REPORT 2.3.2 RHR PUMP SUCTIONS AND DISCHARGES Unit 3 takes a sucfion on the C loop hot leg while Unif4 takes a suction on the A loop.

The alfernafe discharge forthe Unif3 pumpis loop C and the alfernafe discharge of Unif4 is loop A.

2.3.3 BORIC ACID STORAGE The 'B'torage tank and the Bafch tank are shared befween the two Unifs. The bafch tank alarms only exisf on Unif 3.

2.3.4 SAFETY INJECTION SYSTEMS Portions ofthe safety injection sysfems ofthe two unifs are shared.

For example, all four safety injection pumps (fwo for each unif) start on an Sl on either unit.

The porfions of Unif 4 needed for Unif 3 simulafion are included in the Unif 3 simulator.

Unit 4 operates similarly to Unif3 otherwise.

2.3.5 EMERGENCY CONTAINMENTCOOLER FILTERS AND FANS On a loss ofoffsife power, three ECC filters and fans start in Unif3 while only two start on Unif4.

2.3.6 SPENT FUEL PIT EXHAUSTSYSTEMS The Unit3 spent fuelpifexhausf fans exhaust fo a dedicated venf. The Unit4 fan exhausfs to the plant venf.

2.3.7 RADIATIONMONITORINGSYSTEMS Planf common areas are monitored on fhe Unit 3 side ofthe control room (and are included in the simulator).

The plant venf and liquid release radiafion monifors only alarm on Unit 3.

2.3.8 MAINSTEAM ISOLATION VALVEBACKUPAIR NITROGEN SUPPLY Unit 3 has backup nitrogen boffles for emergency closure of the MSIV's. Unif4 has had an air accumulafor insfalled to assure MSIV closure during a loss of instrument air.

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TURKEYPOINT UNIT4 INITIALSIMULATORCERTIFICATION REPORT AUXILIARYFEEDWATER PUMPS The three AFW pumps are shared between fhe two units and have power supplies forfhe supply valves from both units. Unif4 is modelled in the simulator sufficienfly to provide the correct Unif4 supplies.

GENERATOR MONITORING Unif 3 vertical board confains the moniforing cabinef for both units'ain generafors.

Unit4 has a local panel that contains a radiotrequency detecfor fo defect arcing in the generator.

This detecfor was never installed on Unif3.

MAINGENERATOR EXCITERS The Unit4 exciter has slightly quicker response characteristics and has different profection seftings than the Unit 3 exciter.

Vnif4 has no sfartup exciter current limiter.

EMERGENCY COMMUNICATIONFACILITIES The Planf Supervisor - Nuclear sfafion is common to both unifs and is provided in the simulator.

The fire horn pushbutton, fire phone, and the local government radio are on the Unit 3 side only.

The radio set used as a backup method for communicafion with FPL Load Dispafchers is in the Unif4 side ofthe control room and is not included in the Simulafor.

ELECTRICAL DISTRIBUTION Some ofthe bus backup power supplies operate slightly differently befween the unifs, and some of fhe similar loads have breaker numbers which are different.

The differences are covered in classroom or simulafor fraining as appropriate, but do not have any significant effect on fraining wifh a Vnif3 simulator.

The Unif 3 simulator has the Unif 4 buses modelled to the exfenf necessary to support Unit 3 operation including backup power supplies.

The Unit4 DC buses share some componenfs, such as baffery chargers, wifh Vnif3. The emergency diesel generators are currenfly shared between the fwo unifs. During fhe dual unit outage of 199 1, two additional EDG's willbe added and each unif willthen Page 3

TURKEYPOINT UNIT4 INITIALSIMULATORCERTIFICATIONREPORT have ifs own EDG's.

The EDG's willoperafe similarly between the units.

2.3. 14 BACKUP ELECTRIC INSTRUMENTAIR COMPRESSORS The Unif4 backup elecfric instrumenf air compressors have the same functions as Unit 3, buf one ofthe Unit4 backup compressorsis a 500 SCFM horizonfal type while the ofher Unif4 and bofh Unif3 backup compressors are 325 SCFM vertical type compressors.

2.3. 15 COMPONENT COOLING WATER HEATEXCHANGERS The Unit4 CC Wheat exchangers have a local digifalfemperafure readout panel which was not installed on Unif3.

2.3. 16 WASTE DISPOSAL The Wasfe Disposal system is shared by the two units for fhe most part.

Those componenfs which are unif speci%c operafe similarly between the two units.

2.3. 17 METEOROLOGICAL RECORDERS The mefeorological recorders are only on Unit 3 and are included in the simulafor.

2.3.18 TURBINE RUNBACKSELECTOR SWITCH The Turbine Runback Selecfor Swifch on Unif 4 does not have a keylock as it does on Unit 3.

2.3.19 MISCELLANEOUSANNUNCIATORS The Breathing AirSysfem Trouble, Confro! Room Chiller Trouble and the Demin System Trouble alarms are only on Unif 3.

The Fire Damper Closed alarm is only on Unit 4.

2.3.20 LOOP RTD BYPASS LINELOW FLOW ALARM Page 4

TURKEYPOINT UNIT4 INITIALSIMULATORCERTIFICATION REPORT The Unit 4 "B"loop RTD bypass line experienced lower flow conditions than the other bypass linesin both units. An analysis was done and the alarm setpoint for this bypass line was reduced from 175 gpm to 145 gpm. Allthe other 5 loops in the two units have remained at the 175 gpm setpoint.

2.3.21 ALTERNATESHUTDOWN PANELS ASP Each unit has its own alternate shutdown panel.

Only the Unit3 ASPis modelled but only minor differences exist between the two units'SPs so that the Unit 3 simulator can be used to train for Unit 4 ASP operations.

2.4 TECHNICALSPECIFICATIONS The Turkey Point Technical Speci%cations are common forboth Units 3 and 4 with a few minor exceptions to account for differences in unit operation since construction.

For example, the pressure temperature limitcurves ofSection 3.1 are unit specific due to differencesin initialconstruction and neutron irradiation of the two reactor vessels.

No differences exist which would affect simulator training. In addition, itis FPL policy to maintain the Technical Specifications as similar as possible, within the limits of actual design and operation, in order to facilitate plant operation.

2.5 OPERATING OFF-NORMAL AND EMERGENCY PROCEDURES Due to the similarity of the two units, there are minimal differences in the Operating Procedures, Off-Normal Operating Procedures, and Emergency Operating Procedures between the two units. No differences exist which would negatively affect simulator training.

2.6 CONTROL ROOM DESIGN AND INSTRUMENTATIONLOCATIONS The Turkey Point main control room serves as the control room for both units 3 and 4. The Unit 3 benchboards and vertical panels are located on the left hand side of the Plant Supervisor - Nuclear (PS-N) office.

The Unit 4 main control benchboards are a duplicate ofthe Unit3 benchboards and are located on the right hand side ofthe Plant Supervisor - Nuclear (PSN) office. The Unit4 vertical boards are similarly offset to the right of the PSN's office, but the boards are Page 5

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TURKEYPOINT UNIT4 INITIALSIMULATORCERTIFICATIONREPORT rofafed to enclose the front and right side of fhe confrol room.

The Ieff-right relationship of the panels is maintained from one unif fo the ofher.

There is a common annunciator

panel, designated the "X panel, which confains annunciafors common to bofh unifs. This panel is included in fhe Unif3 simulafor.

Other panels which are different befween the units are fhe confrol room ventilafion panel which is on the Unif4 side of the main control room, and fhe area radiation moniforing panel which is only on the Unit 3 side of fhe main confrol room.

The confrol room venfilafion panel Is included in fhe Unif 3 simulator, buf is locafed in a small room adjacent to fhe simulafor which is nof in the actual plant confrol room.

This room also confains the simulated Unif 3 alfemafe shutdown panel and the reactor coolant pump vibrafion monifor cabinef for bofh units.

The common fire alarm panel is located between the units at the back ofthe confrol room in the plant.

The same panel is located in ifs same position in the slmulafor and it is included in the simulafion.

2.7 OPERATIONAL CHARACTERISTICS Due to the almosf identical design and operafion of Units 3 and 4, there are no significant operafional differences and no differences in operafional characteristics which would negafively affect operator training.

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I.