ML18153A628

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Simulator Certification Second Four Year Rept (1992-1996).
ML18153A628
Person / Time
Site: Surry  Dominion icon.png
Issue date: 11/12/1996
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18153A627 List:
References
NUDOCS 9611200096
Download: ML18153A628 (16)
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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 (Attachment 1)
  • 1997 - 2000 Simulator Test Schedule (Attachment 2)
  • Simulator Fidelity & Upgrade Report (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 INSTRUMENT AIR LEAK MCA02 CONTAINMENT INSTRUMENT AIR COMPRESSOR IA-C-4A,B TRIP MCA04 CONTAINMENT INSTRUMENT AIR HEADER LEAK MCA08 INSTRUMENT AIR COMPRESSOR OVERLOAD TRIP MCCOl LOSS OF CC WATER TO SW THROUGH CC HX'S MCC03 OVERLOAD TRIP OF COMPONENT COOLING WATER PUMP MCC04 LOSS OF COMPONENT COOLING TO NON-REGENERATIVE HEAT EXCHANGER MCC05 THERMAL BARRIER LEAK TO CC SYSTEM MCHOl ISOLABLE LETDOWN LINE LEAK IN CONTAINMENT MCH02 ISOLABLE LETDOWN LINE OUTSIDE CONTAINMENT

MCH03 CHARGING LINE LEAK DOWNSTREAM FCV-1122 OUTSIDE CONTAINMENT MCH05 LOSS OF CHARGING PUMP MCH06 NON-REGENERATIVE HEAT EXCHANGER TEMPERATURE CONTROLLER TC-1144B FAILS MCHll RCP SEAL WATER INJECTION PRESSURE TRANSMITTER FAILURE MCH12 RCP SEAL WATER RETURN HEADER TEMPERATURE TRANSMITTER FAILURE MCH13 TUBE RUPTURE IN THE NON-REGENERATIVE HEAT EXCHANGER MCH17 SEAL WATER RETURN FILTER CLOGS MCH19 VCT LEVEL CONTROLLER FAILURE MCH20 -FUEL MELT MCH21 VCT LEVEL TRANSMITTER FAILURE MCH22 VOLUME CONTROL TANK PRESSURE TRANSMITTER FAILURE MCH23 VOLUME CONTROL TANK TEMPERATURE TRANSMITTER FAILURE MCH24 BORIC ACID FLOW CONTROLLER 1113 FAILURE MCH25 PRIMARY WATER FLOW CONTROLLER 1114 FAILURE MCH28 FAILURE OF CHARGING FLOW CONTROLLER MCH29 FAILURE OF CHARGING FLOW TRANSMITTER MCH31 REGENERATIVE HEAT EXCHANGER OUTLET TEMPERATURE TRANSMITTER CH-TE-1123 MCH35 LOW PRESSURE LETDOWN FLOW TRANSMITTER FAILURE MCH36 LETDOWN PRESSURE CONTROLLER (PC-1145) FAILURE MCH37 LOW PRESSURE LETDOWN LINE PRESSURE TRANSMITTER PT-1145 FAILURE MCH38 REGENERATIVE HEAT EXCHANGER LETDOWN TEMPERATURE TRANSMITTER FAILURE MCH39 LETDOWN LINE RELIEF LINE TEMPERATURE TRANSMITTER FAILURE MCH40 LOW PRESSURE LETDOWN LINE TEMPERATURE TRANSMITTER FAILURE MCH41 NON-REGENERATIVE HEAT EXCHANGER OUTLET TEMPERATURE TRANSMITTER FAILURE MCNOl LOSS OF CONDENSATE PUMP, OVER CURRENT MCN02 AIR LEAK INTO MAIN CONDENSER CN-SC-lA & -lB BOOT MCN03 HOTWELL LEVEL CONTROLLER FAILURE LC-CN-102 MCNOS CONDENSATE LINE LEAK BETWEEN CN 114 AND FCV-CN-107 MCN08 LOSS OF AIR EJECTOR LOOP SEAL MELOl LOSS OF ALL OFFSITE POWER MEL02 MAIN GENERATOR TRIP

e November 1997 - October 1998 Integrated Tests

  • Unit start up operations (Hot Shutdown to Full Power).

Malfunction Tests MEL07 LOSS OF 4160V STATION BUS MEL08 LOSS OF SCREENWELL TRANSFORMER MEL09 LOSS OF EMERGENCY DIESEL GENERATOR MEL12 LOSS OF 480V EMERGENCY SWITCHGEAR MEL13 LOSS OF 480V EMERGENCY MOTOR CONTROL CENTER MEL14 LOSS OF SEMI-VITAL BUS MEL17 LOSS OF 125V D.C. BUS MEL18 LOSS OF 480V STATION SWITCHGEAR MEL19 LOSS OF 480V MOTOR CONTROL CENTER MEL20 LOSS OF AC VITAL BUS MEL21 LOSS OF 4160V EMERGENCY BUS MFWOl MAIN FEEDWATER PUMP RECIRC VALVE FAILS OPEN MFW02 MAIN FEEDWATER REGULATING VALVE FAILS CLOSED MFW04 MAIN FEED PUMP LOW LUBE OIL PRESSURE MFWOS MAIN FEEDWATER BREAK BETWEEN FLOW TRANSMITTER AND DISCHARGE CHECK VALVE MFW07 AUX FEED PUMPS FW-P-3A/B TRIP : OVERCURRENT MFW08 AUX FEED PUMP TURBINE WON'T STOP MFWlO AUXILIARY FEED PUMP CHECK VALVE OPEN MFW12 MAIN FEED PUMP SUCTION LINE BREAK MFW13 STEAM GENERATOR LEVEL TRANSMITTER FAILURE (0-100%)

MFW14 AUXILIARY FEEDWATER BREAK DOWNSTREAM OF FLOW TRANSMITTER AND CHECK VALVE MFW15 MAIN FEEDWATER BREAK DOWNSTREAM OF CHECK VALVE OUTSIDE CONTAINMENT MFW16 MAIN FEEDWATER BREAK IN CONTAINMENT MFW17 DEGRADATION OF MAIN FEED PUMP MFW18 STEAM GEN MAIN FEED FLOW TRANSMITTER FAILURE MFW19 STEAM GEN MAIN FEED FLOW CONTROLLER FAILURE MFW20 STEAM GEN WIDE RANGE LEVEL TRANSMITTER FAILURE MFW21 STEAM GEN AUX FEED FLOW TRANSMITTER FAILURE MFW22 STEAM GEN MAIN FEED HEADER PRESSURE TRANSMITTER FAILURE MFW23 TOTAL LOSS OF FEEDWATER

e MMS08 STEAM GEN STEAM FLOW TRANSMITIER FAILURE

.MMS09 MAIN STEAM TRIP VALVE FAILS SHUT MMSlO FAILURE OF AUTO STEAM DUMP AS IS MMSll MAIN STEAM HEADER PRESSURE TRANSMITTER FAILURE MMS13 STEAM GEN PRESSURE TRANSMITIER FAILURE MMS14 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 SG PORV CONTROLLER FAILURE MNIOl SOURCE RANGE CHANNEL FAILURE MNI02 SOURCE RANGE DETECTOR FAILURE (DISCRIMINATOR ERROR)

MNI03 INTERMEDIATE RANGE CHANNEL UNDERCOMPENSATION MNI04 INTERMEDIATE RANGE CHANNEL OVERCOMPENSATION MNI05 INTERMEDIATE RANGE CHANNEL FAILURE MNI06 FAILURE OF IR TO ALLOW SR BLOCK MNI07 LOSS OF INSTRUMENT POWERTO POWER RANGE CHANNEL MNI08 POWER RANGE CHANNEL UPPER DETECTOR FAILURE MNI09 POWER RANGE CHANNEL LOWER DETECTOR FAILURE MNilO POWER RANGE CHANNEL FAILS MRCOl REACTOR COOLANT SYSTEM COLD LEG PIPE RUPTURE MRC02 REACTOR COOLANT SYSTEM HOT LEG PIPE RUPTURE MRC03 REACTOR COOLANT SYSTEM SUCTION LEG PIPE RUPTURE MRC04 REACTOR COOLANT SYSTEM NONISOLABLE LEAK MRC05 RCP OVERCURRENT TRIP MRC07 FAILURE OF NARROW RANGE T-HOT INSTRUMENT I RTD MRC08 TAYLOR MATH UNIT FAILURE HI/LO MRCll FAILURE OF NARROW RANGE T-COLD INSTRUMENT I RTD MRC14 FAILURE OF RCP SEAL #3 MRC15 PRZR PRESSURE CONTROLLERS FAILURE MRC16 PRZR REL/SFTY VV LINE TEMPERATURE TRANSMITIER FAILURE MRC17 PRESSURIZER LEVEL CONTROL FAILURE MRC20 BOTH PRZR SPRAY VALVES FAIL SHUT MRC21 PRESSURIZER SAFETY VALVE FAILS OPEN MRC22 PRZR SPRAY VALVE FAILS OPEN MRC24 STEAM GENERATOR TUBE RUPTURE MRC25 PRESSURIZER HEATERS GROUP FAIL ON

MRC26

.MRC30 RCP SHAFT SHEARS LOSS OF SEAL INJECTION FLOW TO RCP MRC31 REACTOR COOLANT LOOP FLOW TRANSMITTER FAILURE MRC34 RCS WIDE AND NARROW RANGE PRESSURE TRANSMITfER FAILURE MRC37 PRESSURIZER RELIEF TANK PRESSURE TRANSMITTER FAILURE MRC38 LOSS OF COMPONENT COOLING WATER TO RCP MRC40 PRESSURIZER PORV LEAKAGE MRC42 PRESSURIZER TEMPERATURE TRANSMITTER FAILURE MRC45 PRESSURIZER RELIEF TANK TEMPERATURE TRANSMITTER FAILURE MRC46 REACTOR VESSEL LEAKOFF TEMPERATURE TRANSMITTER FAILURE MRC48 PRESSURIZER PRESSURE TRANSMITTER FAILURE MRC49 PRESSURIZER LEVEL TRANSMITTER FAILURE MRC50 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 CONTINUOUS ROD WITHDRAWAL, MANUAL OR AUTO MRD02 CONTINUOUS ROD INSERTION MANUAL OR AUTO MRD03 LOGIC FAILURE CAUSING TWO BANKS TO MOVE AT THE SAME TIME MRD04 AUTO AND MANUAL ROD CONTROL INOPERABLE MRD05 CONTROL BANKS IN SPEED FAIL TO 72 SPM MRD06 CONTROL BANKS IN SPEED FAIL TO 8 SPM MRD07 CONTROL BANKS OUT SPEED FAIL TO 72 SPM MRD08 CONTROL BANKS OUT SPEED FAIL TO 8 SPM MRD09 CONTROL BANK MOVES OUT WHEN IN DEMANDED IN AUTO MRDlO CONTROL BANK MOVES IN WHEN OUT DEMANDED IN AUTO MRD12 DROPPED CONTROL ROD MRD13 EJECTED CONTROL ROD MRD15 REACTOR TRIP BREAKERS OPEN DUE TO UV COIL FAILURE MRD16 INDIVIDUAL ROD POSIDON INDICATION FAIL MRD18 FAIL OF AUTO TRIP TO SCRAM RX MRD19 FAILURE OF ALL ROD STOPS TO BLOCK ROD MOVEMENT MRD20 STUCK ROD

MRD21 FAILURE OF REACTOR TRIP BUTTON

.MRHOl RESIDUAL HEAT REMOVAL SYSTEM LEAK MRH02 LOSS OF RESIDUAL HEAT REMOVAL PUMP MRH04 HCV-1758 CONTROLLER OUTPUT FAILURE MRH05 RHR FLOW CONTROLLER FC-1605 FAILS MRH06 RELIEF VALVE FAILS OPEN ON RESIDUAL HEAT REMOVAL SYSTEM MRMOl AREA RADIATION MONITOR FAILS MRM02 PROCESS RADIATION MONITOR FAILURE MRS06 LOSS OF OUTSIDE RECIRC SPRAY PUMP MRS07 LOSS OF INSIDE RECIRC SPRAY PUMP MRS08 LOSSOFCONTAINMENTSPRAYPUMP MRSll GRADUAL INCREASE IN CONTAINMENT PRESSURE MSI03 SAFETY INJECTION HOT LEG FLOW TRANSMITTER FAILURE MSI04 SAFETY INJECTION TOTAL FLOW TRANSMITTER FAILURE MSI05 LHSI PUMP FLOW TRANSMITTER FAILURE MSI06 SAFETY INJECTION COLD LEG FLOW TRANSMITTER FAILURE MSI07 SAFETY INJECTION ACCUMULATOR TRANSMITTER FAILURE MSI08 FAILURE OF SAFETY INJECTION RESET TIMER MSI10 LOW HEAD SAFETY INJECTION PUMP IMPELLER DEGRADATION MTUOl TURBINE TRIP DUE TO SOLENOID FAILURE MTU04 FAILURE OF MANUAL TURBINE TRIP MTU13 FAILURE OF AUTOMATIC TURBINE RUNBACK MWDOl DROPPED SPENT FUEL ASSEMBLY IN THE SPENT FUEL PIT MWD03 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)

__J

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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 SPARC 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. DESCRIPTION 9301281000 The simulator did not adequately model RHR mid-loop operation/evolutions.

RHR model upgrade completed on 03-14-94 9411290805 During Reactor Coolant System (RCS) cooldown, .RCS pressure suddenly and unexpectedly decreased.

Repair completed on 04-18-95 9412281237 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

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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. -
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