ML17265A545

Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)

ML17265A545
Person / Time
Site:	Ginna
Issue date:	02/12/1999
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9902250230
Download: ML17265A545 (16)

Text

• - CATEGORY 1 REGULA1 Y INFORMATION DISTRIBUTIO SYSTEM (RIDS)

ACCESSION NBR:9902250230 DOC.DATE: 99/02/12 NOTARIZED: NO DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY]'R.Z. Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.

SUBJECT:

Fortjrards RE Ginna Nuclear Power Plant Simulator Four Yr Certification Rept,IAW 10CFR55.45(b)(5)(ii).

DISTRIBUTION CODE: A'005D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Simulator Facility Certification - GL-90-08 T

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 E

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL VISSING,G. 1 1 INTERNAL: FILE CENTER 01 1 1 EXTERNAL: NRC PDR 1 1 1

I

'Ii D

11 N

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 3 ENCL 3

////I//I////

//Ill/ ll/

//////////I/'RCEZZ'::

/ill//IIIII 0%( ~ 4 ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TELEPHONE AREA coDE TIE 546-2700 February 12, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555

SUBJECT:

Simulator Facility Certification Four Year Report R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing:

In accordance with 10CFR55.45 (b) (5) (ii), we hereby submit the R.E. Ginna Nuclear Power Plant Simulator Four Year Certification Report.

Very ly yours, Robert C. Mecredy xc Mr. Guy S. Vissing (Mail Stop 14B2)

Project Directorate Division of Reactor Projects - UII Office of Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission Washington D.C. 20555 Regional Administrator, Region I 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector.

9902250230 9902i2 PDR ADOCK 05000244 P PDR

R.E..GINNA NUCLEAR POWER PLANT SIMULATORFOUR YEAR REPORT Pursuant to 10CFR55.45(b)(5)(ii), all performance test failures have been corrected. All discrepancies noted during performance testing are identified, prioritized, and corrected per procedure GSS-1.4, "Simulator Discrepancy Reporting". Identified performance testing discrepancies have been corrected with the exception of the following, which will be resolved per the above referenced procedure:

SDR 8 97-80 H2 Temp Controller Demand Low Compared to Plant Data (Priority 4) 98-24 Transformer 14,16,17, &, 18 Response to Loss of DC (Priority 2) 98-63 CCW HX Outlet Temp Increases When CCWP is Off (Priority 3) 98-65 HDT Pump Trip From 100% Should Require Power Reduction (Priority 3) 98-74 PCV 434/435 Should Be Powered From Bus 13 Lighting Panel (Priority 3)

II Pursuant to 10CFR55.45(b)(5)(vi), the following is a description of the simulator performance testing completed satisfactorily during the previous four (4) year test period, January 1995 - January 1999.

1. Performance testing was conducted each year in accordance with ANSI/ANS 3.5 1985, Section 5.4, "Simulator Testing" and Appendix A Section A3 "Simulator Tests" as follows:

A. 14.3.2 Computer Real Time Test (Appendix A Section A3.1)

B. 14.3.1 Instructor System Test ( Section 3.3.2, 3.4)

Steady State and Normal Operations Tests (Appendix A Section A3.2 and Appendix B Section B2.1):

14.4.1 Operating Limits Monitoring 14.4.2 Normal Operations Acceptance Test 14.4.3.1 100% BOL Steady State Accuracy Test 14.4.3.2 100% Power Steady State Drift Check 14.4.3.3 Instrument Error Certification 14.4.3.4 Initial Conditions Stability Check 14.4.4.1 NSSS-BOP Energy Balance Test 14.4.5.1 NSSS-Mass Balance Test 14.4.5.2 BOP-Mass Balance Test

D. Transient Tests ( Section 5.4.2, Appendix A Section A3.3, and Appendix B Section B.2.2)

The transient test parameters were compared with reference plant data where available, or best engineering estimate when plant data was not available, by a Transient Review Committee (TRC). The TRC verified the test results were satisfactory with ANSI/ANS 3.5 1985, Section 4.2.1 Performance Criteria.

14.4.8 BE 1 Manual Reactor Trip 14.4.8 BE 2 Simultaneous Trip of All Feedwater Pumps 14.4.8 BE 3 Simultaneous Closure of Both MSIV's 14.4.8 BE 4 Simultaneous Trip of Both RCP's 14.4.8 BE 5 Single RCP Trip 14.4.8 BE 6 Main Turbine Trip 14.4.8 BE 7 Maximum Rate Power Ramp 14.4.8 BE 8 Maximum Size RCS Rupture with Loss of all Offsite Power 14.4.8 BE 9 Maximum Size Unisolable Main Steam Line Rupture 14.4.8 BE10 Slow RCS Depressurization Using PORV or Safety .

(Activation of ECCS Inhibited) 14.4.8 BE11 Steam Generator Tube Rupture The following performance test was conducted after each reference plant core refueling (1995, 1996, 1998) and evaluated against the reference plant physics testing data in accordance with ANSI/ANS 3.5 1985, Section 5.4, "Simulator Testing".

14.4.6.1 Startup Test - Initial Criticality and Low Power Physics Tests Performance tests scheduled at an approximate rate of 25% per year in accordance with the NRC Form 474 submittal of February 15, 1995 were completed.

Discrepancies identified, other than those listed in Section I, were corrected in accordance with procedure GSS-1.4, "Simulator Discrepancy Reporting". All tests satisfactorily meet ANSI/ANS 3.5 1985, Section 4, Performance Criteria.

A. System Tests The System Tests verify the modeling of plant systems at a level of detail greater than the normal operations tests, and also include those surveillance tests conducted by control room operators, in accordance with ANSI/ANS 3.5 - 1985 Section 3.1.1 (10).

The following System Tests were inadvertently omitted from previous test schedules, but have been recently completed with satisfactory results. In accordance with our internal reporting process, procedure IP-CAP-1, Abnormal Condition Tracking Initiation or Notification (ACTION) Report, ACTION Report 8 99-0159 has been submitted for these items.

Standby Aux Feedwater System Test (Test 8 14.3.4.19)

Test completed January 1999, previous test completed 1990.

Electrical Distribution Test (Test 8 14.3.6.1)

Test completed December 1997, previous test completed 1991.

B. Malfunction Tests Malfunction Tests verify the response of the simulator in real time to demonstrate inherent plant response and automatic plant control functions.

(ANSUANS 3.5 1985, Section 3.1.2, Section 4.2.2, Appendix A Section A3.4).

During the previous four year test period, January 1995 - January 1999, the following malfunctions were deleted:

MIS-7 Loss of Plant Communication (Malfunction was never used. Determined to have no training value)

STM-12 MSR Tube Rupture (Malfunction not used for training. No actual simulator response noted or predicted.)

The following Malfunction Tests were performed during the previous four year test period. These tests were either the result of new malfunctions or malfunctions that were not part of the initial certification package.

14.4.7.4. 16 Seal Water Return Line Safety Valve Failure 14.4.7.4.20 Aux Spray Valve Failure 14.4.7.6.3 Feedwater Recirculation Valve Failure 14.4.7.7.2 Failure of Generator H2 Temperature Sensor 14.4.7.7.9 Diesel Generator Breaker Failure to Close 14.4.7.8.1 Feedwater Heater Tube Leak 14.4.7.8.5 Feedwater Heater Level Control Failure 14.4.7.9.3 Liquid Radwaste Leak

14.4.7.9.4 Gas Decay Tank Rupture 14.4.7.12.4 Reactor Vessel Flange Leak 14.4.7. 12.20 Failure of AVG Tavg Channel 14.4.7. 14.3 Nuclear Sample Room Radiation Level 14.4.7. 15. 14 Inadvertent MRPI Alarms 14.4.7. 15. 17 Rod Motion Reverse Logic 14.4.7.16.4 Spray Additive Tank Leak 14.4.7.19.7 Extraction Steam Non-Return Valve Failure 14.4.7.19.8 Gland Seal Steam Regulator Failure 14.4.7.20.13 Turbine Auxiliary Governor Failure 14.4.7.20. 14 LP Turbine Relief Valve Failure 14.4.7.20. 15 Reheater Control Valve Failure 14.4.7.20. 17 Failure of Turbine Auto Load Pickup In accordance with ANSVANS 3.5 1985, Section 5, Simulator Design Control and Section 5.4.1, Simulator Performance Testing, configuration changes made to the reference plant were evaluated, installed, and tested. The changes listed below, were implemented in the simulator during the previous four (4) year reporting period. Acceptance tests procedures were performed for each modification with satisfactory results in accordance with ANSVANS 3.5 1985, Section 5.4.1 prior to turnover to Nuclear Training.

SIMULATOR TITLE MODIFICATION8 94-03 Recorder Replacement Phase 2 94-08 Main Feed Reg Valve Trim 94-19 PPCS Build 94.1 94-21 PPCS Operating System Upgrade 94-28 N32 2 N32 Source Range Detector Replacement 94-31 PPCS Build 94.2 94-32 Steam Generator Replacement 95-01 SASS Upgrade 95-02 PPCS Build 95.1 95-04 SASS Upgrade 95-09 Condensate Low Pressure Drop Alarm 95-10 RCP Seal LeakofFFlow Setpoints 95-11 Annunciator Window J-19 95-12 Delta T Runback Logic Change 95-13 Reprogram Simulator Phone Numbers 95-14 Deletion of BAST/RWST Swapover Logic 95-15 AFW Lube Oil Pump Alarm

95-16 CRDM Fans Damper Failure on Loss of Instrument Air 95-18 PPCS Build 95.2 95-19 RMS Rack Overheat Correction 95-20 SASS Version 95.2 95-22 Incore Thermocouple Panel Reprogramming 95-24 SASS Modification - NERP Display and Message Center 95-25 SWP D Motor Replacement 95-26 Instrument Air Compressor "C" Replacement 96-01 Reactor Makeup Water Control Setpoint 96-02 RCP 2, Turbine Generator Vibration Monitoring 96-05 Replacement of Instrument Bus Voltmeters 96-06 SASS Update 96.1 96-07 RCP Seal Leakoff Flow Transmitters 96-08 PPCS Build 96.1 96-09 SGRP - FW Isolation Setpoint Change 96-10 SASS Update dated 6/14/96 96-12 Reactor Compartment Cooling Unit Discharge 96-13 Removal of CRDM Fan Suction Dampers 96-14 Main Generator Voltage Reg Auto-Man Transfer Circuit Fuse Indication 96-17 SI Rack DC Power Reconfiguration 96-21 N31 Detector Replacement 96-22 Pressurizer Spray Valve Indication 97-02 PPCS Update for NERP 97-03 RVLIS Setpoint Correction 97-05 FW Pump AB Seal Drain Tank Hi Level Alarm Defeat 97-07 Remove Low Pressurizer Pressure Trip Rate Function 97-08 Electrical Power Feed to AFW Actuation Relays 98-02 PPCS Build 97.1 98-03 Removal of Recorder RK-17 98-04 Reversal of Power k Control Feeds for MOV 515 k, 516 98-05 Safety Related Indicator Replacement for D/G's 98-07 Disable CETs 98-09 CET Display Panel 98-16 EH Controller Speed Error 'B'ard Replacement 98-17 Remove CV Isolation Signal from AOV-9227 98-18 Remove Electrical Power from MOV-5171

5. In accordance with ANSVANS 3.5 1985, Section 5, Simulator Design Control and Section 5.4.1, Simulator Performance Testing, enhancements recommended for simulator performance were evaluated, installed, and tested. The enhancements listed below, were implemented in the simulator during the previous four (4) year reporting period. Acceptance tests procedures. were performed for each modification with satisfactory results in accordance with ANSUANS 3.5 1985, Section 5.4.1 prior to turnover to Nuclear Training.

SIMULATOR MODIFICATION8 DESCRIPTION 91-51 Add LOA to Adjust NIS Trip Setpoints 92-08 Add LOA's for Local Positioning of MOV's 92-25 Abilityto Flag Non-Certified LOA's, MALF's, 2 IC's 92-26 Alert Instructor to UO Lockup Problem 93-14 Add Abilityto Block Snapshot Data From PPCS 93-25 Enhance MALF STM-5 to Allow Partial Closure 93-37 Add MALFFailure of D/G Output Breaker to Close 93-38 Add MALFFailure of AVG TAVG Signal 94-09 Add MALF Failure of Turbine Auto Load Pickup 94-12 Prevent Reset of Bank 'C'tep Counters on Init 94-13 Enhance MALF HTR-4 for Dump Valves to Fail Open 94-14 Expand Scope of Sim to Reflect Siphoning 94-22 Expand Range of MALFRCS-11, RTD Failure 94-33 Add LOA's for Diesel Driven Air Compressor 94-34 Upgrade Simulator 2 Spare Instructor Interface 95-07 Add MALF for Opposite Rod Movement 95-08 Simulator Computer Upgrade 95-21 Enhance Main Condensers to Respond to Backpressure 95-23 Instructor Print Screen to Line Printer Operation 95-28 Determine Setpoints for AOV's to Fail Closed 95-29 Remove Control Board Chart Marking Feature 96-03 Add LOA for Hooking Up Cooling From Fire Water System to Diesel Generator 96-04 Remove Status of Remote Control PB's from Switch Check 96-15 Core Cycle 26 Update

98-01 Install RSX YEAR-2000 Software on RSX's, PPCSS, 0 SASS 98-06 Enhance Cycle 26 Core to Plant Cycle 27 Data 98-10 Add LOA to Defeat Jumpers for AFW Bypass Valves Lo Lo Lvl Closure III Pursuant to 10CFR55.45 (b)(5)(vi), the performance test schedule for the subsequent four (4) year period (January 1999 - January 2003) is provided in Attachment 1. This schedule includes computer real time tests, steady state and normal operations tests, system tests, transient tests, and malfunction tests. The system tests verify the modeling of plant systems at a level of detail greater than the normal operations tests, and also include those surveillance tests conducted by control room operators, in accordance with ANSVANS 3.5 1985 Section 3.1.1 (10). Additional tests for acceptance of simulator modifications due to plant configuration changes and simulator enhancements will be conducted as needed.

ATTACHMENT 1 FOUR YEAR TEST PLAN - (January 1999 - January 2003)

A. ANNUALTEST SCHEDULE 14.3.1 Instructor System Test 14.3.2 Computer Real Time Test 14.4.1 Operating Limits Monitoring 14.4.2 Normal Operations Acceptance Test 14.4.3.1 100% BOL Steady State Accuracy Test 14.4.3.2 100% Power Steady State Drift Check 14.4.3.3 Instrument Error Certification 14.4.3.4 Initial Conditions Stability Check 14.4.4.1 NSSS - BOP Energy Balance 14.4.5.1 NSSS Mass Balance Test 14.4.5.2 BOP Mass Balance Test 14.4.8 BE 1 Manual Reactor Trip 14.4.8 BE 2 Simultaneous Trip of All Feedwater Pumps 14.4.8 BE 3 Simultaneous Closure of Both MSIV's 14.4.8 BE 4 Simultaneous Trip of Both RCP's 14.4.8 BE 5 Single RCP Trip 14.4.8 BE 6 Main Turbine Trip 14.4.8 BE 7 Maximum Power Rate Ramp 14.4.8 BE 8 Maximum Size RCS Rupture With Loss of All 14.4.8 BE 9 Maximum Size Unisolable Main Steamline Rupture 14.4.8 BE 10 Slow RCS Depressurization using PORV or Safety 14.4.8 BE 11 Steam Generator Tube Rupture B. TEST SCHEDULE - YEAR 1 14.3.3.4 Bistable Handler Test 14.3.3.5 Alarm Handler Test 14.3.4. 12 EHC, TGA, and Main Generator System Test 14.3.4. 16 Circulating Water System Test 14.3.4.20 Service Water System Test 14.3.4.23 Process 2 Area Radiation Monitor System Test 14.3.4.25 SAS Fidelity Test 14.3.4.4 Reactor Coolant System Test 14.3.4.7 RHR System Test 14.4.6.1 Startup Test-Initial Criticality 2 Low Power Test

14.4.7.1.2 Loss of Lake Water 1$ .4.7. 10.3 Failure of Source Range Channel High Voltage to Disconnect 14.4.7.10.6 Power Range Channel Detector Failure 14.4.7.10.9 Source Range High Voltage Failure 14.4.7.11.3 Pressurizer Level Channel Failure 14.4.7. 12. 13 RCP No. 2 Seal Failure 14.4.7.12. 16 Fuel Cladding Failure 14.4.7. 12. 19 RCS Leaks Outside Containment 14.4.7. 12.20 Failure of AVG Tavg Channel 14.4.7.12.3 RCS DBA into Containment 14.4.7.12.5 RCP Trip 14.4.7.12.9 Wide Range RCS Pressure Channel Failure 14.4.7.13.1 RHR Pump Trip 14.4.7.13.5 RHR Bypass Line Leak 14.4.7.15.12 Rod Stop Failure 14.4.7. 15. 16 Misaligned Rod-Failure 14.4.7. 15.17 Rod Motion Reverse Logic 14.4.7. 15.4 Control Banks Fail to Move 14.4.7.15.8 Rod Speed Controller Failure 14.4.7. 16.2 Inadvertent Control Room Environmental Isolation 14.4.7. 16.6 Containment Fails to Isolate 14.4.7.16.9 Inadvertent Containment Ventilation Isolation 14.4.7.17.3 Steam Generator Pressure Channel Failure 14.4.7. 17.4 Steam Generator Tube Rupture 14.4.7. 18.4 RWST Leak 14.4.7. 19.2 Steamline Break Outside Containment Upstream of MSIVs 14.4.7.19.6 Main Steam Header Pressure Transmitter Failure 14.4.7.2. 10 CCW Pump Low Pressure Autostart Failure 14.4.7.2.3 Non-regenerative Letdown HX Tube Leak 14.4.7.2.7 CCW Heat Exchanger Tube Leak 14.4.7.2.9 Service Water Pump Discharge Check Valve Failure 14.4.7.20. 1 Inadvertent Turbine Trip 14.4.7.20. 17 Turbine Stop Valve Failure 14.4.7.20. 18 Failure of Turb Auto Load Pickup 14.4.7.20.5 Turbine High Vibration Condensate Pump Failure 14.4.7.3.4'4.4.7.3.8 Condensate Pipe Break 14.4.7.4.12 Charging Pump Trip 14.4.7.4.19 Plugged Seal Injection Filter 14.4.7.4.24 Charging Backpressure Control Valve Failure 14.4.7.4.4 Makeup Control Failure in All Modes 14.4.7.4.8 RCS Filter Plugged 14.4.7.5.1 Loss of Off-Site Power

14.4.7.5.5 Loss of DC Bus 14.4.7.6.13 AFW Pump Suction Line Break 14.4.7.6. 17 Main Feedwater Pump Fails to Trip 14.4.7.6.4 Feedwater Pump Lube Oil System Failure 14.4.7.6.5 Feedline Leak Between Flow Element 2 Check Valve 14.4.7.7.4 Diesel Generator Trip 14.4.7.9.9 Turbine Building Fires C. TEST SCHEDULE - YEAR 2 14.3.3.1 Valve Handler Test 14.3.4.1 Nuclear Instrumentation System Test 14.3.4.13 Condensate and Main Feedwater System Test 14.3.4. 17 Compressed Air System Test 14.3.4.21 Plant Protection System Test 14.3.4.9 Component Cooling Water System Test 14.3.6.2 Electrical Interlocks 14.4.7.1.3 CWS Leak 14.4.7. 10. 10 Source Range Blown Fuse 14.4.7.10.7.1 Power Range Channel Fails High 14.4.7.1 1.4 Pressurizer Master Controller Failure 14.4.7. 11.7 Pressurizer Steam Space Leak 14.4.7.1 1.9 Pressurizer Instrumentation Line Breaks 14.4.7. 12. 10 RCS Loop Flow Transmitter Failure 14.4.7. 12. 14 RCP No. 3 Seal Failure 14.4.7.12.2 RCS Leak into Containment 14.4.7.12.4 Reactor Vessel Flange Leak 14.4.7. 12.6 RCP Shaft Shear 14.4.7.13.2 RHR Heat Exchanger Flow Control Valve Failure 14.4.7.13.6 Containment Sump to RHR Pump Screens Foul 14.4.7.14.3 Nuclear Sample Room Radiation Level 14.4.7.15.1 Uncontrolled Rod Motion 14.4.7.15.5 Rod Ejection 14.4.7. 15.9 Improper Bank Overlap 14.4.7. 16.3 Containment Spray Pump Trip 14.4.7.16.4 Spray Additive Tank Leak 14.4.7.17.1.1 S/G Level Channel Failure - High 14.4.7. 18.1 Inadvertent SIS Actuation 14.4.7.18.5 Accumulator Leak 14.4.7. 19. 10 Steam Dump Failure 14.4.7. 19.3 Steamline Break Outside Containment Downstream of MSIVs 14.4.7.2.4 Loss of CCW to RHR Heat Exchanger 10

14.4.7.2.8 Service Water Leaks 14.4.7.20.10 AMSAC Failures 14.4.7.20. 13 Turbine Auxiliary Governor Failure 14.4.7.20.2 Turbine Failure to Auto Trip 14.4.7.20.6 Turbine Lube Oil Temperature Control Valve Failure 14.4.7.20.9. 1 Turbine EHC Failure - EHC Leak 14.4.7.20.9.2 Turbine EHC Failure - Electronic Failures 14.4.7.3.1 Condensate Booster Pump Trip 14.4.7.3.7 Loss of Condenser Vacuum 14.4.7.4.1 Letdown Line Leak Inside Containment 14.4.7.4.13 Boric Acid Pump Trip 14.4.7.4. 16 Seal Water Return Line Safety Valve Fails 14.4.7.4. 17 RMW to Blender Flow Control Valve Failure 14.4.7.4.20 Aux Spray Valve Failure 14.4.7.4.21 Boric Acid Storage Tank Leak 14.4.7.4.25 VCT H~ Pressure Control Valve Failure 14.4.7.4.26 VCT Outlet Pipe Ruptures Upstream LCV-112C 14.4.7.4.5 Loss of CCW to NE 14.4.7.4.9 VCT Divert Control Valve Failure 14.4.7.5.2 Loss of Station Service Transformer 14.4.7.5.6 Loss of Switchyard (Station Blackout) 14.4.7.6.10 Feed Regulating Valve Failure 14.4.7.6.14 AFW Feed Control Valve Failure 14.4.7.6.19 ADFCS Controllers Fail to Manual 14.4.7.6.2 Feedwater Pump Trip 14.4.7.6.3 Feedwater Recirculation Valve Failure 14.4.7.6.6 Feed Flow Transmitter Failure 14.4.7.6.9 Feedwater Break Inside Containment 14.4.7.7.1 Main Generator Trip 14.4.7.7.2 Failure of Generator H~ Temperature Sensor 14.4.7.7.5 Diesel Generator Failure to Load 14.4.7.8.3 Heater Drain Tank Level Control Valve Failure 14.4.7.8.4 Feedwater Heater High Level Dump Isolation Failure 14.4.7.9.4 Gas Decay Tank Rupture 14.4.7.9.5 Containment Isolation Valve Failure 14.4.7.9.8 Auxiliary Building Fires TEST SCHEDULE - YEAR 3 14.3.3.2 Pump Handler Test 14.3.4. 10 Containment and Containment Spray System Test 14.3.4. 14 Feedwater Heaters, Vents, k, Drains System Test 11

14.3.4. 18 Diesel Generator System Test 14.3.4.22 Steam Dump Control System Test 14.3.4.5 Pressurizer Relief Tank System Test 14.3.4.8 Safety Injection System Test 14.3.6.1 Electrical Distribution Test 14.3.6.3 Electrical Loading Test 14.4.6.1 k Startup Test-Initial Criticality Low Power Test 14.4.7.10.1 Source Range Channel Failure 14.4.7.10.4 Intermediate Range Channel Failure 14.4.7.1 1.1 Pressurizer Spray Valve Failure 14.4.7.1 1.5 Pressure Relief Valve Failure 14.4.7.1 1.8 Pressurizer Level Master Controller Failure 14.4.7.12.1 RCP Thermal Barrier Leak 14.4.7. 12. 11 RTD Failure 14.4.7.'12. 15 RCP High Vibration 14.4.7. 12. 18 Variable RCS Boron Concentration 14.4.7.12.7 RCP Locked Rotor 14.4.7.13.3 RHR Heat Exchanger Tube Leak 14.4.7.13.7 RHR Pump Suction Line Rupture 14.4.7.14. 1 Area Monitor Failure 14.4.7. 15.10 Step Counter Failure 14.4.7. 15. 13 MRPI System Failure 14.4.7. 15. 14 Inadvertent MRPI Alarms 14.4.7.15.2 Dropped Rod 14.4.7. 15.6 Rod Drive MG Set Trip 14.4.7.16.1 Inadvertent Containment Isolation 14.4.7. 17. 1.2 S/G Level Channel Failure - Low 14.4.7.18.2 SIS Failure to Actuate 14.4.7. 18.6 Safety Injection Header Leak 14.4.7. 19. 11 Steamline Break Upstream of Flow Element (Inside Containment) 14.4.7. 19.4 Atmospheric Relief Valve Failure 14.4.7. 19.7 Extraction Steam Non-Return Valve Failure 14.4.7.19.8 Gland Seal Steam Regulator Failure 14.4.7.2.1 Service Water Pump Trip 14.4.7.2.6 Seal Water Heat Exchanger Tube Leak 14.4.7.20.11 Turbine Control Valve Failure 14.4.7.20. 15 Reheater Control Valve Failure 14.4.7.20.3 Turbine Lube Oil Failure 14.4.7.20.7 Turbine Thrust Bearing High Wear 14.4.7.3.2 Main Condenser Tube Leak 14.4.7.3.5 Condensate Bypass Valve Failure 14.4.7.3.6 Condensate Trim Valve Failure 14.4.7.4.10 VCT Level Transmitter Failure 12

14.4.7.4.14 RMWT Pump Trip 14.4.7.4.18 Charging Pump Speed Controller Failure 14.4.7.4.2 Letdown Line Leak Outside Containment 14.4.7.4.22 Regenerative Letdown Heat Exchanger Tube Leak 14.4.7.4.6 Letdown Orifice Isolation Valve Failure 14.4.7.5.3 Loss of Number 11 Aux Transformer 14.4.7.5.7 Loss of Instrument Bus Supply 14.4.7.6.1 Feedwater Suction Header Break 14.4.7.6. 11 Auxiliary Feedwater Pump Failure 14.4.7.6.15 Standby Auxiliary Feedwater Pump Failure 14.4.7.6. 18 Feedwater Header Pressure Transmitter Failure 14.4.7.6.7 Feed Regulating Valve Control Failure 14.4.7.7.6 Diesel Generator Breaker Trip 14.4.7.7.9 Diesel Generator Breaker Fails to Close 14.4.7.8.1 Feedwater Heater Tube Leak 14.4.7.9.10 Screenhouse Fires 14.4.7.9.3 Liquid Radwaste Leak E. TEST SCHEDULE - YEAR 4 14.3.3.3 Controller Handler Test 14.3.4. 11 Main Steam and Supply System Test 14.3.4. 15 Auxiliary Feedwater System Test 14.3.4. 19 Standby Auxiliary Feedwater System Test 14.3.4.2 Incore Instrumentation System Test 14.3.4.24 PPCS Fidelity Test 14.3.4.3 Control Rod Drive and RPI System Test 14.3.4.6 Chemical and Volume Control System Test 14.4.6.1 Startup Test-Initial Criticality 0 Low Power Test 14.4.7.1.1 Circulating Water Pump Trip 14.4.7.10.2 Noisy Source Range Channel 14.4.7. 10.5 Intermediate Range Gamma Compensation Failure 14.4.7. 10.7.2 Power Range Channel Failure - Low 14.4.7.10:8 Intermediate Range Blown Fuse 14.4.7. 11.2 Pressurizer Pressure Channel Failure 14.4.7.11.6 Pressurizer Safety Valve Failure 14.4.7. 12. 12 RCP No. 1 Seal Failure 14.4.7.12. 17 RVLIS Transmitter Failure 14.4.7.12.8 RCP Oil Reservoir Failure 14.4.7.13.4 RHR Heat Exchanger Bypass Valve Control Failure 14.4.7.14.2 Process Radiation Monitor Failure 14.4.7.15.11 RPI Failure 13

14.4.7.15.15 Uncoupled Rod Failure 14.4.7. 15.3 Stuck Rod 14.4.7. 15.7 Tg f Failure in Rod Control 14.4.7. 16. 5 Reactor Trip Failure 14.4.7. 16.7 Failure of ESF Components to Actuate 14.4.7. 16. 8 Containment Spray Failure to Actuate 14.4.7. 18.3 SI Pump Trip 14.4.7.19.1 Steam Flow Channel Failure 14.4.7. 19.5 Main Steam Isolation Valve Failure 14.4.7.19.9 Main Steam Safety Valve Failure 14.4.7.2.2 CCW Pump Trip 14.4.7.2.5 CCW Supply Line Break 14.4.7.20. 12 Reheat Stop/Intercept Valve Failure 14.4.7.20. 14 LP Turbine Relief Valve Failure 14.4.7.20. 16 First Stage Pressure Transmitter Failure 14.4.7.20.4 Turbine High Eccentricity 14.4.7.20.8 TSI Failure 14.4.7.3.3 Hotwell Level Transmitter Failure 14.4.7.4.1 1 Charging Line Leak Outside Containment 14.4.7.4.15 Boric Acid Flow Transmitter Failure 14.4.7.4.23 Letdown Line Safety Valve Fails Open 14.4.7.4.27 Charging Pump Suction Line Failure 14.4.7.4.3 Charging Line Leak Inside Containment 14.4.7.4.7 Letdown Pressure Control Valve Failure 14.4.7.5.4 Loss of Emergency Bus 14.4.7.5.8 Failure of 4 KV Auto Transfer 14.4.7.5.9 Inverter Failover 14.4.7.6.12 AFW Turbine Driven Pump Speed Control Failure 14.4.7.6.16 AFW Pump Discharge Line Rupture 14.4.7.6.8 Feedline Break Outside Containment Downstream of Check Valve 14.4.7.7.3 Main Generator Voltage Regulator Failure 14.4.7.7.7 Failure of Diesel Generator Load Sequencing 14.4.7.7.8 Diesel Generator Autostart Failure 14.4.7.8.2 Heater Drain Tank Pump Trip 14.4.7.8.5 Feedwater Heater Level Control Failure 14.4.7.9.1 Loss of Instrument Air 14.4.7.9.11 Diesel Generator Room Fires 14.4.7.9.12 Containment Building Fires 14