NG-95-1017, Submits Plant Referenced Simulator Four Yr Certification Rept,Per 10CFR55.45
| ML20081L896 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 03/24/1995 |
| From: | Franz J IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NG-95-1017, NUDOCS 9503310075 | |
| Download: ML20081L896 (19) | |
Text
m
,s IES UTILITIES INC.
John F. Franz, Jr.
Vice President. Nuclear March 24,1995
. NO-95-1017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station PI-37 Washington, D. C. 20555
Subject:
Duane Arnold Energy Center Docket No. 50-331 Op. License No: DPR-49 Plant-Referenced Simulator Four Year Certification Report
Reference:
Letter, IELP (Mineck) to NRR (Murley) dated 3/25/91, NG-91-0596 File: A-204h H-41e
Dear Sirs:
j IES Utilities Inc. is submitting the 1995 Duane Arnold Energy Center (DAEC) Simulator i
Certification Report. This report is submitted as required by 10 CFR 55.45 on the fourth anniversary of the initial certification of the DAEC plant referenced simulator (reference 1).
Attachment I describes the performance tests completed from 1991 to 1995, performance test failures, performance test schedule for 1995 to 1999, and major test changes to the simulator and testing schedule since the last report. Attachment 2 describes the performance test schedule for 1995 to 1999. Attachment 3 describes the malfunctions to be tested for 1995 to 1999. Attachment 4 describes the surveillance test procedures to be tested. In order to determine the most cost effective method of certification testing, the DAEC continues to evaluate the testing methods and schedule for possibic future improvement, and will notify the NRC of any changes that may be made to the 1995 -
1999 Performance Test Schedule.
The following new commitments are made in this le:ter:
- 1. Complete software design changes that will enable malfunction RW01," Rod Worth Minimizer Failure", to be certified by 12/31/96.
Ol f O 0,O 9503310075 950324
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PDR ADDCK 05000331 i
P PDR General Office
- RO. Box 351
- Cedar Rapids. Iowa 52406
- 319/398-4411 9
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.An IES INDUSTRIES Company
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U. Nuclear Regulatory Commission, March 24,1995 NG-95-1017 Page 2 i
- 2. Correct discrepancy on malfunction RD04, " Control Rod RPIS Reed Switch Failure Open/ Closed", by 01/31/96.
-l Please inform us ifyou have any questions or comments concerning this submittal.
Sincerely, i
.i Iohn F. Franz
^
Vice President, Nuclear t
JFF/TVW/mbm i
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..ttachments:
- 1. DAEC Simulator Four Year Certification Report
- 2. Performance Test Schedule for 1995-1999 i
- 3. Malfunctions to be Tested for 1995-1999 l
- 4. Surveillance Test Procedures to be Tested l
i cc:
L.Liu L. Root B. Fisher l
T. Van Wyen G. Kelly (NRC-NRR)
J. Martin (Region III)
NRC Resident Office DOCU 1
. v.
L
. Attachment I to NG-95-1017 March 24,1995 Page1of3 DUANE ARNOLD ENERGY CENTER SIMULATOR FOUR YEAR CERTIFICATION REPORT
==
Introduction:==
4 The Duane Arnold Energy Center (DAEC) Four Year Certification Report is required to be submitted to the Nuclear Regulatory Commission in accordance with 10 CFR 55.45 on the fourth anniversary of the initial certification of the Duane Arnold Energy Center Simulator (March 25,1991).
The owners of the simulator are IES Utilities Inc., Central Iowa Power Cooperative, and Corn Belt Power Cooperative. The operator of the simulator is IES Utilities Inc. located in Cedar Rapids, Iowa. The simulator vendor was S3 Technologies of Columbia, Maryland. DAEC is a General Electric Boiling Water Reactor (BWR) rated at 1658 MWth.
The simulator was available for training on October 1,1989.
Performance Tests Completed for the Simulation Facility from 1991-1995:
Annual and quadrennial performance tests on the DAEC simulator, which were identified in the Initial Simulator Certification Report were completed for the years 1991 through 1995.
t Accuracies of non-critical (+/- 10%) and critical (+/- 2%) parameters are demonstrated i
based on the DAEC plant instrument loop range as described in ANSI /ANS-3.5-1993.
Performance Test Failures 1991 - 1995:
Malfunction RW01 - Rod Worth Minimizer Failure has been decertifui RW01 I
Certification Test failed to perform in accordance with the malfunction cause and effects I
document. STP 43C002 - NUMAC RWM Operability test also failed. Due to the need for software design. change these failures have been documented on Simulator Change Requests. Efrorts to resolve these failures are in progress and are scheduled to be
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completed by the end of December 1996.
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Attachment I to
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NG-95-1017 March 24,1995 Page 2 of 3 L
Malfunction RD04 - Control Rod RPIS Reed Switch Failure Open/ Closed failed the j
certification test. The closed malfunction fails to cause proper rod position indication. This discrepancy is documented on a Simulator Discrepancy Report and will be corrected by the end of January 1996.
Performance Test Schedule for 1995 - 1999:
The performance test schedule for 1995 through 1998 is included in Attachments 2,3, and 4.
Certain tests were performed during the past 4 years that will no longer be performed as they are not required by ANSI /ANS-3.5-1985 These tests include the 50% Power Steady State and Remote Function Tests. In addition, DAEC certified a total of five 100% Power 1-hour stabilities for difTerent initial conditions. Only one 100% Power 1-hour stability test will be performed for each of the next four years.
1 Major Changes Since Last Report:
1hefollowing malftmetions were added to the list of those in the initial certification report and have been tested and certified:
CUI1 - Thermal Overload Valve (s) Fail (s) to Operate FW21 - Thermal Overload Valve (s) Fail (s) to Operate HP10 - Thermal Overload Valve (s) Fail (s) to Operate PCl3 - Reactor Pressure Relief Valve Leakage RCIO - Thermal Overload Valve (s) Fail (s) to Operate RH09 - Thermal Overload Valve (s) Fail (s) to Operate RR33 - All GEMAC Reference Legs Flash (Random Oscillations)
RR34 - Yarway Level OfTset RX03 - Core Wide Lasalle Event RX04 - Regional Lasalle Event SW35 - Steam Tunnel Coolers GSW Flow Blockage SW36 - Well Water Leak - Outside Containment I
Attachment I to NG-95-1017 March 24,1995 Page 3 of 3
' hefollowing malfunctions have had new subsets added to either incorporate reference I
plant design changes or to increasefunctionalityfor trainingpurposes. These malfunctions have also been testedand certified:
AN01 - Control Room Annunciator Panel Failure - ICl4A/B were added.
ED01 - Loss of Offsite Power Sources: C - Breaker K, D - Breaker 5960, E - Breaker 5940, and F - Loss of Startup Transformer IX3 Lockout Relay were added.
ED12 - 250 VDC Distribution Panel Fault - Added D -Invener ID45.
ED13 - 125 VDC Distribution Panel Fault - Added F - Inverter ID15, and G - Inverter ID25 RP05 - RPS Scram Circuit Failure (ATWS)- Added E - Allindividual rod scram switches failure and F -Ilydraulic Lock Scram Discharge Volume.
Modifications to DAEC plant systems have been evaluated annually and applicable modifications were implemented on the simulator within one year of this evaluation. The singular exception is the Containment Isolation Monitoring System printer output logic which was not implemented in the original plant modification. An evaluation for implementing this modification is being conducted.
A physical fidelity audit is performed each year to ensure the simulator environment matches the DAEC plant main control room and remote shutdown ; anels as close as is reasonable and practical. Differences noted between the simulator and DAEC are maintained on file, and corrected based on training value.
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. to NG-95-1017 March 24,1995 Page 1 of 2 PERFORMANCE TEST SCHEDULE FOR 1995 - 1999 TEST Number of Number of Number of -
Number of i
Tests: 1995 Tests: 1996 Tests: 1997 Tests: 1998 Quadrennial 25% of attached 25% of attached 25% of attached 25% of attached Malfunctions:
list list list list Quadrennial 25% of attached 25% of attached 25% of attached 25% of attached Sunelllance Test list list list list Procedures:
Annual Normal I cold S/U & S/D 1 cold S/U & S/D 1 cold S/U & S/D 1 cold S/U & S/D Plant Evolutions:
I recovery from I recovery from I recovery from I recovery from trip trip trip
' trip Annual 10 10 10 10 Transients: (see list page 2)
Annual Real i
1 1
1 Time Test:
Annual Simulator I
i 1
1 Out-Of-flounds:
Annual Plant 1
I 1
1 Process Computer Alarm Check-Annual Plant i
1 1
1 Process Computer Turn-On-Codes:
Annual Loss of 1
I I
I Powcr:
Annual Steady I @ 25% power I @ 25% power i @ 25% power i @,25% power State:
1 @ 75% power 1 @ 75% power i @ 75% power i @ 75% power
! @ 100% power I @ 100% power I @ 100% power 1 @ 100% power i 100% power 1100% power 1100% power 1100% power stability stability stability stability
. to NG-95-1017 March 24,1995 Page 2 of 2 Annual Transients:
1.
Manual Scram 2.
Simultaneous trip of all feedwater pumps 3,
Simultaneous closure of all Main Steam isolation Valves 4.
Simultaneous trip of all recirculation pumps 5.
Single recirculation pump trip 6.
Main turbine trip (maxirnum power level which does not result in immediate reactor scram) 7.
Maximum rate power ramp down to approximately 75% and back up to 100%
8.
Maximum size reactor coolant system rupture combined with loss of all offsite power 9.
Maximum size unisolable main steam line rupture
- 10. Simulataneous closure of all Main Steam Isolation Valves combined with single stuck open safety /rclief valve. (Inhibit activation of High Pressure Coolant Injection System)
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. *. to NG-95-1017 March 24,1995 Page 1 of 10 Malfunctions To Be TcSted 1995 - 1999 AD01 Reactor Pressure Relier/ Safety Leakage - 8 tests AD02 Automatic Depressurization System Channel Fails to Initiate - 2 tests ADO.s Reactor Pressure Relief Valve Second Stage Valve Leak - 6 tests AD04 Reactor Pressure Relief Valve Bellows Failure - 6 tests AD05 Spurious Automatic Depressurization System Actuation - 2 tests AD06 Reactor Safety Relief Valve Cycles - 6 tests AD07 Automatic Depressurization System Logic Power Failure - 2 tests AD08 Safety Relief Valve Vacuum Breaker Fails Open/ Closed - 12 tests AD09 Low-Low Set Fails To Arm - 2 tests AD10 Low-Low Set Pressure Switch Fails Low - 2 tests AN01 Control Room Annunciator Panel Failure - 35 tests CS01 Core Spray Pump Trip - 2 tests CS02 Core Spray Injection Line Break - 2 tests CS03 Core Spray inadvertent Initiation - 2 tests CSO4 Thermal Overload Valvc(s) Fail (s) To Operate - 2 tests CU01 Reactor Water Cleanup Pump Trip - 2 tests CUO2 Reactor Water Cleanup Nonregenerative Heat Exchanger Tube Leak - I test CUO3 Reactor Water Cleanup Resin Depletion - 2 tests CUO4 Reactor Water Cleanup Drain Flow Control Valve Failure - I test CUO6 Cleanup Pump Speed Controller Failure - 2 tests CUO7 Reactor Water Cleanup Leak in Heat Exchanger Room - I test CUO8 Reactor Water Cleanup Return Flow Transmitter Failure - I test CUO9 Cleanup Regenerative Heat Euanger Leak - I test CU10 Coolant Leak Outside the Primary Containment - I test Cull Thermal Overload Valve (s) Fail (s) To Operate - 3 tests DG01 Diesel Generator Fails To Start - 2 tests DG02 Diesel Generator Breaker Auto-Close Circuit Failure in Auto - 2 tests DG03 Diesel Generator Trip - 2 tests DG04 Diesel Generator Fails to Develop Power (<50KW)- 2 tests DG05 Diesel Generator Voltage Regulator Oscillates in Auto - 2 tests
,D(;06 Diesel Generator Overspeed Trip - 2 tests EDO1 Loss of Offsite Power Sources - 6 tests ED02 Power Grid Frequency Disturbance - I test ED03 Pour Grid Voltage Transient - I test ED04 Power Grid Power Factor Change - I test ED05 Any Transfo. 'nct Cooling Loss - 4 tests ED06 Loss of Any hansformer - 4 tests ED07 Any Bus Auto Tranfer Failure - 5 tests
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ED08 4160 Volt /480 Volt Bus Fault - 14 tests ED09 480 VAC Motor Control Center Fault - 32 tests EDIO 120 VAC Instrument Bus Fault - 3 tests
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i r to NG-95-1017
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March 24,1995 Page 2 of 10' EDil 120 VAC Uninterruptible Bus Fault - I test ED12 250 VDC Distribution Panel Fault - 4 tests j
EDl3 125 VDC Distribution Panel Fault - 7 tests EDl4
+/- 24 VDC Distribution Panel Fault - 2 tests EDl5 125 VDC Charger Failure - 3 tests ED16 250 VDC Charger Failure - 2 tests ED17 24 VDC Charger Failure - 4 tests 7
ED18 Total Loss of 125 VDC System 1 - I test EDl9 Total Loss of 125 VDC System 2 - I test ED20 Essential Bus Slow Transfer - 2 tests ED21 Essential Bus Degraded Voltage - 2 tests EG01 Main Generator Trip - 2 tests EG02 Main Generator Lockout Relay Fails To Actuate - 2 tests EG03 Generator Stator Temperature High - I test EG04 Voltage Regulator Fails High/ Low in Automatic - 2 tests EG05 Generator Field Breaker Fails Open - I test EG07 Loss of Generator Hydrogen - I test EG08 Loss of Seal Oil Pump - 3 tests EG09 Seal Oil Vacuum Pump Trip - I test EGIO Stator Cooling Pump Trip - 2 tests EGil Stator Cooling Water High Conductivity - I test EG12 Loss of Stator Cooling Water Flow - I test FPol Fire Pump Fails to Start - 2 tests FP02 Fire Main Rupture - I test FP03 Smoke and Fire Detection Alarm - 35 tests FPO4 Smoke and Fire Detector Trouble - 35 tests FWOI Condenser Hotwell Level Controller Failure - 2 tests FWO2 Condensate Pump Trip - 2 tests FWO3 Condensate Demineralizer Resin Depletion - 5 tests FWO4 Condensate Filter Demineralizer Resin injection - 5 tests FWO5 Feedwater Hydrogen Controller Failure - 2 tests FWO6 Feedwater Heater Drain Valve Fails - 10 tests FWO7 Feedwater Heater Dump Valve Fails - 12 tests FWOS Feedwater Heater Tube Leak - 12 tests q
FWO9 Reactor Feedwater Pump Trip - 2 tests
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FW10 Reactor Feedwater Pump Mmimum Flow Valve Fails Open - 2 tests FW11 Feedwater Inverter Fails - 2 tests l
FW12 Feedwater Regulating Valve Controller Failure (Auto)- 3 tests FWl3 Master and Feedwater Regulatiag Valve Controller Oscillation - 3 tests FWl4 Feedwater Flow Transmitter Failure - 2 tests FWl5 Condensate Demineralizer Air injection - I test FWl6 Feedwater Regulating Valve Lockup - 2 tests FW17 Main Feedwater Line Break Inside Primary Containment - 2 tests FWl8 Main Feedwater Line Bre:ik Outside Primary Containment - 2 tests FW19 Hydrogen Injection Lea's at Reactor Feed Pumps - 2 tests FW20 Feedwater Break inside Containment - Isolable - 2 tests
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, to NG-95-1017 March 24,1995 Page 3 of 10 FW21 Feedwater Thermal Overload Valve (s) Fail (s) to Operate - 2 tests HP01 High Pressure Coolant Injection inadvertent Initiation - I test HP02 High Pressure Coolant Injection Turbine Trip - I test HP03 High Pressure Coolant Injection Flow Controller Fails - I test HPO4 High Pressure Coolant Injection Flow Controller Oscillation - I test HP05 High Pressure Coolant Injection Steam Supply Line Break (HPCI Room)- I test HP06 High Pressure Coolant injection Pump Discharge Line Break - I test HP07 High Pressure Coolant Injection Inverter Trouble - I test HP08 High Pressure Coolant Injection Steam Supply Line Break (Torus Room)- I test HP09 High Pressure Coolant Injection Exhaust Diaphragm Failure - I test HP10 High Pressure Coolant Injection Thermal Overload Valve (s) Fail (s) to Operate - 3 test IA01 Loss ofInstrument Air - I test IA02 Instrument Air Header Leaks - 4 tes;s LD01 Drywell Leakage - 2 tests LD04 High Pressure Coolant injection Room Leakage - I test LD05 Reactor Core injection Cooling Room Leakage - I test LD06 Southeast Corner Room Leakage - I test LD07 Northwest Corner Room Leakage - I test LD08 Torus Room Leakage - I test MC01 Main Circulating Water Pump Trip - 2 tests MCO2 Main Condenser Tube Blockage - I test MCO3 Cooling Tower Fans Trip - 24 tests MC04 Main Condenser Air Inleakage - 2 tests MC05 Circulating Water Expansion Joint Failure - 7 tests MC06 Steam Jet Air Ejector Condenser Drain Pump Trip - 2 tests MC07 Main Condenser Tube Leakage - I test MC08 Cooling Tower Riser Pipe Break - 4 tests MSol Pressure Averaging Manifold Leak - I test MS02 Steam Leak Inside the Primary Containment - I test MS03 Main Steam Line Rupture Inside Primary Containment - 4 tests MSO4 Main Steam Line Rupture Outside Primary Containment - 4 tests MS05 Main Steam isolation Valve Disc Failures - 8 tests MS06 Main Steam isolation Valve Fails Closed - 8 tests MS07 Main Steam Isolation Valve Slow / Fast Closure Time - 8 tests MS08 Steam Leakage in Steam Tunnel - 6 tests MSO9 Main Steam Line Flow Transmitter Failure - 4 tests MS10 Main Steam Line Pressure Transmitter Failure - 4 tests MS14 Loss of Extraction Steam to Feedwater Heater - 12 tests MSIS Moisture Separator Reheater Drain Tank Drain / Dump Valve Fails - 4 tests MS16 Moisture Separator Reheater Reheat Drain Tank Drain / Dump Valve Fails - 8 tests MSl7 Seal Steam Regulator Fails - I test MS18 Valve CVil58A/B Failure - 2 tests MS19 Spurious Group 1 Isolation - 2 tests MS20 Group I Isolation Valve (s) Fail (s) to Close - 12 tests MS21 Spurious Group 2 Isolation - 2 tests MS22 Group 21 solation Valve (s) Fail (s) to Close - 13 tests
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. to NG-95-1017 March 24,1995 Page 4 of 10 MS23 Spurious Group 3 Isolation - 2 tests MS24 Group 3 Isolation Component Failure (s)- 59 tests MS25 Spurious Group 4 Isolation - 2 tests MS26 Group 4 Isolation Valve (s) Fail (s) to Close - 2 tests MS27 Spurious Group 5 Isolation - 2 tests MS28 Group 5 Isolation Valve (s) Fail (s) to Close - 3 tests MS29 Spurious Group 6A Isolation (RCIC) - 2 tests MS30 Spurious Group 6B Isolation (HPCI) - 2 tests MS3i Group 6 Isolation Valve (s) Fail (s) To Close - 6 tests MS32 Spurious Group 71 solation - I test MS33 Group 7 Isolation Valve (s) Fail (s) To Close - 6 tests NM01 Source Range Monitor Channel Fails - 4 tests NM02 Source Range Momtor Channel Fails, Inoperable - 4 tests NM03 Source Range Monitor Channel Detector Stuck - 4 tests NM04 Intermediate Range Monitor Channel Fails - 6 tests NMOS Intermediate Range Monitor Channel Fails, Inoperable - 6 tests j
NM06 Intermediate Range Monitor Channel Detector Stuck - 6 tests NM07 Local Power Range Monitor Channel Fails - 80 tests NMOS
,, Average Power Range Monitor Channel Fails - 6 tests NM09 Rod Black Monitor Channel Fails - 2 tests NM10 Traversing Incore Probe Detector Stuck - 3 tests NMII Recire Flow Unit Fails - 4 tests NMl2 Recire Flow Unit Oscillates - 4 tests NM13 Recire Flow Comparator Fails - 4 tests NM14 Recirc Flow Comparator Fails. Inoperative - 4 tests NMIS Average Power Range Monitor Fails, Inoperative - 6 tests
$Tay j
NM16 Rod Block Monitor Fails, Inoperative - 2 tests N Th e
OG01 Explosion in the OITgas Piping - I test OG02 Recombiner Closed Cooling Water DifTerential Pressure Indicator Failure - I test OG03 Oligas Isolation - I test OG04 Oligas High Pressure - I test PC01 Primary Containment Leakage - I test PC02 Drvucil Purge Relief Valve Fails Open - I test PC04 Torus-Drywell Vacuum Breaker Fails Open/ Closed - 14 tests PC05 Drvwell Pressure Transmitter Failure - 4 tests PC06 Torus-Reactor Building Vacuum Breaker Fail Open/ Closed - 4 tests PC07 Standby Gas Treatment Fan Trips - 2 tests PC08 Drvwell Cooling Fan Trip - 14 tests PC09 Torus Core Spray / Residual lleat Removal Suction Line Break - 4 tests PC10 Standby Gas Treatment Controller Failure - 2 tests PCll Standby Gas Treatment Heater Failure - 2 tests 1
PCl2 Standby Gas Treatment Charcoal High Temperature - 2 tests PCl3 Break in Discharge Pipe of PSV440x Into the Torus Airspace - 6 tests RCO2 Reactor Core Isolation Cooling Turbine Trip - I test RC03 Reactor Core Isolation Cooling Flow Controller Fails in Automatic - I test RC04 Reactor Core Isolation Cooling Flow Controller Oscillation in Automatic - I test
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< to NG-95-1017 March 24,1995 Page 5 of10 RC05 -
Reactor Core Isolation Cooling Inverter Trouble - I test RC06 Reactor Core Isolation Cooling Steam Sur> ply Line Break (RCIC Room) - I test RC07 Reactor Core Isolation Cooling Steam Supply Line Break (Torus Room) - I test RC08 Inadvertent Reactor Core Isolation Cooling Initiation - I test RC09 Reactor Core Isolation Cooling Exhaust Check Valve Failure - I test RC10 Reactor Core Isolation Cooling Thermal Overload Valve (s) Fail (s) to Operate - 2 tests RD01 Control Rod Drifts Out - 89 tests RD02 Control Rod Blade Stuck - 89 tests RD03 Control Rod Uncoupled - 89 tests i
RD04 Control Rod Rod Position Indicating System Reed Switch Failure (Open/ Closed) 178 tests (89 tests for open. 89 tests for closed)
RDOS Control Rod Slow Scram Time - 89 tests RD06 Control Rod Drives In - 89 tests
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l RD07 Control Rod Accumulator Trouble - 89 tests RD08 Control Rod Scrams - 89 tests RD09 Control Rod Drive Flow Control Valve Failure (Auto) I test RD10 Individual Control Rod Drive Drive Water Filter Clogged - 89 tests RDII Control Rod Drive Hydraulic Pump Trip - 2 tests RDl2 Control Rod Dris e Stabilizing Valve Failure - 4 tests RDl3 Loss of Air Pressure to Control Rod Drive Hydraulic Control Units - I test RD14 Scram Discharge Volume Level High - I test RD15 Scram Discharge Volume Vent / Drain Fails - 4 tests RD16 Scram Discharge Volume Rupture - I test RDl7 Rod Drive Control Timer Malfunction - I test RDl8 Spurious Alternate Rod insertion Actuation - 2 tests RDl9 Control Rod Drive Insert (Drive Pressure) Solenoid Valve Failure - 89 tests RD20 Control Rod Drive Withdrawal (Drive Pressure) Solenoid Valve Failure - 89 tests RD21 Control Rod Drive Insert (exhaust) Solenoid Valve Failure - 89 tests RD22 Control Rod Drive Withdrawal (exhaust) Solenoid Valve Failure - 89 tests RH01 Residual Heat Removal Pump Trip - 4 tests RH02 Residual Heat Removal licat Exchanger Tube Leak - 2 tests RH03 Residual Heat Removal Pump Discharge Line Break - 2 tests RIIO5 Residual Heat Removal / Suppression Pool Suction Line Blo:kage - 2 tests R1106 Residual Heat Removal Heat Exchanger Bypass Valve Failure - 2 tests RH07 Low Pressure Core Injection Loop Select Failure - I test R}{08 Inadvertent Low Pressure Cnre injection initiation - 2 tests RH09 Residual Heat Removal Thermal Overload Valve (s) Fail (s) to Operate - 11 tests RM01 Area Radiation Monitor Channel Fails - 30 tests RM02 Process Radiation Monitor Channel Fails - 22 tests RM03 Process Radiation Monitor Channel Fails. Inoperable - 22 tests RM04 Containment Radiation Monitor Failure - 4 tests RP01 Control Rod Group Fails ;o Scram - 4 tests RP02 Reactor Protection System Electrical Protection Assembly Breaker Trip - 3 tests RP03 Spurious Scram - I test RPO4 Control Rod Group Power Fuse Failure - 8 tests
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. to NG-95-1017 March 24,1995 Page 6 of 10 RP05 Reactor Protection System Scram Circuit Failure (Anticipated Transient Without Scram)- 6 tests RP06 Mode Switch Bank Failure - 4 tests RR01 Recirculating Pump Discharge / Suction Valve Fails in Closed Position - 4 tests RR02 Recirculating Pump Discharge / Suction Valve Fails Closed - 4 tests RR05 Recirculating Pump Shaft Seizure - 2 tests RR06 Recirculating Pump Motor-Generator Drive Motor Break.er Trip - 2 tests RR07 Recirculating Motor-Generator Field Breaker Trip - 2 tests RR08 Recirculating Pump High Vibration - 2 tests RR09 Recirculating Pump Seal Restrictor Orifices Plugged - 4 tests RRIO Recirculating Pump Speed Feedback Signal Failure - 2 tests RRll Recirculating Pump Seal Failure - 4 tests RR12 Recirculating Motor-Generator Oil Pump Failure - 8 tests RR13 Recirculating Loop Flow Transmitter Failure - 8 tests RR14 Recirculating Jet Pump Riser Failure - 4 tests RRIS Recirculating Loop Rupture (Design Basis Loss of Coolant Accident at 100%)- 2 tests RR16 Recirculating Pump Recirculating Pump Trip (RPT) Breaker Trip - 4 tests RR17 Recirculating Motor-Generator Flow Controller Fails, Automatic / Manual Modes
- 2 tests RR18 Recirculating Motor-Generator Scoop Tube Oscillation, Automatic / Manual Modes
- 2 tests RR19 Wide Range Level Transmitter Failure (Fuel Zone) - 4 tests RR20 Narrow Range Level Transmitter Failure (GEMAC) - 3 tests RR21 Yarway Level Transmitter Failure - 2 tests RR22 High/ Low Level Switch Failure (Open/ Closed) - 16 tests RR23 Low-Low Level Switch Failure (Open/ Closed) - 16 tests RR24 Reactor Pressure Vessel Pressure Transmitter Failure - 5 tests RR25 Reactor Pressure Vessel Yarway Reference Leg Leak - 2 tests RR26 Reactor Pressure Vessel Yarway Variable Leg Leak - 2 tests RR27 Reactor Pressure Vessel GEMAC Reference Leg Leak - 2 tests RR28 Reactor Pressure Vessel GEMAC Variable Leg Leak - 2 tests RR29 Recirculating Valves Fail to Reposition - 4 tests RR30 Coolant Leakage Inside Primary Containment - I test RR31 Jet Pump Instrument Line Leakage Inside Containment - 6 tests RR32 Lo-Lo-Lo Level Switch Failure (Open/ Closed) - 16 tests RR33 All GEMAC Reference Legs Flash (Random Oscillations)- I test RR34 Yarway Reference Leg Flashing - I test RWOI Rod Worth Minimizer Failure - I test - DECERTIFIED RX01 Fuel Cladding Failure - I test RX02 Control Rod Worth Change. Any Control Rod - 89 tests RXO3 Core Wide Lasalle Event - I test RXO4 Regional Lasalle Event - I test SLOI Standby Liquid Pump Trip - 2 tests SLO 2 Squib Valves Fail to Fire - 2 tests SLO 3 Squib Valve Loss of Continuity - 2 tests STCSol Core Spray injection Valve Fails to Open - MO-2117 - I test
. to NG-95-1017 March 24,1995 Page 7 of 10 STCS02 Core Spray Injection Valve Fails to Open - MO-2137 - I test 3-STHP01 High Pressure Coolant Injection System Automatic Initiation Block - I test STHP02 High Pressure Coolant Injection Inject Valve Fails to Open - MO2312 - I test j
STHP03 High Pressure Coolant Injection Suction Valve Fails to Auto Transfer MO-2321-1 test l
STNM01 Source Range Monitor Channel A Fails to Trip Inoperative - I test
.t STNM02 Source Range Monitor Channel B Fails to Trip Inoperative - I test STNM03 Source Range Monitor Channel C Fails to Trip Inoperative - I test STNM04 Source Range Monitor Channel D Fails to Trip Inoperative - I test STNM05 Source Range Monitor Channel A Fails to Trip Downscale - I test STNM06 Source Range Monitor Channel B Fails to Trip Downscale - I test
~ STNM07 Source Range Monitor Channel C Fails to Trip Downscale - I test j
STNM08 Source Range Monitor Channel D Fails to Trip Downscale - 1 test STNM09 Source Range Monitor Channel A Fails to Trip Upscale Hi - 1 test STNM10 Source Range Monitor Channel B Fails to Trip Upscale Hi - 1 test STNMI1 Source Range Monitor Channel C Fails to Trip Upscalc Hi - I test STNM12 Source Range Monitor Channel D Fails to Trip Upscale Hi - I test STNMl3 Intermediate Range Monitor Channel A Fails to Trip Inoperative - I test STNM14 Intermediate Range Monitor Channel B Fails to Trip Inoperative - I test STNM15 Intermediate Range Monitor Channel C Fails to Trip Inoperative - I test STNM16 Intermediate Range Monitor Channel D Fails to Trip Inoperative - I test STNMl7 Intermediate Range Monitor Channel E Fails to Trip Inoperative - I test STNM18 Intermediate Range Monitor Channel F Fails to Trip Inoperative - I test STNM19 Intermediate Range Monitor Channel A Fails to Trip Downscale - I test STNM20 Intermediate Range Monitor Channel B Fails to Trip Downscale - I test STNM21 Intermediate Range Monitor Channel C Fails to Trip Downscale - I test STNM22 Intermediate Range Monitor Channel D Fails to Trip Downscale - I test STNM23 Intermediate Range Monitor Channel E Fails to Trip Downscale - I test STNM24 Intermediate Range Monitor Channel F Fails to Trip Downscale - I test STNM25 Intermediate Range Monitor Channel A Fails to Trip Upscale Hi - I test STNM26 Intermediate Range Monitor Channel B Fails to Trip Upscale Hi - I tcst STNM27 Intermediate Range Monitor Channel C Fails to Trip Upscale Hi - I test STNM2K Intermediate Range Monitor Channel D Fails to Trip Upscale Hi - I test STNM29 Intermediate Range Monitor Channel E Fails to Trip Upscale Hi - I test STNM30 Intermediate Range Monitor Channel F Fails to Trip Upscale Hi - 1 test 3
STNM31 Intermediate Range Monitor Channel A Fails to Trip Upscale Hi-Hi - I test STNM32 Intermediate Range Monitor Channel B Fails to Trip Upscale Hi-Hi - I test STNM33 Intermediate Range Monitor Channel C Fails to Trip Upscale Hi-Hi - I test STNM34 Intermediate Range Momtor Channel D Fails to Trip Upscale Hi-Hi - I test STNM35 Intermediate Range Monitor Channel E Fails to Trip Upscale Hi-Hi - I test STNM36 Intermediate Range Monitor Channel F Fails to Trip Upscale Hi-Hi - I test STNM37 Average Power Range Monitor Channel A Fails to Trip Inoperative - 1 test STNM38 Average Power Range Monitor Channel B Fails to Trip Inoperative - I test STNM39 Average Power Range Monitor Channel C Fails to Trip Inoperative - I test STNM40 Average Power Range Monitor Channel D Fails to Trip Inoperative - I test STNM41 Average Power Range Monitor Channel E Fails to Trip Inoperative - I test STNM42 Average Power Range Monitor Channel F Fails to Trip Inoperative - I test
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STNM43 Average Power Range Monitor Channel A Fails to Trip Downscale - I test STNM44 Average Power Range Monitor Channel B Fails to Trip Downscale - I test STNM45 Average Power Range Monitor Channel C Fails to Trip Downscale - I test STNM46 Average Power Range Monitor Channel D Fails to Trip Downscale - I test STNM47 Average Power Range Monitor Channel E Fails to Trip Downscale - I test STNM48 Average Power Range Monitor Channel F Fails to Trip Downscale - I test STNM49 Average Power Range Monitor Channel A Fails to Trip Upscale Alarm - I test STNM50 Average Power Range Monitor Channel B Fails to Trip Upscale Alarm - I test STNM51 Average Power Range Monitor Channel C Fails to Trip Upscale Alarm - I test STNM52 Average Power Range Monitor Channel D Fails to Trip Upscale Alarm - I test STNM53 Average Power Range Monitor Channel E Fails to Trip Upscale Alarm - I test STNM54 Average Power Range Monitor Channel F Fails to Trip Upscale Alarm - I test STNM55 Average Power Range Monitor Channel A Fails to Trip Upscale - I test STNM56 Average Power Range Monitor Channel B Fails to Trip Upscale - I test STNM57 Average Power Range Monitor Channel C Fails to Trip Upscale - I test STNM58 Average Power Range Monitor Channel D Fails to Trip Upscale - I test STNM59 Average Power Range Monitor Channel E Fails to Trip Upscale - I test STNM60 Average Power Range Monitor Channel F Fails to Trip Upscale - I test STNM61 Rod Block Monitor Channel A Fails to Trip Inoperative - I test STNM62 Rod Block Monitor Channel B Fails to Trip Inoperative - I test STPC01 Standby Gas Treatment A Fails to Automatically Initiate - I test STPC02 Standby Gas Treatment B Fails to Automatically initiate - I test STRC01 Reactor Core Isolation Cooling Fails to Auto Start - I test STRCO2 Reactor Core Isolation Cooling Injection Valve Fails to Automatically Open - I test STRII01 Low Pressure Core Injection A Inject Valve Fails to Automatically Open MO-2003
- I test STR1102 Low Pressure Core injection B Inject Valve Fails to Automatically Open MO-1905
- I test STRR01 Recirculating Motor-Generator Set Fails to Start - 2 tests SWOI General Service Water Pump Trip - 3 tests
_S W O2 Stator Water Coolers General Senice Water Flow Blockage - 2 tests SWO3 Recirculating Pump Motor-Generator Set Coolers General Senice Wr.ter Flow
' Blockage - 2 tests SWO4 Main Turbine Lube Oil Coolers General Senice Water Flow Blockage - 1 test SWO5 Reactor Feedwater Pump Lube Oil Coolers General Senice Water Flow Blockage
- 2 tests SWO6 Reactor Feedwater Pump Motor Coolers General Senice Water Flow Blockage
- 2 tests SW37 Electro-llydraulic Control Ccolers General Senice Water Flow Blockage - 2 tests SWO8 F.cactor Building Closed Cooling Water !! cat Exchanger General Senice Water Flow Blockage - 3 tests SWO9 Condensate Pump Motor Coolers General Service Water Flow Blockage - 2 tests SWlo Reactor Building Closed Cooling Water Pump Trip - 3 tests SWII Reactor Building Closed Cooling Water IIcat Exchanger Tube Leak - 3 tests SW12 Emergency Senice Water Pump Trip - 2 tests
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'NG-95-1017 March 24,1995 Page 9 of 10 SW13 High Pressure Coolant Injection Room Cooler Emergency Senice Water Flow Blockage - 2 tests SW14 Reactor Core Isolation Cooling Room Cooler Emergency Senice Water Flow
' Blockage - 2 tests SWIS Emergency Diesel Generator Emergency Senice Water Flow Blockage - 2 tests SW16 Reactor Building Closed Cooling Water /Drywell Equipment Drain Sump Cooler Leak
- I test SWl7 Core Spray / Residual Heat Removal Pump Room Cooler Emergency Service Water _
' Flow Blockage - 2 tests SW18 Control Building Chillers Condenser Flow Blockage - 2 tests J
SW19 River Water Supply Pump Trip - 4 tests SW20 River Water Make-Up Controller Fails - 3 controllers SW21 Well Water Pump Trip - 4 tests SW22 Drywell Cooling Units Well Water Flow Blockage - 14 tests SW23 Offgas Condensers Well Water Flow Blockage - 2 tests SW24 Well Water Load Blockage - I test l
SW25 OITgas Refrigerator Machine Well Water Flow Blockage - 2 tests SW26 Reactor Building Closed Cooling Water System Leak - I test
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SW27 Well Water Pump Co,ntroller Failure - I test SW28 Main Generator H21pmperature Controller Failure - I test SW29 Loss of Cooling to G;nerator H Coolers - 4 tests SW30 Main Plant Intake Cmler Flow Blockage - I test SW31 Control Rod Drive Pump Room Cooler Flow Blockage - 2 tests SW32 Isolated Phase Bus Duct Coolers Plugged - 2 tests SW33 Reactor Water Cleanup Non-Regenerative Heat Exchanger Reactor Building Closed
" Cooling Water Flow Blockage - I test SW34 Residual Heat Removal Senice Water Pump Trips - 4 tests SW35 Steam Tunnel Coolers General Senice Water Flow Blockage - I test SW36 Well Water Break - I test TC01 Main Turbine Trip - I test TCO2 Electro-Hydraulic Control Ilydraulic Pump Trip - 2 tests TC03 High Pressure Turbine Stop Valve Failure - 4 tests TC04 High Pressure Turbine Control Valve Failure - 4 tests TC05 Low Pressure Turbine Stop/ Intercept Valve Failure - 4 tests TC06 Turbine Bvpass Valve Failure 2 tests TC07
. Electro-Hydraulic Control Pressure Transmitter Failure - 2 tests TC08 Pressure Regulator Oscillation - 2 tests TC09 Load Set Failure - I test TC10 Main Turbine Acceleration Control Fails - I test TC)1 Turbine Runback Failure - 2 tests TCl2 Electro-Hydraulic Control Fluid Header Leak - I test TCl3 Electro-Hydraulic Control Pressure Reference Summer Failure - 2 tests TU0I Main Turbine Bearing High Temperature - 10 tests TUO2 Main Turbine Bearing High Vibration - 10 tests
_TUO3 Emergency Bearing Oil Pump Trip - I test
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~I March 24,1995 Page 10 of 10 TUO4 Main Turbine Bearing Oil Pressure Decrease - 1 test TUOS Turning Gear Oil Pump Trip - I test TUO6 Main Shaft Oil Pump Failure - I test TUO7 Motor Suction Pump Trip - I test TUOR Main Turbine Lube Oil Tank Level Increase - 2 tests TUO9 Loss of 125 VDC to Emergency Bearing Oil Pump - I test TUll Exhaust Hood Spray Valve Fails - 2 tests YC01 Plant Process Computer Failure - I test i
e to NG-95-1017 March 24,1995 Page 1 of 2 SURVEILLANCE TEST PROCEDURES TO BE TESTED PROCEDURE TITLE 410A001-CY Control Room Positive Pressure Test 410B004-CY Remote Shutdown Panel Functional Test 41 A009-Q Main Steam Isolation Valve Functional Test 41 A0l l-W Weekly Manual Scram Instrument Functional Test 41 A012-CY Mode Switch in Shutdown - Instrument Functional Test 41A028 Reactor Protection System - APRM to IRM Comparison on Controlled Shutdowns 42A001 Daily and Shill Instrument Checks 42A003-CY PCIS Group 7 Logic System Functional Test 42A009-CY PCIS Group 2,3, and 4 Isolation Logic System Functional Test 42A030-CY Standby Gas Treatment System and Reactor Building Isolation Logic System Functional Test 42C004 SRM/IRM Detector Not in the Startup Position Functional Test 42C006-Q Quarterly APRM Flow Bias Instrument Functional Test 42D008 Offgas System Isolation and Charcoal Bed Bypass Valve Logic System Functional Test 42D009-Q Main Steam Line Radiation Monitor Functional Test 42F007 APRM Gain Adjust Calibration 43A002 Control Rod Exercisc 43A005 Control Rod Coupling Integrity Check 43B007 Scram Discharge Volume Valve Time Quarterly Test 43C002 NUMAC RWM Operability Test 42C003 RWM Inoperative Verification 43F001 Two Loop APRM/LPRM Baseline Noise Determination 43F002 Two Loop APRM/LPRM Noise Monitoring 43F003 Single Loop Base Line Noise Determination 43F004 Single Loop Operation Procedure 43F005 Extended Region Single Loop Operation Procedure 44 A002-CY SBLC System Manual Initiation. Explosion Test, and Relief Valve Test 45A001-Q Core Spray System Quarterly Operability Tests 45A002-Q LPCI System Quarterly Operability Tests 45A007-A Core Spray System Simulated Automatic Actuation 45C001-Q RIIR Service Water Operability Test 45D001-CY llPCI System Cycle Operability Tests 45D001-Q HPCI System Quarterly Operability Test 45D003-A HPCI System Simulated Automatic Actuation 45E001-Q RCIC System Quarterly Operability Test 45G002 Standby Diesel Generators Daily Operability Test 45J002 River Water Supply System Operability Test 45J002-Q River Water Supply and Screen Wash System Quarterly Vibration Measurement And Operability Test 4
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46A003 Heatup & Cooldown Rate Log 46A004 Recirc Pump Start Temperature Recording 46D004-CY Manual Opening and Exercising of the ADS and Two LLS Relief Valves i
46E001 Daily Jet Pump Operability Test 46E001-SLO Daily Jet Pump Operability Single Loop Operation 46E002 Jet Pump Operability Baseline Data 46G033-CY Main Steam Isolation Valves Trip / Closure Time Check - Refueling 46G034-CY LPCI Inject Check Valve Full Flow Test 47B009-Q PCIS Valve Functional Test 478010-Q MSIV Trip / Closure Time Check 47D012-CY Mechanical Vacuum Pump Trip and Isolation Logic System Functional Test 47E003-M Drywell-Suppression Chamber Vacuum Breaker 47J001-CY Secondary Containment Integrity 47 LOO 4-A Standby Gas Treatment System Bypass Cooling Test 48A001-M Standby Diesel Generators Monthly Operability Test 48A001-Q Standby Diesel Generators Quarterly Operability Test 48A001 SA Standby Diesel Generators Semi-Annual Operability Test 498001 Core Alterations - Core Monitoring Source Range Monitor Daily Response Check -
BS-01 ASME In-Service Valve Test (Cold Shutdown)
BS-02 ASME In-Service Valve Testing (Quarterly)
BS-18 ASME CRD Accumulator Check Valve Test NS 13 Col 2 Charcoal Bed Deluge Systems Functional and Air Flow Tests NS 13E015 Secondary Containment Test NS-13G005 Low Pressure Coolant Injection (LPCI) Swing Bus AC and DC Undervoltage Transfer Cyclic Test NS-70001 Valve Test NS 93001 Main Turbine Operational Tests NS-93002 Bypass Valves Monthly Test q
NS-93003 Main Turbine Overspeed Trip System Tests NS-99301 Control Room Panel Shiftly Checklist r
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