ML17354B189
| ML17354B189 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 11/09/1998 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17354B187 | List: |
| References | |
| NUDOCS 9811180151 | |
| Download: ML17354B189 (55) | |
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~ ~ oo, SIMULATOR CERTIFICATIONUPDATE 0 2 98iii80i5i
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Plant-Referenced. Simulator Certification Report Turkey Point Units 3 and 4
FLORIDAPOWER ANDLIGHTCOMPANY TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 TABLEOF CONTENTS
1.0 INTRODUCTION
2.0 SIMULATORTESTS COMPLETED (1995 - 1998) 2.1 1995 TESTS 2.2 1996 TESTS 2.3 1997 TESTS 2.4 1998 TESTS 3.0 CERTIFICATIONTEST CHANGES (1999 - 2002) 3.1 CHANGES 3.2 DELETION S 3.3 ADDITIONS 4.0 FOUR YEARTEST PLAN(1999 - 2002) 5.0 OUTSTANDINGDISCREPANCIES APPENDIXA TESTABSTRACTS A.l TESTS ADDED A.2 TESTS CHANGED APPENDIXB TEST MATRICIES
TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2
1.0 INTRODUCTION
In accordance with the requirements of 10 CFR 55.45 (bX5Xii)and (bX5Xvi),this report is submitted for the Turkey Point Unit 3 Simulator. Turkey Point Unit 4 training willbe performed using the Unit 3 Training Simulator. Changes to the test plan as described in this update do not change the basis for the Unit 4 certification. The diQerences between Unit 3 and Unit 4 were reviewed by the Simulator Configuration Review Board (SCRB)'nd itwas determined. that none willhave a negative aQect on operator training or examinations.
This report presents the information required to be submitted on a four year cycle per the referenced sections of 10 CFR 55.45. Included herein are the certification tests completed during the previous four years, outstanding Simulator Discrepancy Reports (DR's), and the schedule for completion ofthese DR's.
Experience gained during initialcertification testing and the testing during the last four year cycle, changes to the plant, and the availability ofplant data have resulted in some changes to the plan. The changes made to the test plan for the next four year cycle are presented along with a discussion ofthe basis for the changes.
The changes in the plan are organized into the followingthree categories:
Changes, Deletions, and Additions. Ten tests have been changed, three tests have been deleted, and two tests have been added.
Changes to the Turkey Point Simulator test plan have been reviewed and approved by the SCRB.
The certification test plan is presented for each ofthe next four years and the abstracts for the tests that have been added or changed are included in Appendix A.
'he Turkey Point SCRB was established by administrative procedure O-ADM-305, Simulator Con6guration Management.
The SCRB provides overall control and direction of changes to the Simulator. The SCRB also reviews and approves the Certification test program and test results. Membership on the SCRB is selected per the guidelines ofthe Institute ofNuclear Plant Operations, "Simulator Configuration Management System,"
INPO 87-016, August 1987.
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TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 2.0 SIMULATORTESTS COMPLETED (1995 - 1998) 2.1 1995 TESTS TE T¹ TE TDE IPTI MPLETI N DATE MFW-002 MFW-007 MGG-002 MGG-003 MGG-004 MGG-005 MGG-006 MMP-001 MMP-002 MMP-003 MMP-004 MMP-005 MMP-006 MMP-007 MMP-008 MRC-006 MRC-007 MSG-007 MSP-001 NPE-002 NPE-003 SUR-026 SUR-030 SUR-031 Loss ofNormal Feedwater Equivalent TMI-2Scenario Loss of4KVBus 3A Loss of4KVBus 3B Loss ofAllAC Loss of4KVBus 3C Loss of4KVBus 3D Loss ofVitalAC Bus 3P06 Loss ofVitalAC Bus 3P07 Loss ofVitalAC Bus 3P08 Loss ofVitalAC Bus 3P09 Loss ofDC Bus 3A (3D01)
Loss ofDC Bus 3B (3D23)
Loss ofDC Bus 4B (4D01)
Loss ofDC Bus 4A (4D23)
Loss ofa Single RCP With Power Below P-8 Stuck Open Spray Valve Main Steam Line Break from Hot Standby with Reduced Shutdown Margin Bus Stripping and Load Sequencing Tests Plant Startup Cold Shutdown to Hot Standby Plant Startup from Hot Standby to Rated Power Engineered Safeguards Integrated Test, 3-OSP-203.1 Er 3-OSP-203.2 Full Length RCC - Periodic Exercise, OP-1604.1 Inducing Xenon Oscillations to Produce Various Incore AxialOffsets, O-OP-059.3 08-25-95 12-11-95 07-21-95 07-21-95 11-09-95 07-21-95 07-21-95 08-25-95 08-25-95 08-25-95 08-25-95 08-25-95 08-25-95 08-25-95 08-25-95 11-09-95 08-25-95 12-11-95 12-11-95 11-17-95 12-11-95 11-17-95 08-25-95 11-09-95 Page 3
TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 1995 TESTS (CONTINUED)
ANNUALTESTS
~TE T¹ TE TDE IPTI N MPLETI N DATE MFW-003 MRC-002 MRC-004 MRC-005 MRX-001 MRX-009 MSG-001 MSG-003 MTU-001 SST-001 SST-002 SST-003 SST-004 Loss ofNormal and Emergency Feedwater Large Break LOCAInside Containment With Loss ofOII'site Power PORV Failure (Open) Without High Pressure Injection Loss ofForced Reactor Coolant Flow Maximum Rate Power Ramp (100% to 75% and back to 100%)
Manual Reactor Trip from 100% Power Main Steam Line Break Inside Containment Simultaneous Closure ofAllMSIVs Turbine Trip Which Does Not Cause Automatic Reactor Trip Steady State 50% Power Heat Balance Steady State 75% Power Heat Balance Steady State 100% Power Heat Balance 100% Power 60 min NullTransient 08-25-95 07-21-95 07-21-95 11-09-95 11-17-95 07-21-95 11-09-95 08-25-95 08-25-95 11-09-95 11-09-95 11-09-95 07-21-95 Page 4
TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 2.2 1996 TESTS TE T4 TE TDE RIPTI N MPLETI N DATE MCV-001 MCV-002 MCV-004 MFW-004 MFW-006 MRC-003 MRC-009 MRX-010 MSG-006 MTU-003 MTU-005 MTU-009 MTU-011 NPE-005 NPE-006 SUR-004 SUR-009 SUR-015 SUR-017 SUR-020 SUR-035 SUR-036 SUR-037 Uncontrolled Maximum Rate Boron Dilution Charging System Failures Letdown and Volume Control Tank Operations and Malfunctions Feedwater Line Break Inside Containment Failure ofSteam Generator Level Channel Providing Input to the Feedwater Controller Small Break LOCAInside Containment Fast Load Reduction, 3-ONOP-100 Spurious High Containment Pressure SI Closure ofa Single MSIVAtSeveral Different Power Levels Turbine Lube Oil System (Bearings)
Turbine Turning Gear Operation Turbine Lube Oil Control &Auto-Stop Oil Failure ofTurbine 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-OSP-030.5 Reactor Protection System Logic Test, 3-OSP-049.1 Intermediate Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.2 Power Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.4 Main Steam Isolation Valve Closure Test, 3-OSP-072 Containment Isolation Racks QR50 and QR51 Periodic Test, OP-4004.4 Component Cooling Water System Flow Balance, 3-OSP-030.9 Determination ofQuadrant Power Tilt Ratio, 3-OSP-059.10 Page 5 12-08-96 12-03-96 12-03-96 12-03-96 09-27-96 09-27-96 12-03-96 12-03-96 09-27-96 09-27-96 09-27-96 12-03-96 12-03-96 12-08-96 12-03-96 07-03-96 12-03-96 07-03-96 07-08-96 09-23-96 09-23-96 12-08-96 07-03-96
TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE I%UMBER2 1996 TESTS (CONTINUED)
ANNUALTESTS
~TE T¹ TE TDE IPTI N MPLETI DATE MFW-003 MRC-002 MRC-004 MRC-005 MRX-001 MRX-009 MSG-001 MSG-003 MTU-001 SST-001 SST-002 SST-003 SST-004 Loss ofNormal and Emergency Feedwater Large Break LOCAInside Containment With Loss ofOQsite Power PORV Failure (Open) Without High Pressure Injection Loss ofForced Reactor Coolant Flow Maximum Rate Power Ramp (100% to 75% and back to 100%)
Manual Reactor Trip from 100% Power Main Steam Line Break Inside Containment Simultaneous Closure ofAllMSIVs Turbine TripWhich Does Not Cause Automatic Reactor Trip Steady State 50% Power Heat Balance Steady State 75% Power Heat Balance Steady State 100% Power Heat Balance 100% Power 60 min NullTransient 09-27-96 07-03-96 09-27-96 09-27-96 12-03-96 09-27-96 09-27-96 12-03-96 09-27-96 12-03-96 12-03-96 07-03-96 09-27-96 Page 6
TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 2.3 1997 TESTS TE T¹ TE TDE IPTI N MPLETI N DATE MCS-001 MFW-001 MGG-001 MRC-001 MRX-003 MRX-006 MRX-007 MRX-Oll MSG-005 MTU-002 NPE-001 RTT-001 RTT-002 SUR-003 SUR-005 SUR-010 SUR-011 SUR-021'UR-022 s
12-11-97 Component Cooling Water Operations and Malfunction Loss ofVacuum Tests, Including Loss of Condenser Level Control Generator Trip Steam Generator Tube Rupture Nuclear Instrumentation Failure During Startup Dropped Control Rod Dropped With Inabilityto Drive Control Rods Loss ofC 4KVBus Reactor Trip Failure ofReference Temperature to Steam Dumps Turbine Trip from 100% Power Plant Filland Vent from a Partial Drain Down to a Solid Pressurizer Simulator Real Time Test Simulator Real Time Test Validation Test Diesel Generator 24 Hour Load Test and Load Rejection, 3-OSP-023.2 Reactor Coolant System Leak Rate Calculations, 3-OSP-041.1 RHR MOVs/System Pressure Interlock Test, 3-OSP-050.7 RHR MOVs 750, 751, 862, 863, Interlock Test, 3-OSP-050.8 Standby Steam Generator Feedwater Pumps
/ Cranking Diesels Test, O-OSP-074.4 AuxiliaryFeedwater Train 1 Operability Veri6cation, 3-OSP-075.1 12-11-97 08-18-97 08-18-97 08-18-97 08-18-97 12-11-97 12-11-97 08-18-97 08-18-97 12-11-97 05-29-97 05-29-97 08-18-97 05-29-97 05-29-97 05-29-97 05-29-97 05-29-97
'Procedure O-OSP-074.4 cancelled due to PC/M 95-060, Elimination ofcranking diesels tie to Unit's 3 &4. Procedure O-OSP-074.4 replaced with O-OSP-074.3, Standby Steam Generators Feedwater Pumps AvailabilityTest.
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TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 1997 TESTS (CONTINUED)
T~ETII TE TDE IPTI N MPLETI DATE SUR-024 Main Turbine Valves Operability Test, 3-OSP-089 SUR-032 Normal Operation ofIncore Moveable Detector System And Power Distribution Surveillance, OP-12404.1 SUR-033 Accident Monitoring Instrumentation Channel Checks, 3-OSP-204 SUR-034 Safeguards Relay Rack Train A, B, Periodic Test, OP-4004.2 08-18-97 12-11-97 05-29-97 05-29-97 The followingtests were moved up from 1998 to 1997 due to the incorporation ofthe Cycle 15 core into the simulator.
~TE TII TE TDE IPTI MPLETI N DATE SUR-001 InitialCriticalityaRer Refueling, O-OSP-040.6 SUR-002 Nudear Design Check Tests During Startup Sequence AfterRefueling, O-OSP-040.5 08-18-97 08-18-97
'Procedure OP-12404.1 Cancelled and replaced by O-OP-059.4, Operation ofthe Moveable Incore Detectors.
'Procedure O-OSP-040.5 title changed to Nuclear Design Verification.
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TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 1997 TESTS (CONTINUED)
ANNUALTESTS
~TE T¹ TE TDE RIPTI MPLETI N DATE MFW-003 MRC-002 MRC-004 MRC-005 MRX-001 MRX-009 MSG-001 MSG-003 MTU-001 SST-001 SST-002 SST-003 SST-004 Loss ofNormal and Emergency Feedwater Large Break LOCAInside Containment With Loss OfOQsite Power PORV Failure (Open) Without High Pressure Iajection Loss ofForced Reactor Coolant Flow Maximum Rate Power Ramp (100% to 75% and back to 100%)
Manual Reactor Trip from 100% Power Main Steam Line Break Inside Containment Simultaneous Closure ofAllMSIVs Turbine Trip Which Does Not Cause Automatic Reactor Trip Steady State 50% Power Heat Balance Steady State 75% Power Heat Balance Steady State 100% Power Heat Balance 100% Power 60 min NullTransient 08-18-97 12-11-97 08-18-97 08-18-97 08-18-97 08-18-97 08-18-97 08-18-97 08-18-97 12-11-97 08-18-97 08-18-97 05-29-97 Page 9
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TURKEYPOINT UNIT3 2.4 1998 TESTS SIMULATORCERTIFICATIONUPDATE NUMBER2 TE T¹ TE TDE IPTI MPLETI N DATE MCN-001 MCS-002 MCS-003 MCS-004 MCV-005 MFW-005 MFW-008 MRX-002 MRX-004 MRX-005 MRX-008 MSG-002 MSS-001 MSS-002 MSS-003 MSS-004 MTU-006 MTU-008 NPE-004 SUR-014 SUR-016 SUR-019 Containment Emergency Systems Operations and Malfunctions Intake Cooling Water System Operations and Malfunctions Turbine Plant Cooling Water Operation and Malfunctions Instrument AirSystem Operation and Malfunctions Non-Regenerative Heat Exchanger Tube Leak Main Feedwater Line Break Outside Containment Loss ofNormal Feedwater/ATWS Loss ofProtection 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 Injection Piping Outside Containment Accumulator Operations and Malfunctions Loss ofRHR While in Cold Shutdown Loss ofInventory During AShutdown and Partial Draindown Condition Hydrogen Seal Oil Hydrogen Cooling Reactor Trip Followed By Recovery to Rated Power Source Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.1 Intermediate Range NIS Setpoint Verification, 3-OSP-059.3 Process Radiation Monitoring Operability Test, 3-OSP-067.1 09-15-98 09-15-98 09-15-98 09-15-98 09-15-98 09-01-98 09-15-98 09-01-98 09-01-98 09-01-98 09-15-98 04-22-98 09-01-98 09-15-98 09-01-98 09-01-98 09-01-98 09-01-98 08-05-98 08-05-98 08-05-98 08-05-98 Page 10
TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 1998 TESTS (CONTINUED)
ANNUALTESTS
~E'~T¹ TE T DE IPTI MPLETI N DATE MFW-003 MRC-002 MRC-004 MRC-005 MRX-001 MRX-009 MSG-001 MSG-003 MTU-001 SST-001 SST-002 SST-003 SST-004 Loss ofNormal and Emergency Feedwater Large Break LOCAInside Containment With Loss OfOffsite Power PORV Failure (Open) Without High Pressure Injection Loss ofForced Reactor Coolant Flow Maximum Rate Power Ramp (100% to 75% and back to 100%)
Manual Reactor Trip from 100% Power Main Steam Line Break Inside Containment Simultaneous Closure ofAllMSIVs Turbine Trip Which Does Not Cause Automatic Reactor Trip Steady State 50% Power Heat Balance Steady State 75% Power Heat Balance Steady State 100% Power Heat Balance 100% Power 60 min NullTransient 04-22-98 04-22-98 04-22-98 04-22-98 08-05-98 08-05-98 04-22-98 04-22-98 08-05-98 08-05-98 08-05-98 08-05-98 04-22-98 Page 11
TURKI<YPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUINBER2 3.0 CERTIFICATIONTEST CHANGES (1995 - 1998)
Experience gained during initialcertification testing and during the last four year cycle has resulted in several changes to the Turkey Point Simulator Certification Test plan. These changes in the plan are organized into the followingthree categories: Changes, Deletions, and Additions. These modifications to the test plan were made to eliminate duplication, eliminate test runs that provide littleor no incremental information and to modify tests to reflect changes in the plant.
The abstracts for tests added and changed are included, in Appendix A. Table 1 in Appendix B updates the profile ofthe certification test program by general type of test. Table 2 provides an updated cross-reference between each ANS-3.5-1985 section and the associated Turkey Point certification test(s).
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TURKEYPOINT UNIT3 3.1 CHANGES SIMULATORCERTIFICATIONUPDATE NUMBER2 MCS-004, Instrument AirOperations and Malfunctions This test consists of6 cases: (1) Loss ofdiesel air compressor, (2) Instrument air dryer fouling, (3) Instrument air reservoir leak, (4) Complete loss ofinstrument air, (5) Loss ofcontainment air header, and (6) Loss ofturbine air header. PCM 93-108 removed the portable diesel instrument air compressors and replaced them with permanent diesel and electric air compressors on each unit. The new air compressors auto start on low air pressure while the old portable compressors had to be manually started. This necessitated.
a change to the scenario to fail one or more ofthe compressors either initiallyor during the scenario to get the desired loss ofair. Run 1, Loss ofDiesel AirCompressor was changed to Sequential Loss ofAirCompressors and Control Valve Logic. This run verifies the auto start capability ofeach air compressor and then verifies that the control valves that cross tie the units, isolate to protect the unaffected unit. Run 3, instrument air reservoir leak, is performed as part ofRun 1 to verify auto start capability ofeach ofthe compressors.
Therefore Run 3 willbe deleted and replaced with a loss ofUnit 3 instrument air. In this run, Unit 4 willstillbe supplying air to the intake area, the control room and the auxiliary building.
MCV-002, Charging System Failures This test consists offour runs: (1) Seal injection filterclogging, (2) Charging pump discharge valve failed closed, (3) Charging pump discharge leak, and (4) Loss ofall charging. Run 1 provides littleindication in the control room with the exception of an alarm. Therefore this failure provides little training value and this run willbe deleted. Runs 2, 3, and 4 produce very similar results. They all involve a loss of charging to the regenerative heat exchanger, which causes the letdown line to Gash.
Therefore Run 2 willbe deleted and Run 4 willbe modified. Currently Run 4 involves a total loss ofcharging with no operator actions. The scenario willbe changed to perform operator actions using ONOP-047.1, Loss ofAllCharging. The scenario willstart from 50% power and willinvolve shutting the unit down to hot standby, blocking SI, starting an HHSI pump and depressurizing the RCS until the HHSI pump begins to inject.
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TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 MCV-004, Letdown and Volume Control Tank Operations and Malfunctions This test consists offour runs: (1) Letdown pressure control valve failed open, (2)
Letdown pressure control valve failed. closed, (3) VCT level control valve failed in the Divert position, and (4) Letdown isolation valve failed closed. Run 3, which simply failed the valve to divert willbe modified to failVCT level transmitter LT-115 high.
This willcause the valve to go to divert but willalso bring in the VCTHi/Lolevel annunciator, prevent an auto makeup to the VCT and prevent auto swap over ofthe charging pump suction &om the VCT to the RWST. No operator action willtake place until all ofthe failures can be verified. Then 3-ONOP-046.4, Malfunction ofthe Boron Concentration Control System willbe used to recover from the failure.
Runs 2 and 4 both involve letdown line valve closure and produce very similar results. Therefore, Run 4 willbe replaced by failure ofVCT level transmitter LT-112 high. This willcause the VCT level control valve to go to fulldivert and ifthe makeup flowis less than charging flow, actual VCT level willdrop. When the failure has been identified, then ONOP-046.4 willbe used to recover from the transient.
MFW-006, Failure ofSteam Generator Level Channel Providing Input to the Feedwater Controller This test currently runs two cases, one in which no operator action is taken, and one in which manual operator action is taken to stabilize the plant. Athird case was run in 1996 to compare a failure ofthe steam flowinput to the feedwater controller that occurred on Unit 3 in 1995. The test description willbe modified to run a third case that willcompare the simulator against the 1995-plant failure or against newer plant data ifitbecomes available. The title willbe changed to "Failure ofInput Channels to the Feedwater Controller".
MRX-003, Nuclear Instrumentation Failure During Startup This test consisted oftwo runs: (1) Failure ofboth intermediate range channels to prevent the source range trip from being blocked and (2) Failure of3 out ofthe 4 power range. channels to prevent the intermediate range trip from being blocked.
These scenarios involve multiple failures and operator actions that are unrealistic.
Therefore, these failures willbe deleted and replaced by three new runs: (1) Failure ofa source range channel, (2) failure ofan intermediate range channel, and (3) failure ofa power range channel. In each run the appropriate oE-normal procedure willbe used to take the failed channel out ofservice. The title ofMRX-003 willbe changed to "Nuclear Instrumentation Failures".
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TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 MRX-007, Dropped Rod with Inabilityto Drive Control Rods This test consisted ofa dropped rod causing an automatic turbine runback to 70%
power with control rods immovable. With the elimination ofthe dropped rod runback the scenario is very similar to certification test MRX-006, Dropped Rod. Since this test was intended to satisfy ANS-3.5 section 3.1.2 (13) "Inabilityto insert control rods" the scenario willbe changed. The initialcondition willbe 50% power versus 100% power and the initiatingevent willbe an urgent failure in the logic cabinet.
This willrequire a shutdown to hot standby using boration only. The test wiHbe renamed "Shutdown with Inability to Drive Control Rods".
SUR-001 InitialCriticalityARer Refueling, O-OSP-040.6 Plant procedures O-OSP-040.5, Nuclear Design Verification and O-OSP-040.6, Initial CriticalityAfterRefueling have been cancelled and combined into one procedure:
O-OSP-040.16, InitialCriticalityARer Refueling and Nuclear Design Verification.
Therefore SUR-001, InitialCriticalityafter Refueling and SUR-002, Nuclear Design Verification willbe combined into one test, SUR-001, InitialCriticalityaRer Refueling and Nuclear Design Verification and SUR-002 willbe deleted.
SUR-030 Full Length RCC Periodic Exercise, OP-1604.1 The plant has cancelled OP-1604.1 and replaced itwith 3-OSP-028.6, RCCA Periodic Exercise. Therefore SUR-030 willbe renamed "RCCAPeriodic Exercise, 3-OSP-028.6", however, the intent ofthis test remains the same.
SUR-034 Safeguards Relay Rack Train A,B, Periodic Test, OP-4004.2 The plant has cancelled OP-4004.2 and replaced itwith 3-OSP-063.1, Safeguards Actuation System Logic Test. Therefore SUR-034 willbe renamed "Safeguards Actuation Systems Logic Test, 3-OSP-063.1", however, the intent ofthis test remains the same.
SUR-035 Containment Isolation Racks QR50 and QR51 Periodic Test, OP-4004.4 The plant has cancelled OP-4004.4 and replaced itwith 3-OSP-063.2, Containment Isolation System Logic Test. Therefore SUR-035 willbe renamed "Containment Isolation System Logic Test, 3-OSP-063.2", however, the intent ofthis test remains the same.
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TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 3.2 DELETIONS MTU-006, Hydrogen Seal Oil This test checks normal and abnormal operation ofthe seal oil system. Allofthe controls and indicators for the seal oil system are located outside ofthe control room.
The only indication in the control room ofa seal oil failure is the hydrogen panel trouble annunciator. Thus, continuing to test this system provides littlevalue in terms oftraining. This test was successfully run in 1990, 1994, and 1998. Therefore MTU-006 willbe deleted.
RTT-001 Simulator Real Time Test This test is designed to verifythat the simulator is operating in real time. In order to run in real time the execution ofall ofthe modules must be completed every 200 milliseconds. Modules are divided into 4 legs of50 milliseconds each. Ifthe computer is unable to complete all module calculations within one leg, an overrun is generated. When an overrun occurs, the computer reschedules the missed tasks, and tries to makeup the time during the remaining legs. Four consecutive overruns would mean that all calculations were not completed within the 200 millisecond time step and the computer would no longer be running in real time. This test used to modify the computers to abort iffour consecutive overruns occurred and then run various transients such as LBLOCA's, steam breaks, and ATWS's for an hour. After the test was over the computers were set back to not abort on overruns. However to ensure that overruns were not occurring during training, the computers were modified in 1994 to abort on four consecutive overruns. Therefore the simulator is continuously monitored and willabort during training, examinations or during certification testing ifitis not operating in real time. Therefore this test is no longer required and willbe deleted.
Note that RTT-002 Simulator Real Time Validation Test willstillbe run. This test verifies that the simulator willabort if:(1) Four consecutive overruns occur, (2) One ofthe computers stops running, or (3) An overflow condition such as dividing by zero occurs.
SUR-002 Nuclear Design Verification, O-OSP-040.5 As explained in Section 3.1, SUR-001 and SUR-002 have been combined into one test (SUR-001) and SUR-002 willbe deleted.
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TURKEYPOINT UNIT3 3.3 ADDITIONS SIMULATORCERTIFICATIONUPDATE NUMBER2 MRC-010, Pressurizer Pressure and Level Control Malfunctions This test willconsist oftwo runs: (1) Failure ofthe pressure control channel (PT-444) high, and (2) Failure ofthe level control channel (LT-459A)low. The intent of this test willbe to demonstrate correct simulator response to the control failure.
Therefore, operator action willbe delayed until proper simulator response can be verified. However, operator action willbe permitted quickly enough to prevent a reactor trip and re-establish normal operations. In Run 1 ONOP-041.5, Pressurizer Pressure Control Malfunction willbe used to recover from the failure while in Run 2 ONOP-041.6, Pressurizer Level Control Malfunction willbe used.
MRX-012, Control Room Evacuation, 0-ONOP-105 This test willsimulate the evacuation ofthe control room due to a fire and the stabilization ofthe plant using the alternate shutdown panel. 0-ONOP-105 willbe used to shutdown the plant, control the plant at hot standby and then begin a cooldown to cold shutdown.
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TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 4.0 FOUR YEARTEST PLAN(1999-2002)
Per the requirements ofRegulatory Guide 1.149, the Simulator Certification test program willbe conducted in its entirety on a four year cycle. Allofthe ANSI/ANS-3.5-1985 Appendix B tests willbe performed annually. Approximately 25% ofthe remaining tests in the Certification program willbe performed each year.
Table 4-1 presents the ANSI/ANS-3.5-1985 tests that willbe performed annually. Tables 4-2 through 4-5 present the test plan for each ofthe next four years.
The tests planned each year represent a cross section ofthe various types oftests.
As in the previous four year cycle, tests may be added to meet new or special requirements.
The 1999-2002 Turkey Point Simulator test plan has been reviewed and approved by the Simulator Configuration Review Board (SCRB).
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TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 Table 4-1 Annual Tests MFW-003 MRC-002 MRC-004 MRC-005 MRX-001 MRX-009 MSG-001 MSG-003 MTU-001 SST-001 SST-002 SST-003 SST-004 Loss ofNormal and Emergency Feedwater Large Break LOCAInside Containment With Loss OfOffsite Power PORV Failure (Open) Without High Pressure Injection Loss ofForced Reactor Coolant Flow Maximum Rate Power Ramp (100% To 75% and back to 100%)
Manual Reactor Trip from 100% Power Main Steam Line Break Inside Containment Simultaneous Closure ofAllMSIVs Turbine Trip Which Does Not Cause Automatic Reactor Trip Steady State 50% Power Heat Balance Steady State 75% Power Heat Balance Steady State 100% Power Heat Balance 100% Power 60 Minute NullTransient Page 19
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TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 Table 4-2 1999 Test Plan MFW-002 MFW-007 MGG-002 MGG-003 MGG-004 MGG-005 MGG-006 MMP-001 MMP-002 MMP-003 MMP-004 MMP-005 MMP-006 MMP-007 MMP-008 MRC-006 MRC-007 MSG-007 MSP-001 NPE-002 NPE-003 SUR-026 SUR-030 SUR-031 Loss ofNormal Feedwater Equivalent TMI-2Scenario Loss of4KVBus 3A Loss of4KVBus 3B Loss ofAllAC Loss of4KVBus 3C Loss of4KVBus 3D Loss ofVitalAC Bus 3P06 Loss ofVitalAC Bus 3P07 Loss ofVitalAC Bus 3P08 Loss ofVitalAC Bus 3P09 Loss ofDC Bus 3A(3DOl)
Loss ofDC Bus 3B (3D23)
Loss ofDC Bus 4B (4DOl)
Loss ofDC Bus 4A (4D23)
Loss ofa Single Reactor Coolant Pump With Power Below P-8 Stuck Open Spray Valve Main Steam Line Break from Hot Standby with Reduced Shutdown Margin.
Bus Stripping and Load Sequencing Tests Plant Startup Cold Shutdown to Hot Standby Plant Startup from Hot Standby to Rated Power Engineered Safeguards Integrated Test, 3-OSP-203.1 &3-OSP-203.2 RCCA Periodic Exercise, 3-OSP-028.6 Inducing Xenon Oscillations to Produce Various Incore Axial Offsets,O-OP-059.3 Page 20
TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 Table 4-3 2000 Test Plan MCV-001 MCV-002 MCV-004 MFW-004 MFW-006 MRC-003 MRC-009 MRX-010 MS6-006 MTU-003 MTU-005 MTU-009 MTU-Oll NPE-005 NPE-006 SUR-004 SUR-009 SUR-015 SUR-017 SUR-020 SUR-035 SUR-036 SUR-037 Uncontrolled, Maximum Rate Boron Dilution Charging System Failures Letdown and Volume Control Tank Operations and'Malfunctions Feedwater Line Break Inside Containment Failure ofInput Channels to the Feedwater Controller Small Break LOCAInside Containment Fast Load Reduction, 3-ONOP-100 I
Spurious High Containment Pressure SI Closure ofa Single MSIVAt Several Different Power Levels Turbine Lube Oil System (Bearings)
Turbine Turning Gear Operation Turbine Lube Oil Control LAuto-Stop Oil Failure ofTurbine 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-OSP-030.5 Reactor Protection System Logic Test, 3-OSP-049.1 Intermediate Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.2 Power Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.4 Main Steam Isolation Valve Closure Test, 3-OSP-072 Containment Isolation System Logic Test, 3-OSP-063.2 Component Cooling Water System Flow Balance, 3-OSP-030.9 Determination ofQuadrant Power TiltRatio, 3-OSP-059.10 Page 21
TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 Table 4-4 2001 Test Plan MCS-001 MFW-001 MGG-001 MRC-001 MRC-010 MRX-003 MRX-006 MRX-007 MRX-011 MSG-005 MTU-002 NPE-001 RTT-002 SUR-003 SUR-005 SUR-010 SUR-011 SUR-021 SUR-022 SUR-024 SUR-032 SUR-033 SUR-034 Component Cooling Water Operations and Malfunctions Loss ofVacuum Tests, Including Loss ofCondenser Level Control Generator Trip Steam Generator Tube Rupture Pressurizer Pressure and Level Control Malfunctions Nuclear Instrumentation Failures Dropped Control Rod Shutdown With Inabilityto Drive Control Rods Loss of C 4KVBus Reactor Trip Failure ofReference Temperature to Steam Dumps Turbine Trip from 100% Power Plant Filland Vent from a Partial Drain Down to a Solid Pressurizer Simulator Real Time Test Validation Test Diesel Generator 24 Hour Load Test and Load Rejection, 3-OSP-023.2 Reactor Coolant System Leak Rate Calculations, 3-OSP-041.1 RHR MOVs/System Pressure Interlock Test, 3-OSP-050.7 RHR MOVs 750, 751, 862, 863, Interlock Test, 3-OSP-050.8 Standby Steam Generator Feedwater Pumps AvailabilityTest, O-OSP-074.3 AuxiliaryFeedwater Train 1 Operability Verification, 3-OSP-075.1 Main Turbine Valves Operability Test, 3-OSP-089 Operation ofthe Moveable Incore Detectors, O-OP-059.4 Accident Monitoring Instrumentation Channel Checks, 3-OSP-204 Safeguard Actuation System Logic Test, 3-OSP-063.1 Page 22
TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 Table 4-5 2002 Test Plan MCN-001 MCS-002 MCS-003 MCS-004 MCV-005 MFW-005 MFW-008 MRX-002 MRX-004 MRX-005 MRX-008 MRX-012 MSG-002 MSS-001 MSS-002 MSS-003 MSS-004 MTU-008 NPE-004 SUR-001 SUR-014 SUR-016 SUR-019 Containment Emergency Systems Operation and Malfunctions Intake Cooling Water System Operations and Malfunctions Turbine Plant Cooling Water Operation and Malfunctions Instrument AirSystem Operation and Malfunctions Non-Regenerative Heat Exchanger Tube Leak Main Feedwater Line Break Outside Containment Loss ofNormal Feedwater / ATWS Loss ofProtection System Channel Stuck Control Rod Uncoupled Control Rod Test Fuel Cladding Failure Resulting in High Reactor Coolant Activity Control Room Evacuation, 3-ONOP-105 Main Steam Line Break Outside Containment Small Leak in Safety Injection Piping Outside Containment Accumulator Operations and Malfunctions Loss ofRHR While in Cold Shutdown Loss ofInventory During Partial Draindown Hydrogen Cooling Reactor Trip Followed By Recovery to Rated Power InitialCriticalityaRer Refueling and Nuclear Design Verification, O-OSP-040.16 Source Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.1 Intermediate Range NIS Setpoint Verification, 3-OSP-059.3 Process Radiation Monitoring Operability Test, 3-OSP-067.1 Page 23
(j r
(
TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 5.0 OUTSTANDINGDISCREPANCIES In general all Simulator Discrepancy Reports (DR's) are addressed within one calendar year after they are written. The schedule may be extended beyond one year in special circumstances such as the need for certain equipment or very low priorityDR's. The SCRB willreview and approve the extension ofthe schedule for any DR that willnot be completed in one year.
5.1 1995 CERTIFICATIONTEST DR's 40 Certification test DR's were written and all have been completed.
5.2 1996 CERTIFICATIONTEST DR's 17 Certification test DR's were written and all have been completed.
5.3 1997 CERTIFICATIONTEST DR's 16 Certification test DR's were written and all have been completed.
5.4 1998 CERTIFICATIONTEST DR's 20 Certification test DR's were written and 6 have been completed. The open DR's are listed in Table 5-1.
Page 24
TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER2 Table 5-1 OPEN DISCREPANCIES T~ET DR 4 MCN001 9800103 MCS003 9800107 MCS004 9800104 TITLE Iodine concentrations increase when ECF fans started H2 cooler inlet temperature drops to zero momentarily CV-1605 setpoint incorrect DUE DATE 09-02-99 09-16-99 09-16-99 MCV005 9800074 9800108 NRHXtube leak does not work properly R-17B spiked during NIBS tube leak 07-17-99 09-16-99 MFW008 9800109 Investigate RETRAN / Simulator pressure diQerence MRC005 9800008 HighMSRtemperatures afterRxtrip MRX009 9800006 MSR reliefvalves don't likwhen MSR steam supply valves left open 09-16-99 02-09-99 02-09-99 MSS003 9800098 9800099 RCS pressure decreases below atmospheric pressure Cold Leg Temperature decreases throughout transient 09-02-99 09-01-99 SST001 9800048 Hotwell level doesn't match plant 04-24-99 SUR016 9800077 9800078 Add 5 minute average ~T to ERDADS display Tave and Trefneed. 2 decimal precision on ERDADS MA2 display 07-17-99 07-17-99 N/A 9800105 Physical Fidelity 12-31-98 Page 25
TURKEYPOINT UNIT3 APPENDIXATEST ABSTRACTS A.l TESTS ADDED SIMULATORCERTIFICATIONUPDATE NUMBER2
TURKEYPOINT SIMUIATORCERllFICATIONTEST PROCEDURE llTLEr PRESSURIZER PRESSURE ANDLEVELCONTROL MALFUNCTIONS NUMBER MRC-010 AN$3.5 REFERENCE SECTIONS:
3.1.2 (18) Failure ofreactor coolant pressure and volume control systems DESCRIPTION This test examines the simulator's abilityto model malfunctions In the pressurizer pressure and level control system. Two cases willbe run. In the firstcase, the pressure control transmitter PT-3-444 willbe failed high. Afterthe response ofthe simulator Is verified operator action willbe taken to mitigate the transient using 3-ONOP-041.5, Pressurizer Pressure Control Malfunction. In the second case, pressurizer level control transmitter LT~Awillbe failed low. Afterthe response ofthe simulator ls verifiedoperator action willbe taken to mitigate the transient using 3-ONOPM 1.6, Pressurizer Level Control Ma!function.
OPTIONS This test could be performed at any power level and at any time In core life.
INITIALCONDmONS FINALCONDITIONS Fullpower steady state, Plant stabilized in accordance with the ONOP.
SIMULATORCONFIGURATIONREVIEWBOARDAPPROVAL FOR USE TEST TEAM DATE:
DATE:
DATE:
DATE:
DATE:
TURKEYPOINTSIMUlATORCERTIFICA11ON TEST PROCEDURE TITLE:
CONTROL ROOM EVACUATION,0-ONOP-105 NUMBER MRX-012 ANS 3.5 REFERENCE SECTIONS:
3.1.2 Plant Malfunctions DESCRIPTION This test simulates a control room evacuation and the stabBization ofthe plant using the alternate shutdown panel. The control Room Evacuation procedure, 3-ONOP-105 willbe used to shutdown the plant, control the plant at hot standby, and then begin a coo!down to cold shutdown.
OPTIONS This test could be performed at any power level and at any time in core life.
INI11ALCONDITIONS FINALCONDmONS Fullpower steady state.
Plant stabilized at HSB and a cooldown begun In accordance with the ONOP.
SIMUlATORCONFIGURATIONREVIEWBOARD APPROVAL FOR USE TEST TEAM DATE:
DATE:
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DATE:
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TURKEYPOINT UNIT3 APPENDIXATEST ABSTRACTS A.2 TESTS CHANGED SIMULATORCERTIFICATIONUPDATE NUMBER2
TURKEYPOINTSIMUlATORCERTIFICATIONTEST PROCEDURE TITLE:
INSTRUMENTAIRSYSTEM OPERATIONS ANDMAIFUNCTIONS NUMBER MCS-004 ANS 3.5 REFERENCE SECTIONS:
3.1.2(2) Loss ofInstrument Air DESCRIPTION The purpose of this test is to verifythe proper performance ofthe simulator during operations involving the Instrument air system and with various instrument air malfunctions.
There willbe six separate runs involved in the completion of this test.
The firstrun Involves an air reservoir leak to test the logic associated with auto starting ofthe diesel and electric air compressors and the Units 3 &4 cross tie control valves. The abilityto supply Instrument air from the service air header is also Unit4 cross tie control valve willIsolate to protect Unit4's afr supply and continue to supply Unit3's Intake area, the control room, and the auxiliary building. The fourth run willInvolve a total loss ofinstrument air on both Units 3 &4. The fifthrun wiibe a loss ofthe containment air header and the sixth run willbe a loss ofthe turbine air header.
OPTIONS leaks can be instated.
The diesel air compressor discharge pressure and the amount and rate ofdryer fouling can also be varied.
The instrument air filters can be used Instead ofthe dryers.
INITIALCONDITIONS FINALCONDmONS MOLsteady state at IK%power Simulator response to the failure verified.
SIMUIATORCONFIGURATIONREVIEWBOARD APPROVAL FOR USE TEST TEAM DATE:
DATE:
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TURKEYPOINTSIMULATORCERTIFICATION TEST PROCEDURE TITLEr CHARGINGS YSTEMFAILURES NUMBER MCV-002 ANS 3.5 REFERENCE SECTIONS:
3.1.2 (18) Failure ofReactor Coolant System Pressure and Volume Control Systems DESCRIP11ON The purpose ofthis test Is to simulate various malfunctions in the charging and seal injection systems in order to ven'fyproper simulator modeling ofthese systems.
Two cases willbe run. The firstrun willconsist ofa leak downstream ofHCV-121 with no operator actions.
The second run wi7Ibe a total loss of charging and 3-ONOPM7.1. Loss ofAllCharging willbe used to mitigate the event.
OPTIONS The Turkey Point simulator has the capability offailingalmost any component in the charging system.
Therefore there are wide variety offailures are possible.
INITIALCONDITIONS FINALCONDITIONS Run 1: 100% power, steadystate.
Run 2: 50K power, steady state.
Run 1: System parameters stabilized Run 2: 3~OPM7.1 completed, HHSIpumps maintaining pressurizer level.
SIMULATORCONFIGURATIONREVIEWBOARD APPROVALFOR USE DATE:
DATE:
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TURKEYPOINTSIMUIATORCERTIFICATION TEST PROCEDURE TITLEr LEIDOWNAND VOLUMECONTROL TANKSYSTEM OPERATIONS ANDMALFUNCTIONS NUMBER:
MCV-004 ANS 3.5 REFERENCE SECTIONS:
3.1.2 (18) Failure ofReactor Coolant Pressure and Volume Control Systems DESCRIPTION The test checks the response ofthe Letdown and Volume Control Tank portions ofthe CVCS system.
Various malfunctions, which affect this system, willbe initiated to verifyproper system response.
A total offour different malfunction tests willbe run: (I) The letdown control valve PCV-145 willbe failed open, 0 PCV-145 wi7Ibe failed closed, (3) The VCTlevel control transmitter LT-1 15 willbe fai!ed high, and (4) The VCTlevel transmitter LT-1 12 failed high. Runs 1 and 2 willbe leftto run without any operator action. In Runs 3 and 4 operator action willbe taken using 3-ONOP-046.4, Malfunction ofthe Boron Control System.
OPTIONS There are numerous malfunctions, which can be run on the Letdown and Volume Control Tank systems.
Representative malfunctions should be chosen to exercise as many parts of the systems as possible.
INITIALCONDITIONS FINALCONDmONS IK%power, normal letdown lineup.
Runs 1 and 2: Terminate after system parameters have stabilized.
Runs 3 and 4: Terminate affer 3-ONOP-N6.4 complete.
SIMULATORCONFIGURATIONREVIEWBOARDAPPROVAL FOR USE TEST TEAM DATE:
DATEr DATE:
DATE:
DATE:
TURKEYPOINTSIMUIATORCERTIFICATIONTEST PROCEDURE TITLEr FAILUREOF INPUTCHANNELS TO THE FEED WATERCONTROllER NUMBER MFW-006 ANS 3.5 REFERENCE SECTIONS:
3.1.2 (9) Normal Feedwater System Failures 3.1.2 (22) Process Instrumentation, Alarm, and Control System Failures DESCRIPTION This test checks the response ofthe simulator to a failed steam generator level, steam flow, or feed flowchannel when that channel is the controlling Input to the feedwater regulating valve. Three cases willbe run. The firstrun willbe a failure ofthe controlling level channel with no operator actions. The second run willbe the failure ofthe controlling level channel but operator action willbe taken to stabilize the plant. The last run willbe a failure ofone the controlling inputs (steam flow. feed flowor level) where plant data Is available and operator action willbe taken to mitigate the event.
OPllONS Anyofthe three steam generators may be used.
INITIALCONDITIONS FINALCONDITIONS IK% power, steady state.
Run 1-Plant stable after the reactor trip Run 2-Plant stable with the associated channel In auto Run 3-Plant stable SIMUlATORCONFIGURATIONREVIEWBOARD APPROVAL FOR USE DATE:
DATE:
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DATB
TURKEYPOINTSIMUIATORCERTIFICATIONTEST PROCEDURE TITLE:
NUCLEARINSTRUMENTATIONFAILURES NUMBER MRX-003 ANS 3.5 REFERENCE SECTIONS:
3.1.2 (21) Nuclear Instrumentation Failures DESCRIPTION This test examines the simulator's abilityto model malfunctions ofthe nuclear instrumentation system. Three cases willbe run. In the firstcase, a source range channel willbe failed. Operator action willbe taken to remove the channel from service using 3-ONOP-059.5, Source Range Nuclear Instrumentatlon Malfunction.
In the second case, an intermediate range channel willbe underwompensated and the reactor tnpped. Afterthe channel is visually verllied to be under-compensated it willbe taken out ofservice using ~OPM9.7. Intermediate Range Nuclear Instrumentation Malfunction. In the third case. a power range channel willbe fai!ed. The channel willbe removed from service using 3-ONOP-059.8, Power Range Nuclear Instrumentation Malfunction.
OP11ONS Anyofthe source, Intermediate, orpower range channels may be failed.
INITIALCONDITIONS FINALCONDITIONS Run 1: Cold shutdown.
Run 2: Fullpower steady state.
Run 3: Fullpower steady state.
Run 1: Source range channel removed from service per ~OP-059.5.
Run 2: Intermediate range channel removed from service per 3-ONOP-059.7.
Run 3: Power range channel removed from service per 3~OP-059.8.
SIMUIATORCONFIGURATIONREVIEWBOARDAPPROVAL FOR USE DATE:
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TURKEYPOINTSIMUlATORCERTIFICA11ON TEST PROCEDURE 11TLE:
SHUTDOWN WITHINABILITYTO DRIVECONTROL RODS NUMBER MRX-007 ANS 3.5 REFERENCE SECTIONS:
3.1.1 (6) Load Changes 3.1.2 (12) Control Rod Failures including Stuck, Uncoupled, Mfsalfgned, and Dropped rods 3.1.2 (13) Inabilityto Drive Control Rods DESCRIPTION This test wfllperform a shutdown to hot standby without control rods. An urgent failure ln the logic cabinet willprevent rod movement and require a shutdown to hot standby. The plant willbe stabilized using boratlon alone In accordance wfth~OP%28, Reactor Control System Malfunctfon and GOP-103, Power to Hot Standby.
OPTIONS None INI11ALCONDITIONS FINALCONDITIONS Steady state R% power, MOL Stable fn hot standby.
SIMUIATORCONFIGURATIONREVIEWBOARDAPPROVALFOR USE DATE:
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TURKEYPOINTSIMULATORCERTIFICATIONTEST PROCEDURE TITLE:
INITIALCRmCALITYAFTERREFUELINGANDNUCLEARDESIGN VERIFICA11ON, 0-OSP-040. 16 NUMBER SUR-001 ANS 8.5 REFERENCE SECTIONS:
8.1.1 (9) Core Performance Testing DESCRIPTION This test willbe a performance ofthe initialcnticaifty after refueling and nuclear design verification procedure. 0-OSLO. 16. The procedure willbe followed as closely as possible to Insure that the simulator can support training on the Initialcnticalityand core performance testing procedures.
The reactor willbe Ch7uted to criticalityand power escalated to establish the point ofadding nuclear heat. Core performance testing including measurement ofthe boron endpoint, differential boron worth, isothermal temperature coefficient and control rod worth willbe performed. The results willbe compared withplant test data and design data from the nuclear design report.
OPTIONS parts ofthe test requfre chemistry testing forboron concentration.
The simulator computed values forboron concentration may be used for these steps.
INITIALCONDI11ONS FINALCONDITIONS BOL. hot standby.
Allrods In.
Surveillance procedure complete SIMUIATORCONFIGURATIONREVIEW'OARDAPPROVAL FOR USE TEST TEAM DATE:
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TURKEYPOINT SIMULATORCERTIFICATIONlEST PROCEDURE TITLE:
RCCA PERIODIC EXERCISE, 3-OSP-028.6 NUMBER BUR-030 ANS 3.5 REFERENCE SECTIONS:
3.1.1(10) Operator Conducted Surveillance Testing on Safety Related Equipment DESCRIPTION This test willconsist ofperforming the surveillance procedure 3-OSP-Q2B.6, which exercises the control and shutdown rods. In this surveillance each bank ofrods ls moved In 10 to 20 steps. The step counters and rod position indicators gal s1 willbe monitored forproper movement and forless than 12steps deviation. The proper operation ofthe rod offtop lights willbe checked and the actuation ofthe shutdown bank offtop alarm willbe verifiedforshutdown banks Aand B. With no malfunctions present this test should pass the applicable acceptance cn'teria contained in 3-OSP-Q2B.6.
The data sheets ofthis test willbe compared with the data sheets from an actual performance of this test at Turkey Point.
OPTIONS This test can be conducted from any steady state power level.
INlllALCONDITIONS IK%power.
FINALCONDITIONS The test ls complete when the procedure ls complete.
SIMUlATORCONFIGURATIONREVIEWBOARDAPPROVAL FOR USE DATE:
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DAlE:
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TURKEYPOINTSIMUlATORCERTIFICATIONTEST PROCEDURE TITLE:
SAFEGUARDS ACTUATIONSYSTEM LOGIC TEST, 3-OSP-063.1 NUMBER SUR-N4 ANS 3.5 REFERENCE SECTIONS:
3.1.1 (10) Operator Conducted Surveillance on Safety-Related Equipment or Systems DESCRIPTION This certflication test willdemonstrate the abilityofthe simulator to support the operator conducted surveillance procedure 3-OSP-M. I, Safeguards Actuation System Logic Test. Withno malfunctions present, the abilityto successfully perform this surveillance willbe verifIed.
OPTIONS This test can be performed at any power level and at time In core life.
INITIALCONDITIONS FINALCONDITIONS IIX%power. steady state, NIOL Surveillance complete.
SIMULATORCONFIGURATIONREVIEWBOARDAPPROVAL FOR USE DATE:
DATE:
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TURKEYPOINTSIMUlATORCERTIFICATIONTEST PROCEDURE TITLEr CONMINMENTISOIATIONSYSlEMLOGIC TEST, 3-OSP-OQ.2 NUMBER:
SUR-035 ANS 3.5 REFERENCE SECTIONS:
3.1.1 (10) Operator Conducted Surveillance on Safety-Related Equipment or Systems DESCRIPTION This certification test willdemonstrate the abilityofthe simulator to support the operator conducted surveillance procedure 3-OSP~.2. Containment Isolation System Logic Test. Withno malfunctions present, the abilityto successfully perform this surveillance willbe verified.
OPTIONS This test can be performed at any power level and at time in core life.
INITIALCONDITIONS FINALCONDlllONS IR% power, steady state, MOL Surveillance complete.
SIMUlATORCONFIGURATIONREVIEWBOARD APPROVAL FOR USE TEST lEAM DATE:
DAlB DATE:
DAlB DATE:
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TURKEYPOINT UNIT3 APPENDIXB TEST MATRICIES SIMULATORCERTIFICATIONUPDATE NUMBER2
TABLEB-1 TURKEYPOINT CERTIFICATIONTEST MATRIXPROFILE l!AAL EROFTE T MALFUNCTIONS CONTAINMENT(MCN)
COMMONSERVICES (MCS)
CHEMICAL&VOLUMECONTROL SYSTEM (MCV)
GENERATOR &GRID (MGG)
MAINPOWER DISTRIBUTION(MMP)
REACTOR COOLANTSYSTEM (MRC)
REACTOR (MRX)
STEAM GENERATOR &MAINSTEAM (MSG)
STANDBYPOWER &SYNCHRONIZATION(MSP)
SAFETY SYSTEMS (MSS)
TURBINE (MTU)
SUBTOTAL 6
8 12 70 OTHERS COMPUTER REALTIMETEST (RTT)
STEADYSTATE TESTS (SST)
NORMiALPLANTEVOLUTIONS(NPE)
OPERATOR CONDUCTED SURVEILLANCETESTING (SUR)
SUBTOTAL 25 36 TOTAL 106
TABLEB-2 ANSI/ANS-3.5-1985 CERTIFICATIONTEST MATRIX A~NS
.SS 5
G ERSISGA I N S
3.1.1(6) 3.1.1(7) 3.1.1(8)
NPE-001 NPE-002 NPE-003 NPE-004 NPE-003 NPE-004 NPE-004 NPE-002 NPE-003 NPE-004 NPE-005 NPE-006 MRC-009 MRX-007 NPE-003 NPE-004 NPE-005 NOT APPL NPE-005 NPE-006 SUR-001 Plant Filland Vent &om 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 Fast Load Reduction, 3-ONOP-100 Shutdown with Inabilityto Drive Control Rods Plant Startup &om Hot Standby to Rated Power Reactor Trip Followed By Recovery to Rated Power Plant Shutdown from Rated Power to Hot Standby ICABLE Plant Shutdown from Rated. Power to Hot Standby Cooldown from Hot Standby to Cold Shutdown InitialCriticalityAfterRefueling and Nuclear Design Verification, O-OSP-040.16
~S.
S D
CERTIFICATI NTE T 3.1.1(10) 3.1.2(l)(a) 3.1.2(1Xb)
NPE-006 SUR-003 SUR-004 SUR-005 SUR-009 SUR-010 SUR-011 SUR-014 SUR-015 SUR-016 SUR-017 SUR-019 SUR-020 SUR-021 SUR-022 SUR-024 SUR-026 SUR-030 SUR-031 SUR-032 SUR-033 SUR-034 SUR-035 SUR-036 SUR-037 MRC-001 MRC-002 MRC-003 MCV-005 MSS-001 Cooldown from Hot Standby to Cold Shutdown Diesel Generator 24 Hour Load Test and Load Rejection, 3-OSP-023.2 Component Cooling Water Pumps Low Header Pressure Start Test, 3-OSP-030.5 Reactor Coolant System Leak Rate Calculations, 3-OSP-041.1 Reactor Protection System Logic Test, 3-OSP-049.1 RHR MOVs/System Pressure Interlock Test, 3-OSP-050.7 RHR MOVs 750, 751, 862, 863, Interlock Test, 3-0SP-050.8 Source Range Nuclear Instrumentation Analog Channel Operational Test, 3-0SP-059.1 Intermediate Range Nuclear Instrumentation Analog Channel Operational Test, 3-0SP-059.2 Intermediate Range NIS Setpoint Verification, 3-OSP-059.3 Power Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.4 Process Radiation Monitoring Operability Test, 3-OSP-067.1 Main Steam Isolation Valve Closure Test, 3-OSP-072 Standby Steam Generator Feedwater Pumps AvailabilityTest, O-OSP-074.3 AuxiliaryFeedwater Train 1 Operability Verification, 3-OSP-075.1 Main Turbine Valves Operability Test, 3-OSP-089 Engineered. Safeguards Integrated Test, 3-OSP-203.1 &3-OSP-203.2 RCCA Periodic Exercise, 3-OSP-028.6 Inducing Xenon Oscillations to Produce Various Incore AxialOQsets, O-OP-059.3 Operation ofthe Moveable Incore Detectors, O-OP-059.4 Accident MonitoringInstrumentation Channel Checks, 3-OSP-204 Safeguard Actuation System Logic Test, 3-0SP-063.1 Containment Isolation System Logic Test, 3-0SP-063.2 Component Cooling Water System Flow Balance, 3-0SP-030.9 Determination ofQuadrant Power TiltRatio, 3-0SP-059.10 Steam Generator Tube Rupture Large Break LOCAInside Containment With Loss OfOQsite Power Small Break LOCAInside Containment Non-Regenerative Heat Exchanger Tube Leak Small Leak in Safety Injection Piping Outside Containment
ERTIFICATIONTEST 8.1.2(lxc) 3.1.2(1xd) 3.1.2(2) 3.1.2(3) 3.1.2(4) 3.1.2(5) 3.1.2(6) 3.1.2(7) 3.1.2(8)
MRC-002 MRC-003 MRC-004 MFW-007 MCS-004 MGG-002 MGG-003 MGG-004 MGG-005 MGG-006 MMP-001 MMP-002 MMP-003 MMP-004 MMP-005 MMP-006 MMP-007 MMP-008 MRX-011 MSP-001 MRC-005 MRC-006 MFW-001 MCS-002 MCS-008 MSS-008 MSS-004 MCS-001 Large Break LOCAInside Containment With Loss OfQuite Power Small Break LOCAInside Containment PORV Failure (Open) Without High Pressure Injection Equivalent TMI-2Scenario Instrument AirSystem Operation and Malfunctions Loss of4kV Bus 3A Loss of4kVBus 3B Loss ofAllAC Power Loss of4kV Bus 3C Loss of4kV Bus 3D Loss ofVitalAC Bus 3P06 Loss ofVitalAC Bus 3P07 Loss ofVitalAC Bus 8POS Loss ofVitalAC Bus 8P09 Loss ofDC Bus 3A(3DOl)
Loss ofDC Bus 3B (3D23)
Loss ofDC Bus 4B (4D01)
Loss ofDC Bus 4A (4D28)
Loss ofC 4KVBus Reactor Trip Bus Stripping and Load Sequencing Tests Loss ofForced Reactor Coolant Flow Loss ofa Single Reactor Coolant Pump With Power Below P-8 Loss ofVacuum Tests, Including Loss ofCondenser Level Control Intake Cooling Water System Operations and Malfunctions Turbine Plant Cooling Water Operation and Malfunctions Loss ofRHR While in Cold Shutdown Loss ofInventory During a Shutdown and Partial Draindown Condition Component Cooling Water Operations and Malfunctions
ANS 3.5 SECTI N ERTIFI ATI NTEST 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)
MFW-002 MFW-006 MFW-007 MFW-008 MFW-003 MRX-002 MRX-004 MRX-005 MRX-006 MRX-007 MRX-011 MRX-007 MRX-008 MTU-001 MTU-002 MGG-001 MCV-001 MRC-007 MRC-010 MCV-002 MCV-004 MCV-005 MRX-009 MRX-010 MRX-011 MSG-001 MSG-002 MSG-007 MFW-004 MFW-005 Loss ofNormal Feedwater Failure ofInput Channels to the Feedwater Controller Equivalent TMI-2Scenario Loss ofFeedwater/ATWS Loss ofNormal and Emergency Feedwater Loss ofProtection System Channel Stuck Control Rod Uncoupled Control Rod Test Dropped Control Rod Shutdown With Inabilityto Drive Control Rods Loss ofC 4KVBus Reactor Trip Shutdown 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 kom 100% Power Generator Trip Uncontrolled Maximum Rate Boron Dilution Stuck Open Spray Valve Pressurizer Pressure and Level Control Malfunctions Charging System Failures Letdown and Volume Control Tank Operations and Malfunctions Non-Regenerative Heat Exchanger Tube Leak Manual Reactor Trip &om 100% Power Spurious High Containment Pressure SI Loss ofC 4KVBus Reactor Trip Main Steam Line Break Inside Containment Main Steam Line Break Outside Containment Main Steam Line Break With Reduced Shutdown Margin Feedwater Line Break Inside Containment Main Feedwater Line Break Outside Containment
~AN C
D CERTIFI ATI NTE T 3.1.2(21) 3.1.2(22) 3.1.2(23) 3.1.2(24) 3.1.2(25)
A.3.1 B.2.1 B.2.2(1)
B.2.2(2)
B.2.2(3)
B.2.2(4)
B.2.2(5)
B.2.2(6)
B.2.2(7)
B.2.2(8)
B.2.2(9)
B.2.2(10)
MRX-003 N MFW-006 F MRC-009 F
MRC-010 P
MSG-005 F
MSG-006 C
MTU-003 Tur MTU-008 H MTU-009 Tur MTU-011 F MSS-001 S
MSS-002 A
MCN-001 C
MFW-008 Lo NOT APPL RTT-002 S
SST-003 S
SST-002 SST-001 SST-004 MRX-009 MFW-003 MSG-003 MRC-005 MRC-005 MTU-001 MRX-001 MRC-002 MSG-001 MRC-004 uclear Instrumentation Failures ailure ofInput Channels to the Feedwater Controller ast Load Reduction, 3-ONOP-100 ressurizer Pressure and Level Control Malfunctions ailure ofReference Temperature to Steam Dumps losure ofa Single MSIVat Several DMerent Power Levels bine Lube Oil System (Bearings) ydrogen Cooling bine Lube Oil Control &Auto-Stop Oil ailure ofTurbine Control Valve Spring mall Leak in Safety Injection Piping Outside Containment ccumulator Operations and Malfunctions ontainment Emergency Systems Operations and Malfunctions ss ofFeedwater/ATWS ICABLE imulator Real Time Test Validation Test teady State 100% Power Heat Balance Steady State 75% Power Heat Balance Steady State 50% Power Heat Balance 100% Power 60 minute NullTransient Manual Reactor Trip from 100% Power Loss ofNormal and Emergency Feedwater Simultaneous Closure ofAllMSIVs Loss ofForced Reactor Coolant Flow Loss ofForced Reactor Coolant Flow Turbine Trip Which Does Not Cause Automatic Reactor Trip Maximum Rate Power Ramp (100% To 75% and Back to 100%)
Large Break LOCAInside Containment With Loss OfOKsite Power Main Steam Line Break Inside Containment PORV Failure (Open) Without High Pressure Injection
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