ML20116K077

Submits Simulator Facility Certification Four Yr Rept for Units 1 & 2

ML20116K077
Person / Time
Site:	North Anna
Issue date:	08/09/1996
From:	Saunders R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC (Affiliation Not Assigned)
References
RTR-REGGD-01.149, RTR-REGGD-1.149 96-367, NUDOCS 9608140220
Download: ML20116K077 (19)

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Vinoix1A Er.EcTRIC AND PowzR COMPANY Ricnxown, VIRGINIA 20061 August 9,19%

l Gentlemen: Director, Office Nuclear Reactor Regulation Serial No.96-367 U.S. Nuclear Regulatory Commission NAPS /ETS Washington, D.C. 20555-0001 Docket Nos.

50-338 50-339 License Nos.

NPF-4 NPF-7 l

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VIRGINIA ELECTRIC AND POWER COMPANY l

NORTH ANNA POWER STATION UNITS 1 AND 2 BE21 SED _IE1TJtgiLEBEQUENCY OFTHE POST SIMULATOR CERTIFICATION FOUR-YEAR REPORTS l

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Pursuant to 10 CFR 55.45.(b)(5)(iii), we are submitting the Simulator Facility Certification Four Year Report for North Anna Units 1 and 2. The intent of these reports is to document our continuing compliance with ANSI /ANS-3.5-1985, as modified or endorsed by Regulatory Guide 1.149, dated April 1987. The reports are included as attachments to this letter.

If you have any questions, or require additional information please' contact Dr. Arthur Friedman, Manager Nuclear Training at (804) 273-2701.

Very truly yours, OR R. F. Saunders Vice President - Nuclear Operations Attachments i

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PDR ADOCK 05000338

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Mr. T. A. Peebles Chief, Division of Reactor Safety - Operations Branch U.S. Nuclear Regt:!atory Commission, Region ll 101 Marietta Street, N.W,. Suite 2900 Atlanta, Georgia 30323 (4.18!' Nucleef Regulatory Commesson Document Control Desk Washington, D.C. 20555-0001 Mr. R. D. McWhorter NRC Senior Resident inspector North Anna Power Station

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NORTH ANNA UNIT 1 1

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SIMULATOR CERTIFICATION i

I 2nd FOUR YEAR REPORT

( 1E32 - 1996 )

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j NORTH ANNA UNIT 1 SIMULATOR CERTIFICATION SECOND FOUR YEAR REPORT I

This North Anna Simulator Certification Four Year Report (1992 - 1996 ) consist of the following sections:

Previous Four Year Simulator Test Results Summary (Attachment 1) l 1997 - 2000 Simulator Test Schedule (Attachment 2)

Simulator Fidelity & Upgrade Report (Attachment 3) l Simulator Discrepancies identified During NRC Examinations (Attachment 4) l l

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2 ATTACHMENT 1 PREVIOUS FOUR YEAR SIMULATOR TEST RESULTS

SUMMARY

Since August 1992, many modifications were made to the North Anna simulator.

Testing, which verified simulator fidelity acc.gebie for training and certification, has been completed. Discrepancies uncovered during the previous four years are scheduled to be resolved in a timely manner. The testing schedule in the North Anna Unit 1 Simulator Certification 1992 four year report was satisfactorily completed, with no test failures.

I The Real Time Test was conducted annually during the four year period. During 1994, 1995, and 1996 the test identified several quarter time peaks that exceeded 250 milliseconds.

The duration of the peaks were less than one second in duration.

Evaluation of the integrated response of the simulation showed that there were no discernible effects to the repeatability or functionality of the simulator.

Various modifications have been carried out to resolve this matter.

The following malfunctions wele modified to meet changing training requirements due to the installation of DCP 89-40-1, in 1995.

MRC15 MSS UNIT FAILURE Hl/ LOW The Median Signal Selector unit failure malfunction was conducted initially on December 1,1992 and again on April 21,1995. the test was conducted at normal steady state full power conditions. The simulated microprocessor was tested in the failed high and failed low directions. Data was collected over the 30 second ramp time to demonstrate the degradation feature of the malfunction. The malfunction was degraded to its maximum severity. Various simulator model parameters points were monitored to verify the correct malfunction response. The duration of the test was 262 seconds. Data was collected in the form of computer printoes. There were no discrepancies noted during the test.

MRC17 RTD Fall HI-LO HOT LEG The Protection RTD Failure in Hot Leg malfunction was conducted initially on December 1,1992 and again on April 21,1995 the test was conducted at normal steady state full power conditions. The Channel I transmitter was. tested in the failed high and fai;ed low directions. Data was collected over the 30 second ramp time to demonstrate the degradation feature of the malfunction. The malfuncbon was degraded to its maximum severity. Various simulator model parameters points were monitored to verify the correct malfunction response. The duration of the test was 154 seconds. Data was collected in the form of computer printouts. There were no discrepancies noted during the test.

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MRC18 RTD Fall Hi-LO COLD LEG The Protection RTD Failure in Cold Leg malfunction was conducted initially on December 1,1992 and again on April 21,1995 the test was conducted at normal steady state full power conditions. The Channel I transmitter was tested in the failed high and failed low directions. Data was collected over the 30 second ramp time to demonstrate the degradaten feature of the malfunchon. The malfuncbon was degraded to its maximum severity. Various simulator model parameters points were monitored to verify the correct malfunction response. The duration of the test was 186 seconds. Data was collected in the form of computer printouts. There were no discrepan::ies noted during the test.

Based upon the testing conducted, and their results, the North Anna simulator is acceptable for licensed operator training and retraining.

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4 ATTACHMENT 2 1997 - 2000 SIMULATOR TEST SCHEDULE The next four year simulator test schedule follows.

The tests are divided to ensure that 25% of the tests 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 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.

The Computer Real Time Test will be conducted annually.

August 1996 - July 1997 Intearated Tests Unit Startup from Cold Shutdown Condition (Mode 5) < 200*F with a solid pressurizer to Cold Shutdown Condition (Mode 5) at < 200*F.

Unit Startup from Cold Shutdown Condition (Mode 5) to Hot Shutdown Condition (Mode 4) less than or equal to 350*F.

Malfunction Tests MCA01 FAILURE OF CONTAINMENT INSTRUMENT AIR COMPRESSOR MCA02 CONTAINMENT INSTRUMENT AIR LEAK MCA04 INSTRUMENT AIR LEAK MCC02 FAILURE OF COMPONENT COOLING PUMP TO START MCC03 COMPONENT COOLING FLOW TRANSMITTER FAILURE MCC04 COMPONENT COOLING PRESSURE TRANSMITTER FAILURE MCC05 RCP THERMAL BARRIER LEAK MCC06 COMPONENT COOLING PUMP SHEARED SHAFT MCH01 ISOLABLE LETDOWN LINE LEAK IN CONTAINMENT MCH02 ISOLABLE LETDOWN LINE LEAK OUTSIDE CONTAINMENT MCH03 ISOLABLE CHARGING LINE LEAK OUTSIDE CONTAINMENT MCH04 LETDOWN PRESSURE TRANSMITTER FAILURE

5 MCH05 REACTOR MAKEUP CONTROL BORATES IN THE AUTO MODE MCH06 LOSS OF COMPONENT COOLING TO NRHX MCH07 FAILURE OF CHARGING FLOW CONTROLLER MCH08 FAILURE OF CHARGING FLOW TRANSMITTER MCH09 REACTOR MAKEUP DILUTION IN AUTO MODE MCH11 BORIC ACID LINE TO THE BLENDER PLUGGED MCH12 VCT LEVEL TRANSMITTER FAILURE MCH13 TUBE RUPTURE IN THE NON-REGENERATIVE HEAT EXCHANGER MCH15 LOSS OF REACTOR MAKEUP CONTROL MCH16 LOSS OF CHARGING PUMP MCH18 LETDOWN PRESSURE CONTROL VALVE FAILS OPEN MCH21 CHARGING PUMP CHECK VALVE STICKS OPEN MCN01 LOSS OF CONDENSATE MAKEUP MCN07 HIGH LEVEL DIVERT VALVE LCV-CN-107 FAILS OPEN MCN14 CONDENSATE PUMP DISCHARGE CHECK VALVE STICKS OPEN MCN16 CONDENSER AIR IN LEAKAGE MCV01 GRADUAL INCREASE IN CONTAINMENT PRESSURE MELO1 LOSS OF ALL OFF SITE POWER MELO3 LOSS OF 4160V EMERGENCY BUS MELO4 LOSS OF 4160V STATION BUS MELOS LOSS OF 125V D.C. BUS MELO6 LOSS OF 480V EMERGENCY BUS MELO7 LOSS OF 480V STATION BUS MELO8 LOSS OF EMERGENCY DIESEL GENERATOR MEL11 MAIN GENERATOR TRIP MEL12 LOSS OF SEMI-VITAL BUS MEL13 LOSS OF AC VITAL BUS INVERTER MEL15 LOSS OF 480V EMERGENCY MCC MEL16 LOSS OF 480V STATION SERVICE MCC MEL17 LOSS OF PRIMARY PROCESS RACK POWER SUPPLY August 1997 - July 1998 Intearated Tests Unit Startup from Hot Shutdown Condition (Mode 4) to Hot Standby Condition (Mode 3) at 547'F.

Unit Startup from Hot Standby Condition (Mode 3) to Startup Condition (Mode 2)

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.vith Reactor critical at less than or equal to 5% power.

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6 Malfunction Tests MFWO1 STEAM GENERATOR LEVEL TRANSMITTER FAILURE (0-100%)

MFWO4 MAIN FEED PUMP LOW LUBE OIL PRESSURE MFWO5 MAIN FEEDWATER REGULATING VALVE FAILS CLOSED MFWO6 TOTAL LOSS OF FEEDWATER MFWO8 LOSS OF LEVEL ERROR SIGNAL TO S/G LEVEL CONTROL MFWO9 OVERSPEED TRIP OF AUXILIARY S/G FEED PUMP MFW10 AUXILIARY FEED PUMP CHECK VALVE OPEN MFW11 AUXILIARY FEED PUMP IMPELLER DEGRADATION MFW12 MAIN FEED FLOW TRANSMITTER FAILURE MFW13 MAIN FEEDWATER BREAK UPSTREAM OF FLOW TRANSMITTER MFW14 AUX FEEDWATER BREAK DOWNSTREAM BETWEEN FLOW TRANS

& 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 MAIN FEEDWATER REGULATING VALVE FAILS OPEN MFW19 MAIN FEEDWATER BREAK BETWEEN FLOW ELEMENT AND CHECK VALVE MFW21 MAIN FEEDWATER PUMP SUCTION PIPE BREAK MFW23 AUXlLIARY FEEDWATER PUMP TRIPS ON OVERCURRENT MGWO1 ACCIDENTAL RELEASE OF RADIOACTIVE GAS MMS 01 STEAM FLOW TRANSMITTER FAILURE MMS 02 TURBINE FIRST STAGE PRESSURE TRANSMITTER FAILURE MMS 08 RUPTURE OF MAIN STEAM LINE IN CONTAINMENT BEFORE THE FLOW TRANSMITTER MMSO9 RUPTURE OF MAIN STEAM LINE AFTER THE NON-RETURN VALVE MMS 10 RUPTURE OF MAIN STEAM LINE BEFORE THE TRIP VALVE MMS 11 FAILURE OF STEAM DUMP CONTROL AS IS MMS 12 ATMOSPHERIC STEAM RELIEF VALVE STUCK OPEN MMS 13 MAIN STEAM TRIP VALVE FAILS AS IS MMS 14 MAIN STEAM SAFETY VALVE STUCK OPEN MMS 15 STEAM DUMP VALVE STUCK OPEN MMS 16 FAILURE OF STEAM HEADER PRESSURE CONTROL MMS 17 LOSS OF STEAM GENERATOR PRESSURE CHANNEL MN101 POWER RANGE UPPER DETECTOR FAILURE MN102 POWER RANGE LOWER DETECTOR FAILURE MN103 BLOWN POWER RANGE CONTROL FUSE I

MNIO4 BLOWN POWER RANGE INSTRUMENT FUSE MN106 SOURCE RANGE DETECTOR FAILURE (DISCRIMINATOR ERROR)

MN108 INTERMEDIATE RANGE IMPROPERLY COMPENSATED MN109 INTERMEDIATE RANGE DETECTOR FAILURE MN110 SOURCE RANGE CHANNEL FAILURE MN113 POWER RANGE CHANNEL FAILURE

August 1998 - July 1999 Intearated Tests Unit Power Operation, Mode 2 to Mode 1(to include heat balance test).

Unit Power Operation, Mode 1 to Mode 2.

Computer Real Time Test.

Malfunction Tests MOS01 LOSS OF QUENCH SPRAY PUMP MQS03 FAILURE OF CONTAINMENT HIGH PRESSURE TO INITIATE SPRAY MQS06 SPURIOUS CONTMGiENT SPRAY ACTUATION MQS07 DEGRADATION OF iNSIDE RECIRC SPRAY PUMP MRC01 REACTOR COOLANT SYSTEM COLD LEG PlPE RUPTURE MRCO2 REACTOR COOLANT SYSTEM HOT LEG PIPE RUPTURE MRCO3 REACTOR COOLANT SYSTEM PUMP SUCTION LEG PIPE RUPTURE MRC04 REACTOR COOLANT SYSTEM NON-ISO!.ABLE LEAK MRC05 RCP OVERCURRENT TRIP MRC06 FAILURE OF REACTOR VESSEL LEVEL TRANSMITTER MRC07 PRESSURIZER PRESSURE TRANSMITTER FAILURE MRC08 PRESSURIZER LEVEL TRANSMITTER FAILURE MRC11 REACTOR COOLANT FLOW TRANSMITTER FAILURE MRC14 FAILURE OF RCP NO. 3 SEAL MRC15 MEDIAN SIGNAL SELECTOR (MSS) UNIT FAILURE Hl/ LOW MRC17 RTD Fall HI-LO HOT LEG MRC18 RTD Fall Hi-LO COLD LEG MRC19 PRESSURIZER RELIEF VALVE FAILS OPEN MRC20 PRESSURIZER SPRAY VALVE STUCK OPEN MRC21 PRESSURIZER SAFETY VALVE STUCK OPEN MRC22 PRESSURIZER HEATERS FAIL ON (H BUS)

MRC23 J BUS PRESSURIZER HEATERS FAIL ON MRC24 STEAM GENERATOR TUBE RUPTURE MRC25 BOTH PRESSURIZER SPRAY VALVES FAIL CLOSED MRC26 RCP SHEARED SHAFI MRC29 PRESSURIZER PRESSURE CONTROL FAILS MRC31 FUEL LEAK i

MRC32 PCV-456 SEAT LEAKAGE MRC33 PT-402 WIDE RANGE PRESSURE TRANSMITTER FAILURE MRC34 PT-403 WIDE RANGE PRESSURE TRANSMITTER FAILURE MRC35 PRT LEVEL TRANSMITTER FAILURE MRC36 PRT PRESSURE TRANSMITTER FAILURE MRC37 RCS VESSEL FLANGE LEAK TEMPERATURE DETECTOR FAILURE MRC38 LOSS OF COMPONENT COOLING WATER TO RCP

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MRC40 PZR SURGE LINE TEMPERATURE TRANSMITTER FAILURE MRC41 RCS SPRAY LINE TEMPERATURE TRANSMITTER FAILURE MRC42 PZR LIQUIDNAPOR TEMPERATURE TRANSMITTER FAILURE MRC43 PRESSURIZER PORV TEMPERATURE TRANSMITTER FAILURE MRC44 PZR SAFETY LINE TEMPERATURE TRANSMITTER FAILURE MRC45 PRT LIQUID TEMPERATURE TRANSMITTER FAILURE 4

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Unit Shutdown from Startup Condition with Power less than or equal to 5% (Mode i

2) to Hot Standby Condition (Mode 3) at 547'F.

i Unit Shutdown from Hot standby Condition (Mode 3) to Hot Shutdown Condition (Mode 4) at less than 350* F.

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Unit Shutdown from Hot Shutdown Condition (Mode 4) to Cold Shutdown Condition j

(Mode 5) at less than or equal to 200*F.

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Malfunction Tests f

MRC46 PRESSURIZER SPRAY CONTROLLER FAILS i

MRD01 ROD POSITION INDICATOR FAILURE MRD06 UNCONTROLLED CONTINUOUS ROD WITHDRAWAL IN AUTO AT i

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MRD07 UNCONTROLLED CONTINUOUS ROD INSERTION (AUTO) AT MAXIMUM SPEED MRD08 CONTROL RODS MOVE AT MAXIMUM SPEED

.1 MRD09 CONTROL RODS MOVE AT MINIMUM SPEED l

MRD10 REVERSE DIRECTION IN AUTO ROD CONTROL i

MRD11 RODS REVERSED DIRECTION IN MANUAL i

MRD13 ROD CONTROL FAILURE CAUSING B & D BANKS TO MOVE j

TOGETHER MRD14 RODS Fall TO MOVE ON DEMAND IN AUTO MRD15 RODS Fall TO MOVE ON DEMAND IN MANUAL OR BANK SELECT MRD16 DROPPED ROD MRD21 EJECTED CONTROL ROD MRD26 STUCK CONTROL ROD 1

MRD31 AUTO ROD CONTROL CONTROLS TEMPERATURE ABOVE SP MRD32 FAILURE OF AUTO TRIP TO TRIP REACTOR ANY TIME MRD33 FAILURE OF ALL ROD STOPS TO BLOCK ROD MOTION MRD34 REACTOR TRIP BREAKERS OPEN MRD36 LOSS OF NUCLEAR INSTRUMENT SIGNAL TO ROD CONTROL MRD38 FAILURE OF REACTOR TRIP ON MANUAL DEMAND

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1 MRH01 RESIDUAL HEAT REMOVAL SYSTEM LEAK I

MRH02 RESIDUAL HEAT REMOVAL FLOW TRANSMITTER FAILURE l

MRH03 LOSS OF COMPONENT COOLING TO RESIDUAL HEAT REMOVAL j

MRH05 LOSS OF RESIDUAL HEAT REMOVAL PUMP MRH06 RELIEF VALVE STUCK OPEN ON RESIDUAL HEAT REMOVAL SYSTEM MRM01 AREA RADIATION MONITOR FAILURE MRM02 PROCESS RADIATION MONITOR FAILURE MRS01 LOSS OF OUTSIDE RECIRC SPRAY PUMP ON START MRS02 LOSS OF INSIDE RECIRC SPRAY PUMP ON START MRSO4 RECIRC SPRAY NOZZLES CLOG MRS05 TUBE LEAK IN RECIRC SPRAY HEAT EXCHANGER MSl03 LOW HEAD Si PUMP SUCTION SCREEN CLOGS MSl05 SPURIOUS SAFETY INJECTION MSl06 FAILURE OF SAFETY INJECTION TO RESET MSl07 FAILURE OF ONE SAFETY INJECTION TRAIN TO ACTUATE MSl08 FAILURE OF ANY SAFETY INJECTION SIGNAL TO CAUSE SAFETY INJECTION MSWO1 SERVICE WATER PUMP TRIP MTUO1 TURBINE TRIP DUE TO OVERSPEED MTUO2 FAILURE OF MANUAL TURBINE TRIP TO FUNCTION ON DEMAND MTUO3 FAILURE OF AUTO TURBINE TRIP TO FUNCTION ON DEMAND MTU12 FAILURE OF AUTO TURBINE RUNBACK MTU13 SPURIOUS TURBINE RUNBACK M7U14 REHEATER SAFETY VALVE STUCK OPEN

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10 ATTACHMENT 3 SIMULATOR FIDELITY & UPGRADE REPORT PHYSICAL FIDELITY Physical fidelity is annually 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 during 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 l

identified as requiring no action. Generic Control Room / Panel differences have been identified as necessary.

The simulator Physical Fidelity Reoort is not included with this report, however, it is available for examination.

CONTROL ROOM AND SIMULATOR PANEL COMPARISON UPDATE 1

A review was conducted of the original submittal report on the North Anna 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.

Panels that remain non-simulated because of their relative minor training value or their inoperable status in the reference plant are:

1 STATION AND DIESEL BATTERY MONITORING PANEL SEISMIC PANEL SPILLWAY SUPERVISORY PANEL ROBERT SHAW FIRE PROTECTION PANEL VIBRATION / LOOSE PARTS MONITORING PANEL NA 4

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11 CONTROL ROOM AND SIMULATOR ENVIRONMENTAL REVIEW UPDATE Environmental differences identified in the initial simulator certification report and subsequently updated by the initial four year 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 retraining.

- OTHER SIMULATOR UPGRADES INSTALLED The simulator interface hardware and software manufactured by Computrol, was replaced due to obsolescence and the inability to obtain adequate vender support for repairs. The new system is manufactured by VMIC and is classified as an intelligent 1/O control system. A point to point verification was performed to verify that all dada points were receiving correct data. Any discrepancies found were resolved prior to releasing the simulator for use in normal training activities.

The Residual Heat Removal System model was upgraded to improve mid-loop operation response.

Meteorological Panel recorders were replaced.

In 1994, completed the initial software conversion from Encore / Gold to UNIX Fortran and initial integration testing.

In 1995 the simulator computer hardware configuration was upgraded from a

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Gould 32/8780 to a SUN SPARC 10 workstation. The SUN workstation contains 256 MB of memory and four 90 MHz central processors. Since approximately 95% of the extant simulation software consisted of Fortran code, especially all process models, the simulator code was ported to the new computer and recompiled. Minor coding changes were made to resolve divide-by-zero, overflow, underflow, and other similar calculation errors, which were exposed during the testing phase. The resuit of these coding changes improved the quality of the code being used.

The remaining software which was in assembly language, consisting primarily of device handlers, was rewritten into either Fortran, C, or C++ as necessary. All handlers were extensively tested both stand-along and in conjunction with the full simulator software configuration to ensure response reliability.

No new models were installed during the software conversion process. Extensive simulator testing was conducted to ensure model integrity and that all simulator features responded the same as, or better, than before the simulator computer i

replacement.

12 Reactor core cycle upgrades 9,10, and 11 were installed upon completion of the respective station refueling cycle.

The simulator's audio and video reco-ding capability was enhanced by the addition of upgraded microphones and cameras.

Fast chart advance features were installed on all Hagan recorders in the simulator.

Implemented capability to reflect reactor coolant system vacuum fill operations.

Implemented Station Blackout Diesel via the Altemate AC diesel modification.

Completed an Instructor Consolo upgrade.

Completed a Steam Generator upgrade to reflect results of steam generator replacement project.

Modified malfunctions MRC-15, MRC-17, and MRC-18 due to the installation of DCP 89-40-1 (REACTOR COOLANT SYSTEM RTD BYPASS MANIFOLD REMOVAL).

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13 ATTACHMENT 4 SIMULATOR DISCREPANCIES IDENTIFIED DURING NRC EXAMINATIONS.

The following simulator discrepancies were identified during NRC inspections from October 1993 to February 1996. Simulator discrepancies identified during other simulator training activities are available upon request.

SMR No.

DESCRIPTION 9310130905 AFW flow from FW-P-2 is slightly below required amount with a single S/G steam supply. Completed on 10-25-93.

9310141615 Provide ability to perform 1 -OP-7.3, secSon 5.6, Sluice Accumulators. Completed on 04-25-94.-

9310141617 Addition of simulation capability for CH-292.

Comp;eted on 04-28-94.

l 9509221232 SI cold leg flow indication displays flow under LOCA conditions and no HHSI pumps running. Completed on 10-26-95.

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i NORTH ANNA UNIT 2 4

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SIMULATOR CERTIFICATION i

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2nd FOUR YEAR REPORT s

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( 1992 - 1996 )

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3 NORTH ANNA UNIT 2 l

SIMULATOR CERTIFICATION SECOND FOUR YEAR REPORT The North Anna 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 North Anna 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 North Anna Unit 1 Simulator meets the Unit 2 training needs.

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SIMULATOR FIDELITY & UPGRADE REPORT l

PHYSICAL FIDELITY A review was conducted of the original submittal report on the North Anna Unit 2 l

Control Room and Panel Comparison and Environment. The review was performed to update the changes made during the prior four years and validate the original differences noted. Any additional differences identified as a result of the Unit 1 and Unit 2 Control l

Room Panel Comparison will be implemented via the discrepancy reporting process.

I UNIT 2 EQUIPMENT PANEL (SIMULATOR; The Unit 2 Equipment Panel, located in the simulator coteal room, contains indications and controls for Unit 2 components of systems. This equipment is located in l

the main control room specifically on Unit 2 panels, and is simulated only to the extent to allow training to be conducted on systems that require actions to be taken at Unit 2 locations.

ENVIRONMENTAL REVIEW l

Environmental differences and differences between the simulator and the Unit 1 l

Control Room are discussed within the Control Room / Simulator Panel and Environment Comparison Report of the North Anna Unit 1 Simulator Certification Second Four Year Report.

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