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 CERTIFICATION UPDATE 0 2 98iii80i5i ADQCK 05000250
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Plant-Referenced. Simulator Certification Report Turkey Point Units 3 and 4
FLORIDAPOWER AND LIGHT COMPANY TURKEYPOINT UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 TABLE OF 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 YEAR TEST PLAN (1999 - 2002) 5.0 OUTSTANDING DISCREPANCIES APPENDIX A TESTABSTRACTS A.l TESTS ADDED A.2 TESTS CHANGED APPENDIX B TEST MATRICIES
TURKEYPOINT UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2
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 it was 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 of these DR's.
Experience gained during initial certification testing and the testing during the last four year cycle, changes to the plant, and the availability of plant 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 of the basis for the changes. The changes in the plan are organized into the following three 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 of the 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 of the Institute of Nuclear Plant Operations, "Simulator Configuration Management System,"
INPO 87-016, August 1987.
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TURKEY POINT UNIT 3 SIMULATORCERTIFICATION UPDATE NUMBER 2 2.0 SIMULATORTESTS COMPLETED (1995 - 1998) 2.1 1995 TESTS TE T¹ TE TDE IPTI MPLETI N DATE MFW-002 Loss of Normal Feedwater 08-25-95 MFW-007 Equivalent TMI-2 Scenario 12-11-95 MGG-002 Loss of 4KV Bus 3A 07-21-95 MGG-003 Loss of 4KV Bus 3B 07-21-95 MGG-004 Loss of All AC 11-09-95 MGG-005 Loss of 4KV Bus 3C 07-21-95 MGG-006 Loss of 4KV Bus 3D 07-21-95 MMP-001 Loss of Vital AC Bus 3P06 08-25-95 MMP-002 Loss of Vital AC Bus 3P07 08-25-95 MMP-003 Loss of Vital AC Bus 3P08 08-25-95 MMP-004 Loss of Vital AC Bus 3P09 08-25-95 MMP-005 Loss of DC Bus 3A (3D01) 08-25-95 MMP-006 Loss of DC Bus 3B (3D23) 08-25-95 MMP-007 Loss of DC Bus 4B (4D01) 08-25-95 MMP-008 Loss of DC Bus 4A (4D23) 08-25-95 MRC-006 Loss of a Single RCP With Power Below P-8 11-09-95 MRC-007 Stuck Open Spray Valve 08-25-95 MSG-007 Main Steam Line Break from Hot Standby with Reduced Shutdown Margin 12-11-95 MSP-001 Bus Stripping and Load Sequencing Tests 12-11-95 NPE-002 Plant Startup Cold Shutdown to Hot Standby 11-17-95 NPE-003 Plant Startup from Hot Standby to Rated Power 12-11-95 SUR-026 Engineered Safeguards Integrated Test, 3-OSP-203.1 Er 3-OSP-203.2 11-17-95 SUR-030 Full Length RCC - Periodic Exercise, OP-1604.1 08-25-95 SUR-031 Inducing Xenon Oscillations to Produce Various Incore Axial Offsets, O-OP-059.3 11-09-95 Page 3
TURKEYPOINT UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 1995 TESTS (CONTINUED)
ANNUALTESTS
~TE T¹ TE TDE IPTI N MPLETI N DATE MFW-003 Loss of Normal and Emergency Feedwater 08-25-95 MRC-002 Large Break LOCA Inside Containment With Loss of OII'site Power 07-21-95 MRC-004 PORV Failure (Open) Without High Pressure Injection 07-21-95 MRC-005 Loss of Forced Reactor Coolant Flow 11-09-95 MRX-001 Maximum Rate Power Ramp (100% to 75% and back to 100%) 11-17-95 MRX-009 Manual Reactor Trip from 100% Power 07-21-95 MSG-001 Main Steam Line Break Inside Containment 11-09-95 MSG-003 Simultaneous Closure of All MSIVs 08-25-95 MTU-001 Turbine Trip Which Does Not Cause Automatic Reactor Trip 08-25-95 SST-001 Steady State 50% Power Heat Balance 11-09-95 SST-002 Steady State 75% Power Heat Balance 11-09-95 SST-003 Steady State 100% Power Heat Balance 11-09-95 SST-004 100% Power 60 min Null Transient 07-21-95 Page 4
TURKEYPOINT UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 2.2 1996 TESTS TE T4 TE TDE RIPTI N MPLETI N DATE MCV-001 Uncontrolled Maximum Rate Boron Dilution 12-08-96 MCV-002 Charging System Failures 12-03-96 MCV-004 Letdown and Volume Control Tank Operations and Malfunctions 12-03-96 MFW-004 Feedwater Line Break Inside Containment 12-03-96 MFW-006 Failure of Steam Generator Level Channel Providing Input to the Feedwater Controller 09-27-96 MRC-003 Small Break LOCA Inside Containment 09-27-96 MRC-009 Fast Load Reduction, 3-ONOP-100 12-03-96 MRX-010 Spurious High Containment Pressure SI 12-03-96 MSG-006 Closure of a Single MSIV At Several Different Power Levels 09-27-96 MTU-003 Turbine Lube Oil System (Bearings) 09-27-96 MTU-005 Turbine Turning Gear Operation 09-27-96 MTU-009 Turbine Lube Oil Control & Auto-Stop Oil 12-03-96 MTU-011 Failure of Turbine Control Valve Spring 12-03-96 NPE-005 Plant Shutdown from Rated Power to Hot Standby 12-08-96 NPE-006 Cooldown from Hot Standby to Cold Shutdown 12-03-96 SUR-004 Component Cooling Water Pumps Low Header Pressure Start Test, 3-OSP-030.5 07-03-96 SUR-009 Reactor Protection System Logic Test, 3-OSP-049.1 12-03-96 SUR-015 Intermediate Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.2 07-03-96 SUR-017 Power Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.4 07-08-96 SUR-020 Main Steam Isolation Valve Closure Test, 3-OSP-072 09-23-96 SUR-035 Containment Isolation Racks QR50 and QR51 Periodic Test, OP-4004.4 09-23-96 SUR-036 Component Cooling Water System Flow Balance, 3-OSP-030.9 12-08-96 SUR-037 Determination of Quadrant Power Tilt Ratio, 3-OSP-059.10 07-03-96 Page 5
TURKEYPOINT UNIT 3 SIMULATORCERTIFICATIONUPDATE I%UMBER 2 1996 TESTS (CONTINUED)
ANNUALTESTS
~TE T¹ TE TDE IPTI N MPLETI DATE MFW-003 Loss of Normal and Emergency Feedwater 09-27-96 MRC-002 Large Break LOCA Inside Containment With Loss of OQsite Power 07-03-96 MRC-004 PORV Failure (Open) Without High Pressure Injection 09-27-96 MRC-005 Loss of Forced Reactor Coolant Flow 09-27-96 MRX-001 Maximum Rate Power Ramp (100% to 75% and back to 100%) 12-03-96 MRX-009 Manual Reactor Trip from 100% Power 09-27-96 MSG-001 Main Steam Line Break Inside Containment 09-27-96 MSG-003 Simultaneous Closure of All MSIVs 12-03-96 MTU-001 Turbine Trip Which Does Not Cause Automatic Reactor Trip 09-27-96 SST-001 Steady State 50% Power Heat Balance 12-03-96 SST-002 Steady State 75% Power Heat Balance 12-03-96 SST-003 Steady State 100% Power Heat Balance 07-03-96 SST-004 100% Power 60 min Null Transient 09-27-96 Page 6
TURKEY POINT UNIT 3 SIMULATORCERTIFICATION UPDATE NUMBER 2 2.3 1997 TESTS TE T¹ TE TDE IPTI N MPLETI N DATE MCS-001 Component Cooling Water Operations and Malfunctions 12-11-97 MFW-001 Loss of Vacuum Tests, Including Loss of Condenser Level Control 12-11-97 MGG-001 Generator Trip 08-18-97 MRC-001 Steam Generator Tube Rupture 08-18-97 MRX-003 Nuclear Instrumentation Failure During Startup 08-18-97 MRX-006 Dropped Control Rod 08-18-97 MRX-007 Dropped With Inability to Drive Control Rods 12-11-97 MRX-Oll Loss of C 4KV Bus Reactor Trip 12-11-97 MSG-005 Failure of Reference Temperature to Steam Dumps 08-18-97 MTU-002 Turbine Trip from 100% Power 08-18-97 NPE-001 Plant Fill and Vent from a Partial Drain Down to a Solid Pressurizer 12-11-97 RTT-001 Simulator Real Time Test 05-29-97 RTT-002 Simulator Real Time Test Validation Test 05-29-97 SUR-003 Diesel Generator 24 Hour Load Test and Load Rejection, 3-OSP-023.2 08-18-97 SUR-005 Reactor Coolant System Leak Rate Calculations, 3-OSP-041.1 05-29-97 SUR-010 RHR MOVs/System Pressure Interlock Test, 3-OSP-050.7 05-29-97 SUR-011 RHR MOVs 750, 751, 862, 863, Interlock Test, 3-OSP-050.8 05-29-97 Standby Steam Generator Feedwater Pumps SUR-021'UR-022
/ Cranking Diesels Test, O-OSP-074.4 05-29-97 Auxiliary Feedwater Train 1 Operability Veri6cation, 3-OSP-075.1 05-29-97
'Procedure O-OSP-074.4 cancelled due to PC/M 95-060, Elimination of cranking 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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j 'I g ~ 'HHa J /f TURKEYPOINT UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 1997 TESTS (CONTINUED)
T~ETII TE TDE IPTI N MPLETI DATE SUR-024 Main Turbine Valves Operability Test, 3-OSP-089 08-18-97 SUR-032 Normal Operation of Incore Moveable Detector System And Power Distribution Surveillance, OP-12404.1 12-11-97 SUR-033 Accident Monitoring Instrumentation Channel Checks, 3-OSP-204 05-29-97 SUR-034 Safeguards Relay Rack Train A, B, Periodic Test, OP-4004.2 05-29-97 The following tests were moved up from 1998 to 1997 due to the incorporation of the Cycle 15 core into the simulator.
~TE TII TE TDE IPTI MPLETI N DATE SUR-001 Initial Criticality aRer Refueling, O-OSP-040.6 08-18-97 SUR-002 Nudear Design Check Tests During Startup Sequence 08-18-97 After Refueling, O-OSP-040.5
'Procedure OP-12404.1 Cancelled and replaced by O-OP-059.4, Operation of the Moveable Incore Detectors.
'Procedure O-OSP-040.5 title changed to Nuclear Design Verification.
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TURKEYPOINT UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 1997 TESTS (CONTINUED)
ANNUALTESTS
~TE T¹ TE TDE RIPTI MPLETI N DATE MFW-003 Loss of Normal and Emergency Feedwater 08-18-97 MRC-002 Large Break LOCA Inside Containment With Loss Of OQsite Power 12-11-97 MRC-004 PORV Failure (Open) Without High Pressure Iajection 08-18-97 MRC-005 Loss of Forced Reactor Coolant Flow 08-18-97 MRX-001 Maximum Rate Power Ramp (100% to 75% and back to 100%) 08-18-97 MRX-009 Manual Reactor Trip from 100% Power 08-18-97 MSG-001 Main Steam Line Break Inside Containment 08-18-97 MSG-003 Simultaneous Closure of All MSIVs 08-18-97 MTU-001 Turbine Trip Which Does Not Cause Automatic Reactor Trip 08-18-97 SST-001 Steady State 50% Power Heat Balance 12-11-97 SST-002 Steady State 75% Power Heat Balance 08-18-97 SST-003 Steady State 100% Power Heat Balance 08-18-97 SST-004 100% Power 60 min Null Transient 05-29-97 Page 9
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TURKEYPOINT UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 2.4 1998 TESTS TE T¹ TE TDE IPTI MPLETI N DATE MCN-001 Containment Emergency Systems Operations and Malfunctions 09-15-98 MCS-002 Intake Cooling Water System Operations and Malfunctions 09-15-98 MCS-003 Turbine Plant Cooling Water Operation and Malfunctions 09-15-98 MCS-004 Instrument Air System Operation and Malfunctions 09-15-98 MCV-005 Non-Regenerative Heat Exchanger Tube Leak 09-15-98 MFW-005 Main Feedwater Line Break Outside Containment 09-01-98 MFW-008 Loss of Normal Feedwater/ATWS 09-15-98 MRX-002 Loss of Protection System Channel 09-01-98 MRX-004 Stuck Control Rod 09-01-98 MRX-005 Uncoupled Control Rod Test 09-01-98 MRX-008 Fuel Cladding Failure Resulting in High Reactor Coolant Activity 09-15-98 MSG-002 Main Steam Line Break Outside Containment 04-22-98 MSS-001 Small Leak in Safety Injection Piping Outside Containment 09-01-98 MSS-002 Accumulator Operations and Malfunctions 09-15-98 MSS-003 Loss of RHR While in Cold Shutdown 09-01-98 MSS-004 Loss of Inventory During A Shutdown and Partial Draindown Condition 09-01-98 MTU-006 Hydrogen Seal Oil 09-01-98 MTU-008 Hydrogen Cooling 09-01-98 NPE-004 Reactor Trip Followed By Recovery to Rated Power 08-05-98 SUR-014 Source Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.1 08-05-98 SUR-016 Intermediate Range NIS Setpoint Verification, 3-OSP-059.3 08-05-98 SUR-019 Process Radiation Monitoring Operability Test, 3-OSP-067.1 08-05-98 Page 10
TURKEYPOINT UNIT 3 SIMULATOR CERTIFICATIONUPDATE NUMBER 2 1998 TESTS (CONTINUED)
ANNUALTESTS
~E'~T¹ TE T DE IPTI MPLETI N DATE MFW-003 Loss of Normal and Emergency Feedwater 04-22-98 MRC-002 Large Break LOCA Inside Containment With Loss Of Offsite Power 04-22-98 MRC-004 PORV Failure (Open) Without High Pressure Injection 04-22-98 MRC-005 Loss of Forced Reactor Coolant Flow 04-22-98 MRX-001 Maximum Rate Power Ramp (100% to 75% and back to 100%) 08-05-98 MRX-009 Manual Reactor Trip from 100% Power 08-05-98 MSG-001 Main Steam Line Break Inside Containment 04-22-98 MSG-003 Simultaneous Closure of All MSIVs 04-22-98 MTU-001 Turbine Trip Which Does Not Cause Automatic Reactor Trip 08-05-98 SST-001 Steady State 50% Power Heat Balance 08-05-98 SST-002 Steady State 75% Power Heat Balance 08-05-98 SST-003 Steady State 100% Power Heat Balance 08-05-98 SST-004 100% Power 60 min Null Transient 04-22-98 Page 11
TURKI<Y POINT UNIT 3 SIMULATORCERTIFICATIONUPDATE NUINBER 2 3.0 CERTIFICATIONTEST CHANGES (1995 - 1998)
Experience gained during initial certification 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 following three categories: Changes, Deletions, and Additions. These modifications to the test plan were made to eliminate duplication, eliminate test runs that provide little or 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 of the 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 UNIT 3 SIMULATORCERTIFICATION UPDATE NUMBER 2 3.1 CHANGES MCS-004, Instrument Air Operations and Malfunctions This test consists of 6 cases: (1) Loss of diesel air compressor, (2) Instrument air dryer fouling, (3) Instrument air reservoir leak, (4) Complete loss of instrument air, (5) Loss of containment air header, and (6) Loss of turbine 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 of the compressors either initially or during the scenario to get the desired loss of air. Run 1, Loss of Diesel Air Compressor was changed to Sequential Loss of Air Compressors and Control Valve Logic. This run verifies the auto start capability of each 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 of Run 1 to verify auto start capability of each of the compressors. Therefore Run 3 willbe deleted and replaced with a loss of Unit 3 instrument air. In this run, Unit 4 will still be supplying air to the intake area, the control room and the auxiliary building.
MCV-002, Charging System Failures This test consists of four runs: (1) Seal injection filter clogging, (2) Charging pump discharge valve failed closed, (3) Charging pump discharge leak, and (4) Loss of all charging. Run 1 provides little indication 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 of charging with no operator actions. The scenario willbe changed to perform operator actions using ONOP-047.1, Loss of All Charging. The scenario will start 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 UNIT 3 SIMULATORCERTIFICATION UPDATE NUMBER 2 MCV-004, Letdown and Volume Control Tank Operations and Malfunctions This test consists of four 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 fail VCT level transmitter LT-115 high.
This will cause the valve to go to divert but will also bring in the VCT Hi/Lo level annunciator, prevent an auto makeup to the VCT and prevent auto swap over of the charging pump suction &om the VCT to the RWST. No operator action will take place until all of the failures can be verified. Then 3-ONOP-046.4, Malfunction of the 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 of VCT level transmitter LT-112 high. This willcause the VCT level control valve to go to full divert and ifthe makeup flow is less than charging flow, actual VCT level will drop. When the failure has been identified, then ONOP-046.4 willbe used to recover from the transient.
MFW-006, Failure of Steam 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. A third case was run in 1996 to compare a failure of the steam flow input 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 ifit becomes available. The title willbe changed to "Failure of Input Channels to the Feedwater Controller".
MRX-003, Nuclear Instrumentation Failure During Startup This test consisted of two runs: (1) Failure of both intermediate range channels to prevent the source range trip from being blocked and (2) Failure of 3 out of the 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 of a source range channel, (2) failure of an intermediate range channel, and (3) failure of a power range channel. In each run the appropriate oE-normal procedure willbe used to take the failed channel out of service. The title of MRX-003 willbe changed to "Nuclear Instrumentation Failures".
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TURKEYPOINT UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 MRX-007, Dropped Rod with Inability to Drive Control Rods This test consisted of a dropped rod causing an automatic turbine runback to 70%
power with control rods immovable. With the elimination of the 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) "Inability to insert control rods" the scenario willbe changed. The initial condition willbe 50% power versus 100% power and the initiating event willbe an urgent failure in the logic cabinet.
This will require a shutdown to hot standby using boration only. The test wiH be renamed "Shutdown with Inability to Drive Control Rods".
SUR-001 Initial Criticality ARer Refueling, O-OSP-040.6 Plant procedures O-OSP-040.5, Nuclear Design Verification and O-OSP-040.6, Initial Criticality After Refueling have been cancelled and combined into one procedure:
O-OSP-040.16, Initial Criticality ARer Refueling and Nuclear Design Verification.
Therefore SUR-001, Initial Criticality after Refueling and SUR-002, Nuclear Design Verification willbe combined into one test, SUR-001, Initial Criticality aRer 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 it with 3-OSP-028.6, RCCA Periodic Exercise. Therefore SUR-030 willbe renamed "RCCA Periodic Exercise, 3-OSP-028.6", however, the intent of this 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 it with 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 of this 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 it with 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 of this test remains the same.
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P II ' A>~ I (gs ~ ~ lI e I TURKEYPOINT UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 3.2 DELETIONS MTU-006, Hydrogen Seal Oil This test checks normal and abnormal operation of the seal oil system. Allof the controls and indicators for the seal oil system are located outside of the control room.
The only indication in the control room of a seal oil failure is the hydrogen panel trouble annunciator. Thus, continuing to test this system provides little value in terms of training. 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 verify that the simulator is operating in real time. In order to run in real time the execution of all of the modules must be completed every 200 milliseconds. Modules are divided into 4 legs of 50 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 will abort during training, examinations or during certification testing ifit is not operating in real time. Therefore this test is no longer required and willbe deleted. Note that RTT-002 Simulator Real Time Validation Test will still be run. This test verifies that the simulator will abort if: (1) Four consecutive overruns occur, (2) One of the 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 UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 3.3 ADDITIONS MRC-010, Pressurizer Pressure and Level Control Malfunctions This test willconsist of two runs: (1) Failure of the pressure control channel (PT-444) high, and (2) Failure of the 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 will simulate the evacuation of the control room due to a fire and the stabilization of the 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 UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 4.0 FOUR YEAR TEST PLAN (1999-2002)
Per the requirements of Regulatory Guide 1.149, the Simulator Certification test program willbe conducted in its entirety on a four year cycle. All of the ANSI/ANS-3.5-1985 Appendix B tests willbe performed annually. Approximately 25% of the 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 of the next four years. The tests planned each year represent a cross section of the various types of tests. 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 UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 Table 4-1 Annual Tests MFW-003 Loss of Normal and Emergency Feedwater MRC-002 Large Break LOCA Inside Containment With Loss Of Offsite Power MRC-004 PORV Failure (Open) Without High Pressure Injection MRC-005 Loss of Forced Reactor Coolant Flow MRX-001 Maximum Rate Power Ramp (100% To 75% and back to 100%)
MRX-009 Manual Reactor Trip from 100% Power MSG-001 Main Steam Line Break Inside Containment MSG-003 Simultaneous Closure of All MSIVs MTU-001 Turbine Trip Which Does Not Cause Automatic Reactor Trip SST-001 Steady State 50% Power Heat Balance SST-002 Steady State 75% Power Heat Balance SST-003 Steady State 100% Power Heat Balance SST-004 100% Power 60 Minute Null Transient Page 19
If II TURKEYPOINT UNIT 3 SIMULATORCERTIFICATION UPDATE NUMBER 2 Table 4-2 1999 Test Plan MFW-002 Loss of Normal Feedwater MFW-007 Equivalent TMI-2 Scenario MGG-002 Loss of 4KV Bus 3A MGG-003 Loss of 4KV Bus 3B MGG-004 Loss of AllAC MGG-005 Loss of 4KV Bus 3C MGG-006 Loss of 4KV Bus 3D MMP-001 Loss of Vital AC Bus 3P06 MMP-002 Loss of Vital AC Bus 3P07 MMP-003 Loss of Vital AC Bus 3P08 MMP-004 Loss of Vital AC Bus 3P09 MMP-005 Loss of DC Bus 3A(3DOl)
MMP-006 Loss of DC Bus 3B (3D23)
MMP-007 Loss of DC Bus 4B (4DOl)
MMP-008 Loss of DC Bus 4A (4D23)
MRC-006 Loss of a Single Reactor Coolant Pump With Power Below P-8 MRC-007 Stuck Open Spray Valve MSG-007 Main Steam Line Break from Hot Standby with Reduced Shutdown Margin.
MSP-001 Bus Stripping and Load Sequencing Tests NPE-002 Plant Startup Cold Shutdown to Hot Standby NPE-003 Plant Startup from Hot Standby to Rated Power SUR-026 Engineered Safeguards Integrated Test, 3-OSP-203.1 & 3-OSP-203.2 SUR-030 RCCA Periodic Exercise, 3-OSP-028.6 SUR-031 Inducing Xenon Oscillations to Produce Various Incore Axial Offsets,O-OP-059.3 Page 20
TURKEYPOINT UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 Table 4-3 2000 Test Plan MCV-001 Uncontrolled, Maximum Rate Boron Dilution MCV-002 Charging System Failures MCV-004 Letdown and Volume Control Tank Operations and'Malfunctions MFW-004 Feedwater Line Break Inside Containment MFW-006 Failure of Input Channels to the Feedwater Controller MRC-003 Small Break LOCA Inside Containment MRC-009 Fast Load Reduction, 3-ONOP-100 I MRX-010 Spurious High Containment Pressure SI MS 6-006 Closure of a Single MSIV At Several Different Power Levels MTU-003 Turbine Lube Oil System (Bearings)
MTU-005 Turbine Turning Gear Operation MTU-009 Turbine Lube Oil Control L Auto-Stop Oil MTU-Oll Failure of Turbine Control Valve Spring NPE-005 Plant Shutdown from Rated Power to Hot Standby NPE-006 Cooldown from Hot Standby to Cold Shutdown SUR-004 Component Cooling Water Pumps Low Header Pressure Start Test, 3-OSP-030.5 SUR-009 Reactor Protection System Logic Test, 3-OSP-049.1 SUR-015 Intermediate Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.2 SUR-017 Power Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.4 SUR-020 Main Steam Isolation Valve Closure Test, 3-OSP-072 SUR-035 Containment Isolation System Logic Test, 3-OSP-063.2 SUR-036 Component Cooling Water System Flow Balance, 3-OSP-030.9 SUR-037 Determination of Quadrant Power Tilt Ratio, 3-OSP-059.10 Page 21
TURKEYPOINT UNIT 3 SIMULATORCERTIFICATION UPDATE NUMBER 2 Table 4-4 2001 Test Plan MCS-001 Component Cooling Water Operations and Malfunctions MFW-001 Loss of Vacuum Tests, Including Loss of Condenser Level Control MGG-001 Generator Trip MRC-001 Steam Generator Tube Rupture MRC-010 Pressurizer Pressure and Level Control Malfunctions MRX-003 Nuclear Instrumentation Failures MRX-006 Dropped Control Rod MRX-007 Shutdown With Inability to Drive Control Rods MRX-011 Loss of C 4KV Bus Reactor Trip MSG-005 Failure of Reference Temperature to Steam Dumps MTU-002 Turbine Trip from 100% Power NPE-001 Plant Fill and Vent from a Partial Drain Down to a Solid Pressurizer RTT-002 Simulator Real Time Test Validation Test SUR-003 Diesel Generator 24 Hour Load Test and Load Rejection, 3-OSP-023.2 SUR-005 Reactor Coolant System Leak Rate Calculations, 3-OSP-041.1 SUR-010 RHR MOVs/System Pressure Interlock Test, 3-OSP-050.7 SUR-011 RHR MOVs 750, 751, 862, 863, Interlock Test, 3-OSP-050.8 SUR-021 Standby Steam Generator Feedwater Pumps AvailabilityTest, O-OSP-074.3 SUR-022 Auxiliary Feedwater Train 1 Operability Verification, 3-OSP-075.1 SUR-024 Main Turbine Valves Operability Test, 3-OSP-089 SUR-032 Operation of the Moveable Incore Detectors, O-OP-059.4 SUR-033 Accident Monitoring Instrumentation Channel Checks, 3-OSP-204 SUR-034 Safeguard Actuation System Logic Test, 3-OSP-063.1 Page 22
TURKEYPOINT UNIT 3 SIMULATORCERTIFICATION UPDATE NUMBER 2 Table 4-5 2002 Test Plan MCN-001 Containment Emergency Systems Operation and Malfunctions MCS-002 Intake Cooling Water System Operations and Malfunctions MCS-003 Turbine Plant Cooling Water Operation and Malfunctions MCS-004 Instrument Air System Operation and Malfunctions MCV-005 Non-Regenerative Heat Exchanger Tube Leak MFW-005 Main Feedwater Line Break Outside Containment MFW-008 Loss of Normal Feedwater / ATWS MRX-002 Loss of Protection System Channel MRX-004 Stuck Control Rod MRX-005 Uncoupled Control Rod Test MRX-008 Fuel Cladding Failure Resulting in High Reactor Coolant Activity MRX-012 Control Room Evacuation, 3-ONOP-105 MSG-002 Main Steam Line Break Outside Containment MSS-001 Small Leak in Safety Injection Piping Outside Containment MSS-002 Accumulator Operations and Malfunctions MSS-003 Loss of RHR While in Cold Shutdown MSS-004 Loss of Inventory During Partial Draindown MTU-008 Hydrogen Cooling NPE-004 Reactor Trip Followed By Recovery to Rated Power SUR-001 Initial Criticality aRer Refueling and Nuclear Design Verification, O-OSP-040.16 SUR-014 Source Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.1 SUR-016 Intermediate Range NIS Setpoint Verification, 3-OSP-059.3 SUR-019 Process Radiation Monitoring Operability Test, 3-OSP-067.1 Page 23
(j r
(
TURKEYPOINT UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 5.0 OUTSTANDING DISCREPANCIES 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 priority DR's. The SCRB willreview and approve the extension of the 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
TURKEY POINT UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 Table 5-1 OPEN DISCREPANCIES T~ET DR 4 TITLE DUE DATE MCN001 9800103 Iodine concentrations increase when ECF fans started 09-02-99 MCS 003 9800107 H2 cooler inlet temperature drops to zero momentarily 09-16-99 MCS004 9800104 CV-1605 setpoint incorrect 09-16-99 MCV005 9800074 NRHX tube leak does not work properly 07-17-99 9800108 R-17B spiked during NIBS tube leak 09-16-99 MFW008 9800109 Investigate RETRAN / Simulator pressure diQerence 09-16-99 MRC005 9800008 HighMSRtemperatures afterRxtrip 02-09-99 MRX009 9800006 MSR relief valves don't lik when MSR steam supply valves left open 02-09-99 MSS003 9800098 RCS pressure decreases below atmospheric pressure 09-02-99 9800099 Cold Leg Temperature decreases throughout transient 09-01-99 SST001 9800048 Hotwell level doesn't match plant 04-24-99 SUR016 9800077 Add 5 minute average ~T to ERDADS display 07-17-99 9800078 Tave and Tref need. 2 decimal precision on ERDADS MA2 display 07-17-99 N/A 9800105 Physical Fidelity 12-31-98 Page 25
TURKEY POINT UNIT 3 SIMULATOR CERTIFICATIONUPDATE NUMBER 2 APPENDIX A TEST ABSTRACTS A.l TESTS ADDED
TURKEY POINT SIMUIATOR CERllFICATION TEST PROCEDURE llTLEr PRESSURIZER PRESSURE AND LEVEL CONTROL MALFUNCTIONS NUMBER MRC-010 AN$ 3.5 REFERENCE SECTIONS: 3.1.2 (18) Failure of reactor coolant pressure and volume control systems DESCRIPTION This test examines the simulator's ability to model malfunctions In the pressurizer pressure and level control system. Two cases willbe run. In the first case, the pressure control transmitter PT-3-444 willbe failed high. After the response of the 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~A willbe failed low. After the response of the simulator ls verified operator 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 FINAL CONDITIONS Full power steady state, Plant stabilized in accordance with the ONOP.
SIMULATOR CONFIGURATION REVIEW BOARD APPROVAL FOR USE TEST TEAM DATE:
DATE: DATE:
DATE: DATE:
TURKEY POINT SIMUlATOR CERTIFICA11ON 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 of the 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.
INI11AL CONDITIONS FINAL CONDmONS Full power steady state. Plant stabilized at HSB and a cooldown begun In accordance with the ONOP.
SIMUlATORCONFIGURATION REVIEW BOARD APPROVAL FOR USE TEST TEAM DATE: DATE:
DATE: DATE:
DATE: DATE:
TURKEY POINT UNIT 3 SIMULATORCERTIFICATIONUPDATE NUMBER 2 APPENDIX A TEST ABSTRACTS A.2 TESTS CHANGED
TURKEYPOINT SIMUlATOR CERTIFICATION TEST PROCEDURE TITLE: INSTRUMENTAIRSYSTEM OPERATIONS AND MAIFUNCTIONS NUMBER MCS-004 ANS 3.5 REFERENCE SECTIONS: 3.1.2(2) Loss of Instrument Air DESCRIPTION The purpose of this test is to verify the proper performance of the 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 first run Involves an air reservoir leak to test the logic associated with auto starting of the diesel and electric air compressors and the Units 3 & 4 cross tie control valves. The ability to supply Instrument air from the service air header is also Unit 4 cross tie control valve willIsolate to protect Unit 4's afr supply and continue to supply Unit 3's Intake area, the control room, and the auxiliary building. The fourth run willInvolve a total loss of instrument air on both Units 3 &4. The fifth run wiibe a loss of the containment air header and the sixth run willbe a loss of the turbine air header.
OPTIONS leaks can be instated. The diesel air compressor discharge pressure and the amount and rate of dryer fouling can also be varied. The instrument air filters can be used Instead of the dryers.
INITIALCONDITIONS FINAL CONDmONS MOL steady state at IK% power Simulator response to the failure verified.
SIMUIATOR CONFIGURATION REVIEW BOARD APPROVAL FOR USE TEST TEAM DATE: DATE:
DATE:
DATE: DATE:
TURKEY POINT SIMULATORCERTIFICATION TEST PROCEDURE TITLEr CHARGING S YSTEM FAILURES NUMBER MCV-002 ANS 3.5 REFERENCE SECTIONS: 3.1.2 (18) Failure of Reactor Coolant System Pressure and Volume Control Systems DESCRIP11ON The purpose of this test Is to simulate various malfunctions in the charging and seal injection systems in order to ven'fy proper simulator modeling of these systems. Two cases willbe run. The first run willconsist of a leak downstream of HCV-121 with no operator actions. The second run wi7I be 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 of failing almost any component in the charging system. Therefore there are wide variety of failures are possible.
INITIALCONDITIONS FINAL CONDITIONS Run 1: 100% power, steadystate. Run 1: System parameters stabilized Run 2: 50K power, steady state. Run 2: 3~OPM7.1 completed, HHSI pumps maintaining pressurizer level.
SIMULATOR CONFIGURATION REVIEW BOARD APPROVAL FOR USE DATE: DATE:
DATE: DATE:
DATE: DATE:
TURKEY POINT SIMUIATORCERTIFICATION TEST PROCEDURE TITLEr LEIDOWNAND VOLUMECONTROL TANKSYSTEM OPERATIONS AND MALFUNCTIONS NUMBER: MCV-004 ANS 3.5 REFERENCE SECTIONS: 3.1.2 (18) Failure of Reactor Coolant Pressure and Volume Control Systems DESCRIPTION The test checks the response of the Letdown and Volume Control Tank portions of the CVCS system. Various malfunctions, which affect this system, willbe initiated to verify proper system response. A total of four different malfunction tests willbe run: (I) The letdown control valve PCV-145 willbe failed open, 0 PCV- 145 wi7I be failed closed, (3) The VCT level control transmitter LT-1 15 willbe fai!ed high, and (4) The VCT level transmitter LT-1 12 failed high. Runs 1 and 2 willbe left to run without any operator action. In Runs 3 and 4 operator action willbe taken using 3-ONOP-046.4, Malfunction of the 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 FINAL CONDmONS 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.
SIMULATORCONFIGURATION REVIEW BOARD APPROVAL FOR USE TEST TEAM DATE: DATEr DATE:
DATE: DATE:
TURKEYPOINT SIMUIATOR CERTIFICATION TEST PROCEDURE TITLEr FAILURE OF INPUT CHANNELS TO THE FEED WATER CONTROllER 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 of the simulator to a failed steam generator level, steam flow, or feed flow channel when that channel is the controlling Input to the feedwater regulating valve. Three cases willbe run. The first run willbe a failure of the controlling level channel with no operator actions. The second run willbe the failure of the controlling level channel but operator action willbe taken to stabilize the plant. The last run willbe a failure of one the controlling inputs (steam flow. feed flow or level) where plant data Is available and operator action willbe taken to mitigate the event.
OPllONS Any of the three steam generators may be used.
INITIALCONDITIONS FINAL CONDITIONS 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 SIMUlATOR CONFIGURATION REVIEW BOARD APPROVAL FOR USE DATE: DATE:
DATE: DATE:
DATE: DATB
TURKEYPOINT SIMUIATORCERTIFICATION TEST PROCEDURE TITLE: NUCLEAR INSTRUMENTATIONFAILURES NUMBER MRX-003 ANS 3.5 REFERENCE SECTIONS: 3.1.2 (21) Nuclear Instrumentation Failures DESCRIPTION This test examines the simulator's ability to model malfunctions of the nuclear instrumentation system. Three cases willbe run. In the first case, 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. After the channel is visually verllied to be under-compensated it willbe taken out of service 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 Any of the source, Intermediate, or power range channels may be failed.
INITIALCONDITIONS FINAL CONDITIONS Run 1: Cold shutdown. Run 1: Source range channel removed from service per ~OP-059.5.
Run 2: Full power steady state. Run 2: Intermediate range channel removed from service per 3-ONOP-059.7.
Run 3: Full power steady state. Run 3: Power range channel removed from service per 3~OP-059.8.
SIMUIATORCONFIGURATION REVIEW BOARD APPROVAL FOR USE DATE: DATE:
DATE: DATE:
DATE: DATE:
TURKEYPOINT SIMUlATORCERTIFICA11ON TEST PROCEDURE 11TLE: SHUTDOWN WITH INABILITYTO DRIVE CONTROL 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) Inability to 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 FINAL CONDITIONS Steady state R% power, MOL Stable fn hot standby.
SIMUIATORCONFIGURATION REVIEW BOARD APPROVAL FOR USE DATE: DATE:
DATE: DATE:
DATE: DATE:
TURKEYPOINT SIMULATORCERTIFICATION TEST PROCEDURE TITLE: INITIALCRmCALITYAFTERREFUELINGAND NUCLEAR DESIGN 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 of the initial cnticaifty 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 Initial cnticality and core performance testing procedures. The reactor willbe Ch7uted to criticality and power escalated to establish the point of adding nuclear heat. Core performance testing including measurement of the boron endpoint, differential boron worth, isothermal temperature coefficient and control rod worth willbe performed. The results willbe compared with plant test data and design data from the nuclear design report.
OPTIONS parts of the test requfre chemistry testing for boron concentration. The simulator computed values for boron concentration may be used for these steps.
INITIALCONDI11ONS FINAL CONDITIONS BOL. hot standby. Allrods In. Surveillance procedure complete SIMUIATOR CONFIGURATION REVIEW'OARD APPROVAL FOR USE TEST TEAM DATE: DATE:
DATE: DATE:
DATE: DATE:
TURKEY POINT SIMULATORCERTIFICATION lEST 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 of performing the surveillance procedure 3-OSP-Q2B.6, which exercises the control and shutdown rods. In this surveillance each bank of rods ls moved In 10 to 20 steps. The step counters and rod position indicators gal s1 willbe monitored for proper movement and for less than 12steps deviation. The proper operation of the rod off top lights willbe checked and the actuation of the shutdown bank off top alarm willbe verified for shutdown banks A and B. With no malfunctions present this test should pass the applicable acceptance cn'teria contained in 3-OSP-Q2B.6. The data sheets of this 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 FINAL CONDITIONS IK% power. The test ls complete when the procedure ls complete.
SIMUlATOR CONFIGURATION REVIEW BOARD APPROVAL FOR USE DATE: DATE:
DAlE: DATE:
TURKEYPOINT SIMUlATORCERTIFICATION TEST 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 ability of the simulator to support the operator conducted surveillance procedure 3-OSP-M. I, Safeguards Actuation System Logic Test. With no malfunctions present, the ability to successfully perform this surveillance willbe verifIed.
OPTIONS This test can be performed at any power level and at time In core life.
INITIALCONDITIONS FINAL CONDITIONS IIX% power. steady state, NIOL Surveillance complete.
SIMULATOR CONFIGURATION REVIEW BOARD APPROVAL FOR USE DATE: DATE:
DATE: DATE:
TURKEYPOINT SIMUlATORCERTIFICATION TEST PROCEDURE TITLEr CONMINMENTISOIATIONSYSlEM LOGIC 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 ability of the simulator to support the operator conducted surveillance procedure 3-OSP~.2. Containment Isolation System Logic Test. With no malfunctions present, the ability to successfully perform this surveillance willbe verified.
OPTIONS This test can be performed at any power level and at time in core life.
INITIALCONDITIONS FINAL CONDlllONS IR% power, steady state, MOL Surveillance complete.
SIMUlATOR CONFIGURATION REVIEW BOARD APPROVAL FOR USE TEST lEAM DATE: DAlB DATE: DAlB DATE: DATE:
TURKEYPOINT UNIT 3 SIMULATORCERTIFICATION UPDATE NUMBER 2 APPENDIX B TEST MATRICIES
TABLE B-1 TURKEYPOINT CERTIFICATIONTEST MATRIXPROFILE l!AAL EROFTE T MALFUNCTIONS CONTAINMENT(MCN)
COMMON SERVICES (MCS)
CHEMICAL& VOLUME CONTROL SYSTEM (MCV)
GENERATOR & GRID (MGG) 6 MAINPOWER DISTRIBUTION(MMP) 8 REACTOR COOLANT SYSTEM (MRC)
REACTOR (MRX) 12 STEAM GENERATOR & MAINSTEAM (MSG)
STANDBYPOWER & SYNCHRONIZATION(MSP)
SAFETY SYSTEMS (MSS)
TURBINE (MTU)
SUBTOTAL 70 OTHERS COMPUTER REAL TIME TEST (RTT)
STEADY STATE TESTS (SST)
NORMiALPLANT EVOLUTIONS (NPE)
OPERATOR CONDUCTED SURVEILLANCETESTING (SUR) 25 SUBTOTAL 36 TOTAL 106
TABLE B-2 ANSI/ANS-3.5-1985 CERTIFICATIONTEST MATRIX A~NS .SS 5 G ERSISGA I N S NPE-001 Plant Fill and Vent &om a Partial Drain Down to a Solid Pressurizer NPE-002 Plant Startup from Cold Shutdown to Hot Standby NPE-003 Plant Startup from Hot Standby to Rated Power NPE-004 Reactor Trip Followed By Recovery to Rated Power NPE-003 Plant Startup from Hot Standby to Rated Power NPE-004 Reactor Trip Followed By Recovery to Rated Power NPE-004 Reactor Trip Followed By Recovery to Rated Power NPE-002 Plant Startup from Cold Shutdown to Hot Standby NPE-003 Plant Startup from Hot Standby to Rated Power NPE-004 Reactor Trip Followed By Recovery to Rated Power NPE-005 Plant Shutdown from Rated Power to Hot Standby NPE-006 Cooldown from Hot Standby to Cold Shutdown 3.1.1(6) MRC-009 Fast Load Reduction, 3-ONOP-100 MRX-007 Shutdown with Inability to Drive Control Rods NPE-003 Plant Startup &om Hot Standby to Rated Power NPE-004 Reactor Trip Followed By Recovery to Rated Power NPE-005 Plant Shutdown from Rated Power to Hot Standby 3.1.1(7) NOT APPLICABLE 3.1.1(8) NPE-005 Plant Shutdown from Rated. Power to Hot Standby NPE-006 Cooldown from Hot Standby to Cold Shutdown SUR-001 Initial Criticality After Refueling and Nuclear Design Verification, O-OSP-040.16
~S. S D CERTIFICATI NTE T 3.1.1(10) NPE-006 Cooldown from Hot Standby to Cold Shutdown SUR-003 Diesel Generator 24 Hour Load Test and Load Rejection, 3-OSP-023.2 SUR-004 Component Cooling Water Pumps Low Header Pressure Start Test, 3-OSP-030.5 SUR-005 Reactor Coolant System Leak Rate Calculations, 3-OSP-041.1 SUR-009 Reactor Protection System Logic Test, 3-OSP-049.1 SUR-010 RHR MOVs/System Pressure Interlock Test, 3-OSP-050.7 SUR-011 RHR MOVs 750, 751, 862, 863, Interlock Test, 3-0SP-050.8 SUR-014 Source Range Nuclear Instrumentation Analog Channel Operational Test, 3-0SP-059.1 SUR-015 Intermediate Range Nuclear Instrumentation Analog Channel Operational Test, 3-0SP-059.2 SUR-016 Intermediate Range NIS Setpoint Verification, 3-OSP-059.3 SUR-017 Power Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.4 SUR-019 Process Radiation Monitoring Operability Test, 3-OSP-067.1 SUR-020 Main Steam Isolation Valve Closure Test, 3-OSP-072 SUR-021 Standby Steam Generator Feedwater Pumps AvailabilityTest, O-OSP-074.3 SUR-022 Auxiliary Feedwater Train 1 Operability Verification, 3-OSP-075.1 SUR-024 Main Turbine Valves Operability Test, 3-OSP-089 SUR-026 Engineered. Safeguards Integrated Test, 3-OSP-203.1 & 3-OSP-203.2 SUR-030 RCCA Periodic Exercise, 3-OSP-028.6 SUR-031 Inducing Xenon Oscillations to Produce Various Incore Axial OQsets, O-OP-059.3 SUR-032 Operation of the Moveable Incore Detectors, O-OP-059.4 SUR-033 Accident Monitoring Instrumentation Channel Checks, 3-OSP-204 SUR-034 Safeguard Actuation System Logic Test, 3-0SP-063.1 SUR-035 Containment Isolation System Logic Test, 3-0SP-063.2 SUR-036 Component Cooling Water System Flow Balance, 3-0SP-030.9 SUR-037 Determination of Quadrant Power Tilt Ratio, 3-0SP-059.10 3.1.2(l)(a) MRC-001 Steam Generator Tube Rupture 3.1.2(1Xb) MRC-002 Large Break LOCA Inside Containment With Loss Of OQsite Power MRC-003 Small Break LOCA Inside Containment MCV-005 Non-Regenerative Heat Exchanger Tube Leak MSS-001 Small Leak in Safety Injection Piping Outside Containment
ERTIFICATIONTEST 8.1.2(lxc) MRC-002 Large Break LOCA Inside Containment With Loss Of Quite Power MRC-003 Small Break LOCA Inside Containment 3.1.2(1xd) MRC-004 PORV Failure (Open) Without High Pressure Injection MFW-007 Equivalent TMI-2 Scenario 3.1.2(2) MCS-004 Instrument Air System Operation and Malfunctions 3.1.2(3) MGG-002 Loss of 4kV Bus 3A MGG-003 Loss of 4kV Bus 3B MGG-004 Loss of AllAC Power MGG-005 Loss of 4kV Bus 3C MGG-006 Loss of 4kV Bus 3D MMP-001 Loss of Vital AC Bus 3P06 MMP-002 Loss of Vital AC Bus 3P07 MMP-003 Loss of Vital AC Bus 8POS MMP-004 Loss of Vital AC Bus 8P09 MMP-005 Loss of DC Bus 3A (3DOl)
MMP-006 Loss of DC Bus 3B (3D23)
MMP-007 Loss of DC Bus 4B (4D01)
MMP-008 Loss of DC Bus 4A (4D28)
MRX-011 Loss of C 4KV Bus Reactor Trip MSP-001 Bus Stripping and Load Sequencing Tests 3.1.2(4) MRC-005 Loss of Forced Reactor Coolant Flow MRC-006 Loss of a Single Reactor Coolant Pump With Power Below P-8 3.1.2(5) MFW-001 Loss of Vacuum Tests, Including Loss of Condenser Level Control 3.1.2(6) MCS-002 Intake Cooling Water System Operations and Malfunctions MCS-008 Turbine Plant Cooling Water Operation and Malfunctions 3.1.2(7) MSS-008 Loss of RHR While in Cold Shutdown MSS-004 Loss of Inventory During a Shutdown and Partial Draindown Condition 3.1.2(8) MCS-001 Component Cooling Water Operations and Malfunctions
ANS 3.5 SECTI N ERTIFI ATI NTEST 3.1.2(9) MFW-002 Loss of Normal Feedwater MFW-006 Failure of Input Channels to the Feedwater Controller MFW-007 Equivalent TMI-2 Scenario MFW-008 Loss of Feedwater/ATWS 3.1.2(10) MFW-003 Loss of Normal and Emergency Feedwater 3.1.2(11) MRX-002 Loss of Protection System Channel 3.1.2(12) MRX-004 Stuck Control Rod MRX-005 Uncoupled Control Rod Test MRX-006 Dropped Control Rod MRX-007 Shutdown With Inability to Drive Control Rods MRX-011 Loss of C 4KV Bus Reactor Trip 3.1.2(13) MRX-007 Shutdown With Inability to Drive Control Rods 3.1.2(14) MRX-008 Fuel Cladding Failure Resulting in High Reactor Coolant Activity 3.1.2(15) MTU-001 Turbine Trip Which Does Not Cause Automatic Reactor Trip MTU-002 Turbine Trip kom 100% Power 3.1.2(16) MGG-001 Generator Trip 3.1.2(17) MCV-001 Uncontrolled Maximum Rate Boron Dilution 3.1.2(18) MRC-007 Stuck Open Spray Valve MRC-010 Pressurizer Pressure and Level Control Malfunctions MCV-002 Charging System Failures MCV-004 Letdown and Volume Control Tank Operations and Malfunctions MCV-005 Non-Regenerative Heat Exchanger Tube Leak 3.1.2(19) MRX-009 Manual Reactor Trip &om 100% Power MRX-010 Spurious High Containment Pressure SI MRX-011 Loss of C 4KV Bus Reactor Trip 3.1.2(20) MSG-001 Main Steam Line Break Inside Containment MSG-002 Main Steam Line Break Outside Containment MSG-007 Main Steam Line Break With Reduced Shutdown Margin MFW-004 Feedwater Line Break Inside Containment MFW-005 Main Feedwater Line Break Outside Containment
~AN . C D CERTIFI ATI NTE T 3.1.2(21) MRX-003 Nuclear Instrumentation Failures 3.1.2(22) MFW-006 F ailure ofInput Channels to the Feedwater Controller MRC-009 F ast Load Reduction, 3-ONOP-100 MRC-010 P ressurizer Pressure and Level Control Malfunctions MSG-005 F ailure of Reference Temperature to Steam Dumps MSG-006 C losure of a Single MSIV at Several DMerent Power Levels MTU-003 Turbine Lube Oil System (Bearings)
MTU-008 Hydrogen Cooling MTU-009 Turbine Lube Oil Control & Auto-Stop Oil MTU-011 F ailure of Turbine Control Valve Spring 3.1.2(23) MSS-001 S mall Leak in Safety Injection Piping Outside Containment MSS-002 Accumulator Operations and Malfunctions MCN-001 C ontainment Emergency Systems Operations and Malfunctions 3.1.2(24) MFW-008 Loss of Feedwater/ATWS 3.1.2(25) NOT APPLICABLE A.3.1 RTT-002 S imulator Real Time Test Validation Test B.2.1 SST-003 S teady State 100% Power Heat Balance SST-002 Steady State 75% Power Heat Balance SST-001 Steady State 50% Power Heat Balance SST-004 100% Power 60 minute Null Transient B.2.2(1) MRX-009 Manual Reactor Trip from 100% Power B.2.2(2) MFW-003 Loss of Normal and Emergency Feedwater B.2.2(3) MSG-003 Simultaneous Closure of AllMSIVs B.2.2(4) MRC-005 Loss of Forced Reactor Coolant Flow B.2.2(5) MRC-005 Loss of Forced Reactor Coolant Flow B.2.2(6) MTU-001 Turbine Trip Which Does Not Cause Automatic Reactor Trip B.2.2(7) MRX-001 Maximum Rate Power Ramp (100% To 75% and Back to 100%)
B.2.2(8) MRC-002 Large Break LOCA Inside Containment With Loss Of OKsite Power B.2.2(9) MSG-001 Main Steam Line Break Inside Containment B.2.2(10) MRC-004 PORV Failure (Open) Without High Pressure Injection
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