ML20198B902

From kanterella
Jump to navigation Jump to search
BVPS Unit 1 Simulator Four Yr Certification Rept for 1995-1998
ML20198B902
Person / Time
Site: Beaver Valley
Issue date: 12/31/1998
From:
DUQUESNE LIGHT CO.
To:
Shared Package
ML20198B827 List:
References
NUDOCS 9812210219
Download: ML20198B902 (15)


Text

.- ,:

BEAVER VALLEY POWER STATION UNIT 1 SIMULATOR FOUR YEAR CERTIFICATION REPORT 1995 - 1998 This four year certification report satisfies the reporting requirements identified in 10 CFR 55.45(b)(5)(ii) and (b)(5)(vi).

j!A**iB$$1oI%$g4[

l.-

e.

l 1 TABLE OF CONTENTS i

( )

l

TOPIC PAGE i

References and Requirements 1 Summary of Results,1995 - 1998 2 l SQT Outstanding Test Deficiencies 3 SQT Corrected Test Deficiencies,1995 - 1998 5 Test Schedule for 1998 - 2002 7 l

l l

l l

l I

f l

l' i

Beaver Valley Power Station Unit 1 Four Year Simulator Certification Report 1995 - 1998 l References and Requirements

References:

1. Title 10, Code of Federal Regulations, Part 55, " Operator Licenses," Subpart E, Section 45.

1 i 2. U.S. Nuclear Regulatory Guide 1.149 " Nuclear Power Plant Simulation Facilities for use in Operator l 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).

1

2. A description of performance testing completed for the simulation facility. Subpart ESection 55.45(b)(5)(vi).
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).
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).

I I

. - , . . - - .- _ ~ - . - =-- .- - -- -. - - - . - - - . - - . . . .

a 8 Beaver Valley Power Station Unit 1 Four Year Simulator Certification Report 1995 - 1998

. . Summary of Results 1995 - 1998 All commitments from the previous 4 year certification report have been completed. The plant computer design change which was accepted by Unit 1 in April 1994, has been installed in the Unit 1 Simulator and the computer

points have been added to the Simulator Certification Testing Program.

Four new tests which were added for the 1995 - 1998 4 year certification testing cycle were completed satisfactorily. De changes were required by simulator modifications resulting from plant design changes, or malfuncdon changes to support more effective training. These tests are:

.4.201 - Median Tavg/ Delta T Signal Failure 4.202 - Electrohydraulic Control System Leak 4.203 - Hot leg Narrow Range RTD Sensor Failure 4.204 - Cold leg Naimw Range RTD Sensor Failure ne testing for the second four years following initial certification, as submitted in the original Simulator

. Certification Report,is complete. A total of 271 tests were performed and evaluated. The following tables summarize the test results:

Tests Completed 1995 1996 1997 1998 Simulator Realtime 1 1 1 1 Steady State, Drift, Normal Ops. 5 6 6 7 Transient Test (Appendix B) 11 11 11 11 Malfunction Tests 49 50 51 49 Total 66 68 69 68 Action List 1995 1996 1997 1998 Trouble Reports Written (TR) 2 12 12 15 Trouble Reports Cleared (TR) 2 12 07 10 Uncorrected Test Deficiencies: 0 0 5 5 Pages 3 and 4 list the uncorrected test deficiencies for 1997 and 1998 and the schedule for completion of

. required corrective actions.

l .- \-

Beaver Valley Power Station Unit 1 l_ Four Year Simulator Cenification Report i- 1995 - 1998 l

Summary of Results 1995 - 1998 Simulator Deficiency Trouble Report Schedule Qualification (TR)#

Test #

(SQT) l l 1997 l

SQT-2.4.3 NIS Intermediate Range require calibration. TR - 719 06/99 SQT-2.4.6 Accident Monitoring OST received " poor TR - 711 12/99 f

quality" data on RVLIS Full & Upper range indication.

SQT-4.20 RCP High Temp alarm not received on loss TR - 802 04J 9 of CCR flow.

SQT-4.36 Minimal Main Condenser vacuum TR - 804 04S 9 degradation when Vacuum Break valve fails open.

SQT-4.133 Station Air Compressor High Temp alarms TR - 654 08B9 not received on loss of CCT.

d i

M f

l

. .' Y Beaver Valley Power Station Unit 1 l

Four Year Simulator Certification Report 1995 - 1998 Summary of Results 1995 - 1998 l i

Simulator Dendency Trouble Report Schedule I Qualification (TR)#

Test #

(SQT) 1998 l

' SQT-2.4.11 Low flow alarm on Rad Monitor not TR - 771 12/99 )

mceived when pump isolated and CNMT TR - 773 12/99 l pass did not incmase when condenser air  !

ejector discharge to containment was Opened.

j SQT-4.61 VCr level msponse questionable during TR - 766 04/00 charging headerleak accident.

SQT-4.78 Several In Plant Computer (IPC) indications TR - 728 12/99 incorrect for loss of 120 volt vital bus.

SQT-4.184 Incorrect flow indications during SI with TR - 765 10/99 flow aligned through the fill header and normal SI flow path isolated due to leak.

The cormeted test deficiencies for 1995 - 1998 are listed on pages 5 and 6.

t 2

4 9

a

l '

\l Beaver Valley Power Station Unit 1 Four Year Simulator Certification Report 1995 - 1998 Simulator Qualification Test (SQT)

CornctedTest Deficiencies Simulator Test Description Trouble Report Date Completed Qualification (TR)#

Test #

(SQT) 1995 SQT-4.188 Turbine Bearing High Vibration TR - 561 -12/23S6

TR - 562 1/2B6
SQT-2.4.5 Plant Startup MODE 5 to 100% TR - 599 11SS6 TR - 600 4/2S8
TR - 606 3/27S7 TR - 607 3/27S7 TR - 608 11/7B6

'IR - 619 1/31B7 l SQT-3.8 DBA LOCA With Loss of Offsite Power TR - 628 3/27B7 SQT-4.8 Gaseous Waste Decay Tank Effluent leak TR - 611 1/14S7 SQT-4.80 Loss of DC Bus TR - 572 4/23 S 6 l

l SQT-4.148 Cold Leg Leak TR - 574 7/3S6 SQT-4.149 Steam Generator Tubeleak TR - 677 9/2S7 SQT-4.201 Median Tavg/DeltaT Signal Failure TR - 613 7/28/97 1997 SQT-3.10 PZR Safety Valve Leak With No HHSI TR - 787 12MW8 TR - 788 12/02S 8 TR - 789 12/02 S 8 TR - 790 12/0168 SQT-4.93 Feedwater Leak Outside CNMT TR - 801 12/08S 8 SQT-4.123 Intermediate Range Channel Failure TR - 480 9/2/97 SQT-4.124 Power Range Channel Failure TR - 643 4/16/97

-5

Beaver Valley Power Station Unit 1 Four Year Simulator Certification Report 1995 - 1998 Simulator Qualification Test (SQT)

Corrected Test Deficiencies Simulator Test Description Trouble Report Date Completed Qualification (TR)#

Test #

(SQT) 1998 SQT-2.4.4 NIS Somre Range OST TR - 749 12/01S 8 SQT-2.4.7 RCS Inventory Balance OST TR - 751 12/02S8 SQT-2.4.11 Containment Isolation Valve OST TR - 772 12/01S8 SQT-2.4.14 Aux Feedwater Discharge Stroke Valve TR - 750 10nS8 Test

' SQT-3.10 PZR Safe:y Valve Leak With No HHS1 TR - 796 12/02S8 TR - 797 12/02S8 SQT-4.76 Loss of 4160 Volt Bus TR - 759 12/03S 8 l

SQT-4.78 Loss of 120 Volt Bus TR - 762 9/18S8  !

TR - 763 100B8 l l

SQT-4.79 1.oss ofInverter TR - 760 9/22S8

.. 1.

^

i i Beaver Valley Power Station Unit 1 l Simulator Certification Test Schedule l 1999 - 2002  !

l l

SQTTEST . TEST DESCRIPTION YEAR TO BE TESTED

- NUMBER' i 1999 2000 2001 2002 SQT-1.0 Simulator, Realtime Test X X X X SQT-2.0 Steady State, Drift and Normal Operations Tests i

SQT-2.1 Steady State Drift Test at 100% Power X X X X l 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 l

SQT-2.4 Normal Operations i l

SQT-2.4.1 Plant Shutdown 100% to Mode 5 X SQT-2.4.2 NIS Power Range OST X l 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 l SQT-2.4.6 Accident MonitoringInst. OST X SQT-2.4.7 RCS Inventory Balance OST X l SQT-2.4.11 Containment Isolation Valve OST X r SQT-2.4.12 Cold Shutdown Valve Exercise OST X )

l SQT-2,4.13 MSIV Closure Test OST X l . SQT-2.4.14 Aux Feedwater Discharge Valve Stroke j Test X

. SQT-2.4.17 Reactor Startup After atrip X SQT-3.0 Transient Tests SQT-3.1 Manual Reactor Trip X X X X SQT-3.2 Complete Loss of AllFeedwater X X X X SQT-3.3 Simultaneous Closure of AllMSIVs X X X X SQT-3.4 Simultaneous Trip of All RCPs X X X X SQT-3.5 Trip of One Reactor Coolant Pump X X X X SQT-3.6 Main Turbine Trip (Rods in Manual) X X X X SQT-3.7 Maximum Power Ramp (100%-75%-

100 %) X X X X

- SQT-3.8 DBA IDCA 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-3.11 Main Turbine Trip (Rods in Auto) X X X X l

l I .

/

I 2

Beaver Vdcy Power Station Unit 1 Simulator Certification Test Schedule 1999 - 2002 SQTTEST - -

TESTDESCRIPTION YEAR TO BE TESTED NUMBER 3

1999 2000 2001 2002 l'

SQT-4.0 Malfunction Tests SQT-4.1 Containment Instnament Air Compressor Tdp _

X SQT-4.2 Station AirCompressorTrip X SQT-4.3 Instrument Air leak Outside Containment X i SQT-4.4 Instrument Air Leak Inside Containment X SQT-4.5 Station Air HeaderIsolation Valve Failure X

SQT-4.6 Auxiliary Steam Header Leak X SQT-4.7 Gaseous Waste Surge Tank Effluent leak X SQT-4.8 Gaseous Waste Decay Tank Effluent Ieak X SQT-4.9 RiverWater Pump Trip X SQT-4.10 Raw Water Pump Trip .

X ,

, - SQT-4.11 Auxiliary River Water Pump Trip X SO,T-4.12 Containment Ventilation Fan Failure X l

SQT-4.13 Radiation Monitor Failure X SQT-4.14_ Non-Regenerative Hx Tube leak X RCP Thermal BarrierHx Tubeleak X SQT-4.15 SQT-4.16 CCR Pump Trip X SQT-4.17 CCR Temperature Control Valve Failure X

! SQT-4.18 Non-Regenerative Hx TCV Failure X

. SQT-4.19 CCR Pump Suction Headerleak X SQT-4.20 CCR Supply Line to RCP Leak X SQT-4.21 RCP SealWater Hx Tube I.cak X SQT-4.22 Condensate Pump Trip ,

X SQT-4.23 Feedwater Heater Bypass Valve 1-ailure X

' SQT-4.24 Condensate Pump Discharge Hender leak X SQT-4.25 Feedwater HeaterTube 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 EjectorFailure X 4

SQT-4.29 Vacuum Breaker Leak X SQT-4.30 Conde.aserTube Leak X SQT-4.31 Cooling Tower Pump Trip X SQT-4.32 Cooling TowerPump Discharge Valve Failure X

-SQT-4.33 Condensate Recirc Control Valve Failure - X SQT-4.34 HotwellLCV Failure X

.. - - -= . .. - .- .-.. --. - ... _. . . - -

1 Beaver Valley Power Station Unit 1 Simulator Certification Test Schedule 1999 - 2002 SQT'IEST -

TEST DESCRIPTION YEAR TO BE TESTED NUMBER 1999 2000 2001 2002

)

SQT-4.36 Priming Pump Vac Breaker Valve Failure X l t- Vacuum Priming Pump Trip X SQT-4.37 l SQT-4.38 Loss of Rod Drive MG Set X 4-

. SQT-4.39 Failure of Rods to Move X

' SQT-4.40 : Improper Bank Overlap X

, SQT-4.41 Dropped Contml Rod X l SQT-4.42 Uncontrolled Rod Motion X l

, SQT-4.43 Autamatic Rod Control Speed Failure X l

. SQT-4.44 TrefFailure X SQT-4.45 IRPILoss of Voltage X

, SQT-4.46 Rod Position Step Counter Failure X SQT-4.47 Stuck Control Rod X SQT-4.48 ReactorTrip Failure X ,

i SQT-4.49 Rod Stop Failure X l

SQT-4.50 ReactorTrip X SQT-4.51 letdown Pressure Regulator Valve Failure X l SQT-4.52 letdown Relief Valve Failure X SQT-4.53 letdown Line Leak in Containment X SQT-4.54 Plugged Seal WaterInjection Filter X

! SQT-4.55 VCr Level Control Valve Failure X

! SQT-4.56 VCrDegas LCV Failure X

! SQT-4.57 - RCS Dilution Accident X SQT-4.58 RCS Boration Accident X SQT-4.59 Poric 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 Headerleakage X

^ SQT-4.63 RCP SealHeader FCV Failure X SQT-4.64 Excess Letdown Divert Valve Failure X

SQT-4.66 Volume Control Tank Leak X SQT-4.67 Blender Outlet Flow Control Valve Failure X SQN.68 Boric Acid Transfer Pump Trip X SQT-4.69 VCrlevelTransmitter Failure X SQT-4.70 letdown Isolation Valve Failure X SQT-4.71 Charging FCV Failure X SQT-4.72 Ietdown High Temperature Divert Valve Failure X

-9

i

,. s Beaver Valley Power Station Unit 1

. Simulator Certification Test Schedule l

1999 - 2002 SQTTEST

'IEST DESCRIFFION YEAR TO BE TESTED

, NUMBER i999 2000 2001 2002 t

SOT-4.73 Station Blackout X l SQT-4.74 Unit Station Service Transformer Failure X l

SQT-4.75 System Station Service Transformer Failure X l

l. SQT-4.76 Loss of 4160 Volt Bus X I l SQT-4.77 Loss of 480 Volt Bus X l l 'SQT-4.78 Loss of 120 Volt Bus X L SQT-4.79 Loss ofInverter X L . SQT-4.80 Loss of DC Bus X l

l SQT-4.81 Grid Voltage Variation X L SQT-4.82 DieselGenerator Trip X

.SQT-4.83 Diesel Generator Erratic Speed Control X ,

, . SQT-4.84 Diesel Generator Erratic Voltage

! Regulation X l SQT-4.85 Diesel Generator Output Breaker Trip X l 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 bak in Containment X SQT-4.93 Feedwater Leak Outside Containment X l SQT-4.94 Feedwater Recire Control Valve Failure X SQT-4.95 High Pressure Feedwater Tube Leak X SQT-4.% Feedwater Regulator Valve Failure X t

SQT-4.97 Feedwater Regulator Bypass Valve Failure X SQT-4.98 Erratic Feedwater Flow Contml X L SQT-4.99 - Aux Feedwater Pump Trip X l SQT-4.100 Aux Feedwater FCV Failure X l SQT-4.101' Aux Feedwater Pump Suction leak X SQT-4.102 Feedwater Flow Transmitter Failure X SQT-4.103 Steam Generator Programmed Level SignalFailure X SQT-4.104 - Steam Generator level Transmitter Failure X SQT-4.105 Steam Leak Upstream of MSIV X SQT-4.106 Steam Leak Downstream of MSIV X SQT-4.107 MSIV Drifts Shut X

' SQT-4.108 NRV to First Point Heater Failure X l

l

l ,' *;

L -

. Beaver Valley Power Station Unit 1 l Simulator Certification Test Schedule i

1999 - 2002 SQTTEST TESTDESCRIPTION YEAR TO BE TESTED

l. NUMBER 1999 2000 2001 2002 l

l' SQT-4.109 NRV to Third Point Heater Failurc X SQT-4.110. Steam Generator Safety Valve Fails to Rescat X SQT-4.111 Steam Dump Valve Falls 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 Dumo Failure X SQT-4.115 Steam Pressure Signal to Steam Dump Failure X SQT-4.116 Atmospheric Steam Dump Valve Failure X SQT-4.117 Erratic Control of Atmospheric Steam Dump Valve X SQT-4.118 Ste).in Flow Transmitter Failure X SQT-4.119 Steam Preseure Transmitter Failure (Control) X SQT-4.120 Steam Pressure Transmitter Failure '

L (Protection) X SQT-4.121 Steam Leak on Aux Feedwater Pump Supply Line X SQT-4.122 Source Range Channel Failure X SQT-4.123 Intermediate Range ChannelFailure X SQT-4.124 Power Range ChannelFailure X

' SQT-4.125 Intermediate Range Compensating Voltage Failure X SQT-4.126-- - Source Range High Voltage Cutoff Failure X

. SQT-4.127 Source Range Blown Fuse X

' SQT-4.128 Intermediate Range Blown Fuse X SQT-4.129 Power Range Blown Fuse X SQT-4.130 CCr Pump Trip X

. SQT-4.131 CCrTCV Failure X SQT-4.132 CCr Sr.pply Line leak X SQT-4.133 CCr Suction Headerleak X SQT-4.134 PZR Safety Valve Leakage X l SQT-4.135 - PZR Safety Valve Failure X SQT-4.136 PZR PORY Failure X p SQT-4.137 PZR PORV Rescat Failure X SQT-4.138 - PZR Steam Spaceleak X i

l

  • Beav:r Valley Power Station Unit 1 Simulator Certification Test Schedule 1999 - 2002 SQTTEST - -

IEST DESCRIPTION YEAR TO BE TESTED l NUMBER l 1999 2000 2001 2002

\

l SQT-4.139 PZR12velTransmitter Failure X SQT-4.140 PZR Reference level Signal Fa' lure X SQT-4.141 PZR Pressure Transmitter Failure X SQT-4.142 PZR Spray Valve Failure X SQT-4.143 PZR Heater ControlFailure X SQT-4.144 - PZR Spray Valve Controller Failure X

. SQT-4.145 - PZR Master Pressure Controller Failure X ,

SQT-4.146 PZRI4 vel Control Failure X SQT-4.147 Surge Line Leak X SQT-4.148 Cold Legleak X SQT-4.149 Steam Generator Tube leak X SQT-4.150 ReactorVessel Head Flange Leak X SQT-4.151 RCP Seal #1 Failure X SQT-4.152 RCP Seal #2 Failure X i SQT-4.153. RCP Seal #3 Failure X l

SQT-4.154 Reactor Coolant Pump Trip X i' SQT-4.155 Reactor Coolant Pump Lecked Rotor X SQT-4.156 Reactor Coolant Pump High Vibration X SQT-4.157 Reactor Coolant High Activity X

, SQT-4.158 FuelHandling Accident X SQT-4.160 Hot Leg WR Temperature Sensor Failure X

- SQT-4.162 Cold leg WR Temperature Sensor Failure X

, SQT-4.163 Hot Leg Pressure Transmitter Failure X SQT-4.164 leop Flow Transmitter Failure X SQT-4.165 Incore'Ihermocouple Failure X SQT-4.166 RCS Boron Concentration X L SQT-4.167 RHR Pump Trip X L

SQT-4.168 RHR Relief Valve leak X SQT-4.169 RHR Flow Transmitter Failure X SQT-4.170 . RHR Flow Control Valve Failure X SQT-4.171 RHR Pump Shaft Failure X SQT-4.172 Refueling Water Storage Tankleak X SQT-4.173 Quench Spray Pump Failure X SQT-4.174 Recire Spray Pump Failure X l SQT-4.175 - Recire Spray Hx Tube I2ak X l SQT-4.176 HHSIPump Failure X l SQT-4.177 LHSIPump Failure X j - SQT-4.178 Containment In-leakage X l

y -

Beav rValley Power Station Unit 1 Simulator Certifbation Test Schedule

( 195")- 2002 SQTTEST . -

TEST DESCRIPTION YEAR TO BE TES'mD NUMBER 1999 20(X) 2001 2002 SQT-4.179 Spurious SI Actuation X SQT-4.180 Spurious CIA Actuation 'X

, SQT-4.181 Auto SI Actuation Failure X L SQT-4.182 SafetyInjection AccumulatorLeak X SQT-4.183 SI SignalFailure to Selected Valves X SQT-4.184 SafetyInjection Line Leak X l SQT-4.185 RWST LevelTransmitter Failure X SQT-4.186 LHSIPump Suction Valve Failure X l SQT-4.187 Turbine Trip X

- SQT-4.188 Turbine Bearing High Vibration X SQT-4.189 Governor Valve Failure X L 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 Ims to EHC X SQT-4.199 ' 'SR Steam Supply Valve Failure X-SQT-4.200 First Stage Steam Pressure Transmitter Failure X SQT-4.201 Median Tavg/DeltaT Signal Failure X Electrohydraulic Control System leak X

' SQT-4.202 SQT-4.203 Hot Leg Narrow Range RTD Sensor Failum X SQT-4.204 Cold Leg Narrow Range RTD Sensor Failure X

  • l l.

1 l