ML17352A884
| ML17352A884 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 10/28/1994 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17352A883 | List: |
| References | |
| NUDOCS 9411140078 | |
| Download: ML17352A884 (57) | |
Text
FLORIDAPOWER AND LIGHTCOMPANY TUIGG<rYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER 1 TABLEOF CONTENTS
1.0 INTRODUCTION
2.0 SIMULATORTESTS COMPLETED (1991 - 1994) 2.1 2.2 2.3 2.4 1991 TESTS 1992 TESTS 1993 TESTS 1994 TESTS 3.0 CERTIFICATIONTEST CHANGES (1995 - 1998) 3.1 CHANGES 32 DELETIONS 3.3 ADDITIONS 4.0 FOUR YEARTEST PLAN (1995 - 1998) 5.0 OUTSTANDINGDISCREPANCIES APPENDIXA TEST ABSTRACTS A.1 TESTS ADDED A.2 TESTS CHANGED 9411140078 941028 PDR ADOCK 05000250
.P PDR
SIMULATORCERTIFICATIONUPDATE NUMBER 1
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 differences between Unit 3 and Unit 4 were reviewed by the Simulator Configuration Review Board (SCRB)'nd it was determined that none willhave a negative effect 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 (DRs), and the schedule for completion ofthese DRs.
Experience gained during initial certification testing and the testing during the first 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.
Eight tests have been changed, ten tests have been deleted, and eleven 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 Configuration 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 Operations, "Simulator Configuration Management System," INPO 87-016, August 1987.
Page 2
SIMULATORCERTIFICATIONUPDATE NUMBER 1 2.0 SIMULATORTESTS COMPLETED (1991 - 1994) 2.1 1991 TESTS TEST 0 TEST DESCRIPTION COMPLETION DATE MFW-002 MFW-007 MGG-002 MGG-003 MGG-004 MMP-001 MMP-002 MMP-003 MMP-004 MMP-005 MMP-006 MMP-007 MMP-008 MRC-006 MRC-007 MSP-001 NPE-002 NPE-003 SUR-001 SUR-002 SUR-026 SUR-030 SUR-031 SUR-032 Loss ofNormal Feedwater Equivalent TMI-2 Scenario Loss of4KVBus 3A Loss of4IOt'us 3B Loss ofAllAC 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 4A (4D01)
Loss ofDC Bus 4B (4D23)
Loss of a Single RCP With Power Below P-8 Stuck Open Spray Valve Bus Stripping and Load Sequencing Tests Plant Startup Cold Shutdown to Hot Standby Plant Startup &om-Hot Standby to Rated Power Initial Criticalityafter Refueling, OP-0204.3 Nuclear Design Check Tests During Startup Sequence after Refueling, OP-0204.5 Engineered Safeguards Integrated Test, 3-OSP-203 Full Length RCC - Periodic Exercise, OP-1604.1 Inducing Xenon OsciQations to Produce Various Incore Axial Offsets, OP-12304.8 Normal Operation ofIncore Moveable Detector System and Power Distribution Surveillance, OP-12404.1 06-27-91 11-14-91 05-09-91 05-09-91 05-24-91 05-24-91 05-24-91 05-24-91 05-30-91 05-30-91 05-30-91 05-30-91 05-24-91 06-28-91 06-28-91 11-14-91 12-17-91 12-17-91 11-27-91
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12-17-91 12-17-91 06-25-91 06-25-91 11-14-91 Page 3
0 0
SIMJLATOR CERTIFICATIONUPDATE NUMBER 1 1991 TESTS (CONTINUED)
ANNUALTESTS TEST ¹ TEST DESCRIPTION COMPLETION 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 LOCA Inside Containment With Loss Of OQsite Power PORV Failure (Open) Without High Pressure Injection Loss ofForced Reactor Coolant Flow Spurious Rod Position Indication Resulting in Maximum Rate Runback To 70% Power and Maximum Rate Return to Full Power 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 45% Power Heat Balance Steady State 75% Power Heat Balance Steady State 100% Power Heat Balance 100% Power 60 min Null Transient 12-18-91 06-28-91 12-17-91 07-01-91 06-25-91 06-25-91 12-18-91 11-14-91 06-27-91 11-27-91 11-27-91 12-18-91 11-14-91 Page 4
SIMJLATOR CERTIFICATIONUPDATE NUMBER 1 1991 TESTS (CONTINUED)
As a result ofmajor plant changes that were incorporated into the Simulator in 1991, the followingtests were also run., MGG-005 and MGG-006 are new. The balance ofthe tests were part ofthe original certification test plan.
TEST ¹ TEST DESCRIPTION COMPLETION DATE MFW-008 'oss ofFeedwater / ATWS MGG-005 'oss of4KVBus 3C MGG-006 2 Loss of4Iot'us 3D MRC-001 'team Generator Tube Rupture MRC-003 'mall Break LOCA Inside Containment MRC-008 'oss ofB and C Reactor Coolant Pumps at 100% Power RTT-001 2 Simulator Real Time Test RTT-002 2 Simulator Real Time Validation Test SUR-003 2 EDG 8 Hour Load and Load Rejection Test, OP-4304.3 SUR-009 'eactor Protection Test, 3-OSP-049.1 SUR-021 2 Standby Steam Generator Feedwater Pumps
/ Cranking Diesels Test, O-OSP-074.4 12-17-91 05-09-91 05-09-91 12-17-91 05-24-91 06-28-91 05-09-91 05-09-91 05-09-91 11-14-91 05-09-91
'TD bypass loop removal / EAGLE-21 installation
'mergency Power System Enhancement (EPSE) project Page 5
TUIGGVPOINT UNIT3 2.2 1992 TESTS SIMULATORCERTIFICATIONUPDATE NUMBER 1 TEST 0 TEST DESCRIPTION COMPLETIONDATE MCV-001 MCV-002 MCV-004 MFW-004 MFW-006 MRC-003 MSG-006 MTU-003 MTU-004 MTU-005 MTU-009 MTU-010 MTU-011 NPE-005 NPE-006 SUR-004 SUR-007 SUR-008 SUR-009 SUR-012 SUR-015 SUR-017 SUR-020 Uncontrolled Maximum Rate Boron Dilution Charging System Failures Letdown and Volume Control Tank System Operations and Malfunctions Feedwater Line Break Inside Containment Failure ofSteam Generator Level Channel Providing Input to the Feedwater Controller Small Break LOCA Inside Containment Closure ofa Single MSIVAt Several Different Power Levels Turbine Lube Oil System (Bearings)
Turbine Gland Seal System Turbine Turning Gear Operation Turbine Lube Oil Control gi; Auto-Stop Oil Turbine Lube Oil Pump S Motor Failure ofTurbine Control Valve Spring Plant Shutdown &om Rated Power to Hot Standby Cooldown &om Hot Standby to Cold Shutdown Component Cooling Water Pumps Low Header Pressure Start Test, 3-OSP-030.5 CVCS Boric Acid Transfer Flow Test, 3-OSP-046.2 Boric Acid. Transfer Pump 3B Transfer and Control Switch Test, 3-OSP-046.5 Reactor Protection System Logic Test, 3-OSP-049.1 Emergency Containment Filter Fans Operating Test, 3-OSP-056.1 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 07-16-92 06-10-92 07-16-92 07-10-92 07-16-92 07-10-92 06-10-92 12-01-92 06-10-92 12-01-92 06-10-92 05-08-92 07-16-92 06-19-92 07-10-92 05-08-92 03-19-92 03-19-92 05-08-92 03-19-92 03-19-92 05-08-92 07-10-92 0
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0
SIMULATORCERTIFICATIONUPDATE NUMBER 1 1992 TESTS (CONTINUED)
TEST ¹ TEST DESCRIPTION COMPLETIONDATE 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 05-08-92 12-15-92 12-01-92 07-17-92 06-10-92 Loss ofNormal and Emergency Feedwater 12-14-92 Large Break LOCA Inside Containment With Loss Of OHsite Power 07-10-92 PORV Failure (Open) Without High Pressure Injection 07-16-92 Loss ofForced Reactor Coolant Flow 06-10-92 Spurious Rod Position Indication Resulting in Maximum Rate Runback To 70% Power and Maximum Rate Return To Full Power Manual Reactor Trip from 100% Power Main Steam Line Break Inside Containment Simultaneous Closure ofAllMSIV's Turbine Trip Which Does Not Cause Automatic Reactor Trip Steady State 45% Power Heat Balance Steady State 75% Power Heat Balance Steady State 100% Power Heat Balance 100% Power 60 min NullTransient Page 7
SIMULATORCERTIFICATIONUPDATE NUMBER 1 1992 TESTS (CONTINUED)
As a result ofprotection system hardware changes and major Simulator upgrades incorporated in 1992, the followingtests were also run.
TEST 4 TEST DESCRIPTION COMPLETIONDATE MRX-002
'SS-003
'SS-004 NPE-001 Loss ofProtection System Channel Loss ofRHR While in Cold Shutdown Loss ofInventory during a Shutdown and Partial Draindown Condition Plant Fill and Vent Rom a Partial Draindown to a Solid Pressurizer 12-16-92 07-10-92 07-10-92 07-17-92
'nstallation ofEAGLE-21 hardware in the Simulator 2 Simulator draindown model upgrade Page 8
TUI~POINT UNIT3 2.3 1993 TESTS SIMULATORCERTIFICATIONUPDATE NUINBER 1 TEST 4 TEST DESCRIPTION COMPLETION DATE MCS-001 MFW;001 MGG-001 MRC-001 MRC-008 MRX-003 MRX-006 MRX-007 MSG-004 MSG-005 MTU-002 NPE-001 SUR-003 SUR-005 SUR-010 SUR-011 SUR-021 SUR-022 SUR-024 Component Cooling Water Operations and Malfunctions Up To and Including Total Loss ofCCW Loss ofVacuum Tests, Including Loss of Condenser Level Control Generator Trip Steam Generator Tube Rupture Loss ofB and C Reactor Coolant Pumps at 100% Power Nuclear Instrumentation Failure During Startup Dropped Control Rod Dropped With Inabilityto Drive Control Rods Tamsmitter Failure Resulting In Maximum Atmospheric Dump Demand Failure ofReference Temperature to Steam Dumps Turbine Trip from 100% Power Plant Filland Vent from a Partial Drain Down to a Solid Pressurizer EDG 8 Hour Load and Load Rejection Test, OP<304,3 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 Verification, 3-OSP-075.1 Main Turbine Valves Operability Test, 3-OSP-089 11-18-93 12-06-93 08-27-93 08-10-93 11-18-93 11-18-93 12-06-93 11-18-93 12-06-93 11-18-93 11-18-93 11-15;93 11-18-93 08-27-93 08-27-93 08-27-93 08-27-93 08-27-93 11-18-93 Page 9
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TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER 1 1993 TESTS (CONTINUED)
ANNUALTESTS TEST ¹ TEST DESCRIPTION COMPLETIONDATE 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 08-10-93 11-18-93 11-15-93 11-15-93 11-15-93 08-27-93 Loss ofNormal and Emergency Feedwater Large Break LOCA Inside Containment With Loss Of OQsite Power 12-06-93 PORU Failure (Open) Without High Pressure Injection 08-10-93 Loss ofForced Reactor Coolant Flow 11-18-93 Spurious Rod Position Indication Resulting in Maximum Rate Runback To 70% Power and Maximum Rate Return To Full Power 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 45% Power'Heat Balance Steady State 75% Power Heat Balance Steady State 100% Power Heat Balance 100% Power 60 min Null Transient Page 10
O TURKEYPOINT UNIT3 2.4 1994 TESTS SIMULATORCERTIFICATIONUPDATE NUMBER 1 TEST 0 TEST DESCRIPTION COMPLETION DATE MCN-001 MCS-002 MCS-003 MCS-004 MCV-003 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 RTT-001 RTT-002 SUR-014 SUR-016 Containment Spray System Operations and Malfunctions Intake Cooling Water System Operations and Malfunctions Turbine Plant Cooling Water Operation and Malfunctions Instrument AirSystem Operation and Malfunctions Charging Line Break Outside Containment 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 of Inventory During A Shutdown and Partial Draindown Condition Hydrogen Seal Oil Hydrogen Cooling Reactor Trip Followed By Recovery to Rated Power Simulator Real Time Test Simulator Real Time Test Validation Test Source Range Nuclear Instrumentation Analog Channel Operational Test, 3-OSP-059.1 Intermediate Range NIS Setpoint Verification, 3-OSP-059.3 08-09-94 03-24-94 03-24-94 03-24-94 07-08-94 03-24-94 05-17-94 08-05-94 06-06-94 07-08-94 07-08-94 08-05-94 07-08-94 05-17-94 08-05-94 05-17-94 05-17-94 06-06-94 06-06-94 08-09-94 05-17-94 05-17-94 03-24-94 08-05-94 Page 11
0
TURKEY'OINTUNIT3 SIMJLATOR CERTIFICATIONUPDATE NUMBER 1 1994 TESTS (CONTINUED)
SUR-018 SUR-019 SUR-029 Power Range Nuclear Instrumentation Shift Checks and Daily Calibration, 3-OSP-059.5 Process Radiation Monitoring Operability Test, 3-OSP-067.1 Operational Test ofMOV-535, 536, and PORV 455C,456, OP-1300.2 03-24-94 08-05-94 03-24-94 ANNUALTESTS TEST ¹ TEST DESCRIPTION COMPLETIONDATE 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 LOCA Inside Containment With Loss OfOffsite Power PORV Failure (Open) Without High Pressure Injection Loss ofForced Reactor Coolant Flow Spurious Rod Position Indication Resulting in Maximum Rate Runback To 70% Power and Maximum Rate Return To Full Power 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 45% Power Heat Balance Steady State 75% Power Heat Balance Steady State 100% Power Heat Balance 100% Power 60 min Null Transient 05-17-94 05-17-94 05-17-94 04-29-94 03-24-94 03-24-94 05-17-94 04-29-94 06-06-94 08-05-94 08-05-94 08-05-94 03-24-94 Page 12
'ZUIGGrY POINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER 1 3.0 CERTIFICATIONTEST CHANGES (1995 - 1998)
Experience gained during initialcertification testing and during the first four year cycle has resulted in several changes to the Turkey Point Simulator Certification Test plan.
Furthermore, the availability ofplant data has resulted in additions to the plan.
These changes in the plan are organized into the followingthree categories: Changes, Deletions, and Additions.
Changes have been made to eliminate duplication, eliminate test runs that provide little or no incremental information, and to modify tests to reQect changes in the plant.
Deletions have been made as a result ofchanges in plant configuration and, to eliminate duplication, Five surveillance test procedures, not deemed. sufBciently valuable to repeat for the next four year cycle, were deleted to allow substitution of more important surveillance procedures.
Additions have been made as a result ofplant changes, to make use ofplant transient data from the Emergency Response Data Acquisition Display System (ERDADS), and to add new surveillance procedures.
3.1 CHANGES MCN-001, Containment Spray System Operations and Malfunctions.
This test willbe generalized to include all ofthe containment systems that provide for mitigation ofevents that cause pressurization ofthe containment, i.e., both the spray system and the containment emergency coolers.
The overall behavior ofthe containment pressure and temperature response is monitored in other certification tests such as the large and small break LOCAs, and the inside containment MSLB.
This test willfocus on the response of the individual systems to malfunctions.
The test willbe renamed "Containment Emergency Systems Operations and Malfunctions."
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TUNG~ POINT UNIT3 SI1VKLATORCERTIFICATIONUPDATE NUMBER 1 MCS-001, Component Cooling Water Operations and 1Vbdfunctions.
This test comprised two runs: Run 1, Loss ofIntake Cooling Water (ICW) to the Component Cooling Water (CCW) Heat Exchangers, and Run 2, Total Loss of CCW Flow. Run 1, Loss ofICW to the CCW Heat Exchangers is performed in MCS-002, Intake Cooling Water System Operations and Malfunctions, and willbe deleted from MCS-001. The Total Loss ofCCW Flow willcontinue to be performed in MCS-001.
MCS-003, Turbine Plant Cooling Water System Operations and Malfunctions.
This test comprised two runs; Run 1, Loss ofIntake Cooling Water (ICW) to the Turbine Plant Cooling Water (TPCW) Heat Exchangers, and Run 2, Total Loss of TPCW. Run 1, Loss ofICW to the TPCW Heat Exchangers is performed in MCS-002, Intake Cooling Water System Operations and Malfunctions, and willbe deleted from MCS-003. The Total Loss ofTPCW willcontinue to be performed in MCS-003.
MCV-004, Letdown and Volume Control Tank System Operations and Malfunctions.
This test comprised a total offive diQerent malfunctions, Run 1, Loss of CCW to the Non-Regenerative Heat Exchangers is performed in MCS-001, Component Cooling Water Operations and Malfunctions and willbe deleted from MCV-004.
The remaining four malfunctions (PCV-145 failed open, PCV-145 failed shut, LCV-115A failed to the divert position, and CV-204 failed shut) willcontinue to be tested as before.
MFW-002, Loss ofNormal Feedwater.
Previous certification testing examined two cases, the first with the Auxiliary Feedwater (AFW) Qow controllers set at 135 gpm and the second with the controllers set at 300 gpm. The two tests were designed to examine the sensitivity ofthe response to the magnitude ofthe AFW flowrate. Experience has shown that the response ofthe two cases is largely the same with no additional information being gained by performing the second run. Therefore, the 300 gpm case willbe Page 14
TURKlH'OINTUNIT3 SI1VKILATORCERTIFICATIONUPDATE NUMBER 1 deleted.
Also, the setting for the AFW How controller demand willbe changed to the current plant setting of 130 gpm.
MRX-001, Spurious Rod Position Indication Resulting in Maximum Rate Runback to 70% Power and Maximum Rate Return to Full Power.
The turbine runback due to dropped mds was removed during the Unit 3 Cycle 14 refueling outage.
The test was changed to remove the dropped rod runback &om the scenario and the test title was changed to "Maximum Rate Power Ramp (100%
down to 75% and back up to 100%)". The power reduction and ascension willbe controHed manually by the test team.
MSG-001, Main Steam Line Break Inside Containment.
The initialcertification testing and annual testing included two Main Steam Line Break (MSLB) cases.
In the first case the RCPs were tripped based on the RCP trip criteria &om the Emergency Operating Procedures (EOP).
The second case was performed with the RCPs running as a sensitivity study to provide additional information for the comparison ofthe Simulator with the Best Estimate RETRAN model.
The case with RCPs running is atypical ofthe expected sequence during a MSLB and provides little additional information to justify continuing its performance as an annual test, Therefore, the "RCPs On" case willbe deleted.
(See Section 3,3 for an additional Hot Zero Power (HZP) MSLB test that willbe included for the next four year cycle,)
MSG-003, Simultaneous Closure ofAllMSVPs.
The initialcertification test plan called for two runs to be performed.
The first examined the response with rod control in automatic, and the second with rod control in manual. Previously, these runs were significantly different because the rods in manual case would quickly trip whereas the rods in automatic case would survive for some time. During the Unit 3 Cycle 13 refueling outage a reverse power turbine trip was installed in the plant. This results in a turbine trip/
reactor trip after approximately 60 seconds making both runs very similar.
Therefore, the "Rods in Manual" case willbe deleted.
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TURIG'rYPOINT UNIT3 SIMJLATOR CERTIFICATIONUPDATE NUMBER 1 3.2 DELETIONS MCV-003, Charging Line Break Outside Containment.
This scenario is performed in MCV-002 Charging System Failures and therefore willbe deleted.
MRC-008, Loss ofB and C RCPs at 10¹ power.
This test was compared to a plant trip that occurred on Unit 4 on 4/9/90.
Numerous plant changes have occurred since 1990 including removal ofthe RTD bypass loops and changes to the protection and process control systems.
These changes make the comparison between the present Simulator and the 4/9/90 event inappropriate.
MSG-004, Transmitter Failure Resulting in Maximum Atmospheric Dump Demand.
One atmospheric dump valve has a capacity ofonly 3.3% offullsteam Qow. This results in a change in steam load similar to normal operating changes.
The transient is relatively mild and does not provide unique information. Therefore, this test willbe deleted, MTU-004, Turbine Gland Seal System.
This test checks the normal operation ofthe gland sealing system. These checks are performed during NPE-003, Plant Startup Rom Hot Standby to Rated Power.
Therefore, this test willbe deleted, MTU-010, Turbine Lube Oil Pump and Motor.
This test was mis-titled in the original certification test plan. The test is actually a test ofthe Steam Generator Feed Pumps (SGFP) Lube Oil system.
This is a minor support system which has no indications in the control room and no role in training. Continuing to test this system provides littlevalue in terms oftraining and this test willbe deleted.
Page 16
TURKFrYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER 1 SUR-007, CVCS Boric Acid Transfer Flow Test, 3-OSP-046.2 This test verifies that the boric acid pumps can deliver Qow through the normal and emergency Qowpaths.
These Qowpaths are verified during other certification tests such as the Plant Shutdown &om Rated Power to Hot Standby (NPE-005),
the cooldown from Hot Standby to Cold Shutdown (NPE-006), and during operator training scenarios such as the ATWS event.
Since initial certification testing and testing during the first four year cycle have demonstrated the ability to perform this surveillance procedure and the substantive elements ofthe surveillance are examined via other tests, this test willbe deleted and surveillance test SUR-033 substituted.
(See Section 3.3 - Additions)
SUR-008, Boric Acid Transfer Pump Transfer and Control Switch Test, 3-OSP-046.5 This test checks the operation ofthe boric acid pump &om both the local control station and the control room. Certification testing during the first four year cycle has demonstrated the ability to perform this surveillance.
Continuing to test this surveillance provides littlevalue in terms oftraining and therefore this test willbe deleted and surveillance test SUR-034 substituted.
(See Section 3.3 - Additions)
SUR-012, Emergency Containment Filter Fan Operating Test, 3-OSP-056.1.
Since there are limited filterfan indications inside the control room and initial certification testing and additional testing during the first four year cycle have demonstrated the ability to perform this surveillance, this test willbe deleted and surveillance test SUR-035 substituted.
(See Section 3.3 - Additions)
SUR-018, Power Range NIS Shift Checks and Daily Calibrations, 3-OSP-059.5.
This test is performed during several other tests including the annual steady state tests (SST-001, SST-002, and SST-003).
Therefore, a separate test is not necessary.
This test willbe deleted and surveillance test SUR-036 substituted.
(See Section 3.3 - Additions)
Page 17
TURKEZ'OINTUNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER 1 SUR-029, Operational Test ofMOV-536, 636, and PORV-465C, 466, OP-1300.2.
This test performs a stroke test on the PORV block valves and seat leakage test on the PORVs.
Since initial certification testing and additional testing during the first four year cycle have demonstrated the ability to perform this surveillance, this test willbe deleted and surveillance test SUR-037 substituted.
(See Section 3.3 - Additions) 3.3 ADDITIONS MGG-005, Loss of4KVBus 3C.
This test was added in 1991 followingthe Emergency Power System Enhancement project. This test verifies that the load centers, motor control centers and 480v loads powered from the 3C bus respond correctly to the loss ofthe 3C 4kv bus.
MGG-006, Loss of4KVbus 3D.
This test was added in 1991 followingthe Emergency Power System Enhancement (EPSE) project. The 3D 4kv safety related bus was installed in 1991 during the EPSE project. This test verifies that the 3H load center, 3D motor control center and 480v loads powered &om the 3D bus respond correctly to the loss ofthe 3D 4kv bus.
MRC-009, Fast Load Reduction, 3-ONOP-100..
This test willsimulate high RCP seal leakoK requiring a fast load reduction using 3-ONOP-100.
The Simulator results willbe compared to plant data &om the Unit 3 fast load reduction that occurred on 4-27-92.
MRX-010, Spurious High Containment Pressure Safety Injection.
This test willsimulate a spurious high containment pressure SI &om 28% power.
The Simulator results willbe compared to plant data &om the Unit 4 high containment pressure SI that occurred on 3-26-92.
Page 18
TURKEYPOINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER 1 MRX-011, Loss of C 4KVBus Reactor Trip.
This test willsimulate a loss ofthe C 4kv bus from 10¹ power. The Simulator results willbe compared to plant data &om the Unit 4 loss of C 4kv bus reactor trip that ocnnred on 9-23-94.
MSG-007, Main Steam Line Break with Reduced Shutdown Margin.
This test willexamine a hypothetical Main Steam Line Break (MSLB)&om Hot Standby with a shutdown margin that willresult in a return to power during the cooldown. This willexamine a MSLB event scenario with slightly different characteristics than the standard test (MSG-001).
SUR-033, Accident Monitoring Instrumentation Channel Checks, 3-OSP-204.
This test covers the surveillance ofthe accident instrumentation including core exit thermocouples, reactor vessel level indicators, subcooled margin monitors, and containment radiation, pressure and level indicators.
SUR-034, Safeguard Relay Rack Train A,B, Periodic Test, OP-4004.2.
This test covers the operator surveillance ofthe safeguards logic.
SUR-035, Containment Isolation Racks QR50 and QR51 Periodic Test, OP-4004.4.
This test covers the operator surveillance ofthe containment pressure channels.
SUR-036, Component Cooling Water System Flow Balance, 3-OSP-030.9.
This test verifies that all safety related components cooled by CCW receive the minimum required Qow with the CCW system aligned in its most limitingaccident configuration.
SUR-037, Determination ofQuadrant Power TiltRatio, 3-OSP-059.10.
This test covers the determination ofthe Quadrant Power TiltRatio (QPTR).
Page 19
TUIGGZ'OINTUNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER 1 4.0 FOUR YEAR.TEST PLAN(1995-1998)
Per the requirements ofRegulatory Guide 1.149, the Simulator Certification test program willbe conducted in its entirety on a four year cycle. Allofthe ANSVANS 3.6 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 ANSVANS 3.6 tests that willbe performed annually.
Tables 4-2 through 4-6 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 1996-1998 Turkey Point Simulator test plan has been reviewed and approved by the Simulator Configuration Review Board (SCRB).
Page 20
TUIGGlYPOINT UNIT3 SI1UKLATORCERTIFICATIONUPDATE MiMBER1 Table 4-1 Annual Tests MFW-003 MRC-002
'RC-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%%uo)
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 21
TUI~POINT UNIT3 SIMULATOR CERTIFICATIONUPDATE NUMBER 1 Table 4-2 1995 Test Plan MFW-002 MFW-007 MGG-002 MGG-003 MGG-004 MGG-005 MGG-006 MMP-001 MMP-002 MMP-003 MMP-004 mrtP-005 MMP-007 MMP-008 MRC-006 MRC-007 MSG-007 MSP-001 NPE-002 NPE-003 SUR-026 SUR-030 SUR-031 Loss of¹rmal Feedwater Equivalent TMI-2 Scenario Loss of4KVBus 3A Loss of4KVBus 3B Loss ofAllAC Loss of4KVBus 3C Loss of4IOt'us 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 of a 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 &om Hot Standby to Rated Power Engineered Safeguards Integrated Test, 3-OSP-203.1 & 3-OSP-203.2 Full Length RCC - Periodic Exercise, OP-1604.1 Inducing Xenon Oscillations to Produce Various Incore Axial Offsets, 0-OP-059.3 Page 22
0
TUIGGrY POINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER 1 Table 4-3 1996 Test Plan 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 Chemical Volume Control System 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 of a Single MSIVAt Several 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 &om Rated Power to Hot Standby Cooldown &om 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 TiltRatio, 3-OSP-059.10 Page 23
TURKIC Y POINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER 1 Table 4-4 1997 Test Plan MCS-001 MFW-001 MGG-001 MRC-001 MRX-003 MRX-006 MRX-007 MRX-011 MSG-005 MTU-002 NPE-001 RTT-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 Nuclear Instrumentation Failure During Startup Dropped Control Rod Dropped With Inabilityto Drive Control Rods Loss of C 4KVBus Reactor Trip Failure ofReference Temperature to Steam Dumps Turbine Trip &om 100% Power Plant Filland Vent &om a Partial Drain Down to a Solid Pressurizer Simulator Real Time Test Simulator Real Time Test Validation Test EDG 8 Hour Load Test and Load Rejection Test, 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/Craning Diesels Test, O-OSP-074.4 AuxiliaryFeedwater Train 1 Operability Verification, 3-OSP-075.1 Main Turbine Valves Operability Test, 3-OSP-089 Normal Operation ofIncore Moveable Detector System and Power Distribution Surveillance, OP-12404.1 Accident Monitoring Instrumentation Channel Checks, 3-OSP-204 Safeguard Relay Rack Train A,B, Periodic Test, OP-4004.2 Page 24
TUI~POINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER 1 Table 4-5 1998 Test Plan 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-001 SUR-002 SUR-014 SUR-016 SUR-019 Containment Emergency Systems Operation and Malfunctions Intake Cooling Water System Operations and Ma1lfunctions 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 of Inventory During Partial Draindown Hydrogen Seal Oil Hydrogen Cooling Reactor Trip Followed By Recovery to Rated Power InitialCriticalityaRer Refueling, 3-OSP-040.6 Nuclear Design Check Tests During Startup Sequence after Refueling, 3-OSP-040.5 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 25
TUI~POINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER 1 5.0 OUTSTANDINGDISCREPANCIES In general all Simulator Discrepancy Reports (DRs) 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 DRs. The SCRB willreview and approve the extension of the schedule for any DR that willnot be completed in one year.
5.1 1991 CERTIFICATIONTEST DR'S 73 Certification test DRs were written and all have been completed.
5.2 1992 CERTIFICATIONTEST DR'S 69 Certification test DRs were written and all have been completed.
5.3 1993 CERTIFICATIONTEST DR'S 28 Certification test DRs were written and all have been completed.
5.4 1994 CERTIFICATIONTEST DR'S 26 Certification test DRs were written and all but the followingDRs have been completed.
SUR019 9400075 N/A 9400116 TEST DR 8 MRX005 9400069 MRX008 9400114 NPE004 9400115 TITLE Secondary side oscillations after rod drop Investigate R-11/R-12 response RCP current drops when transferring to the auxiliary Transformer PRMS drawers do not display exact alarm setpoint Physical Fidelity DUE DATE 5/16/95 8/05/95 8/08/95 6/10/95 8/09/95 Page 26
TUIGG~~Y POINT UNIT3 SIMULATORCERTIFICATIONUPDATE NUMBER 1 APPENDIXA TEST ABSTRACTS A.1 TESTS ADDED
OINTSIMULATORCERTIFICATIONTEST PROCEDURE TITLE:
LOSS OF 4KVBUS 3C NUMBER MGG~
ANS 3.5 REFERENCE SECllONS:
J. T,RP) Loss ofElectrical Power DESCRIPllON The purpose ofthis test ls to verifyproper simulator response to a loss ofthe 3C 4kVbus or to a loss ofan Individual load center or motor control center suppNed from the 3C 4kVbus.
This bus suppNes load centers 3E, 3F. and 3G and these supply motor control centers 3B non-vital, 3C non-vital, 3G, 3H, 3B43, RB (which feeds motor control center RC). and F (which feeds motor control center 39. ANloods of450 volts orgreater in this train that hove some Impact ln the control foam; e.g.,
alarm, control, or Indication, wiNbe verified to lose power when the appropifate 4kVbus, load center, or motor control center is energized.
This test wm be performed by failing open the supply breaker to each motor control center, loads on that motor control center w8 be verified lost. and the power wIthen be restored to the motor control center. AfteraN motor control centers have been tested. the supply breaker to each load center wm be fai7ed open, loads on that load center willbe verified lost, Including power to the motor control centers. and the power to the load center wiNthen be restored. AfteraN load centers have been tested. power to the 3C 4kVbus wi7Ibe lost and loads verified, Including power to the toad centers.
In order to make lteasier to start and stop loads, this test willbe conducted from hot standby.
OPllONS The N3 transformer feeders to the 3C 4kVfeeders can be operated by a variety ofmechanisms.
These Include operating them from the control room console, operating them from the Instructor's facility, using the instructor's faci7ity to operate them locally, and placing in a malfunction that w8 cause them to open or prevent their operation.
The load center feeders have sfmNar options.
The motor control center feeders must be opened from the Instructor's faclrity.
INmALCONDmONS FINALCONDIllONS Hot standby.
The 3C 4kVbus is supplied from the P3 transformer.
Hot standby with the 3C 4kVbus ~nerglzed.
The data coNeclion sheet for loss of3C 4kVbus has been completed.
SIMUlATORCONFIGURAllONREVIELIfBOARD APPROVAL FOR USE DATEi DAlE:
DATEi DATEi DATEi DAlE'
INTSIMULATORCERTIFICATIONlEST PROCEDURE EKE:
LOSS OF 4KVBUS 3D NUMBER:
MGG~
ANS 8.5 REFERENCE SECllONS:
8.1.2(J) Loss ofElecMcal Power DESCRIPTION The purpose ofthis test ls to verifyproper simulator response to a toss of the 3D 4kVbus. lhe 3D4kVbus can be supplied from either the 3A4kVbus or the 3B4kV bus.
The 4kVsupply to the 3D bus willbe manually swapped from 3B to 3A and back to 3B In order to verify the proper operation of this function. Since the 3D 4kVbus ls part of the station blackout gBO) cross connection between Unit3 and Unit4, that function wialso be tested In several situations. lhe interlocks that prevent paraMing trains 3Aand 3B via the 3D4kVbus and the 125 VDCtransfer switch 3$75 wNbe tested.
lhe transfer switch provides controlpower forthe drcult breakers on the 3D 4kVbus.
In order to make iteasier to start and stop loads and swap busses, this test weal be conducted from hot standby.
OPllONS During normal operatIons, the 4kVbus 3D can be supplied from the 3A or 3B 4kVbu* lhe breakers being tested can be opened and closed by a vorfety of mechanisms.
These indude operating them from the control room console, operating them from the instructor's facility, using the instructors facilityto operate them locally, and placing In a malfunction that wm cause them to open or prevent their operation.
INlllALCONDITIONS RNALCONDlllONS Hot standby.
The 3D 4kVbus ls energized from the 3B 4kVbus.
Hot standby.
The data collection sheet for loss of 4kV bus 3D has been completed, the manual transfer of supply busses has been completed, the Interlocks that prevent parallelling the 3A and 3B trains via the 3D 4kVbus have been tested, transfer switch 3$75 has been tested, and the SBO function has been tested.
SIMUIATORCONFIGURATIONREVIEWBOARD APPROVAL FOR USE DAlE:
DAlE'ATEr DAlE:
DAlE'AlE:
P OINTSIMUIATORCERTIFICATION TEST PROCEDURE TITLEr FAST LOADREDUCllON, M)NOP-100 NUMBER MRC~
ANS 8.5 REFERENCE SECTIONSr 3.1.1(5) Load Changes 3.1.2@5 Process Instrumentatton, Alarms, and Control System Failures DESCRIPllON This test wiltsimuiate excessive Ieakoff from the Number 1 seal on the 3C RCP requiring a fast reduction In power using 3C)NOP-100, Fast Load Reduction.
lhis scenario has been chosen to compare the simuiator response to the Unit 3 fast toad reduction on Ap8 27, 1992 from the same cause.
Actions wilbe simutated to approximate those taken during the Unit 3 load reduction.
OPllONS None INITIALCONDITIONS FINALCONDITIONS 87% power, Steady state PIant stabie at hot standby and the C RCP secured.
SIMUlATORCONRGURATIONRENEW BOARD APPROVAL FOR USE DAlE:
DATEr DATEr DAlE:
DATEr DAlE:
OINTSIMULATORCER11RCAllON TEST PROCEDURE llTLEr SPURIOUS HIGH CONTAINMENTPRESSURE SAFETYINJECllON NUMBER:
MR)M10 ANS S.5 REFERENCE SECllONS:
S.1.2(19) Reactor Tifp DESCRIPllON This test wfiisimuiate a reactor tripcaused bya B train Safety InjecffonsignaiInitfated durfng the perfonnance ofthe containment prelure channel test. ibisscenario has been chosen to compare the simulator response to the Unit 4 trfp on March 26, 1992 tram the same cause.
Actions wfiibe simulated to approxfmate those taken foiiowfngthe Unit4 trfp.
OPllONS INIllALCONDITIONS FihfALCONDIllOh5 28% power, Steady state Plant stabie at hot standby.
SIMUIATORCONFIGURAllONREVIEMIBOARDAPPROVAL FOR USE DATEr DAlE:
DATEr DAlE:
DAlE:
DATEr
OINTSIMULATORCENlFICAllONTEST PROCEDURE llRE:
LOSS of C 4KVBUS REACTOR IIP NUMBER MRX<11 ANS 8.5 REFERENCE SECIlONS:
8.1.2(8) Loss ofEiectrtcai Power 8.1.2(12) Control Rod Failures DESCRIPllON This test wisimulate a loss ofthe C 4KVbus withpower at 100%, which wm result In a reactor trip. Thisscenarlo has been chosen to compare the simulator response to the Unit 4 trip on September 23, 1994 from the same cause.
Due to degraded power horn the MG set to the IACcontrol rod power cabinet and the loss of the 4C 4RVbus which supplies backup power, the 12 rods supplied from the IACpower cabinet dropped into the core resuNng In an OTATreactor trip. Actions wIIIbe simulated to approxfmate those taken followingthe Unit4 Irfp.
OPllONS INllMLCONDlllONS FINALCONDmONS 1%% power, EOL Steady state.
Plant stable at hot standby.
SIMUlATORCONFIGURATIONREVIEW BOARD APPROVAL FOR USE DAlE:
DATEr DATEr DAlE:
DATEr DAlE:
OINTSIMULATORCERTIFICATIONTEST PROCEDURE llILEr MAINSTEAMONE BREAK NTHREDUCED SHUTDONNMARGIN NUMBER MSGR ANS J.5 REFERENCE SECllONS:
8.1.2L20)
Mafn Steam Line as wellas Main Feed One Breaks goth inskte and outside Containment)
DESCRIPllON This steam linebreak tronsfent wSexamine the response ofthe simulator to amain steam line break inskfe containment from hot standby conditfons witha reduced shutdown margin. The shutdown margfn willbe reduced to a degree that wfllallow a return to power as a resuft of the moderator feedback during the cooktown transient.
The test Is not Intended to followIn detail the emergency operoffng procedures covering this type oftransient.
However. operator actions to turn offthe reactor coolant pumps on Iowsu&cooling margin and isolate the auxiliaryfeedwoter to the affected steam generator have been programmed into the scenarfo.
No other operator actions willbe taken during the coune ofthe event. Allcontrol and safety systems wSbe in automatic ond fullyfunctional. Asteam line break equivalent to the area of the flowreshfctor at the steam generator outlet is assumed to occur in the B steam line Inskte containment.
OPTIONS The simulator is capable ofsimulating steam Tine breaks ofany stre at several locations Inside and outside containment on each of the steam Enes.
INmALcoNDmoNs FINALcoNDmoNs Hot Standby, Subcrfticof, EOL The test wS run for 15 minutes.
SIMUIATORCONFIGURAllONREVlES'BOARD APPROVAL FOR USE DATEr DAlE:
DATE:
DATE:
DATE DAlE:
OINTSIMUIATORCERllFICATIONTEST PROCEDURE NIE:
ACCIDENTMONITORINGINSlRUMENTAllONCHANNB. CHECKS, M)SP404 NUMBER:
SUR-D38 ANS 8.5 REFERENCE SECllONSr 8.1.1 (ID) Operator Conducted Survellkrnce on Safety-Related Equipment or Systems DESCRIPllON This certification test wI demonstrate the ability of the slmukrtor to support the operator conducted surveNance procedure 3~P-2N, Acckfent Monitoring Instrumentation Channel Checks. With no malfunctions present. the ability to successfully perform this survesance willbe verNed.
OPllONS This test can be performed at any time in core fife.
INITIAI.CONDITIONS FINAI. CONDITIONS 100% power. steady state, MOL SurveNance complete.
SIMUlATORCONFIGURAllONRENEW BOARD APPROVAI FOR USE DATEr DATEr DATEr DATEr DAlE:
DATEr
INTSIMULATORCER77FICATION TEST PROCEDURE TITLE:
SAFEGUARD REIAYRACX TRAINA,B, PERIODIC TEST, OPADLR2 NUMBERs SUR~
ANS 3.5 REFERENCE SECTIONSs 3.1.1 (10) Operator Conducted Surveiiksnce on Safety-Related Equipment or Systems DESCRIPTION This certification test willdemonstrate the aMityofthe simulator to support the operator conducted surveIance procedure OPAN42. Safeguard Relay Rack Train A,B, Periodic Test. With no malfunctions present, the abilityto successfully perform this survei7!ance wi7Ibe verified.
OP17ONS This test can be performed at any power level and at time in core life.
INITIALCONDmONS RNALCONDmONS IR% power, steady state. MOL Surveillance complete.
SIMUIATORCONFIGURA11ON REVIEWBOARD APPROVAL FOR USE DA7B DA1E:
DATB D41B DA1B DATE'
INTSIMUlATORCERllFICAlloNTEST PROCEDURE llILE:
CONTAINMENTISOIA11ON RACKS CÃ50 AND QR51 PERIODIC TEST, OPMD04.4 NUMBER SUR-N5 ANS 8.5 REFERENCE SEClloNS:
8.1.1 (IO) Operator Conducted Surveiikrnce on Safety-Retated Equipment or Systems DESCRIPlloN This certÃcation test wIIIdemonstrate the abiiityofthe simulator to support the operator conducted surveillance procedure OM0044, Contairment isoiatlon Racks QR50 and QR51~c Test. Withno maifunctions present, the abffityto successfuiiy perform this surveillance wIbe verified.
OPTIONS lhis test can be performed at any power level and at time in core kfe.
INmALCoNDmoNS FINALcoNDmoNs 100% power, steady state, MOL Surveiilance complete.
SIMUIATORCONRGURATIONREVIEWBOARD APPROVAL FOR USE DAlEr DAlE:
DATEr DAlE'
INTSIMULATORCERTIFICATIONTEST PROCEDURE llREi COMPONENT COOLING WATER SySTEM FLOWBALANCE,3&SP~.9 e
NUMBER:
SURES ANS 3,5 REFERENCE SECllONS:
3.1.1 (10) Operator Conducted Surveiikrnce on Safety-Related Equipment or Systems DESCRIPllOH lhlscertification test wmdemonstrate the abilityofthe simulator tosupport the surveillance procedure 3~F0.9. Component Cooling Water System HowBakince.
This test verities that all safety rekrted components cooled by CCWreceive the minimum required flowwith the CCW system aligned In its most ilmNng acckient conjuration.
With no malfunctions present, the abiTity to successfully perfom this surveillance wIIIbe ventied.
OPTIONS lhfs test can be performed at time ln core life.
INITIALCONDmONS Cokt shutdown FINALCONDITIONS Survelance complete.
SIMUIATORCONFIGURAllONREVlEWBOARD APPROVAL FOR USE DATE:
DATEi DATEs DATEi DAlE:
OINTSIMULATORCERTIFICATIONTEST PROCEDURE lllLEr DETERMINATIONOF ClUADRANTPOWER TILTRAllO, M)SPM9. 10 NUMBER:
5UR-N7 ANS J.5 REFERENCE SECTIONSr 8.1.1 (10) Operator Conducted Surveillance on Safety-Related Equipment or Systems DESCRIPllON lhls certification test will demonstrat the abilityofthe simulator to support the operator conductedsurveNance procedure 3-OSMSR 10, Determination ofQuadrant Power lilfRatio.
With no malfunctions present, the abilityto successfully perform this surveillance willbe verified.
OPIIONS TMs test can be performed at time in core life.
INITIALCONDITIONS RNALCONDmONS MOL IR% power, steady state SurveIance complete.
SIMUIATORCONFIGURATIONREVIBYBOARD APPROVAL FOR USE DATEr DATEr DAlE:
DAlE:
DATEr DATEr
TUI~rY'OINTUNIT3 SIMUILATORCERTIFICATIONUPDATE NUMBER 1 APPENDIXA TEST ABSTRACTS A.2 TESTS CHANGED
OINTSIMUIATORCERllFICAllONlEST PROCEDURE m1Ei CONTAINMENTEMERGENCY SYSTEMS OPERAllONS ANDMAIFUNCllONS NUMBER:
MCÃ-001 ANS 8.5 REFERENCE SECTIONSi
- 8. 14@8) Passive Malfunctions ln Engineered Safety Features Systems DESCRIPTION This test wfifexercise varfous malfunctions In the containment emergency systems. Proper system response to the malfunctions wlbe verified. lhe containment emergency systems include the containment spray pumps, the emergency containment cooler fans, and the emergency containment filterfans.
OPllONS There are a wide vaifety offailures available in the containment emergency systems.
INITIALCONDITIONS FINALCONDmONS MOL stead'y state at 100% power Each run willcontfnue until the proper response has been verifie.
SIMUIATORCONFIGURAllONREVIEWBOARDAPPROVE FOR USEDAlE'AlE:
bAlE:
DAlE:
DAlE:
DATEi
INTSIMUIATORCERllFICAllONTEST PROCEDURE TITLEs COMPONENT COOLING WATER OPERAllONS AND MALFUNCllONS NUMBER MCS40l ANS 8.5 REFERENCE SECllONS:
8.1.2 (8) Loss of Component Cooling System DESCRIPllON This test weal verify the simulators response to a malfunction ofthe Component Cooling Water system. AilCCWpumps willbe tripped resuNng In a total loss ofCCW cooling.
OPllONS lhere are several different means to cause a loss ofCCW.
INITIALCONDITIONS FINALCONDITIONS Steady state 100% power.
The test wIrun for20 minutes after the loss ofCCW.
SIMUIATORCONFIGURAllONREVIEWBOARD APPROVAL FOR USE DATE'AlE'AlE'ATEs
INTSIMULATORCENlFICAllONTEST PROCEDURE TTTLEr TllRBINEPlANTCOOLING WATER SySTEM OPERAllONS ANDMAIFUNCTTONS NUMBER.
MCS-ON ANS 3.5 REFERENCE SECTTONS:
8.1.2g) Loss ofService Water or Cooling fo Individual Components DESCRIPllON This test willverifythe simulators response to a malfunction ofthe Turbine Plant Cooing Water system. AIITPCWpumps wi7Ibe tripped resulting in a total loss of TPCW cooling.
OPllONS There are several different means to cause a loss of Turbine Plant Cooling Water.
INIllALCONDITIONS FINALCONDlllONS MOLsteady state at 100% power The test willbe stopped 30 minutes after the Initiationof the event.
SIMULATORCONHGURATIONREVIEWBOARD APPROVAL FOR USE DATEr DAlE:
OINTSIMULATORCERTIRCATION lEST PROCEDURE TIILEr LETDONVAND VOLUMECONlROL TANK5NSIEM OPERAllONS AND MALFUNCTIONS NUMBER MCV~
ANS 3.5 REFERENCE SECllONS: 3.1.2 (18) Failure ofReactor Cookrnt Pressure and Volume Control Systems DESCRIPllON The test checks the response ofthe Letdown and Volume Control Tank porttonsof the CVCSsystem.
Various malfunctions whichaffect these systems wNbe Initiated to verifyproper system response.
A total of four different malfunction tests wNbe run: (1) The letdown control valve PCV-145 wiNbe failed open, g PCV-145 wN be fai7ed closed, (3) The VCTlevel control valve LCV115A wNbe faBed to the chert position. and (4) The letdown Isolation valve CV204 wNbe failed closed.
OPllONS lhere 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.
INlllALCONDITIONS FINALCONDITIONS IRKpower, normal letdown lineup.
Terminate each run after system parametershave stabII!zedor trends are clearly evktent.
SIMUIATORCONHeURAnON REVIaIfBOARD APPROVAL FOR USE DAlE:
DAlE:
DAlE:
DAlE'ATEr DAlE:
INTSIMUlATORCERllFICATIONTEST PROCEDURE TITLE:
LOSS OF NORMALFEEDWATER NUMBER:
MFW~
ANS 3.5 REFERENCE SECllONS:
3.1.2(f9 Loss ofNormal Feedwater or Feedwater System Failure DESCRIPllON The purpose ofthis cerNffcaNon test Is to examine the simulator response to a loss ofnormal feedwater.
This loss ofnormal feedwater transient willbe compared to a best estfmate analysis usfng the Turkey Point RHPANmodel. As such, no operator octions wiNbe taken during the course ofthe event and several assumptions have been mode to make the imufotorand the RETRANmodels consistent.
Since the RElRANmodel does not Include charging and letdown models, these paths willbe Isolated In the simulator. The transient willbe inltfatedby tripping open both feedwater pump motor breakers. lhe turbine runback that wouldnormally result hom the tripping ofthese breakers is blocked. AMSACwillalso be blocked.
AIIcontrol systems ore In automatic except the control rods.
OPllONS The main feedwater can be lost via a variety of mechanisms Including the flingclosed of the IsolaNon or regulalfon valves, pump bearing failures, and motor breaker failures.
INmALCONDITIONS FINALCONDmONS Steady state at 100% power. BOL, EquiTbifum xenon The test wfffrun for20 minutes. By that Nme the steam generator levels should be recovering steadily and the system approaching a stable hot standby condiNon.
SIMUlATORCONFIGURATIONREVIEW BOARDAPPROVAL FOR USE DAlE:
DAlE:
DATEi DAlE:
OINTSIMUIATORCERTIFICAllONTEST PROCEDURE TITLE:
MAXIMUMRATE POWER RAMP (100% to 75% and back to 100%)
NUMBER:
MRX-001 ANS 8.5 REFERENCE SECllONS:
B.22 PJ Maximum rate Power Ramp (100% down to 75% and back up to 100%)
DESCRIPTION TNs certilicatlon test wi7levaluate the ablfityofthe simulator to perform a rapid decrease Inpower from 100% power to 75% and return back to 100%. Although this Is an Appendix B test, due to the nature of this test manual actions have to be token.
The off-normal operating procedure 3NOP-100, Fast Load Reduction wi be used to rapidly reduce power to approximately 75%. Afterthe plant has stablRzed, a return to power at the maximum rate possible wIoccur. lhe test team wi8pullcontrol rods and di7ute the PCS whilepicking up load on the turbine. Ifrequired, extra letdown ortflces and charging pumps wNbe used to dPute.
During the return fo power average temperature wIIIbe closely matched with the reference temperature and the al Emits willbe obseived.
OPllONS INlllALCONDITIONS RNALCONDITIONS Steady state, 100% power, MOL 100% power after recovery.
SIMUlATORCONRGURAllONREVIEWBOARD APPROVAL FOR USE DAlE:
DAlE:
DAlE:
DATEr
INTSIMUIATORCERTIFICATIONTEST PROCEDURE llRE:
MAINSlEAMLINEBR&LKINSIDE CONTAINMENT
'UMBER:
MSG-001 ANS 8.5 REFERENCE SECllONS:
3.1.2I20)
Main Steam Line as wellas Main Feed One Breaks (Both Inskfe and outside Containment)
B 22 (9)
Maximum SIze Unlsolabie Main Steam Line Rupture DESCRIPllON This steam fne break transient wIIIbe compared to a best estimate analysis using the Turkey Point RETRANmodel. As such, the test Is not intended to followin detai7 the emergency operating procedures covering this type oftransient. However, operator actions to turn offthe reactor coolant pumps on lowsu&cooling margin and isolate the auxiliary feedwater to the affected steam generator have been programmed into the scenario.
No other operator actions wIIIbe taken during the course of the event.
Several assumptions have been mode In order to make the simulator and the REIPANmodel consistent.
Since the RETRANmodel does not Include charging and letdown models or accumulatoo, these paths wi7Ibe isolated ln the simulator by the scenario.
Allother control and safety systems will be in automatic and fullyfunctional. A steam line break equivalent to the area ofthe flowrestrictor at the steam generator outlet Is assumed to occur in the B steam line inside containment.
Since this an ANS 3.5 Appendix B transient no operator actions willbe allowed after the transient starts.
However, as mentioned above, the reactor coolant pumps willbe stopped when there is an Indication that Sl Is occurring with a lowsu&cooling margin. lhe aum7iary feedwater willalso be Isolated to the affected steam generator.
OPllONS The simulator is capable ofsimulating steam fine breaks ofany dze at several locations Inside and outside contairvnent on each of the steam lines.
INITIALCONDmONS FINALCONDlllONS 1006'ower steady state. EOL lhe fest wiIIrun for 10 minutes.
SIMUIATORCONHGURAllONREVIEWBOARD APPROVAL FOR USE DAlE'AK DAlE'
lllLE:
SIMULTANEOUSCLOSURE OF ALLMSIYS NUMBER:
MSG~
ANS 8.5 REFERENCE SECllONS:
B22P) Simultaneous Closure ofAllMSIYs DESCRIPllON This test examines the simulator response to the simultaneous closure ofallof the main steam Ene Isolation valves (MSIYs).
ANcontrol and protection systems wm be In automatic.
Since this is an ANS 3.5 Appendor B test, no operator followup actions wi8be taken OPTIONS Anyor allofthe MSIV's can be closed by a variety offailure mechanisms.
These include giving the valves a failclose signal or using an instructor override on the control board handswitches.
INmALCONDmONS RNALCONDIllONS 100% power steady state. BOL The transksnt Is analyzed for approxlmatet'y 10 minutes.
SIMULATORCONFIGURAllONREVIEWBOARD APPROVAL FOR USEDAlE'AlE:
DAD DAlE:
DAlE:
DAlE: