ML20212E903
| ML20212E903 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/30/1999 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20212E901 | List: |
| References | |
| NUDOCS 9909270182 | |
| Download: ML20212E903 (31) | |
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i FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 PLANT REFERENCE SIMULATOR FOUR-YEAR SIMULATOR CERTIFICATION REPORT SEPTEMBER 1995 - SEPTEMBER 1999 l
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I TABLE OF CONTENTS
1.0 INTRODUCTION
. . . . . . . . . . . . . . . . . 3 2.0 SIMULATOR TESTING . . . . . . . . . . . . . . . 3 2.1 - Testing Exceptions . . . . . . . . . . . . . . . . . 4 2.2 Test Schedule . . . . . . . . . . . . . . . . . . 5 2.3 Test Results . . . . . . . . . . . . . . . . . . . 5 2.4 Test Changes since Last Submittal . . . . . . . . . . . . . 5 3.0 SIMULATION SCOPE . . . . . . . . . . . . . . . 5 3.1 Major Control Room Changes . . . . . . . . . . . . . 6 3.2 Instructor Facility Changes . . . . . . . . . . . . . . 7 4.0 SIMULATOR DISCREPANCY RESOLUTION PROGRAM . . . . . 7 4.1 Trouble Reports . . . . . . . . . . . . . . . . . 7 APPENDICES / TABLES / ATTACHMENTS Appendix A Completed Performance Tests 1996-1999 Appendix B Performance Test Schedule 2000-2003 Appendix C Plant Modifications Implemented on the Simulator since the Last Submittal Appendix D Plant Modifications Requiring Implementation on the Simulator Appendix E Open Simulator Trouble Reports .
Appendix F Priority X Trouble Reports Table l' Simulator Initial Conditions Attachment 1 Terminology and Definitions I
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1.0 INTRODUCTION
The information contained in this report is provided to demonstrate compliance of the Crystal l
River Unit 3 (CR-3) Simulator with the requirements of 10CFR55.45 (b)(5)(ii) and 10CFR55.45 (b)(5)(vi).
The Crystal River Unit 3 Simulator continues to meet the applicable requirements of ANS/ ANSI-
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3.5 (1985), as endorsed by. Regulatory Guide 1.149.
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Since the initial certification in September 1991, the CR-3 simulator has been used continually .
for various licensed and non-licensed training programs at CR-3. Simulator fidelity is high based on the absence of performance test failures, an aggressive plant modification incorporation program, a manageable Trouble Report backlog, and positive operator / instructor feedback.
2.0 SIMULATOR TESTING l Appendix A lists, by year, all Performance Tests completed during the last four years. The following information is provided to show the correlation between the CR-3 Performance Tests / rest Numbers and the testing requirements identified in ANS/ ANSI-3.5 (1985):
The tests identified in Appendix B, Section B.2.2," Transient Performance", of the ANS/ ANSI-3.5 Standard are performed annually and designated PTTI through PTT10.
The test identified in Appendix B, Section B.2.1," Steady State Performance", of the
- ANS/ ANSI-3.5 Standard is performed annually and designated PTSI.
- The test identified in Appendix A, Section A.3.1," Computer Real Time Test", of the ANS/ ANSI-3.5 Standard is performed annually and designated PTCl.
The' tests identified in Section 3.1.1," Normal Plant Evolutions", of the ANS/ ANSI-3.5 Standard are performed every four years and designated PTN1 through PTN7 as follows:
- PTN 1 includes 3.1.1 (1) Plant startup - cold to hot standby; 3.1.1 (2) Nuclear startup from
, hot standby to rated power; 3.1.1 (3) Turbine startup and generator synchronization: and
- . 3.1.1 (5) Operation at Hot Standby, l
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- PTN2 corresponds to 3.1.1 (4) Reactor trip followed by recovery to rated power.
- PTN3 corresponds to 3.1.1 (6) Load changes.
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. FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 PLANT REFERENCE SIMULATOR FOUR-YEAR SIMULATOR
, . CERTIFICATION REPORT e PTN4 corresponds to 3.1.1 (7) Startup, shutdown and power operations at less than full L
reactor coolant flow.
- PTN5 corresponds to 3.1.1 (8) Plant shutdown from rated power to hot standby and cooldown to cold shutdown conditions.
i e PTN6 corresponds to 3.1.1 (9) Core performance testing.
e PTN7 corresponds to 3.1.1 (10) Operator conducted surveillance testing on safety-related equipment or systems. Additional surveillance testing is also conducted as part of normal plant evolutions such as plant heatup, cooldown and power escalation.
Each type of generic malfunction identified in' Section 3.1.2, " Plant Malfunctions" of the ANS/ ANSI-3.5 standard is included in the Performance Test Base. These tests are performed every four years and designated PTM1 A1 through PTM24B. At least one Performance Test per malfunction type is performed. In many cases, it has been determined that more than one test -
should be performed to demonstrate either simulator capabilities or to replicate an actual plant transient.
2.1 . TESTING EXCEPTIONS The Crystal River Unit 3 Simulator continues to meet the testing requirements of ANS/ ANSI-3.5 (1985). The following sections of ANS/ ANSI-3.5 are not applicable to CR-3:
- Section 3.1.2," Plant Malfunctions", Item (12) Control rod failure includes drifling rods.
' Rationale: The design of the CR-3 control rod drive system precludes drifting rods; this item has hem. replaced by degraded rod motion which results in a decrease in control rod drive speed of 25%. !
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- Section 3.1.2, " Plant Malfunctions", Item (25) Reactor pressure control system failure )
including turbine bypass failure (BWR). Rationale: This item is only required for Boiling l Water Reactors; CR-3 is a Pressurized Water Reactor (PWR).
l e Section 4.1, " Steady State Operation", Item (2) Principal mass and energy balances shall be satisfied; (b) Reactor coolant system temperature to steam generator pressure and (e) Mass balance of steam generator. Rationalei These items are not applicable to Babcock and j Wilcox Plants with Once-Through Steam Generators (OTSGs). !
e' Section 4.1, " Steady State Operation", Item (3) (f) Recirculation flow. Rationale: This item is only applicable to Boiling Water Reactors; CR-3 is a Pressurized Water Reactor.
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,. FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 PLANT REFERENCE SIMULATOR FOUR-YEAR SIMULATOR
. . CERTIFICATION REPORT
- Appendix B, Section B2,"PWR Simulator Operability Test". Rationale: Several subsections of the section require recording pressurizer pressure as a critical parameter. Since Babcock and Wilcox Plants do not monitor this parameter, narrow range Reactor Coolant System (RCS) pressure has been sub~stituted.
2.2 TEST SCHEDULE The scope of the performance testing to be conducted over the next four-year certification cycle is similar to that conducted over the last four years and that used to conduct initial certification testing. The schedule for conducting these performance tests is contained in Training Department Procedures and the CR-3 Simulator Configuration Management System as part of the Performance Test database. A copy of the schedule is included as Appendix B of this report.
The schedule ensures that all tests specified in Appendix B, Section B2 of ANS/ ANSI-3.5 will be performed annually, that approximately 25% of all the other performance tests will be tested annually, and that all performance tests will be performed at least once over the next four-year i cenification cycle. l l
2.3 TEST RESULTS l Performance Tests scheduled to be conducted during this four-year certification cycle (1996-1999) have been successfully completed per written acceptance critcria. I i
2.4 TEST CHANGES SINCE LAST SUBMITTAL Although a number of the performance tests have undergone revision for editorial corrections, I plant modifications, or plant procedure changes, there have been no changes which alter the intent of the test. In addition, there have been no deletions to the scope of testing identified in the pervious four-year certification submittal.
3.0 SIMULATION SCOPE
- Plant modifications are evaluated for simulator impact, tracked until they are declared in-service l at the plant, and subsequently incorporated on the simulator in accordance with applicable FPC
' Nuclear Operations Training Department Procedures and Simulator Operating Instructions. For modifications that have significant training impact, the incorporation of the modification on the simulator is frequently done ahead of the plant installation. However, the simulator change package is not closed until the simulator is verified to be like the plant as-built modification.
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, , CERTIFICATION REPORT Appendix C lists the plant modifications that have been implemented on the simulator since the last four-year certification submittal. Note: Attachment 1 has been included to clanfy terminology associated with Appendices C-F.
- The last four-year certification submittal included a list of three mndifications installed in the plant but not implemented on the simulator within the ANS/ ANSI-3.5 one-year window.
These modifications (MAR 90-02-03-01 Replacement of the Emergency Dose Assessment System, MAR 91-05-03-02 Hydrogen Purge System Redundancy, and MAR 93-06-16-01 Install Gammametric Nuclear Instrumentation Channels NI 14/15) have since been implemented.
Appendix D lists the in-service plant modifications that remain to be implemented on the ;
simulator. These modifications have insignificant training impact and will be incorporated on ;
the simulator within one year of their declared plant in-service date.
3.1 MAJOR CONTROL ROOM CHANGES 3.1.1 Control Room Physical Arrangement The CR-3 main control room underwent significant remodeling and sound suppression modification. The operator desks were changed and rearranged. The Nuclear Shift Supervisor (NSS) and Nuclear Shift Manager (NSM) common seating area was elevated for improved visibility. Emergency lighting was added to the rear sections of the main control panel. The simulator was modified to be consistent with these main control room changes.
3.1.2 Panels / Equipment The following changes to the CR-3 simulator panels were made to replicate main control room modifications: i e Two N-16 monitors (RMG-26 & 27) were added to improve small OTSG tube leak detection.
. The Plant Process Computer (PPC) has been replaced with a PC based Plant Information Computer System (PICS). This included replacing Recall (for post transient analysis) and
! Safety Parameter Display System (SPDS).
l e The replacement of a Reactor Coolant Pump (RCP-1 A) resulted in the removal of the AC lift
! oil pump from the ICS section of the main control board.
. The old Foxboro batch controller was replaced with a new digital controller.
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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3
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- Improved Accuracy Digital Dixon meters were added for High Pressure Injection (HPI) low flow, Low Pressure Injection (LPI) flow, Emergency Feedwater Pump flow, Reactor Coolant System (RCS) low pressure, LPI crossflow, Borated Water Storage Tank (BWST) narrow range level, and Emergency Diesel Generator (EDG) load.
3.2 INSTRUCTOR FACILITY CHANGES I
3.2.1 Initial Conditions '
The last four-year certification submittal contained a list of the eight (8) initial conditions that are permanently maintained. However, during the last four-years the scope of simulator training has been broadened such that two permanently maintained initial conditions have been added, i bringing the number of permanent initial conditions up to ten (10). These ten initial conditions l include a variety of plant operating conditions, fission product poison concentrations and times in l core life (see Table 1). All pre-planned training / examination scenarios can be initiated from these ten controlled initial conditions or from scenario specific storepoints derived from the ten controlled initial conditions. Additionally, CR-3 simulator initial condition storage capability was increased from seventy-two (72) to one hundred (100) initial conditions.
3.2.2 Background Workstations FPC has installed five (5) background workstation / server computer pairs. The five background computer systems provide a development environment for the instructors, a test facility for the simulator support staff, and can also be used in the classroom as a Classroom Simulator.
4.0 SIMULATOR DISCREPANCY RESOLUTION PROGRAM Performance anomalies, physical fidelity discrepancies, and hardware problems within the existing scope of simulation are identified through simulator Trouble Reports (TRs).
4.1 TROUBLE REPORTj Once a Trouble Report is v ritten, correction of the problem, testing of the resolution, and documentation of the correction are conducted in accordance with applicable FPC Nuclear Operations Training Department Procedures and Simulator Operating Instructions. Appendix E lists the open Simulator Trouble Reports at the time of this report.
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- . FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 PL. ANT REFERENCE SIMULATOR FOUR-YEAR SIMULATOR l , ,
CERTIFICATION REPORT Currently, there are no outstanding Trouble Reports written against acceptance criteria .for Performance Tests conducted during this four-year certification period. Additionally, all TRs previously identified on the last four-year certification submittal have been resolved, including two (TR-127.4, Hot Leg level recorder response during a LOCA and TR-1319, PPC incorrect power supply dependency) which had minor impact on Performance Tests.
I A new priority for a Trouble Report has been added: priority X. A Trouble Report is given an X ;
priority when after close inspection the problem cannot be business justified as requiring i resolution. The decision to assign priority X is typically based on a combination of high resource investment to resolve the problem coupled with low or no training value. Priority X Trouble i Reports also can be used to disposition minor physical fidelity differences between the simulator j and the reference plant. Appendix F lists all Priority X Trouble Reports at the time of this report, i i
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FLORIDA POWER CORPORATION E . CRYSTAL RIVER UNIT 3 i- PLANT REFERENCE SIMULATOR L FOUR-YEAR SIMULATOR L .
, . CERTIFICATION REPORT l
L ^ Appendix A L
Completed Performance Tests 1996-1999 l TEST TEST TITLE . 1996 1997 1998 1999 L NUMBER L. PTN1- PLANT STARTUP- MODE 5 TO FULL POWER X PTN2 REACTOR TRIP AND RECOVERY TO FULL POWER X i
PTN3 LOAD CHANGES AT POWER X PTN4 3 RCP STARTUP/ SHUTDOWN / POWER OPERATIONS X PTN5 PLANT SHUTDOWN AND COOLDOWN X PTN6 CORE PERFORMANCE TESTING X PTN7 SURVEILLANCE TESTING X PTSI STEADY STATE PERFORMANCE TEST X X X X PTCl COMPUTER REAL TIME TEST X .
X X X l PTTI REACTOR TRIP X X X X
[ PTT2 TOTAL LOSS OF FEEDWATER X X X X PTT3 SIMULTANEOUS CLOSURE OF ALL MSIVs X X X X PTT4- LOSS OF OFFSITE POWER FROM FULL POWER X X X X PTT5 REACTOR COOLANT PUMP TRIP X X X X l~
PTT6- MAIN TURBINE TRIP X X X X PTT7- MAXIMUM RATE POWER RAMP X X X X PTT8 LARGE DREAK LOCA (DBA) X X X X l PTT9 MAIN STEAM LINE BREAK INSIDE CONTAINMENT X X X X PTT10 PORY FAILURE WITH HPI INOPERABLE X X X X PTM1A1 STEAM GENERATOR TUBE LEAK X PTM1A2. STEAM GENERATOR TUBE RUPTURE X PTM1B LETDOWN LEAK DOWNSTREAM OF MUV-49 X- ;
PTMICI REPRESSURIZING SMALL BREAK LOCA X j PTMIC2 SMALL BREAK LOCA X PTMIC3 SMALL BREAK LOCA/ EPI INOPERABLE X PTM1D PRESSURIZER SAFETY VALVE FAILURE X PTM2 LOSS OF INSTRUMENT AIR X ;
PTM3A LOSS OF OFFSITE POWER (LOW DECAY HEAT) X X
PTM3B1 LOSS OF EMERG. OFFSITE SOURCE PTM3B2 LOSS OF EMERG. OFFSITE SOURCE /EDG FAILURE X 1of4 i p
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Completed Performance Tests 1996-1999 -
TEST. TEST TITLE 1996 1997 1998 1999 NUMBER PTM3Cl LOSS OF NNI-Y t24 VDC X PTM3C2 LOSS OF NNI-Y 120 VDC X PTM3D1 LOSS OF ICS DC POWER X PTM3D2 LOSS OF ICS AC POWER X PTM3E LOSS OF VITAL BUS X PTM3F LOSS OF 480 VAC ES BUS A X PTM3G LOSS OF DC DISTRIBUTION X PTM4A REACTOR COOLANT PUMP SHAFT SHEAR X PTM4B LOSS OF 2 RCPS X PTM4C REACTOR COOLANT PUMP SEAL FAILURE X PTM4D REACTOR COOLANT PUMP LOCKED ROTOR X PTM5A LOSS OF CONDENSER VACUUM X PTM5B LOSS OF CONDENSER LEVEL CONTROL X PTM6A LOSS OF NUCLEAR SERVICES RAW WATER X PTM6B LOSS OF CIRCULATING WATER X PTM6C LOSS OF DECAY HEAT RAW WATER X PTM6D. PARTIAL LOSS OF CIRCULATING WATER - X PTM7 LOSS OF DECAY HEAT REMOVAL X PTM8A LOSS OF NSCCC X PTM8B LOSS OF SSCCC X PTM8C LOSS OF DHCCC X-PTM9A MAIN FEEDWATER PUMP TRIP AND RUNBACK X PTM9B LOSS OF BOTH MAIN FEEDWATER PUMPS X PTM9C OTSG OVERFILL X PTM9D LOSS OF BOTH CONDENSATE PUMP X PTM10 TOTAL LOSS OF FEEDWATER X PTM11 A LOSS OF RPS +15V CABINET POWER SUPPLY X PTM1IB FAILURE OF ES CABINET POWER SUPPLY X PTM12A MECHANICALLY STUCK ROD X PTM12B . UNCOUPLED ROD X 2 of 4
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Appendix A (Continued) l Completed Performance Tests 1996-1999 TEST TEST TITLE 1996 1997 1998 1999 NUMBER !
PTM12C DEGRADED ROD MOTION X I PTM12D DROPPED CONTROL ROD X l X
PTM13 INABILITY TO DRIVE CONTROL RODS PTM14A , HIGH RCS ACTIVITY X PTM14B WASTE GAS DECAY TANK LEAK X l PTM16 MAIN GENERATOR TRIP X PTM17A CONTROL ROD OUT INHIBIT FAILURE X PTM17B CONTROL ROD GROUP COMMAND ENABLE FAILED X PTM17C FAILURE OF THE MAIN TURBINE TO TRIP X l PTM17D ATMOSPHERIC DUMP VALVE FAILURE X I PTM17E TURBINE BYPASS VALUE FAILURE X PTM17F CONTINUOUS ROD WITHDRAWEL X PTM17G DILUTION ACCIDENT X PTM18A MAKEUP PUMP TRIP X !
PTM18B PRESSURIZER LEVEL CONTROL VALVE FAILURE X ;
PTM18C LETDOWN ISOLATON VALVE FAILURE X j PTM18D PRESSURIZER HEATER CONTROLLER FAILURE X !
PTM18E PRESSURIZER SPRAY VALVE FAILURE X I PTM18F RCS NR PRESSURE TRANSMITTER FAILURE X -l PTM20A MAIN STEAM LINE BREAK OUTSIDE CONTAINMENT X l PTM20B MAIN STEAM LINE BREAK INSIDE CONTAINMENT X PTM20C MAIN FEED LINE BREAK OUTSIDE CONTAINMENT X PTM21 A - POWER RANGE CHANNEL FAILURE X l PTM21B INTERMEDIATE RANGE CHANNEL FAILURE X PTM21C SOURCE RANGE CHANNEL FAILURE X l PTM22A RCS THOT TRANSMITTER FAILURE X PTM22B RCS TCOLD TRANSMITTER FAILURE X 1 PTM22C MAIN FW FLCW TRANSMITTER FAILURE X PTM22D OTSG OP RANGE LEVEL TRANSMITTER FAILURE X PTM22E ICS RUNBACK FAILURE X 3 of 4
r 1 FLORIDA POWER CORPORATION l^ CRYSTAL RIVER UNIT 3 i PLANT REFERENCE SIMULATOR I FOUR-YEAR SIMULATOR CERTIFICATION REPORT Appendix A (Continued) ,
Completed Performance Tests 1996-1999 l
TEST TEST TITLE 1996 1997 1998 1999 i NUMBER PTM22F ICS HEADER PRESSUIE BIAS FAILURE X PTM?'.G MAIN FW TEMPERATURE FAILURE X PTM22H FAILURE OF ICS TO TRANSFER TO TRACK X PTM22I REACTOR DEMAND SIGNAL FAILURE X PTM22J SELECTED TAVE FAILURE X ,
PTM23A MS ISOLATION ACTUATION FAILURE X I PTM23B MFWISOLATION ACTUATION FAILURE X PTM23C ES CHANNEL FAILURE TO ACTUATE HPI X PTM23D ES CHANNEL FAILURE TO ACTUATE RBl&C X PTM23E EFIC AUTO ACTUATION FAILURE X PTM24A ATWS (NO OPERATOR INTERVENTION) X PTM24B ATWS (OPERATOR INTERVENTION) X I f
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, FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 PLANT REFERENCE SIMULATOR i FOUR-YEAR SIMULATOR l CERTIFICATION REPORT Appendix B Performance Tests Schedule 2000-2003 I TEST TEST TITLE 2000 2001 2002 2003 NUMBER PTN1 PLANT STARTUP- MODE 5 TO FULL POWER X ;
PTN2 REACTOR TRIP AND RECOVERY TO FULL POWER X l PTN3 LOAD CHANGES AT POWER X l PTN4 3 RCP STARTUP/ SHUTDOWN / POWER OPERATIONS X PTN5 PLANT SHUTDOWN AND COOLDOWN X l PTN6 CORE PERFORMANCE TESTING X PTN7 SURVEILLANCE TESTING X PTSI STEADY STATE PERFORMANCE TEST X X X X PTCl COMPUTER REAL TIME TEST X X X X PTTI REACTOR TRIP X X X X PTT2 TOTAL LOSS OF FEEDWATER X X X X PTT3 SIMULTANEOUS CLOSURE OF ALL MSIVs X X X X PTT4 LOSS OF OFFSITE POWER FROM FULL POWER X X X X PTT5 REACTOR COOLANT PUMP TRIP X X X X PTT6 MAIN TURBINE TRIP X X X X PTT7 MAXIMUM RATE POWER RAMP X X X X PTT8 LARGE BREAK LOCA (DBA) X X X X PTT9 MAIN STEAM LINE BREAK INSIDE CONTAINMENT X X X X PTT10 PORV FAILURE WITH HPI INOPERABLE X X X X a PTM1A1 STEAM GENERATOR TUBE LEAK X PTM1A2 STEAM GENERATOR TUBE RUPTURE X PTMlB LETDOWN LEAK DOWNSTREAM OF MUV-49 X ;
PTMICl REPRESSURIZING SMALL BREAK LOCA X l PTMIC2 SMALL BREAK LOCA X PTMIC3 SMALL BREAK LOCA/HPI INOPERABLE X PTM1D PRESSURIZER SAFETY VALVE FAILURE X PTM2 LOSS OF INSTRUMENT AIR X l PTM3A LOSS OF OFFSITE POWER (LOW DECAY HEAT) X PTM3B1 LOSS OF EMERG. OFFSITE SOURCE X PTM3B2 LOSS OF EMERG. OFFSITE SOURCE /EDG FAILURE X 1of4 l
, FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 PLANT REFERENCE SIMULATOR FOUR-YEAR SIMULATOR CERTIFICATION REPORT Appendix B (Continued)
Performance Tests Schedule 2000-2003 TEST TEST TITLE 2000 2001 2002 2003 NUMBER PTM3Cl LOSS OF NNI-Y 124 VDC X PTM3C2 LOSS OF NNI-Y 120 VDC X PTM3D1 LOSS OF ICS DC POWER X PTM3D2 LOSS OF ICS AC POWER X PTM3E ~ LOSS OF VITAL BUS X PTM3F LOSS OF 480 VAC ES BUS A X PTM3G LOSS OF DC DISTRIBUTION X PTM4A REACTOR COOLANT PUMP SHAFT SHEAR X PTM4B LOSS OF 2 RCPS X.
PTM4C REACTOR COOLANT PUMP SEAL FAILURE X PTM4D REACTOR COOLANT PUMP LOCKED ROTOR X PTM5A LOSS OF CONDENSER VACUUM X PTM5B- LOSS OF CONDENSER LEVEL CONTROL X )
PTM6A- LOSS OF NUCLEAR SERVICES RAW WATER X PTM6B LOSS OF CIRCULATING WATER X PTM6C LOSS OF DECAY HEAT RAW WATER X
) PARTIAL LOSS OF CIRCULATING WATER X I(TM6D fM7 LOSS OF DECAY HEAT REMOVAL X PTM8A LOSS OF NSCCC X :
PTM8B LOSS OF SSCCC X l PTM8C LOSS OF DHCCC X PTM9A MAIN FEEDWATER PUMP TRIP AND RUNBACK X PTM9B LOSS OF BOTH MAIN FEEDWATER PUMPS X PTM9C OTSG OVERFILL- X j PTM9D LOSS OF BOTH CONDENSATE PUMP X PTM10 TOTAL LOSS OF FEEDWATER X :
PTMll A . LOSS OF RPS +15V CABINET POWER SUPPLY X !
PTM11B ' FAILURE OF ES CABINET POWER SUPPLY X PTM12A MECHANICALLY STUCK ROD X i PTM12B UNCOUPLED ROD - X i
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Performance Tests Schedule 2000-2003 TEST TEST TITLE 2000 2001 2002 2003 NUMBER PTM12C DEGRADED ROD MOTION X PTM12D DROPPED CONTROL ROD X PTM13 INABILITY TO DRIVE CONTROL RODS X PTM14A HIGH RCS ACTIVITY. X PTM14B WASTE GAS DECAY TANK LEAK X PTM16 MAIN GENERATOR TRIP X PTM17A CONTROL ROD OUT INHIBIT FAILURE X PTM17B CONTROL ROD GROUF nMMAND ENABLE FAILED X PTM17C FAILURE OF THE MAIN 2 tJRBINE TO TRIP X PTM17D ATMOSPHERIC DUMP VALVE FAILURE X PTM17E TURBINE BYPASS VALUE FAILURE X PTM17F CONTINUOUS ROD WITHDRAWEL X PTM17G DILUTION ACCIDENT X PTM18A MAKEUP PUMP TRIP X PTM18B PRESSURIZER LEVEL CONTROL VALVE FAILURE X PTM18C LETDOWN ISOLATON VALVE FAILURE X PTM18D - PRESSURIZER HEATER CONTROLLER FAILURE X PTM18E PRESSURIZER SPRAY VALVE FAILURE X PTM18F RCS NR PRESSURE TRANSMITTER FAILURE X PTM20A MAIN STEAM LINE BREAK OUTSIDE CONTAINMENT X PTM20B MAIN STEAM LINE BREAK INSIDE CONTAINMENT X PTM20C MAIN FEED LINE BREAK OUTSIDE CONTAINMENT X PTM21A POWER RANGE CHANNEL FAILURE X PTM21B INTERMEDIATE RANGE CHANNEL FAILURE X PTM21C SOURCF D ANGE CHANNEL FAILURE X PTM22A RCS ThM TRANSMITTER FAILURE X PTM22B RCS TCOLD TRANSMITTER FAILURE X PTM22C MAIN FW FLOW TRANSMITTER FAILURE X PTM22D OTSG OP RANGE LEVEL TRANSMITTER FAILURE X PTM22E ICS RUNBACK FAILURE X 3 of 4
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. Appendix B (Continued)
!- Performance Tests Schedule 2000-2003 i TEST TEST TITLE 2000 2001 2002 2003 NUMBEP.
PTM22F ICS HEADER PRESSURE BIAS FAILURE X
, PTM221 REACTOR DEMAND SIGNAL FAILURE X I PTM22J SELECTED TAVE FAILURE X PTM23A MS ISOLATION ACTUATION FAILURE X PTM23B MFWISOLATION ACTUATION FAILURE X PTM23C ES CHANNEL FAILURE TO ACTUATE HPI , X PTM23D ES CHANNEL FAILURE TO ACTUATE RBl&C X PTM23E EFIC AUTO ACTUATION FAILURE X ,
PTM24A ATWS (NO OPERATOR INTERVENTION) X l PTM24B ATWS (OPERATOR INTERVENTION) X f i
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FOUR-YEAR SIMULATOR J CERTIFICATION REPORT Appendix C i
Plant Modifications Implemented on the Simulator since the Last Submittal l
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I 5 5 6 7 5 5 2 8 1 5 5 5 9 9 2 5 2 7 2 5 3 5 6 1 3 3 6 7 5 1 5 5 5 5 5 S 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 0 1 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 L
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Open Simulator Trouble Reports I
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O B N I OM S P N R H I H N O C L F N F MG T O D N P O T F S D / Y A A A N S 6 L N T I T P E U R , O P E O I I E I D A E U B M F W P 1 E T D S D / A T T N P L R S S S W N G T L O A L H S A T L - E R S L O C O I K T L Y N / A G_ N B B N IA S D N F E W L D C U S Y R O A L I S A C E R E A A H D A & C C T S 0 N E P E O I L U T E P P E E F A L O S T R T W R N A P U A D B U P H M B S I N L O R B B P M S T O D - O 2 -Y N P I H R 2 P E A S S A O N I E O G D A A U E E R T C N R L S E E L T E 5 R L O B V T N 1 T O R L W 6 G R E E S P R O T Y S P O R M - E C M R E I R L - E R B P 91 N I T E V E W E T T P F L C S G N R 3 D U L G S E E P S T E O C F W O G F P E C A N I N
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1 FLORIDA POWER CORPORATION.
CRYSTAL RIVER UNIT 3 PLANT REFERENCE SIMULATOR FOUR-YEAR SIMULATOR
, , CERTIFICATION REPORT l
! Appendix F )
l Priority X Trouble Reports l
l 4
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l, FLORIDA POWER CORPORATION l CRYSTAL RIVER UNIT 3 I PLANT REFERENCE SIMULATOR l FOUR-YEAR SIMULATOR CERTIFICATION REPORT l TABLE 1 SIMULATOR INITIAL CONDITIONS CORE RCS RCS POWER IC# AGE TEMP PRESS LEVEL DESCRIPTION 1 MOL 579 2155# 100 % Full Power, Steady State, Middle of Core Life 2 BOL 579 .2155# 100 % Full Power, Steady State, Beginning of Core Life 3 EOL 579 2155# 100 % Full Power, Steady State, End of Core Life 4 MOL 579 2155# 75 % Recent Power Decrease, Xenon Increasing 5 MOL 579 2155# 45 % One MFW Pump Operation, MFW Block Valves Closed 6 MOL 579 '2155# 20% Turbine Ready to Synchronize to Grid 7 MOL 536 2155# 0% Mode 3, Safety Rods out, Ready for Reactor Startup 8 MOL 115 50# 0% Mode 5, Press Steam Bubble, Condenser Vacuum, MUP 9 MOL 120 20# 0% Mode 5, Cold Iron, Secondary Secured 10 MOL 555 2155# 10 % Ready to Roll Turbine l
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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 PLANT REFERENCE SIMULATOR FOUR-YEAR SIMULATOR CERTIFICATION REPORT Attachment 1 Terminology and Definitions This attachment is provided to clarify terminology used in this report (Appendices C through F).
SOURCE DOCUMENT - a document that identifies or describes a change to the reference plant design or operation.
TROUBLE REPORT (TR) - a document which identifies a discrepancy between the simulator performance / appearance and the reference plant as defined by the existing simulator design database.
IN-SERVICE DATE - the date the modification is formally turned over to Operations personnel.
IMPACT - Source Documents and Trouble Reports are evaluated for their impact on simulator software (S) and/or hardware (H).
FINAL EVAL DATE -The date that the Source Document is formally evaluated against the existing simulator configuration to determine impact.
SIMULATOR DATE - The date that the simulator change (if required) is formally accepted on the simulator by virtue of an acceptance test by the Simulator Test Opea, : oclear Operations Instructor, or designee.
FINAL EVAL FLOAT DAYS - Final Evaluation of a Source Documents shall be completed within 12 months of the in service date at the reference plant.
SIM INSTALL FLOAT DAYS - Implementation of required changes to the simulator shall be completed within 12 months of the in-service date or 12 months of the Final Evaluation date (whichever is later).
CHANGE CONTROL NUMBER (CCN)- A unique 6 digit numeric designator assigned to track impact on the simulator configuration. A CCN is auto-assigned by the Simulator Configuration Management System whenever a Source Document is determined to have impact or a Trouble Report is written.
SW/HW ASSIGNEE - the initials of the simulator support staff member who has resolution responsibilities for a particular CCN " software" or "hardwae" activity.
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