ML18153A628
| ML18153A628 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/12/1996 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18153A627 | List: |
| References | |
| NUDOCS 9611200096 | |
| Download: ML18153A628 (16) | |
Text
e SURRY UNIT 1
. SIMULATOR CERTIFICATION 2nd FOUR YEAR REPORT
( 1992 - 1996)
e SURRY UNIT 1 SIMULATOR CERTIFICATION FOUR YEAR REPORT This Surry Simulator Certification Four Year Report (1992 - 1996) consists of the following sections:
- Previous Four Year Simulator Test Results Summary
- 1997 - 2000 Simulator Test Schedule
- Simulator Fidelity & Upgrade Report (Attachment 1)
(Attachment 2)
(Attachment 3)
ATTACHMENT 1 PREVIOUS FOUR YEAR SIMULATOR TEST RESULTS
SUMMARY
Since October 1992, a number of modifications have been made to the Surry simulator. Testing, which verified simulator fidelity acceptable for training and certification, has been completed.
Discrepancies that are identified during the report period are resolved in a timely manner in accordance with training administrative procedures.
The Integrated Tests for the Unit Cooldown for Hot Shutdown to lntermedi,ate Shutdown and Unit Cooldown for Intenµediate Shutdown to Cold Shutdown were performed in the first year of this cycle, 1992, instead of the fourth year as scheduled; The Integrated Tests for the Unit Heatup from Cold Shutdown to Intermediate Shutdown and Heatup from Intermediate Shutdown to Hot Shutdown were performed in the fourth year of this cycle, 1996, instead of the first year as scheduled. All testing was satisfactorily completed within the four-year time frame specified.
Based upon the testing conducted, and their results, the Surry simulator is acceptable for licensed operator training and retraining.
e MALFUNCTION MODIFICATIONS The following malfunctions were modified to meet changing training requirements.
MMI03 GRADUAL INCREASE IN CONTAINMENT PRESSURE Modification to instructor console program required the deletion of the "MI" System designation for all instructor console malfunctions and overrides. Therefore MMI03, Gradual.
Increase In Containment Pressure, was renamed to MRS 11, Gradual Increase In Containment Pressure. No modeling changes were made as a result of this action.
MMI04 FAILURE OF REACTOR TRIP BUTTON Modification to instructor console program required the deletion of the "Ml" System designation for all instructor console malfunctions and overrides. Therefore MMI04, Failure Of Reactor Trip Button, was renamed to MRD21, Failure Of Reactor Trip Button. No modeling changes were made as a result of this action.
ATTACHMENT 2 1997-2000 SIMULATOR TEST SCHEDULE The next four year simulator 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 to be conducted over the next four years will consist of the following.
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 1996 - October 1997 Integrated Tests Plant Heatup from Cold Shutdown to Intermediate Shutdown.
Plant Heatup froni Intermediate Shutdown to Hot Shutdown.
Malfunction Tests MCAOl MCA02 MCA04 MCA08 MCCOl MCC03 MCC04 MCC05 MCHOl MCH02 INSTRUMENT AIR LEAK CONTAINMENT INSTRUMENT AIR COMPRESSOR IA-C-4A,B TRIP CONTAINMENT INSTRUMENT AIR HEADER 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
MCH03 MCH05 MCH06 MCHll 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 CHARGING LINE LEAK DOWNSTREAM FCV-1122 OUTSIDE CONTAINMENT LOSS OF CHARGING PUMP NON-REGENERATIVE HEAT EXCHANGER TEMPERATURE CONTROLLER TC-1144B FAILS RCP SEAL WATER INJECTION PRESSURE TRANSMITTER FAILURE RCP SEAL WATER RETURN HEADER TEMPERATURE TRANSMITTER FAILURE TUBE RUPTURE IN THE NON-REGENERATIVE HEAT EXCHANGER 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 1113 FAILURE PRIMARY WATER FLOW CONTROLLER 1114 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 LOW PRESSURE LETDOWN 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 CONDENSATE PUMP, OVER CURRENT AIR LEAK INTO MAIN CONDENSER CN-SC-lA & -lB BOOT HOTWELL LEVEL 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
e November 1997 - October 1998 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 MFWlO MFW12 MFW13 MFW14 MFW15 MFW16 MFW17 MFW18 MFW19 MFW20 MFW21 MFW22 MFW23
- MMSOl MMS03 MMS04 MMS06 MMS07 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 VAL VE OPEN MAIN FEED PUMP SUCTION LINE BREAK STEAM GENERATOR LEVEL TRANSMITTER FAILURE (0-100%)
AUXILIARY FEEDWATER BREAK DOWNSTREAM OF FLOW TRANSMITTER AND CHECK VAL VE 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 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 VALVE FAILS AS IS MAIN STEAM SAFETY VALVE FAILS OPEN
MMS08
.MMS09 MMSlO MMSll MMS13 MMS14 e
STEAM GEN STEAM FLOW TRANSMITIER FAILURE MAIN STEAM TRIP VALVE FAILS SHUT FAILURE OF AUTO STEAM DUMP AS IS MAIN STEAM HEADER PRESSURE TRANSMITTER FAILURE STEAM GEN PRESSURE TRANSMITIER FAILURE TURBINE FIRST STAGE PRESSURE TRANSMITTER FAILURE November 1998 - October 1999 Integrated Tests
~
Decreasing power from 100 % power level to Hot Shutdown conditions.
Computer Real Time Test.
Malfunction Tests MMS15 MNIOl MNI02 MNI03 MNI04 MNI05 MNI06 MNI07 MNI08 MNI09 MNilO MRCOl MRC02 MRC03 MRC04 MRC05 MRC07 MRC08 MRCll MRC14 MRC15 MRC16 MRC17 MRC20 MRC21 MRC22 MRC24 MRC25 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 POWERTO 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 RCP OVERCURRENT TRIP FAILURE OF NARROW RANGE T-HOT INSTRUMENT I RTD TAYLOR MATH UNIT FAILURE HI/LO FAILURE OF NARROW RANGE T-COLD INSTRUMENT I RTD FAILURE OF RCP SEAL #3 PRZR PRESSURE CONTROLLERS FAILURE PRZR REL/SFTY VV LINE TEMPERATURE TRANSMITIER FAILURE PRESSURIZER LEVEL CONTROL FAILURE BOTH PRZR SPRAY VALVES FAIL SHUT PRESSURIZER SAFETY VALVE FAILS OPEN PRZR SPRAY VALVE FAILS OPEN STEAM GENERATOR TUBE RUPTURE PRESSURIZER HEATERS GROUP FAIL ON
MRC26
.MRC30 MRC31 MRC34 MRC37 MRC38 MRC40 MRC42 MRC45 MRC46 MRC48 MRC49 MRC50 RCP SHAFT SHEARS LOSS OF SEAL INJECTION FLOW TO RCP REACTOR COOLANT LOOP FLOW TRANSMITTER FAILURE RCS WIDE AND NARROW RANGE PRESSURE TRANSMITfER 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 PRESSURIZER LEVEL TRANSMITTER FAILURE PRESSURIZER RELIEF TANK LEVEL TRANSMITTER FAILURE November 1999 - October 2000 Integrated Tests Unit cooldown from Hot Shutdown to Intermediate Shutdown.
Unit cooldown from Intermediate Shutdown to Cold Shutdown.
Malfunction Tests MRDOl MRD02 MRD03 MRD04 MRD05 MRD06 MRD07 MRD08 MRD09 MRDlO MRD12 MRD13 MRD15 MRD16 MRD18 MRD19 MRD20 CONTINUOUS ROD WITHDRAWAL, 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 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 POSIDON INDICATION FAIL FAIL OF AUTO TRIP TO SCRAM RX FAILURE OF ALL ROD STOPS TO BLOCK ROD MOVEMENT STUCK ROD
~-
MRD21
.MRHOl MRH02 MRH04 MRH05 MRH06 MRMOl MRM02 MRS06 MRS07 MRS08 MRSll MSI03 MSI04 MSI05 MSI06 MSI07 MSI08 MSI10 MTUOl MTU04 MTU13 MWDOl MWD03 FAILURE OF REACTOR TRIP BUTTON 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 LOSSOFCONTAINMENTSPRAYPUMP GRADUAL INCREASE IN CONTAINMENT PRESSURE 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
ATTACHMENT 3 SIMIJLATOR 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.
Identified discrepancies are scheduled for resolution during the current year.
The report includes identification of all unresolved Simulator Control Panel discrepancies and indicates 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 A review was conducted of the original and the first four-year submittal reports on the Surry Control Room and Simulator Comparison of Panel Layout. The review was performed to update the changes made during the prior four years and to validate the original differences noted. This comparison also identifies any differences between Unit 1 and Unit 2 Control Room Panels.
The review of the Control Room and Simulator Panel Comparison is not included with this report; however, it is available for examination.
Panels that remain non-simulated because of their relative minor training value are:
ROBERTSHAW FIRE PROTECTION PANEL STATION FIRE PROTECTION PANEL FLOOD CONTROL PANEL (Hardware only.installed)
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e CONTROL ROOM AND SIMULATOR ENVIRONMENTAL REVIEW The following minor environmental differences identified in the original and the first four year simulator certification report have been incorporated into the simulator:
Simulator Gaitronics system has been modified to mute the paging feature from the control room.
The remaining environmental differences identified in the initial and the first four year.
simulator certification reports have been reviewed and found to have no impact on training.
Based upon the review results, the simulator is acceptable for operator training and retraining.
OTHER SIMULATOR UPGRADES INSTALLED The simulator Electronic Associates Inc. hardware 1/0 system was replaced and upgraded to a VMIC "Intelligent 1/0 Control" system.
The simulator computer hardware configuration was upgraded from a Gould 32/8780 to a SUN SP ARC 10 workstation. The simulation software was then recompiled to run on the new UNIX platform. Extensive testing was conducted to ensure model integrity and functionality of all simulator features.
Reactor core cycles upgrades 13, and 14 were installed upon completion of the respective station refueling cycle.
A Simulator model modification was installed during the normal Design Change process for DCP-94-30-3, Core Uprate Setpoint Change. This change increased the core operating power level to 2546 MWt. This Design Change also modified the RWST, Hi Steam Flow, SI Pressurizer Pressure Low, Tave and Delta T setpoints.
Modification was also performed to the Steam Dump, Rod Speed, Pressurizer Level, Turbine First Stage, and EHC System control and equipment protection functions.
A Simulator model modification was installed during the normal Design Change process for DCP-92-028, Radiation Monitor Ratemeter and Recorder Replacement.
This design change is still in progress; however, the portion which was completed replaced the Radiation Monitor Alarm Panel in its entirety.
The simulator's audio and video recording capability was enhanced by the addition of upgraded microphones and cameras.
e e
SIMULATOR DISCREPANCIES IDENTIFIED DURING NRC EXAMINATIONS.
The following simulator discrepancies were identified during NRC inspections from September, 1993 to September, 1996.
SMRNo.
9301281000 9411290805 9412281237 DESCRIPTION The simulator did not adequately model RHR mid-loop operation/ evolutions.
RHR model upgrade completed on 03-14-94 During Reactor Coolant System (RCS) cooldown,.RCS pressure suddenly and unexpectedly decreased.
Repair completed on 04-18-95 Simulator label plate for 2-VS-HF-4 incorrectly reads 2-VS-F-4.
Label replaced on 03-23-95
e SURRY UNIT 2 SIMULATOR CERTIFICATION 2nd FOUR YEAR REPORT
( 1992 - 1996)
'I -~-------=~* ---
SURRY UNIT 2 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 consist of the following sections:
- Simulator Fidelity & Upg~ade 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. *
~ -
e ATTACHMENT 1 SIMULATOR FIDELITY & UPGRADE REPORT PHYSICAL FIDELITY A review was conducted of the original and the first four-year submittal reports on the Surry Unit 2 Control Room and Simulator Panel Comparison. The review was performed to update the changes made during the prior four years and to validate the original differences noted. This comparison also identifies any differences between Unit 1 and Unit 2 Control Room Panels.
The review of the Control Room and Simulator Panel Comparison is not included with this report; however, it is available for examination.
- Panels specific to Unit 2 operation that remain non-simulated because of their relative minor training value are:
VICTOREEN RADIATION MONITORING INCORE FLUX DISTRIBUTION PANEL NUCLEAR INSTRUMENTATION PANEL CONTAINMENT HIGH RANGE RADIATION MONITORING PANEL EMERGENCY DIESEL GENERATOR #2 PANEL EMERGENCY DIESEL GENERATOR #3 PANEL (UNIT 2 SIDE)
TURBINE SUPERVISORY PANEL REACTOR COOLANT PUMP VIBRATION PANEL SECONDARY CHEMISTRY MONITORING PANEL VERTICAL BOARD #1 VERTICAL BOARD #2 POST ACCIDENT MONITORING PANEL
- BENCHBOARD #1 BENCHBOARD #2 PLANT COMPUTER P-250 OPERATOR STATION RADIATION MONITORING PANELS ENVIRONMENTAL REVIEW Environmental differences between the simulator and the Unit 1 Control Room are discussed within the Surry Unit 1 Simulator Certification Four Year Report. -