ML20078Q527

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Simulator Four Yr Certification Rept 1991-94
ML20078Q527
Person / Time
Site: Beaver Valley
Issue date: 12/13/1994
From:
DUQUESNE LIGHT CO.
To:
Shared Package
ML20078Q526 List:
References
NUDOCS 9412220230
Download: ML20078Q527 (15)
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Text

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d on BEAVER VALLEY POWER STATION .

UNIT 1 SIMULATOR FOUR YEAR CERTIFICATION REPORT 1991 - 1994 This four year certification report satisfies the reporting requirements identified in 10 CFR 55.45(b)(5)(ii) and (b)(5)(vi).

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TABLE OF CONTENTS-TOPIC PAGE References and Requirements 1 Summary of Results, 1991 - 1994 2 SQT Corrected Test Deficiencies, 1991 - 1994 3 Tests and Schedule for 1995 - 1998 5 Test Schedule for 1995 - 1998 6

't ATTACHMENTS PAGE Letter, Simulator Facility Certification,

- NRC form 474, Update Information 13 4

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Beaver Valley Power Station Unit 1 Four Year Simulator Certification Report 1991 - 1994 References and Requirements

References:

1. Title 10, Code of Federal Regulations, Part 55, " Operator Licenses," Subpart E, Section 45.
2. U.S. Nuclear Regulatory Guide 1.149 " Nuclear Power Plant Simulation Facilities for use in Operator License Examinations."
3. ANSI 3.5,1985, " Nuclear Power Plant Simulators for use in Operator Training."

Reporting Requirements:

The requirements of this report as outlined in 10 CFR 55 are:

1. Identification of any uncorrected performance test failures and a schedule for corrections of such performance failures if any. Subpart E, Section 55.45(b)(5)(ii). (Refer to page 2.)
2. A description of performance testing completed for the simulation facility. Subpart E, Section 55.45(b)(5)(vi). (Refer to pages 2,3 and 4.)
3. A description of the performance tests, if different, to be conducted on the simulation facility during the subsequent four year period. Subpart E, Section 55.45(b)(5)(vi). (Refer to page 5.)
4. A schedule for the conduct of approximately 25 percent of the performance tests per year for the subsequent four years. Subpart E, Section 55.45(b)(5)(vi). (Refer to pages 6 through 12.)

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Beaver Valley Power Station Unit 1 Four Year Simulator Certification Report 1991 - 1994 Summary of Results 1991 - 1994 All commitments from the original certification report have been completed with the exception of the plant computer upgrade. The plant computer design change was accepted by Unit 1 in April 1994. The Unit 1 Simulator Certification Committee, consisting of personnel from Licensing, Training, Engineering and Operations, met in April 1994 to reevaluate this upgrade. The Committee determined that including the plant computer hardware would provide physical fidelity. Details of the evaluation are provided in the DLCo letter of November 3,1994. For your convenience, a copy is enclosed in Attachment 1.

The testing for the first four years following initial certification, as submitted in the original Simulator Certification Report, is complete. A total of 324 tests were performed and evaluated. The following tables summarize the test results:

Tests Completed 1991 1992 1993 1994 Simulator Real Time 1 1 1 1 Steady State, Drifl, Normal Ops. 20 20 20 20 Transient Test (Appendix B) 11 11 11 11 Malfunction Tests 49 49 49 49 Tctal 81 81 81 81 Action List 1991 1992 1993 1994 Trouble Reports Written (TR) 8 9 5 4 Trouble Reports Cleared (TR) 8 9 5 3 4 l

Change Request Written (CR) 2 2 1 1 l

Change Request Implemented (CR) 2 2 1 1 l Uncorrected Test Deficiencies: 0 0 0 1 Below is the uncorrected test deficiency for 1994.

Test # Deficiency TR/CR# Scheduled SQT-4.157 Incorrect RMS TR-506 12/95 Recorder Response l The corrected test deficiences for 1991 - 1994 are listed on pages 3 and 4. l l

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Beaver Valley Power Station Unit 1 Four Year Simulator Certification Report  ;

1991 - 1994 1

Simulator Qualification Test (SQT) 1 Corrected Test Deficiencies SQT Test- Test Description Trouble Report (TR) Date Completed Number . Change Request (CR) i

'199i SQT-2.4.2 - NIS Power Range Operations Surveillance Test (OST) TR-292 11/08/91 SQT-2.4.5 Plant Startup Mode 5 to 100% TR-359 11/12/91 l TR-366 05/12/92 TR-367 11/23/92 Boric Acid Pump OST TR-355 05/19/92 l SQT-2.4.8 SQT-2.4.9 EDG #1 OST TR-352 06/05/91- ]

SQT-2.4.10 EDG #2 OST TR-352 06/05/91 SQT-2.4.13 MSIV Closure Test OST CR-175 10/17/91 SQT-2.4.14 Aux Feedwater Discharge Valve Stroke Test CR-178 04/07/92 SQT-2.4.16 Turbine Aux Feedwater Pump OST TR-369 10/30/92 SQT-3.9 Maximum Steam Break in Containment TR-365 04/23/92 1992 SQT-2.1 Steady State Drift Test at 100% Power CR-196 01/29/93 SQT-2.4.5 Plant Startup Mode 5 to 100% TR-391 04/28/93 TR-392 05/18/92 TR-393 05/26/92 SQT-2.4.6 Accident Monitoring Inst. OST TR-429 11/15/93 SQT-2.4.12 Cold Shutdown Valve Exercise OST CR-195 02/12/93 l SQT-3.8 DBA LOCA With Loss of Offsite Power TR-445 06/16/93 SQT-4.86 Load Rejection TR-426 05/20/93  !

SQT-4.121 Steam Leak to Turbine Aux Feedwater J Pump TR-424 01/29/93 SQT-4.136 Pressurizer PORV Leakage TR-373 05/19/92 I SQT-4.156 Reactor Coolant Pump High Vibration TR-427 12/15/92  ;

1993 i SQT-2.4.6 Accident Monitoring In2. OST TR-429 11/15/93 SQT-2.4. l l Containment Isolation Valve OST CR-220 - 10/07/94 SQT-2.4.12 Cold Shutdown Valve Exercise OST CR-220 10/07/94 1 SQT-2.4.17 Reactor Startup After a Trip TR-488 12/16/93 )

SQT-4.50 Reactor Trip TR-478 11/12/93 SQT-4.93 Feedwater Leak Outside Containment TR-482 11/15/93 l SQT-4.133 CCT Suction Header Leak TR-483 11/30/93 I

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l Beaver Valley Power St tion Unit 1 Four Year Simulator Certification Report  ;

1991 - 1994 i Simulator Qualification Test (SQT)

Corrected Test Deficiencies I SQT Test Test Description Trouble Report (TR) Date Completed Number Change Request (CR) 1994 SQT-2.4.3 NIS Intermediate Range OST CR-22 10/11/94 SQT-2.4.5 Plant Startup Mode 5 to 100% TR-509 09/15/94 SQT-4.75 System Station Service Transformer Failure TR-505 05/23/94 SQT-4.78 Loss of120 Volt Bus TR-507 05/23/94 9

Beaver Valley Power Station Unit 1 Four Year Simulator Certification Report 1991 - 1994 Tests and Test Schedule for 1995 - 1998 Five Normal Operations Tests have been removed from the testing schedule. These tests are:

2.4.8 - Boric Acid Pump Test 2.4.9 - Emergency Diesel Generator #1 Test 2.4.10 - Emergency Diesel Generator #2 Test 2.4.15 - Motor Auxiliary Feedwater Pump Test 2.4.16 - Turbine Auxiliary Feedwater Pump Test Each test was evaluated, and only the N'ormal Operations Tests that provide enhancements to the simulator were retained. The five tests that were removed from the testing schedule were either redundant to other testing methods, or the critical parameters for the test were read outside the control room and relayed back to the control board operator.

Four Malfunction Tests from the original cenification report were also deleted. These .

tests are: I 4.65 - Hydrogen Supply Pressure Regulator Failure 4.86 - Load Rejection .

4.159 - Hot Leg Narrow Range RTD Sensor Failure I 4.161 - Cold Leg Narrow Range RTD Sensor Failure 1 Four tests were added to the 1995 - 1998 testing cycle. The changes were required by sim.ulator modif. cations resulting from plant design changes, or malfunction changes to support more effective training. These tests are:

4.201 - Median Tavg/ Delta T Signal Failure j 4.202 - Electrohydraulic Control System Leak l 4.203 - Hot Leg Narrow Range RTD Sensor Failure 4.204 - Cold Leg Narrow Range RTD Sensor Failure

Beaver Valley Power Station Unit 1 Simulator Certification Test Schedule 1995 - 1998 SQT TEST TEST DESCRIPTION YEAR TO BE TESTED NUMBER 1995 1996 1997 1998 SQT-1.0 Simulator Real Time Test X -X X X SQT-2.0 Steady State, Drift and Normal Operations Tests SQT-2.1 Steady State Drift Test at 100% Power X X X X SQT-2.2 Steady State Test at 75% Power X X X X SQT-2.3 Steady State Test at 30% Power X X X X SQT-2.4 Normal Operations SQT-2.4.1 Plant Shutdown 100% to Mode 5 X SQT-2.4.2 NIS Power Range OST X SQT-2.4.3 NIS Intermediate Range OST X SQT-2.4.4 NIS Source Range OST X SQT-2.4.5 Plant Startup Mode 5 to 100% X SQT-2.4.6 Accident Monitoring Inst. OST X SQT-2.4.7 RCS Inventory Balance OST X SQT-2.4.8 Deleted-Boric Acid Pump OST SQT-2.4.9 Deleted-EDG #1 OST SQT-2.4.10 Deleted-EDG #2 OST SQT-2.4.11 Containment Isolation Valve OST X SQT-2.4.12 Cold Shutdown Valve Exercise OST X SQT-2.4.13 MSIV Closure Test OST X SQT-2.4.14 Aux Feedwater Discharge Valve Stroke Test X SQT-2.4.15 Deleted-Motor Aux Feedwater Pump OST  :

SQT-2.4.16 Deleted-Turbine Aux Feedwater Pump )

OST i SQT-2.4.17 Reactor Startup After a Trip X SQT-3.0 Transient Tests l

SQT-3.1 Manual Reactor Trip X X X X l SQT-3.2 Complete Loss of All Feedwater X X X X SQT-3.3 Simultaneous Closure of All MSIVs X X X X SQT-3.4 Simultaneous Trip of All RCPs X X X X i SQT-3.5 Trip of One Reactor Ceolant Pump X X X X SQT-3.6 Main Turbine Trip (Rois in Manual) X X X X l SQT-3.7 Maximum Power Ramp (100%-75%-

100 %) X X X X SQT-3.8 DBA LOCA With Loss of Offsite Power X X X X

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Beaver Valley Power Station Unit 1 Simulator Certification Test Schedule .

1995 - 1998 SQT TEST TEST DESCRIPTION YEAR TO BE TESTED NUMBER 1995 1996 1997 1998 SQT-3.8 DBA LOCA With Loss of Offsite Power X X X X SQT-3.9 Maximum Steam Break in Containment X X X X SQT-3.10 PZR Safety Valve Leak with No HHSI X X X X SQT-3. ll Main Turbine Trip (Rods in Auto) X X X X SQT-4.0 Malfunction Tests SQT-4.1 Containment Instrument Air Compressor Trip X SQT-4.2 Station Air Compressor Trip X SQT-4.3 Instrument Air Leak Outside Containment X SQT-4.4 Instrument Air Leak Inside Contaimnent X SQT-4.5 Station Air Header Isolation Valve failure X SQT-4.6 Auxiliary Steam Header Leak X SQT-4.7 Gaseous Waste Surge Tank Efiluent Leak X SQT-4.8 Gaseous Waste Decay Tank Efiluent Leak X SQT-4.9 River Water Pump Trip X SQT-4.10 Raw Water Pump Trip X SQT-4. l l Auxiliary River Water Pump Trip X SQT-4.12 Containment Ventilation Fan Failure X SQT-4.13 Radiation Monitor Failure X SQT-4.14 Non-Regenerative Hx Tube Leak X SQT-4.15 RCP Thermal Barrier Hx Tube Leak X  !

SQT-4.16 CCR Pump Trip X SQT-4.17 CCR Temperature Control Valve Failure X SQT-4.18 Non-Regenerat:;c Hx TCV Failure X SQT-4.19 CCR Pump Suction Header Leak X SQT-4.20 CCR Supply Line to RCP Leak X  ;

SQT-4.21 RCP Seal Water Hx Tube Leak X SQT-4.22 Condensate Pump Trip X SQT-4.23 Feedwater Heater Bypass Valve Failure X SQT-4.24 Condensate Pump Discharge Header Leak X SQT-4.25 Feedwater Heater Tube Leak (2nd Pt) X SQT-4.26 Fourth Point Heater LCV Failure X SQT-4.27 Fifth Point Heater LCV Oscillation X-SQT-4.28 Air Ejector Failure X SQT-4.29 Vacuum Breaker Leak X SQT-4.30 Condenser Tube Leak X SQT-4.31 Cooling Tower Pump Trip X  ;

SQT-4.32 Cooling Tower Pump Discharge Valve Failure X  !

SQT-4.33 Condensate Recirc Control Valve Failure X

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Beaver Valley Power Station Unit 1 Simulator Certification Test Schedule 1995 - 1998 SQT TEST TEST DESCRIPTION YEAR TO BE TESTED NUMBER 1995 1996 1997 1998 SQT-4.34 Hotwell LCV Failure X SQT 4.36 Priming Pump Vac Breaker Valve Failure X SQT-4.37 Vacuum Priming Pump Trip X SQT-4.38 Loss of Rod Dr'/e MG Set

. X SQT-4.39 Failure ofRods to Move X SQT-4.40 Improper Bank Overlap X SQT-4.41 Dropped Control Rod - X  :

SQT-4.42 Uncontrolled Rod Motion X SQT-4.43 Automatic Rod Control Speed Failure X i

SQT-4.44 TrefFailure X SQT-4.45 IRPI Loss of Voltage X SQT-4.46 Rod Position Step Counter Failure X SQT-4.47 Stuck Control Rod X ,

SQT-4.48 Reactor Trip Failure X ,

SQT-4.49 Rod Stop Failure X ,

SQT-4.50 Reactor Trip X SQT-4.51 Letdown Pressure Regulator Valve Failure X j SQT-4.52 Letdown Relief Valve Failure X  ;

SQT-4.53 Letdown Line Leak in Containment X l SQT-4.54 Plugged Seal Water Injection Filter X SQT-4.55 VCT Level Control Valve Failure X SQT-4.56 VCT Degas LCV Failure X l SQT-4.57 RCS Dilution Accident X SQT-4.58 RCS Boration Mcident X SQT-4.59 Boric Acid to Blender Flow Transmitter Failure X SQT-4.60 Blender Outlet Flow Transmitter Failure X SQT-4.61 Charging Header Leakage X SQT-4.62 RCS Fill Header Leakage X SQT-4.63 RCP Seal Header FCV Failure X SQT-4.64 Excess Letdown Divert Valve Failure X SQT-4.65 Deleted-Hydrogen Supply Pressure Regulator Failure SQT-4.66 Volume Control Tank Leak X SQT-4.67 Blender Outlet Flow Control Valve Failure X-SQT-4.68 Boric Acid Transfer Pump Trip X SQT-4.69 VCT Level Transmitter Failure X SQT-4.70 Letdown Isolation Valve Failure X SQT-4.71 Charging FCV Failure X SQT-4.72 Letdown High Temperature Divert Valve Failure X

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Beaver Valley Power Station Unit 1 Simulator Certification Test Schedule 1995 - 1998 SQT TEST TEST DESCRIPTION YEAR TO BE TESTED - l NUMBER 1995 1996 1997- 1998 SQT-4.73 Station Blackout X l SQT-4.74 ~ Unit Station Service Transformer Failure X SQT-4.75 System Station Service Transformer J Failure - X l SQT-4.76 Loss of 4160 Volt Bus X' l SQT-4.77 Loss of 480 Volt Bus - X .

SQT-4.78 Loss of120 Volt Bus X-  !

SQT-4.79 Loss ofInverter X l SQT-4.80 Loss ofDC Bus X l SQT-4.81 Grid Voltage Variation X  ;

SQT-4.82 Diesel Generator Trip X  ;

SQT-4.83 Diesel Generator Erratic Speed Control X '

SQT-4.84 Diesel Generator Erratic Voltage Regulation X-  !

SQT-4.85 Diesel Generator Output Breaker Trip X ,

Deleted-Load Rejection SQT-4.86 SQT-4.87 Main Generator Output Breaker Failure X SQT-4.88 Voltage Adjuster Setpoint Failure X SQT-4.89 Main Transformer Failure X SQT-4.90 Main Feedwater Pump Trip X SQT-4.91 Heater Drain Pump Trip X SQT-4.92 Feedwater Leak in Containment X SQT-4.93 Feedwater Leak Outside Containment X SQT-4.94 Feedwater Recirc Control Valve Failure X SQT-4.95 High Pressure Feedwater Tube Leak X j SQT-4.96 Feedwater Regulator Valve Failure X  !

SQT-4.97 Feedwater Regulator Bypass Valve Failure X j SQT-4.98 - Erratic Feedwater Flow Control X l SQT-4.99 - Aux Feedwater Pump Trip X J SQT-4.100 Aux Feedwater FCV Failure X i SQT-4.101 Aux Feedwater Pump Suction Leak - X j SQT-4.102 Feedwater Flow Transmitter Failure X l SQT-4.103 Steam Generator Programmed Level 1 Signal Failure X l SQT-4.104 Steam Generator Level Transmitter Failure X

. SQT-4.105 Steam Leak Upstream of MSIV X l SQT-4.106 Steam Leak Downstream of MSIV X l SQT-4.107 MSIV Drifts Shut X i SQT-4.108 NRV to First Point Heater Failure X SQT-4.109 NRV to Third Point Heater Failure X

Beaver Valley Power Station Unit 1 l

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Simulator Certification Test Schedule l 1995 - 1998  !

SQT TEST TEST DESCRIPTION YEAR TO BE TESTED NUMBER -l 1995 1996 1997 1998

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SQT-4.110 Steam Generator Safety Valve Fails to Rescat X SQT-4.ll ! Steam Dump Valve Fails to Operate X SQT-4.112 Steam Dump Valve Sticks X SQT-4.113 Erratic Tavg Control X SQT-4.114 Reference Temperature to Steam Dump .

Failure X SQT-4.115 Steam Pressure Signal to Steam Dump Failure X j SQT-4.116 Atmospheric Steam Dump Valve Failure X  !

SQT-4.117 Erratic Control of Atmospheric Steam  ;

Dump Valve X l SQT-4.118 Steam Flow Transmitter Failure X l SQT-4.119 Steam Pressure Transmitter Failure j (Control) X i SQT-4.120 Steam Pressure Transmitter Failure (Protection) X '

SQT-4.121 Steam Leak on Aux Feedwater Pump i Supply Line X l SQT-4.122 Source Range Channel Failure X SQT-4.123 Intermediate Range Channel Failure X l SQT-4.124 Power Range Channel Failure X ,

SQT-4.125 Intermediate Range Compensating i Voltage Failure X l SQT-4.126 Source Range High Voltage Cutoff Failure X l SQT-4.127 Source Range Blown Fuse .X l SQT-4.128 Intermediate Range Blown Fuse X l 4

SQT-4.129 Power Range Blown Fuse X l SQT-4.130 CCT Pump Trip X SQT-4.131 CCT TCV Failure X  ;

SQT-4.132 CCT Supply Line Leak X SQT-4.133 CCT Suction Header Leak X SQT-4.134 PZR Safety Valve Leakage X SQT-4.135 PZR Safety Valve Failure X SQT-4.136 PZR PORV Failure X -I SQT-4.137 PZR PORV Reseat Failure X SQT-4.138 PZR Steam Space Leak X SQT-4.139 PZR Level Transmitter Failure X SQT-4.140 PZR Reference Level Signal Failure X SQT-4.141 PZR Pressure Transmitter Failure X SQT-4.142 PZR Spray Valve Failure X

Braver Valley Power Station Unit 1 Simulator Certification Test Schedule l 1995 - 1998 ]

I SQT TEST TEST DESCRIPTION YEAR TO BE TESTED NUMBER' 1995 1996 1997 1998 SQT-4.143 PZR Heater Control Failure X SQT-4.144 PZR Spray Valve Controller Failure X SQT-4.145 PZR Master Pressure Controller Failure X SQT-4.146 PZR Level Control Failure X SQT-4.147 Surge Line Leak X SQT-4.148 Cold Leg Leak X SQT-4.149 Steam Generator Tube Leak X '

SQT-4.150 Reactor Vessel Head Flange Leak X SQT-4.151 RCP Seal #1 Failure X SQT-4.152 RCP Seal #2 Failure X SQT-4.153 RCP Seal #3 Failure X SQT-4.154 Reactor Coolant Pump Trip X SQT-4.155 Reactor Coolant Pump Locked Rotor X SQT-4.156 Reactor Coolant Pump High Vibration X SQT-4.157 Reactor Coolant High Activity X SQT-4.158 Fuel Handling Accident X SQT-4.159 Deleted-Hot Leg NR RTD Sensor Failure SQT-4.160 Hot Leg WR Temperature Sensor Failure X SQT-4.161 Deleted-Cold Leg NR RTD Sensor Failure SQT-4.162 Cold Leg WR Temperature Sensor Failure X SQT-4.163 Hot Leg Pressure Transmitter Failure X SQT-4.164 Loop Flow Transmitter Failure X I SQT-4.165 Incore Thermocouple Failure X SQT-4.166 RCS Boron Concentration X SQT-4.167 RHR Pump Trip X l SQT-4.168 RHR Relief Valve Leak X SQT-4.169 RHR Flow Transmitter Failure X l SQT-4.170 RHR Flow Control Valve Failure X j SQT-4.171 RHR Pump Shaft Failure X  ;

SQT-4.172 Refueling Water Storage Tank Leak X  !

SQT-4.173 Quench Spray Pump Failure X SQT-4.174 Recirc Spray Pump Failure X SQT-4.175 Recirc Spray Hx Tube Leak X SQT-4.176 HHSI Pump Failure X SQT-4.177 LHSI Pump Failure X l SQT-4.178 Containment In-Leakage X SQT-4.179 Spurious SI Actuation X SQT-4.180 Spurious CIA Actuation X SQT-4.181 Auto SI Actuation Failure X SQT-4.182 Safety Injection Accumulator Leak X SQT-4.183 SI Signal Failure to Selected Valves X I

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Beaver Valley Power Station Unit'l Simulator Certification Test Schedule 1995 - 1998 SQT TEST TEST DESCRIPTION YEAR TO BE TESTED NUMBER 1995 1996 1997 1998 SQT-4.l t , Safety Injection Line Leak X SQT-4.185 RWST Level Transmitter Failure X SQT-4.186 LHSI Pump Suction Valve Failure X SQT-4.187 Turbine Trip X SQT-4.188 Turbine Bearing High Vibration X SQT-4.189 Governor Valve Failure X SQT-4.190 Erratic Governor Valve Control X SQT-4.191 Turbine Trip Throttle Valve Failure X SQT-4.192 Erratic Throttle Valve Control X SQT-4.193 EHC Pump Trip X SQT-4.194 Turbine Bearing Lube Oil Pump Failure X SQT-4.195 EHC Speed Control Channel Failure X SQT-4.196 Turbine Runback Failure X SQT-4.197 Valve Position Limiter Failure X -

SQT-4.198 First Stage Pressure Signal Loss to EHC X SQT-4.199 MSR Steam Supply Valve Failure X ,

SQT-4.200 First Stage Steam Pressure Transmitter Failure X SQT-4.201 Median Tavg/ Delta T Signal Failure X SQT-4.202 Electrohydraulic Control System Leak X SQT-4.203 Hot Leg Narrow Range RTD Sensor Failure X SQT-4.204 Cold Leg Narrow Range RTD Sensor Failure X l

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l ATTACHMENT i 4

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s Beaver Valley Power Stat.on Shippingport. PA 15077-0004 (412) 393-5206 (412) 643-8069 FAX GEORGE S. THOMAS November 3, 1994 Owiswan wee President Nuclear Services Nuclear P>wer Dwiston U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 l

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Subject:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 ,

Simulation Facility Certification - NRC Form 474 l Update Information I

Reference:

NRC Form 474, dated December 18, 1990  !

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" Simulation Facility Certification" i

1 In the above reference, Duquesne Light Company identified l exceptions to ANSI /ANS 3.5-1985 and Regulatory Guide 1.149. One of these exceptions, the plant process computer, was identified as not being replicated as part of the simulator because the installed computer was scheduled for replacement and because its main functions were computerized trending and monitoring.

The submittal identified our intention to install a simulator process computer 18 months after the final acceptance of a new plant process computer. In the interim, the monitoring and trending functions of the process computer would continue to be provided by the training instructors, as they have been since 1985 when the simulator was first placed -in service. Training of operators on features of the process computer system would continue to be performed on the in-plant computer. In Section 1.2.3 of the above reference, the need to assess the training impact resulting from any future upgrade of the plant process computer was also identified.

The Unit i Simulator certification Committee, which is comprised of representatives from Operations, Training, Engineering and Licensing, met on April 12, 1994 at which time they determined that the simulator process computer should be upgraded to visually simulate and replicate the Unit 1 plant process computer consistent with ANSI /ANS 3.5-1985. This upgrade associated with physical fidelity will be completed by March 31, _1995. The committee also N concluded that ANSI /ANS 3.5-1985 does not require a working simulation of the plant process computer as part of the simulator.

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Banvar Valley Powar Station, Unit-No. 1

.Situlation Facility Cartification - NRC Form 474 ,

Upd, ate Information l Page 2-The Committee based its determination on the following:

1. The current plant process computer is used for periodic monitoring and trending of equipment and heat balance calculations.
2. The guidance of ANSI /ANS 3.5-1985 for physical fidelity will be achieved with the upgrade.
3. The simulator training program has had an excellent record  ;

over the last nine years and will continue using proven '

methods relative to the plant process computer.

4. The in-plant process computer will be utilized to train operators on the features of the computer system.
5. Information associated with annunciators, recorders, and computerized monitoring and trending of plant parameters driven by the plant process computer will continue to be provided in the simulator by the training instructors.
6. The UFSAR, Chapter 7, states that the plant process computer provides supplemental information for monitoring and is not required for safe operation of the unit.

This information is being provided as a status update and will be i reflected in the quadrennial racertification scheduled for December 1994. Any questions concerning this topic may be directed to Ernie Chatfield, General Manager, Nuclear Support Unit, at (412) 393-5710.

Sincerely, jb n_5 George S. Thomas Attachment cc: Mr. L. W. Rossbach, Sr. Resident Inspector Mr. T. T. Martin, NRC Region I Administrator Mr. G. E. Edison, Sr. Project Manager Mr. T. E. Murley, Director, ,

Office of Nuclear Reactor Regulation '

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