ML18152A391
| ML18152A391 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/24/1992 |
| From: | Bowling M VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.149, RTR-REGGD-1.149 92-485A, NUDOCS 9209300235 | |
| Download: ML18152A391 (20) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 24, 1992 Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY Serial No.
NL&P/ETS Docket Nos.
License Nos.
SURRY POWER STATION UNITS 1 AND 2 SIMULATOR CERTIFICATION FOUR-YEAR REPORTS 92-485A 50-280 50-281 DPR-32 DPR-37 Pursuant to the provisions of 1 O CFR 55.45 (b) (5) (ii), the Simulator Facility Certification Four-Year Reports for Surry Units 1 and 2 are being submitted. The initial certification reports were dated October 14, 1988. The intent of these quadrennial reports is to document our continuing compliance with ANSI/ANS-3.5-1985, as modified or endorsed by Regulatory Guide 1.149 (April 1987).
The reports are included as Attachments 1 and 2.
A discussion between Mr. N. K. Hunemuller of the NRC and Mr. E. J. Wheeler of my staff concerning the North Anna simulator certification four-year report indicated that a description of the performance testing successfully completed during the previous four year interval is not required to be included.
Accordingly, this description is not provided for the Surry simulator facility.
If further information is required, please contact Dr. Terry M. Williams, Manager Nuclear Training, at (804) 273-2701.
Very truly yours,
!Pl.A~
M. L. Bowling, Manager Nuclear Licensing & Programs Attachments 280133
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Mr. R. M. Gallo Chief, Operator Licensing Branch U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. T. A. Peebles Chief, Division of Reactor Safety - Operations Branch U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station
e SURRY UNIT 1 SIMULATOR CERTIFICATION FOUR YEAR REPORT e
SURRY UNIT 1 SIMULATOR CERTIFICATION FOUR YEAR REPORT This Surry Unit 1 Simulator Certification Four Year Report consists of the following sections:
- Previous Four Year Simulator Test Results Summary
- Simulator Instructor Console Upgrade Summary
- 1993 - 1996 Simulator Test Schedule
- Simulator Fidelity & Upgrade Report (Attachment 1)
(Attachment2)
(Attachment3)
(Attachment 4)
ATTACHMENT 1 PREVIOUS FOUR YEAR SIMULATOR TEST RESULTS
SUMMARY
Since October 1988, many modifications have been made to the Surry simulator.
Testing, which verified simulator fidelity acceptable for training and certification, has been completed. The discrepancies uncovered during the previous four years are expected to be resolved in a timely manner. All testing originally scheduled in the Surry Unit 1 Simulator Certification Submittal was satisfactorily completed, with no test failures.
A Simulator Real Time Test was conducted during the final quarter of the test cycle, instead of the 3rd year as scheduled. This test verified the simulator models were running in "real" time. The test consisted of three simulator runs to cover a range of model loading, which included, Steady State, Steam Generator Tube Rupture, and Loss of Coolant Accident. Variables were monitored and data collected that verified model execution times reflected real time.
Based upon the testing conducted, and their results, the Surry simulator is acceptable for licensed operator training and retraining.
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MALFUNCTION MODIFICATIONS The following malfunctions were modified to meet changing training requirements.
MCH20 FUEL MELT Modification to the Radiation Monitor System response via Simulator Modification Report# 9010160800 caused the range of the Core Activity Released (MCH20) malfunction to increase. Malfunction MCH20 (Core Activity Released) was renamed to Fuel Melt. The malfunction was tested satisfactorily on June 14,1991.
MRC04 REACTOR COOLANT SYSTEM NONISOLABLE LEAK The resolution of Simulator Modification Report# 9202251300, caused the range of malfunction MRC04, "Reactor Coolant System Nonisolable Leak" to increase.
The maximum leakage of the malfunction was increased from 600 GPM to 1200 GPM. The malfunction was satisfactorily tested on August 6, 1992.
REACTOR COOLANT RTD BYPASS LINE ELIMINATION DCP-91-05-3 The Simulator software was modified to reflect station implementation of Design Change Package DCP-91-05-1, Reactor Coolant RTD Bypass Line Elimination. The DCP was resolved via Simulator Modification Report# 9112310900 and caused the renaming of the following malfunctions:
Malfunction MRC07 - RTD Fails High in the Hot Leg (Protection) was renamed to "Failure of Narrow Range T-Hot Instrument/ RTD".
Malfunction MRC08 - RTD Fails High in the Cold Leg (Control) was renamed to "Taylor Math Unit Failure HI/LO".
Malfunction MRCll - RTD Fails High in the Cold Leg (Protection) was renamed to "Failure of Narrow Range T-Cold Instrument/ RTD".
The malfunctions were satisfactorily tested on March 24, 1992. The scope of the model changes are discussed within Attachment 4 (Other Simulator Upgrades Installed).
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MRD09 CONTROL BANK MOVES OUT WHEN IN DEMANDED IN. AUTO MRD09 was renamed from "Control Bank Moves Out When In Demanded" to "Control Bank Moves Out When In Demanded In Auto" to clearly define the malfunction.
This malfunction can be implemented only when in Auto Mode. No modeling changes were made as a result of this action.
MRDlO CONTROL BANK MOVES IN WHEN OUT DEMANDED IN AUTO MRDlO was renamed from "Control Bank Moves In When Out Demanded" to "Control Bank Moves In When Out Demanded In Auto" to clearly define the malfunction.
This malfunction can be implemented only when in Auto Mode. No modeling changes were made as a result of this action.
MSI07 SAFETY INJECTION ACCUMULATOR TRANSMITTER FAILURE MSI07 was renamed from "Safety Injection Accumulator Level Transmitter Failure" to "Safety Injection Accumulator Transmitter Failure" to clearly define the malfunction.
This malfunction can be implemented on the Accumulator Level or Pressure Transmitter.
No modeling changes were made as a result of this action.
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ATTACHMENT 2 INSTRUCTOR CONSOLE UPGRADE
SUMMARY
The upgrade of the Simulator Instructor Console and Instructor Booth was completed. The upgrade included the installation of additional monitors for improved instructor flexibility by allowing two instructors simultaneous use of the console features.
The upgrade eliminated the need for the push button function panel which was replaced with a keyboard entry menu based system. Two additional features were developed and added for increased instructor flexibility. They are:
Controller Override Processor - This feature allows one or all of a particular controller's functions to be selected and overridden to the desired position.
MOV Override Processor - This feature allows the instructor to act as a local operator and take control of any MOV's power and position it to the desired position.
The simulator audio system was enhanced to minimize background noise and to provide better recording and monitoring quality.
The Malfunction Cause and Effects Document was extensively revised to provide more detail to the user.
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e ATTACHMENT 3 1993 -1996 SIMULATOR TEST SCHEDULE The next simulator four year test schedule follows. The tests are divided in such a manner as to ensure that 25 % are performed each year thereby ensuring that all testing is completed within the four year time frame specified.
SIMULATOR PERFORMANCE TEST SCHEDULE The performance testing schedule to be conducted over the next four years will consist of the following tests:
The Steady State Tests of ANS-3.5-1985 Appendix B section B.2.1 will be conducted annually.
- The Transient Performance Tests of ANS-3.5-1985 Appendix B section B.2.2 will be conducted annually.
November 1992 - October 1993 Integrated Tests Plant Heatup from Cold Shutdown to Intermediate Shutdown.
Plant Heatup from Intermediate Shutdown to Hot Shutdown.
Malfunction Tests MCAOl MCA02 MCA04 MCA08 MCCOl ***
MCC03 MCC04 MCCOS MCHOl MCH02 MCH03 MCHOS MCH06 INSTRUMENT AIR LEAK CONTAINMENT INSTRUMENT AIR COMPRESSOR IA-C-4A,B TRIP CONTAINMENT INSTRUMENT AIR LEAK INSTRUMENT AIR COMPRESSOR OVERLOAD TRIP LOSS OF CC WATER TO SW THROUGH CC HX'S OVERLOAD TRIP OF COMPONENT COOLING WATER PUMP LOSS OF COMPONENT COOLING TO NON-REGENERATIVE HEAT EXCHANGER THERMAL BARRIER LEAK TO CC SYSTEM ISOLABLE LETDOWN LINE LEAK IN CONTAINMENT ISOLABLE LETDOWN LINE OUTSIDE CONTAINMENT CHARGING LINE LEAK DOWNSTREAM FCV-1122 OUTSIDE CONTAINMENT LOSS OF CHARGING PUMP NON-REGENERATIVE HEAT EXCHANGER TEMPERATURE CONTROLLER TC-1144B FAILS 5
MCH11 MCH12 MCH13 MCH17 MCH19 MCH20 MCH21 MCH22 MCH23 MCH24 MCH25 MCH28 MCH29 MCH31 MCH35 MCH36 MCH37 MCH38 MCH39 MCH40 MCH41 MCNOl MCN02 MCN03 MCNOS MCN08 MELOl MEL02 RCP SEAL WATER INJECTION PRESSURE TRANSMITTER FAILURE RCP SEAL WATER RETURN HEADER TEMPERATURE TRANSMITTER FAILURE TUBERUPTUREINTHENON-REGENERATIVEHEATEXCHANGER SEAL WATER RETURN FILTER CLOGS VCT LEVEL CONTROLLER FAILURE FUEL MELT VCT LEVEL TRANSMITTER FAILURE VOLUME CONTROL TANK PRESSURE TRANSMITTER FAILURE VOLUME CONTROL TANK TEMPERATURE TRANSMITTER FAILURE BORIC ACID FLOW CONTROLLER 113 FAILURE PRIMARY WATER FLOW CONTROLLER 114 FAILURE FAILURE OF CHARGING FLOW CONTROLLER FAILURE OF CHARGING FLOW TRANSMITTER REGENERATIVE HEAT EXCHANGER OUTLET TEMPERATURE TRANSMITTER CH-TE-1123 LOW PRESSURE LETDOWN FLOW TRANSMITTER FAILURE LETDOWN PRESSURE CONTROLLER (PC-1145) FAILURE WW PRESSURE IBTDOWN LINE PRESSURE TRANSMITTER PT-1145 FAILURE REGENERATIVE HEAT EXCHANGER LETDOWN TEMPERATURE TRANSMITTER FAILURE LETDOWN LINE RELIEF LINE TEMPERATURE TRANSMITTER FAILURE LOW PRESSURE LETDOWN LINE TEMPERATURE TRANSMITTER FAILURE NON-REGENERATIVE HEAT EXCHANGER OUTLET TEMPERATURE TRANSMITTER FAILURE LOSS OF MAIN CONDENSATE PUMP AIR LEAK INTO MAIN CONDENSER CN-SC-lA & 1B BOOT HOTWELLLEVEL CONTROLLER FAILURE LC-CN-102 CONDENSATE LINE LEAK BETWEEN CN 114 AND FCV-CN-107
- LOSS OF AIR EJECTOR LOOP SEAL LOSS OF ALL OFFSITE POWER MAIN GENERATOR TRIP 6
November 1993 - October 1994 Integrated Tests
- Unit start up operations (Hot Shutdown to full power).
Malfunction Tests MEL07 MEL08 MEL09 MEL12 MEL13 MEL14 MEL17 MEL18 MEL19 MEL20 MEL21 MFWOl MFW02 MFW04 MFWOS MFW07 MFW08 MFW10 MFW12 MFW13 MFW14 MFW15 MFW16 MFW17 MFW18 MFW19 MFW20 MFW21 MFW22 MFW23 MMI03 MMI04 LOSS OF 4160V STATION BUS LOSS OF SCREENWELL TRANSFORMER LOSS OF EMERGENCY DIESEL GENERATOR LOSS OF 480V EMERGENCY SWITCHGEAR LOSS OF 480V EMERGENCY MOTOR CONTROL CENTER LOSS OF SEMI-VITAL BUS LOSS OF 125V D.C. BUS LOSS OF 480V STATION SWITCHGEAR LOSS OF 480V MOTOR CONTROL CENTER LOSS OF AC VITAL BUS LOSS OF 4160V EMERGENCY BUS MAIN FEEDWATER PUMP RECIRC VALVE FAILS OPEN MAIN FEEDWATER REGULATING VALVE FAILS CLOSED MAIN FEED PUMP LOW LUBE OIL PRESSURE MAIN FEEDWATER BREAK BETWEEN FLOW TRANSMITTER AND DISCHARGE CHECK VALVE AUX FEED PUMPS FW-P-3A/B TRIP : OVERCURRENT AUX FEED PUMP TURBINE WON'T STOP AUXILIARY FEED PUMP CHECK VALVE OPEN MAIN FEED PUMP SUCTION LINE BREAK STEAM GENERATOR LEVEL TRANSMITTER FAILURE (0-100%)
AUXILIARY FEEDWATER BREAK DOWNSTREAM OF FLOW TRANSMITTER AND CHECK VALVE MAIN FEEDWATER BREAK DOWNSTREAM OF CHECK VALVE OUTSIDE CONTAINMENT MAIN FEEDWATER BREAK IN CONTAINMENT DEGRADATION OF MAIN FEED PUMP STEAM GEN MAIN FEED FLOW TRANSMITTER FAILURE STEAM GEN MAIN FEED FLOW CONTROLLER FAILURE STEAM GEN WIDE RANGE LEVEL TRANSMITTER FAILURE STEAM GEN AUX FEED FLOW TRANSMITTER FAILURE STEAM GEN MAIN FEED HEADER PRESSURE TRANSMITTER FAILURE TOTAL LOSS OF FEEDWATER GRADUAL INCREASE IN CONTAINMENT PRESSURE FAILURE OF REACTOR TRIP BUTION 7
MMSOl MMS03 MMS04 MMS06 MMS07 MMS08 MMS09 MMSlO MMSll RUPTURE OF MAIN STEAM LINE AT HEADER RUPTURE OF MAIN STEAM LINE UPSTREAM OF FLOW ELEMENT RUPTURE OF MAIN STEAM LINE BEFORE THE TRIP VALVE MAIN STEAM TRIP VAL VE FAILS AS IS MAIN STEAM SAFETY VALVE FAILS OPEN STEAM GEN STEAM FLOW TRANSMITTER FAILURE MAIN STEAM TRIP VAL VE FAILS SHUT FAILURE OF AUTO STEAM DUMP AS IS MAIN STEAM HEADER PRESSURE TRANSMITTER FAILURE November 1994 - October 1995 Integrated Tests Decreasing power from 100% power level to Hot Shutdown conditions.
Computer Real Time Test.
Malfunction Tests MMS13 MMS14 MMS15.
MNIOl MNI02 MNI03 MNI04 MNIOS MNI06 MNI07 MNI08 MNI09 MNI10 MRCOl MRC02 MRC03 MRC04 MRCOS MRC07 MRC08 MRCll MRC14 STEAM GEN PRESSURE TRANSMITTER FAILURE TURBINE FIRST STAGE PRESSURE TRANSMITTER FAILURE SG PORV CONTROLLER FAILURE SOURCE RANGE CHANNEL FAILURE SOURCE RANGE DETECTOR FAILURE (DISCRIMINATOR ERROR)
INTERMEDIATE RANGE CHANNEL UNDERCOMPENSATION INTERMEDIATE RANGE CHANNEL OVERCOMPENSATION INTERMEDIATE RANGE CHANNEL FAILURE FAILURE OF IR TO ALLOW SR BLOCK LOSS OF INSTRUMENT POWER TO POWER RANGE CHANNEL
- POWER RANGE CHANNEL UPPER DETECTOR FAILURE POWER RANGE CHANNEL LOWER DETECTOR FAILURE POWER RANGE CHANNEL FAILS REACTOR COOLANT SYSTEM COLD LEG PIPE RUPTURE REACTOR COOLANT SYSTEM HOT LEG PIPE RUPTURE REACTOR COOLANT SYSTEM SUCTION LEG PIPE RUPTURE REACTOR COOLANT SYSTEM NONISOLABLE LEAK RCPOVERCURRENTTRIP FAILURE OF NARROW RANGE T-HOT INSTRUMENT/ RTD TAYLOR MATH UNIT FAILURE HI/LO FAILURE OF NARROW RANGE T-COLD INSTRUMENT / RTD FAILURE OF RCP SEAL #3 8
MRC15 MRC16 MRC17 MRC20 MRC21 MRC22 MRC24 MRC25 MRC26 MRC30 MRC31 MRC34 MRC37 MRC38 MRC40 MRC42 MRC45 MRC46 MRC48 PRZR PRESSURE CONTROLLERS FAILURE PRZR REL/SFTY VV LINE TEMPERATURE TRANSMITIER FAILURE PRESSURIZER LEVEL CONTROL FAILURE BOTH PRZR SPRAY VALVES FAIL SHUT PRESSURIZER SAFETY VAL VE FAILS OPEN PRZR SPRAY VALVE FAILS OPEN STEAM GENERATOR TUBE RUPTURE PRESSURIZER HEATERS GROUP FAIL ON RCP SHAFT SHEARS LOSS OF SEAL INJECTION FLOW TO RCP REACTOR COOLANT LOOP FLOW TRANSMITIER FAILURE RCS WIDE AND NARROW RANGE PRESSURE TRANSMITIER FAILURE PRESSURIZER RELIEF TANK PRESSURE TRANSMITTER FAILURE LOSS OF COMPONENT COOLING WATER TO RCP PRESSURIZER PORV LEAKAGE PRESSURIZER TEMPERATURE TRANSMITTER FAILURE PRESSURIZER RELIEF TANK TEMPERATURE TRANSMITTER FAILURE REACTOR VESSEL LEAKOFF TEMPERATURE TRANSMITTER FAILURE PRESSURIZER PRESSURE TRANSMITTER FAILURE November 1995 - October 1996 Integrated Tests Unit cooldown from Hot Shutdown to Intermediate Shutdown.
Unit cooldown from Intermediate Shutdown to Cold Shutdown.
Malfunction Tests MRC49 MRCSO MRDOl MRD02 MRD03 MRD04 MRDOS PRESSURIZER LEVEL TRANSMITTER FAILURE PRESSURIZER RELIEF TANK LEVEL TRANSMITTER FAILURE CONTINUOUS ROD WITHDRAW AL, MANUAL OR AUTO CONTINUOUS ROD INSERTION MANUAL OR AUTO LOGIC FAILURE CAUSING TWO BANKS TO MOVE AT THE SAME TIME AUTO AND MANUAL ROD CONTROL INOPERABLE CONTROL BANKS IN SPEED FAIL TO 72 SPM 9
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MRD06 MRD07 MRD08 MRD09 MRDlO MRD12 MRD13 MRD15 MRD16 MRD18 MRD19 MRD20 MRHOl MRH02 MRH04 MRHOS MRH06 MRMOl MRM02 MRS06 MRS07 MRS08 MSI03 MSI04 MSI05 MSI06 MSI07 MSI08 MSilO MTUOl MTU04 MTU13 MWDOl MWD03 CONTROL BANKS IN SPEED FAIL TO 8 SPM CONTROL BANKS OUT SPEED FAIL TO 72 SPM CONTROL BANKS OUT SPEED FAIL TO 8 SPM CONTROL BANK MOVES OUT WHEN IN DEMANDED IN AUTO CONTROL BANK MOVES IN WHEN OUT DEMANDED IN AUTO DROPPED CONTROL ROD EJECTED CONTROL ROD REACTOR TRIP BREAKERS OPEN DUE TO UV COIL FAILURE INDIVIDUAL ROD POSITION INDICATION FAIL FAIL OF AUTO TRIP TO SCRAM RX FAILURE OF ALL ROD STOPS TO BLOCK ROD MOVEMENT STUCK ROD RESIDUAL HEAT REMOVAL SYSTEM LEAK LOSS OF RESIDUAL HEAT REMOVAL PUMP HCV-1758 CONTROLLER OUTPUT FAILURE RHR FLOW CONTROLLER FC-1605 FAILS RELIEF VALVE FAILS OPEN ON RESIDUAL HEAT REMOVAL SYSTEM AREA RADIATION MONITOR FAILS PROCESS RADIATION MONITOR FAILURE LOSS OF OUTSIDE RECIRC SPRAY PUMP LOSS OF INSIDE RECIRC SPRAY PUMP LOSS OF CONTAINMENT SPRAY PUMP SAFETY INJECTION HOT LEG FLOW TRANSMITTER FAILURE SAFETY INJECTION TOTAL FLOW TRANSMITTER FAILURE LHSI PUMP FLOW TRANSMITTER FAILURE SAFETY INJECTION COLD LEG FLOW TRANSMITTER FAILURE SAFETY INJECTION ACCUMULATOR TRANSMITTER FAILURE FAILURE OF SAFETY INJECTION RESET TIMER LOW HEAD SAFETY INJECTION PUMP IMPELLER DEGRADATION TURBINE TRIP DUE TO SOLENOID FAILURE FAILURE OF MANUAL TURBINE TRIP FAILURE OF AUTOMATIC TURBINE RUNBACK DROPPED SPENT FUEL ASSEMBLY IN THE SPENT FUEL PIT ACCIDENTAL RELEASE OF RADIOACTIVE GAS 10
e ATIACHMENT 4 SIMULATOR FIDELITY & UPGRADE REPORT PHYSICAL FIDELITY Physical fidelity is verified with an item by item comparison of the Simulator Control Room to a series of Unit 1 Plant Control Room photographs that are taken annually during the month of January. Identified discrepancies are scheduled for resolution during the current year.
The report includes identification of all unresolved Simulator Control Panel discrepancies; indicating the work to be performed based on training impact, cost effectiveness, and other considerations as appropriate. Also included are discrepancies identified as requiring no action. Generic Control Room/Panel differences have been identified as necessary.
The simulator Physical Fidelity Report is not included with this report, however, it is available for examination.
CONTROL ROOM AND SIMULATOR PANEL COMPARISON UPDATE A review was conducted of the original submittal report on the Surry Control Room and Simulator Comparison of Panel Layout and Environment. The review was performed to update the changes made during the prior four years and validate the original differences noted.
A Meteorological Panel was added to support the requirements of Emergency Plan Implementing Procedure (EPIP) training and Site Emergency Preparedness training.
The panel is common to both Units 1 and 2. The panel's location on the Unit 2 side of the station control room is effectively reproduced in the simulator by locating it next to the Unit 2 Ventilation Panel. Only the common monitors relating to the Meteorological information are simulated.
The Unit 2 Ventilation Panel was added to enhance operator training. The panel contains components common to both Units 1 and 2. The panel's location on the Unit 2 side of the station control room is effectively reproduced in the simulator by locating it next to the Meteorological Panel. Only the common monitors relating to the Control Room Ventilation information are simulated.
The Gas Turbine Remote Control Panel has been redesignated the Common Ventilation Panel. All Gas Turbine Control components were removed. The Common Ventilation Panel contains instrumentation and controls for the ventilation equipment associated with the Main Control Room.
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Panels that remain non-simulated because of their relative minor training value :
ROBERT SHAW FIRE PROTECTION PANELS STATION FIRE PROTECTION PANELS FLOOD CONTROL PANEL (Hardware only installed)
CONTROL ROOM AND SIMULATOR ENVIRONMENTAL REVIEW UPDATE The following differences identified in the original simulator certification report have been incorporated into the simulator:
The Simulator carpet was installed to match the station The main control room has chairs used by the operating staff that are a different color than those in the simulator.
Floor riser sections are installed on both the east and west ends of the bench board which physically raises the floor height approximately four inches with a sloping grade of 45 degrees. The simulator floor has been modified to include these riser sections.
A digital clock has been installed over the Auxiliary Ventilation Panel.
The local control room radiation monitor detector and readout with alarm were installed in the simulator.
The remaining environmental differences identified in the initial simulator certification report have been reviewed and found to have no impact on training. Based upon the review results, the simulator is acceptable for operator training and testing.
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e OTHER SIMULATOR UPGRADES INSTALLED The simulator systematic upgrade was completed in 1989. Dates of completion are available upon request.
The Reactor Core model was upgraded to cycle 10, 11, then 12.
Upgraded the response of the reactor core thermocouple response to better reflect response during core voiding events.
The telephone capabilities available in the reference control room for use by the operators and the System Operator was reproduced and installed in the simulator.
Systems required by Emergency Preparedness have the capability of cross-connecting the stating and simulator systems during emergency drills.
The Gaitronics paging system was tied to the station's system for use with the emergency drills.
Chart recorder power relays were installed to allow freezing of the recorders and the simulation of the loss of power to individual recorders for enhanced realism.
The simulator computer configuration was altered from a "shared memory configuration between a Gould 32/2750 and a Gould 8780 to that of a single Gould 8780 with shadow memory. The change improved spare real execution time significantly.
The Reactor Vessel Level Indication System was installed.
The Simulator Software was modified to reflect implementation of Design Change Package DCP-91-05-1, Reactor Coolant RTD Bypass Line Elimination. The narrow range reactor coolant temperature measurement system, including the associated bypass piping, valves, and manifolds were removed and replaced with a new narrow range temperature measurement system. The new system consists of RTD's installed directly in the hot and cold legs of the reactor coolant piping.
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SURRYUNIT2 SIMULATOR CERTIFICATION FOUR YEAR REPORT e
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SURRYUNIT2 SIMULATOR CERTIFICATION FOUR YEAR REPORT The Surry Power Station is a two unit station, operating from a common control room. The respective unit control panels are identical in their configuration and layout with respect to the operator. A few auxiliary systems panels present a mirror image layout to the operator in order to maintain an overall balanced appearance of the control room.
This Surry Unit 2 Simulator Certification Four Year Report consists of the following sections:
Simulator Fidelity & Upgrade Report (Attachment 1).
There were no significant differences identified during the previous four years.
The Surry Unit 1 Simulator meets the Unit 2 Training needs.
ATTACHMENT 1 SIMULATOR FIDELITY & UPGRADE REPORT PHYSICAL FIDELITY A review was conducted of the original submittal report on the Surry Unit 2 Control Room and Panel Comparison and Environment. The review was done to update the changes made during the prior four years and validate the original differences noted.
No additional differences were identified as a result of the Unit 1 and Unit 2 Control Room Panel Comparison.
A Meteorological Panel was added in order to support the requirements of EPIP training and Site Emergency Preparedness training. The panel is common to both Units 1 and 2. Its location on the Unit 2 side of the station control room is effectively reproduced in the simulator by locating it next to the Unit 2 Ventilation Panel.
The Unit 2 Ventilation Panel was added to enhance operator training. The panel contains components common to both Units 1 and 2. The panel's location on the Unit 2 side of the station control room is effectively reproduced in the simulator by locating it next to the Meteorological Panel.
ENVIRONMENTAL REVIEW Environmental differences and differences between the simulator and the Unit 1 Control Room are discussed within the Control Room/Simulator Panel and Environment Comparison Report (Attachment 4) of the Surry Unit 1 Simulator Certification Four Year Report.
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