ML20072R226
| ML20072R226 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/20/1991 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20072R225 | List: |
| References | |
| NUDOCS 9103220310 | |
| Download: ML20072R226 (344) | |
Text
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WATERFORD-3 PLANT REFERENCE SIMULATOR CERTIFICATION PACKAGE Entergy Operations, Inc. fbg32$83c0obO$hj2
I t r WATERFORD 3 PLANT REFERENCE SIMULATOR f CERTIFICATION PROGRAM DESCRIPTION < k O COffENTS l
1.0 INTRODUCTION
2.0 GENERAL SIMULATOR.INFORMATION i 3.0 SIMULATOR CONTROL ROOM i 4.0 INSTRUCTOR INTERFACE : 5.0 CERTIFICATION PERSONNEL I APPENDICES A. ANSI /ANS 3.5 - 1985 CHECKLIST JUSTIFICATION OF MAJOR EXCEPTIONS B. SIMULATOR CONTROL ROOM / PLANT CONTROL ROOM LAYOUT ' MINOR HARDWARE EXCEPTION LIST ! C. PERFORMANCE TEST LIST ' PERFORMANCE TEST EXAMPLES ! D. PERFORMANCE TEST ABSTRACTS E. CERTIFI' CATION DISCREPANCIES AND SCHEDULE OF RESOLUTION I t
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1.0 INTRODUCTION
.The simulator certification plan was written to plan and !
document compliance with Reg. Guido 1.149 and ANSI /ANS 3.5 - 1985. It will also document Waterford 3 meeting the requirements of 10 CFR 55 for a simulation facility consisting solely of a plant referenced simulator. 2.0 GENERAL INFORMATION The Waterford 3 Steam Electric Station Plant Reference r Simulator was built by the Singer / Link Co. (S3 Technology) and is owned by Louisiana Power and Light Company and operated by Entergy Operations Incorporated. On sito acceptance testing was completed and the sjmulator was declared ready for training June, 1987. The Waterford simulator was designed based on the Waterford 3 Steam Electric Station control room. Waterford 3 is a single unit Combustion Engineering pressurized water reactor _ ' rated at 3410 MWt and 1104 MWo which was declared commercial September 24, 1985. 3.0 SIMULATOR CONTROL ROOM The Waterford 3 simulator control room consists of the main (~'T. "L" shaped control boards along with those extra auxiliary (/ boards doomed necessary for training. Layouts of the plant and simulator control rooms are contained in Appendix B. All panels included in the simulation occupy the samo . positions as in the actual control room. One panel, CP-12, which was located Jn a auxiliary bank of control panels has been moved to a position behind the main control panels. ' The Waterford 3 simulator also includes the. remote shutdown panel LCP-43. All of the hardware provided on the simulator control panels is functionally simulated with the exception of the Containment Personnel / Escape Air Lock which is present but not modeled.- The Plant Monitoring Computer is a hybrid stimulated / simulated model and uses the same data base and display programs to provide the same information as in the e plant. The Qualified Safety-Parameter Display System (QSPDS) and the Radiation Monitor Display system are functionally simulated. The design of the simulator control room duplicates, as exactly as possible, the real control room's appearance while standing at the main control boards. The operator's desks, computer consolos, along with the shift supervisor and control room supervisors office are included. The i7 V ') lighting, flooring, and wall materials duplicato the
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- original material in the control room. All of the room furniture and consolos are duplicates of the actual control ,
room and occupy the same positions. The rear wall opposite ; the main control boards has been modified to accommodate the i Instructor station and a visitors viewing area. Cameras and audio microphones have been added to the simulator control l l room as aids for use in training exercises. j All communications systems in use in the control room also a are functionally duplicated in the simulator. Those audible cues which were determined to be discernable in the real , control room have been audio synthesized for the simulator. 4.0 INSTRUCTOR INTERFNCE ' The. instructor station is located behind the wall cpposite the main panels and-is separated from the control room by i one-way glass windows. The instructor station houses the , two instructor consoles and allaof the communications equipment necessary.to conduct training exercises. The instructor-station-also contairr TV monitors and-recording , equipment to record training exercises.
.The-instructor console contains all of the controls-and indication necessary to conduct training using the exercise guides developed by the training department along with many additional control functions used in staging Emergency Plan drills using the simulator.
[} i INITIAL CONDITIONS The simulator.has 100 initial conditions with two reserved for the operating system. Of the 98 remaining ICs for instructor use, the first 35 are password ; protected for use-in training and examinations. The-rest of the ICs are used for software and scenario development. REMOTE FUNCTIONS Over 600 remote functions are presently available on ?
- the Waterford simulator. These functions serve as duplicate controls for much-of the plant-equipment outside o' the control room. Using these remote <
functions the instructor can operate the remote areas of.the plant in a realistic manner to simulate the functions of the auxiliary operators. Additional , -remote functions are. continuing to be added as-training requirements develop. 4 O
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-- MALFUNCTIONS The simulator has over 350 malfunctions available for use in the training scenarios and operator testing.
These malfunctions singly or in combination provido the abnormal and emergency conditions used on the simulator. Additional malfunctions can be added as training noods dictato. OTilER FEATURES The simulator is equipped with the features to freeze Jimulation, backtrack, and operate the simulator in slow timo. Some models of the simulator can operate in a fast timo mode as necessary. 6
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5.0 CEWTIFICATION PERSONNEL () Experience Highlights of personnel who participated in the certification of the Waterford 3 Simulator. Entergy Operations, Inc. Personnel Wayne L. Smith
. Nuclear Industry Experience - 26 years
. Navy - 12 years
. Commercial - 14 years
. SRO License at Waterford 3
. Waterford 3 - 14 yeara
. Shift Supervisor
. Simulator Supervisor
. Current Position: Supervisor - Nuclear Simulator Training Dennid E. Barr
. Nuclear Industry Experience - 12 years commercial
. B.S., M.S. Nuclear Engineering
. STA at Brown's Ferry Nuclear Plant, TVA
. Waterford 3 - 2 years
. Current Position: Senior Engineer - Nuclear Simulator Training William A. Lowrance
. Nuclear Industry Experience - 14 years commercial
. B.S. Nuclear Engineering
. B.S. Electrical Engineering
. Waterford 3 - 12 years
. Current Position: Senior Engineer - Nuclear Simulator Training O
Glenn M. McDougald
. Nuclear Industry Experience - 11 years commercial
. Waterford 3 - 11 years
. Current Position: Senior Specialist - Nuclear Simulator Training R2 L. Ciminel
. Nuclear Industry Experience - 27 years
. Navy - 7 years
. Commercial - 20 years
. SRO License at Beaver Valley Power Station
. SRO Certified Simulator Instructor on the Sequoyah and Vogal PWR Simulators
. SRO License-at Waterford 3 NSSS
. Waterford 3 - 3 years O . Current Position: Senior Instructor - Nuclear Mark D. Phillippe
. Nuclear Industry Experience - 21 years commercial
. RO License at TMI 2
. Waterford 3 - 8 years
. Various positions in Quality Assurance and Operations Support and Assessment
. Current Position: Senior Engineer - Operations Support and Assessment O
- . _ _ _ _ =- . -- .. - - _ _ _ _ _ _ _ . - - - _ ___
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. Paul' Sicard.
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.' Nuclear: Industry Experience - 8 years commercial ,
. B.S. Nuclear Engineering
. M.E. Nuclear Engineering
. B.S. Physics i
. M.S. Mechanical
. Waterford_3 --3 years-
. Current Position: Engineer III - Safety and Engineering Analysis
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' Contract: Personnel - Interfacts,!Inc., Columbia, Maryland
-The following contract personnel were used as Performance.
TestLOperators.-to perform the certification performance testing.= l
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/H. C.- Crummy.
. Nuclear Industry' Experience 24:: years.
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- c Navy -'8Lyears "
s -. Commercial .16 years _
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1 SRO' ; Virginia Electric-& Power Company,.Surry Plant , '. Participated in performanceotasting of the Comanche Peak Power Station >as part.of~the NRC Form 474 certification process
. Waterford.3 - 5 months.as a Performance Test' Operator X, as part of-the NRC Form 4474 -
certification process x i I NO; . i '; - s.,-.-_ ,; .._.,_; . . - . , ....s . _ _ _ _ . - ,
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1 a't . j'p M1ke'Asher f
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-. Nuclear Industry Experience - 24 years
. Navy - 6~ years
.. Commercial - 18 years
. RO Arkansas Nuclear 1, Unit 1
. . SRO Arkansas Nuclear 1, Unit 2-Contract Instructor on Shearon Harris Nuclear Plant
- and Crystal River Nuclear-Plant Simulators.
. Waterford-3' 5 months as a Performance Test Operator i
as-part of the-NRC Form 474 ;
, certification process. ~
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-i George-M.-Vaux, Jr. ,
e , Nuclear Industry-Experience - 27 years
. Navyf--7fyears u,; .- . Commercial -:20 years =
. -SRO St. Lucie Nuclear Plant '
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-: . On-Shift _EngineeringlAdvisor at V.C. Summer Nuclear ;
Power Plant and-St.:Lucie Nuclear Plant. _t m -. - Waterford"3:-15 months as a Performance Test-Operator.
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as part of?the NRC' Form 474 -! certification process. 1
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I u' i l: i.- ~ APPENDIX A L ANSI /ANS 3.5 - 1985 CllECKLIST JUSTIFICATION OF MAJOR EXCEPTIONS 1 I (' i, j 1 1 I
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I APPENDIX A
<~s ANSI 3.5 1985 SIMULATOR CERTIFICATION CHECKLIST CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION Section 3.1 A. The response of the simu- YES Performance testing on lator resulting from the Waterford 3 Plant operator action, improper Reference Simulator has operator action, automat- been conducted from June ic plant controls, and 1990 through February inh ent operating char- 1991. The total simula-acter:stics shall be tor response to a variety realistic to the extent of malfunctions, tran-that within the limits of sients, t .irmal and emor-the performance criteria gency operator actions (Section 4, Performance was testsd and the re-Criteria) the operator sults are listed in the shall not observe a dif- test abstracts contained forence betwoon the re- in Apper. dix D. Roselu-sponse of the simulator tion of those responses control room and the not considered reallotic
(\ reference plant. to the reference plant is scheduled in Appendix E. Section 3.1.1 A. The simulator shall be YES NTI-602, Normal Opera-capable of simulating tions Test was designed continuously, and in real to take the simulator time, plant operations of from cold conditions up the reference nuclear through 100% and return plant, to cold conditions using the plant procedures as guidelines. NTI-601, Computer Real Time Test, was used to determine that the models of the simulator are operating in real time. A-1
APPENDIX A ("%g ANSI 3.5 1985-SIMULATOR CERTIFICATION CHECKLIST CONFORM SUPPORTING REQUIREMENT -(Y/N) DOCUMENTATION B.- The simulator-shall cal- YES Any discrepancies or culate plant system pa - problems resulting from rameters corresponding to the performance testing particular-operating of the simulator are conditions,-display these listed along with the parameters on the.appro- schedule of resolution in priate instrumentation, Appendix E. and provide proper alarm ; or protective system action, or both.
- C. The minimum evolutions that the' simulator shall be< capable: of performing, using only operator ac-tion. normal,to the refer-ence-plant are as fol-lows:
- 1. : -Plant startup - cold YES NTI-602, Normal Opera-
[~'Y. to hot standby. The tions Test took the simu - (_I_ starting. conditions lator from cold condi-shall be cold' shut-- tions up to hot
- standby down condition'of using-the plant proce-temperature and dures as. guidelines. '
pressure. Removal of,the reactor-ves-sel head is not a required condition for simulation.
-2.- Nuclear startup from NO 'The simulator was_taken-
~ hot standby to rated from hot standby to rated -- i power. power using NTI-602, l L Normal Operations Test.
L- However, equilibrium xenon conditions could not be achieved.. A prob-~ lem report has been writ-- ten and scheduled for-work. The schedule for completion of this test is included.in Appendix E. R A-2 1 4
APPENDIX A
-g g ANSI 3.5 1985 SIMULATOR OERTIFICATION CHECKLIST \-) CONFORM- SUPPORTING REQUIREMENT- (Y/N) DOCUMENTATION
- 3. Turbine startup and YES NTI-602, Normal-Opera-generator synchroni- tions Test performed a t zation. .
turbine startup and gen-- erator synchtonization - using-the plant proce- ; dures as guidelines.
- 4. Reactor trip-fol- NO NTI-604.01, Manual Reac-lowed by recovery to tor Trip tested plant-rated power. -response to a reactor trip. Recovery to rated power was not a part of the test. NTI-602, Nor-mal Operations Test, started the-simulator up from shutdown. NTI-601.-
11, Reactor Trip'Followed j . by Recovery to Rated
- Power, will be written : '(- and testedito check plant startup;at peak. xenon conditions. A schedule of completion is listed ~
in Appendix _E. S. Operations at hot. YES The transient test,;NTI-standby. 640.07,1MS-Line Break at HZP and several malfunc-
.tions are designed:to.be- ,
used at hot-standby. l 6. . Load changes.- YES NTI-604.07, Maximum Rate Power hamp demonstrates extreme load: changes at h power. l
APPENDIX A ANSI 3.5 1985 SIMULATOR CERFIFICATION CHECKLIST O CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION
- 7. Startup, shutdown NO Waterford 3 Technical and power operations Specifications do not with less than full allow any power opera-reactor coolant tions with less than full flow, reactor coolant flow. An exception will be taken for this event.
- 8. Plant shutdown from YES NTI-602, Normal Opera-rated power to hot tions Test took the simu-standby to Cooldown lator from rated power to to cold conditions, hot standby to cooldown to cold conditions using the plant procedures as guidelines.
- 9. Core performance NO The plant heat balance is testing such as performed as a part of plant heat balance, NTI-602, Normal Opera-G. determination of tions Test and NTI shutdown margin, and 3.03, 100% Accuracy Test.
measurement of reac- NTI-650.04, Isothermal tivity coefficients Temperature Coefficient and control rod Test measured one of the worth using perma- reactivity coefficients, nontly installed The other core perfor-instrumentation, mance tests are included in the NTI-650 series. The schedule for comple-tion of those' tests is included in Appendix E.
- 10. Operator conducted YES The series NTI-645 and-surveillance testing NTI-647 were developed to on safety-related perform the plant safety equipment or sys- related surveillance tems, testing. Some of the tests in that series have not been performed. A schedule for their com-pletion is included in Appendix E.
A-4 I
APPENDIX A rS ANSI 3.5 1985 SIMULATOR CERTIFICATION CHECKLIST CONFORM SUPPORTING REQUIREMENT {Y/N) DGCUMENTATION SECTION 3.1.2 A. The deterrination of the YES Waterford 2 training type and number of mal- programs have been ac-functions to be simulated credited by the National should be part of.a sys- Academy for Nuclear Trai-tematic process for de- ning. These training signing performance- programs are evaluated based operator training biennially as per NTP-011 curricula. The malfunc- " Training Program Evalua-tion assessment process tion" and problems /chan-should utilize ges documented and re-solved as per NTP-004
- 1) Licensee Event Re- " Training Requests".
ports (particularly These training requests like-plant) are analyzed as per NTP-008 " Job analysis" for
- 3) Probabilistic Risk their impact prior to
-Assessment studies resolution. Simulator malfunctions are present
(__ i 3) NSSS and BOP manu- for all tasks identified s_) - facturer equipment as simulator training availabili- items, ty/ro11 ability data and technical infcr-mation service bul-letins
- 4) ' Local site consider-ations and plant-specific operating
. experiences.
- 5) NRC bulletins and circulars L ^~
1 1
APPENDIX A
- f(~$i ANSI 3.5 1905 SIMULATOR CERTIFICATION CHECKLIST
_ . CONFORM SUPPORTING
' REQUIREMENT (Y/N) DOCUMENTATION B.- -The simulator 1shall be YES The simulator has over capable of simulating inL 350 malfunctions modeled ;
real-time abnormal-and to perform a variety of l emergency events-includ- real time abnormal and '
.ing malfunctions to dem- emergency events, onstrate inherent plant -
response and automatic plant control functions.
.C.- Each type of_ accident NO All of the events-: listed analyzed in the reference in Chapter 15 of the plant: safety analysis Updated Final Safety
; report-that.results in Analysis Report can be observable indications on performed on the simula-Econtrol room instrumenta- tor as: malfunctions or as tion-and for-which the- a combination of: remote simulator..is determined. functions-and instructor Lto.be appropriate for- overrides.- The perfor-
' training shall'be.simu- mance tests. designed to-
;(, ;) . lated. . duplicate-the:FSAR acci-A' dent conditions were all' '
determined to be unsatis-factory. A schedule _for the rewrite _and rerunning of these tests is includ-ed in Appendix E. . D. Where the operator ac- -YES Those malfunctions that tic *ns i are a function of were determined by a the degree of severity,of systemacic analysis of, the malfunction (e.g.,. the operator training
-loss of. condenser vacuum, ' curriculum to requira
, steam line. break,-loss of- adjustable rates of se-Ecoolant,: degraded feed; verity-have'that-capabil- ;i 4 water;-flow, etc.), the- ity.- Additional adjust-
-simulator shall-have able severity malfunc-adjustable rates for the -tions are added as: train-malfunction of'such a ing needsLdictate.-
irange to represent the' plant malfunction. lg A-6 L g It O
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APPENDIX A ANSI 3.5 1985 SIMULATOR CERTIFICATION CHECKLIST
-]
' >/ COh/ORM SUPPORTING REQUIREMENT- _, __
(Y/N) DOCUMENTATION-E.- The remaining _ events YES .The simulator.has modeled-shall consist of-a vari- a large number of mal-ety-of malfunctions asso- functions above the ones-clated with the electri- listed in this section. cal,' auxiliary, enginee-- These malfunctions are red _ safety features sys- spread through nearly all tems,-_ steam systems, of the simulator models. reactor coolant system and instrumentation and control systems. The Malfunctions listed-below-can be cross refer- - enced-to the Performance-Test using Appendix C. Those pa1 functions noted with-(T) have not com-pleted testing.- The
' schedule for completion 1
/5p F.- 'The' malfunctions listed is included in Appendix
\_/ below shall-be included: E.
- 1. . Loss of coolant-a) -Significant-PWR YES SG01 steam generator
--leaks b) -Inside and. YES CV14, CV15, CV16, RC25i outside primary-containment ,
c). Large and small YES' --RC23i , RC24i-reactor; coolant-a breaks-includ-ing demonstra-tion of:satura-tion condition d) Failure of =YES RC11, RC12i safety and relief valvesi r i
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.h APPENDIX A ,
(N:l- ANSI'3.5 1985 SIMULATOR CERTIFICATION CHECKLIST- ' CONFORM SUPPORTING -r
, ' REQUIREMENT' (Y/N) DOCUMENTATION
=2)- Loss of instrument YES IA01, IA02, IA03 i , IA04, '-
air to the' extent- IA05 that the whole sys- ' tem or individual - headers can, lose ' pressure and affect the--plant's-static or. dynamic perfor-RidnCe 3); Loss.or' degraded electrical power to the statien,-includ-ing a) Loss ofLoffsite VES ED01
-power:
~
- b)-- Loss 7of emer- YES ED10
, i gency power-
; k. n-c ,' Loss of emer - YES- EG08, EG09, LEG 10,'EGil gency genera -
tors g . d ) .- Loss oftpower- YES ED02, ED04,.ED05, ED06, to the; plant's. ED07 electrical: dis-tribution' buses e)- -Loss of power-YES ED09-tosthe:indi-
-vidual instru-L mentation buses ll ..(AC as-well'as DC) that-: pro-
-vide power to ,
~ Control?' room '
indication or
- plantTcontrol~
functions af-fectingLthe plar' s~:respo-
- nse. .
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AP'PENDIX A v /7-? -' ANSI 3 5 1985iSIMULATOR CERTIFICATION CHECKLIST fij: : REQUIREMENT' T ON - 4)' Loss _of forced core ,_ YES RC01,.RC03, RC04, RC05,- coolant flow due to RC08, RC09 single.or multiple-i pump' failure. ' ' 5): Loss-of condenser YES CWD1, FW10, FW14,--FW21i vacuum including of condenser level Control.
- 6) . Loss _of service YES TP01, TPO4, TPOSi ,i TP06i-water..or cooling.to -!
Lindividual compo- ' nents. 17 )- Loss'of. shutdown- YES CC07, SIO4, SIO8,-Sill cooling.- _ 8) Lossiof component. YES CC01, CCO2, CCO3, CC05
.. cooling system,or.. CC06, CC07, CC08, CC09I ,-
b cooling: to -individu - . CC12, CC15 CC16, CC17~, ' al' components.: CC18, CC19I, CC21-t q. 9)- LossLof normal feed- YES FWO1 ;
} water;or normal: FW12I,FWO3, FWO4,-FWO8,
--FW19,KFW20, RXO4- 2 0/ '
feedwater-system-Tfallure. 10)-~ Loss.of all feed-. YES ' FWO6,'FWO7i water ~(normal and emergency).
- 11) . Loss ofs protective.
YES' PW0 l ', PWO2,-~PWO3, PWO6
-system channel.
12 ) '. Control rodifallure - YES RD01 RD02, RD05i ,-RD06 RD08I k RD02,fRD10, RD11;,.
._ including stuck:: ,
; rods',' uncoupled RD12,_RD13T, RD14,.RD21
. rods, driftingsrods, Waterford 3 takes an ex- -
-and" misaligned rods. ' ception'on thenmalfunc-tion:for; uncoupled-rods.1 Similar plant experience has demonstrated-that-the -
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APPENDIX A ANST 3.5 1985 SIMULATOR CERTIFICATION CHECKLIST
b CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION uncoupled rod is unde-tectable for permanently installed instrumenta-tion.
- 13) -Inability to, drive YES RD03, RD04 control rods.
- 14) Fuel cladding fail- YES CR01 ure resulting in high activity in reactor coolant or- '
off gas and the associated high radiation alarms.
' 15 )- Turbine trip. NO A specific malfunction does-not exist presently for a turbine trip. Many. ,
other malfunctions, as a
. (~ y consequence, wil1~cause
( _,A the turbine to-trip. ~ A specific malfunction will be developed and NTI-635.06 will.be writter, for testing.l A_ schedule forLresolution will be included in Appendix E. 16): ~ Generator trip. YES EG03i , 17); Failure in automatic YES MSO4 i ,.MS05, RC1]i, RP06, control systems that RP07,;RX01,'TC01T-affect reactivity and core heat-~remov-al . -
-18)- Failure'of reactor' YES CV01, CV02,-CV03, CV05 P coolant pressure / . R C 1 4 ,-- R C 1 5 , RXO7Y-
_CV06 l volume control.sys- RXO8 Y , RX10, RX11, RX14Y tem.
- 19 )- Reactor trip. YES RP03 l [Jb A-10 .t
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,~ - APPENDIX A J /~i- ANSI 3.5 1985 SIMULATOR CERTIFICATION CHECKLIST -
Q 5
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CONFORM SUPPORTING
. REQUIREMENT- (Y/N) DOCUMENTATION-
- 20) Main steam line=as- YES- FW36, FW37,--FW383'MS11, well as. main feed- MS12, MS13, MS21 _;
line-break:(both-
'inside and-outside containment), ,
a
- 21) Nuclear instrumenta- YES NIO1, NIO3, NIO5 i, NIO7,
-tionifallnres. J
- 22) Process-instrumenta - YES EG04 : EGOS, EG07, EG18,J tion,-alarms, and- EG19 ,-MS09
,RC16f,MS10,MS22,.
control-system fail- -PC01 RC]8,-RC19,: A ures. . -RC20,:RC21i-RC22T, RX05,- RXO9,-SG04,;SG05, SIO1 . L23) Passive malfunctions YES CS02,-RPO4,RP05,FW29.I i in systems,wsuch as FW30-engineered safety : features', emergency. 5%,)
~) feedwater syctems. -
\
RD24','RP02-24);iFa11ure:of theJauto . YES matic reactor;tripi : h system. components. :
-25). Reactor-pressure YES ~ RXO7i , RX 10 --. ,
< control. system' fail--
ure. cG. "The-response ofkthe simu- YES 'TheEPerformance: Test's ' {1atoreshallibetcompared were: evaluated by?the 3 lto' actual plant-response- Waterfordf3JNuclear Oper-
-or.bestLestimate: plant'.
fations/ Engineering Groupf c response:z-( see : section } 4, - using plant data, best ,
-performance-. criteria).
~
estimate dataTif avail -
~
able, and? tabletop.analy-
- sis ~by; operations experi =
enced personnel. NTI-601,_. Computer.Real Time': Test, Li was reviewed by simulatorz . personnel.- VIk A-11
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APPENDIX A ANSI 3.5 1985 SIMULATOR CERTIFICATION CHECKLIST g ~3 ' '/ ' CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION H. Comparing simulator re- YES Best Estimate analysis sponse to safety analysis has been obtained for may show significant that date for which there discrepancies which shall is no plant data for-be resolved based on best reference. This Best estimate results. Estimato data will be refined further during the Annual Performance Testing and will be used to compliment or replace the tabletop analysis by operations experienced personnel. I. Where applicable to the YES The simulator has a vari-malfunction, the simula- oty of both recoverable tor shall provide to the and nonrecoverable mal-operator the capability functions as determined of taking action to re- by the systematic analy-
, cover the plant, or miti- sia of operator training.
( ) gate the consequences, or x/ both, J. -The simulation shall be YES The Waterford 3 simulator capable of continuing demonstrates this capa-such time that a stable, bility several times each controllable.and safe year while being used for condition is attained Emergency Plan drills and which can be continued to annual exercise. These cold shutdown-conditions, drills / exercises range or until the simulator from 4 to 6 hours in operating limits (4.3 length and the annual . Simulator Operating Lim- exercise is observed by its) are reached. the NRC. ,m ( \ A-12 %)
i APPENDIX A
~
ANSI 3.5 1985 SIM!1ATOR CERTIFICATION CHECKLIST I' ') CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION SECTION 3.2.1 A. The simulator shall con- YES Appendix a contains tain sufficient opera- floor plans of the simu-tional panels to provide lator and actual control the controlc, instrumen- rooms. Those panels tation, alarms, and other determined by a review of man-machine interfaces to the training curriculum conduct the normal plant as being required are evolutions of 3.1.1 (nor- included. mal plant evolutions) and respond to the malfunc-tions of 3.1.2 (Plant Malfunctions). B. The control panels and YES __ Every effort was made to consoles that are simu- duplicato as exactly as lated shall be designed possible, the arrangement to duplicate the size, of the control panels.
, shape, color, and config- The only planned excep-((_/') uration of the function-ally simulated hardware tion is CP-12. CP-12 contains the excore of the reference plant, channels and the reactor There may~oe devictions regulation system drawers in dimensions and arrang- and is located with the ements of panels provided auxiliary panels in the these deviations do not rear section of the plant detract from training, control room. Since the-rear section of the plant control room and the auxiliary panels are not simulated, these panels have been moved to the edge of the simulated panels. The configura-tion of the plant control room and the simulator-control room is contained in Appendix B. All devi-ations on size shape and color are listed along with the discrepancies in Appendix B.
( ). A-13
k
-APPENDIX A j-s ANSI 3'.5'1985ESIMULATOR-CERTIFICATION CHECKLIST
<( ).
CONFORM SUPPORTING
-REQUIREMENT (Y/N) DOCUMENTATION SECTION-3.2.2' -
A . -- TheLcontrois on panels YES The identical controls and consoles that,are from the plant control simulated shall-be de- room were used in all signed to duplicate the instances except when the size, shape, color, and part was out of manufac-configuration of the ture. In those cases, functionally simulated the most similar compo-hardware of the. reference nent available-that per-plant. formed the same_ function was used.- The-minor deviations in-size, shape,-or color are list-ed in Appendix B. B., Consideration should be YES All meters,1 recorders, given to face-front simu- lights, and switches on
/5 ~1ation-of hardware compo- the simulated panels are k_ T nents located on simulat- . functional (with the ex- ,
ed panels-butinotLused by ception of the person-the trainee.during, train- nel/ escape airlock indi-ing. All functionally. :cators which are present-simulated and: visual.ly but unlit) zand can be . simulated hardware shall' operated by the simu-replicate that in the. lation models or by the reference plant-control instructors using instru-
. room.- ment 1 overrides.
LC. There may beLdimensional YES- No components-orJinstru-deviation 11n<the configu-mentation on the simula-
~. " ration of components =and tor have been: knowingly-
-instrumentation,-provided moved to-a. panel location:
u
.these deviations do not
- Impact on_ actions 1to be other than that-in1 the reference-plant. Very.
takeniby-the operator. minor deviations may have occurred'during-cutout and installation of the-components. I^
/N Q) A_14
-. -- ~ . . . _ - - ... - --. -
Y APPENDIX A W- ANSI 3.5 1985 SIMULATOR CERTIFICATION CHECKLIST l ^ CONFORM SUPPORTING. REQUIREMENT- (Y/N) DOCUMENTATION 4
- D. Plant information shall YES The plant monitor comput-be' displayed to the oper- er is a hybrid stimulat- ,
ator in the'same form and ed/ simulated system on
- units that are available the simulator. All dis-in the reference plant. . plays generated by the Meters,-recorders, swit- simulator plant computer ches,-annunciators, con- program are identical to trollers, plant computer that of the reference
-interface hardware,-and plant.- Periodic updates other' components or dis- of the display program plays that would function insure that the displays during normal, abnormal, are accurate. :The QSPDS and-emergency evolutions and Radiation Monitor shall be. included in the Displays are simulated simulator.. and any discrepancies will be noted in Appendix E with a schedule of resolution.
SECTION 3.2.3 A. Consideration ~shall-be- YES The wall coverings,.floo-given~to simulating as ring, lighting, desks, much of the control' room and office areas are environmont as is reason- identical to the refer-able and practical, for ence plant. Minor dif-example,. turbine noise, forences'in the back wall control rod step counter were made to. allow for noise, flooring, obstruc- the instructor station
- tions'and lighting, and-a viewing area.to be.
Installed. Also cameras and audio equipment were . added for training pur-poses. Noise-generators were also added for those ' noises that were notice-able to.the trainee dur-ing plant operations. Any deviations in envi-ronment are included in. Appendix B. L b> x-A-15
APPENDIX A
'~. ANSI 3.5 1985 SIMULATOR CERTIFICATION CHECKLIST
]
CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION B. Communication systems YES All telephone and radio that a control room oper- communications are.simu-ator would use to commu- lated between the control nicate with an auxiliary room and the instructor operator or other support station. An upgrade in activities shall be oper- the simulator telephons ational to the extent system to match the plant that the simulator in- system is listed and structor, when performing scheduled with the dis-these remote activities, crepancies in Appendix E. shall be able to communi-cate over the appropriate communication system. SECTION 3.3.1 A. The inclusion of systems YES The systems simulated and of the reference plant the extent of simulation 7s and the degree of simula- provides more than ade-i ) tion shall be to the ex- quate controls, instru-
~> tent necessary to perform mentation, alarms, and the reference plant evo- man-machine interface to lutions described in conduct the normal plant 3.1.1 and the malfunc- evolutions and malfunc-tions described in 3.1.2. tions listed in ANS 3.5 section 3.1.1 and 3.1.2.
B. It shall be possible to YES All systems-that have perform these control displays of system param-manipulating and observe eters and controis on the . plant response as in the simulated panels are reference plant. functionally simulated. ,,~ N. .
- .c APPENDIX A
).4 (
t ANSI 3.5 1985 SIMULATOR-CERTIFICATION CHECKLIST -;
- =
1 J CONFORM SUPPORTING y _- REQUIREMENT (Y/N) DOCUMENTATION ' C .- .This shall include system -YES Those system interactions
--interactions with other whose impact is directly systems simulated and or indirectly observable shall provide total sys- by the trainee during tem integrated response, normal plant evolutions-and malfunctions are totally integrated.- Any.
discrepancies found_dur-ing performance testing
'are listed in Appendix E.
SECTION'3.3.2 A. The systems that are YES Over 600 remote' functions operated-outside tha are availableoto the-control room or that instructor-to perform provide sone input to the system operations outside simulation model and are- of the' control room that-necessary to perform ~directly influence plant-reference plant evolu- evolutions. l\ . .tions-described in 3.1.1 7
;( /i ' '
and malfunctions. des- ~ cribed in 3.1.2 shall be simulated. B.- The simulator trainee YES The. simulator communica-shall-be able to-inter - tionsisystem; allows the face with the remote trainee to interface with activity in--the same the instructor in,the , manner.as'in the refer- same manner as'with re - ' ence plant., mote : operations and -sup-
- port' personnel.in the- ,
plant. .'Using the remote functions,.the instructor - can duplicate all needed remote-activity and pro-vide: feedback-cues as- t needed.during plant evo-lutions. A-17 J
.l,'. - - _- , . _ -
h.I APPENDIX A r ANSI 3.5 1985 SIMULATOR CERTIFICATION CHECKLIST .
'~'
CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION 1 SECTION 3.4 SECTION 3.4.1 A. The simulator shall pos- YES The Waterford 3 reference. sess a minimum capability plant simulator has the forf20 initialization- capability of using 100 conditions. Initial conditions. Two of these are reserved for system use and the re . ' maining 98.are available
.for-training uses.
B. At the-time of commence- YES There are 35 initial. ment.of the simulator.in conditions reserved ahd the= training program, a- protected for instructorL minimum of. ten initial- use in training.arKi test-ization conditions shal1~ ing. Eighteen of these
;be operational and shall have'been certified by
.j_q; g _ include a-variety of the Simulator Supervisor
; 3 plant-operating condi- for use.
V- tions, fission product poison concentrations, at various times:in core life.-
.SECTION 3.4.2:
A. It shall be possible-to YES- ~ Malfunctions are quickly conveniently _ insert and inserted and removed. , terminate the plant mal- using tableausicalled^up functions specified in on the simulator instruc- , 3.1.2. . tor: station.- B. The simulator.shall be' YES The Waterford-3 simulator 1 capable of simulating- can support up to 30-simultaneous or.sequen- active malfunctions and-
-tia1' malfunctions or: includes delay _ times >and both, if these-malfunc- event triggers.--This tions can.be expected to allows for simultaneous, occur by design or opera staggered, and sequential tional experience, malfunctions.
.m (v}. A-18 I
f L . . - . _
, . . ~ - - .. . . . _ . - - - - -.- . . . -
APPENDIX A
' ANSI 3.6 1985 SIMULATOR CERTIFICATION CHECKLIST
- )r~N1 CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION C. The introduction of a YES .The only indication that malfunction shall not a malfunction has been alert the operator to the introduced is the proper impending malfunction in plant response to the any manner other than ' malfunction event. wouldtoccur inLthe refer-ence plant. D.- Provisions shall-be made YES Malfunctions continue to for incorporating addi- be added to the simulator tional malfunctions iden-~ as they are identified by tified from operational = training requirements. experience and not in- There are no software cluded in 3.1.2 (plant limitations on the number malfunctions). of possible malfunctions.
-SECTION 3.4.3-gg A. The simulator shall have -YES The Waterford 3 plant a ;j \~-
the' capability of freez-ing. simulation. In addi-reference simulator has the capability for. tion, consideration freeze, fast time, slow should be given to incor- time, backtrack, and poration of fast time, snapshot, slow time, backtrack-and
. snapshot.
SECTION 3.4.4
; A .~ _ 'The.capab111ty.shall be- YES The simulator includes provided for the'instruc- over-600 remote-functions. .
tor to act in the capac1- that allow the instructor ty-of auxiliary or other to act'as an auxiliary operations ~ remote from operator or other remote the control: room; for_ personnel. example, change the oper- - i ating condition of-valves, breakers or other devices. A
-Q A-19 1
- . - . _ . , . + . . . , ,, , ~ ~ -
.~. . __ .__.____... _ . . _ . . _ . _ . - - . . _ _ _ . - - .
1 APPENDIX A
/- LANSI 3.5 1985 SINULATOR CERTIFICATION CHECKLIST T
"" ..' CONFORM- SUPPORTING-LREQUIRENENT (Y/N) DOCUNENTATION SECTION 4.1~
cA. The simulator accuracles YES Any inaccuracles encoun-
- shall be relatedJto. full tered.during performance .
power values and interim testing will be listedL power-levelsffor.which. along with a schodule of
-valid information ist resolution in' Appendix-E.- '
available. :Tho:parame- Comparison of.the simula-ters displayed on the tor results to plant data control _panelsLmay have was-performed by the + the instrument error Nuclear Operations Engi-added to.the' computed ~
.neering group. NTI-601, values.' During : tes ting,: Computer Real Time Test, ;
the1 accuracy _of< computed- was evaluated by simula-1
. values shall be deter-- . tor-personnel.
-mined for.a minimumfof 3
-points-over1the; power
- range.-
$7 _ .1. : LThe simulator In-- YES Simulator instruments are
. ;fS_/( .strument error shall- calibrated tc theisame-
- beLno greater than specification.(t 24)fas that of'the:compara- .the reference plantras '
.ble meter, transduc- -per NTI-198'" Panel: Meter
- er and related-in- Calibration"'.
strument? system of. i
, ;theLreference plant.: ;
-2..
-: Principal massfand
-energy balances. .;
shall=beisatisfied.
' Examples?aras' a) NetjNSSS.ther- HNO Presentif there aregno Lmal power indi- -
procedures;availabletins _. ; cation tongen- either;thezplant.orJthe- . erated-electri - simulator to performethis; T cal" power.= balance. f
~A-20
~
_i
,~, a 'l -
me.,, R., e 2 -nl- -wh ske_%- wd+m ,4i* Y }. La -n -- maa*n'. A- -b , - - s - a-.en+ -4A-- N t APPENDIX A (~s ANSI-3.5 1985 SIMULATOR CERTIFICATION CHECKLIST i q' ' CONFORM SUPPORTING REQUIREMENT' (Y/N) DOCUMENTATION 3 b) Reactor coolant NO Presently there are_no , system tempera- procedures.available in ture to steam either the plant or the i generator _ pres- simulator to perform this sure, balance. 4 - c) Feedwater flow YES NTI-603.03, 100% Accuracy to reactor Test performs a secondary. ?
- thermal power. side heat balance _calcu-lation on the simulator. -i d) Mass balance of NO Presently there are no pressurizer, procedures available in-either the plant or the-simulator to perform this balance, e) Mass balance of YES NTI-603.03, 100% Accuracy steam genera-- Test performs u-secondary' j 7 ,.
tor . . side heat balance calcu-7% / lation'on the simulator. B._ : The simulator computed YES NTI-603.03, 100%. Accuracy
' values for steady state, Test and NTI-603.04, 100% )
- full-power-operation with - Stability Test-were writ-the. reference plant con- ton to test:the stability troitsystem configuration -and accuracy of the simu-sha13 be stable and not lator models-at full vary more_than i 2% of power operations.-
the initial values over a 60 minute-period, a t/~ . ,{j A-21
APPENDIX A j r~g ANSI 3.5 1985 SIMULATOR CERTIFICATION CHECKLIST 1
~'
CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION- ,
'l
- 1. The simulator com- YES The critical paramet9rs puted values of were evaluated during critical parameters performance testing and shall: agree _ with _ any discrepancies will be i 2% of the refer - included in Appendix E enco plant _parame- along with a echedule of ters and shall not resolution. '
detract from train-ing. uome? examples of critical parame-ters ares c) Reactor thermal power b) . Reactor hot and
' cold leg tem-peratures c). Feedwater flow
)
-d) . Steam-pressure e)- _ Generated elec-trical power f) Recirculation-fJow.
g )'. Reactor coolant 5 system pressure ,
\
5
!. } '- -O a A-22
APPENDIX A
.A. ANSI-3.5 1985 SIMULATOR CERTIFICATION CHECKLIST
^" ~-)4 CONFORM SUPPORTING
. REQUIREMENT (Y/N) DOCUMENTATION s 2.- The calculated val- YES The noncritical parame-- .
ues of noncritical ters were also evaluated ;
-parameters-pertinent during performance test--
to plant operation, ing and any discrepancies Lthat.are included on will be included in Ap- j
-the-simulator con- -pendix E along withEa- -
trol room panels, schedule of resolution. < shall-agree within . 1 10% of the refer- ~ ence plant parame-ters shall not-de -
- tract from training.
SECTION 4.2 SECTION 4.2.11 LA.- ' Tests:shall:be1 conducted YES Performance tests were
.. to prove.the; capability. conducted on-the Water-
- .OJ-- 'of=the simulator to per- ford 3 simulator from -
!s,/- form correctly during the June,.1990 through Febru- '
limiting . cas'ni of those ary, 1991. Abstracts of evolutionsriduntified:in those tests are contained- ' 3.1.1;and-3 4.2. in. Attachment D, discrep-ancies and a schedule for- 7, their resolution are 1 contained"in Attachment E.. if I L s (u)- A , 9, . . ,u, y +-.rr -* r-w .e * - + - * 'r-- ---
~ ='N ' - " " - - ' " ^ ^ - - - ^ '- - - - - '
APPENDIX A f s ANSI 3.5 1985 SIKULATOR CERTIFICATION CHECKLIST k CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION B. Acceptance criteria for _ YES Examples of the test these tests shall: procedures and their acceptance criteria are
- 1. Where applicable, be included in Attachment C.
the same as plant startup test.proce-dure acceptance criteria.
- 2. Require that the observable change in the parameters cor-respond in the di-rection to those expected from best estimate for the simulated transient and do not violate the physical laws of nature.
- 3. Require that the simulator shall not fail to cause an alarm or automatic action if the refer-ence plant would have caused an alarm or automatic action if the reference plant would not cause an alarm or automatic action.
SECTION 4.2.2 A. Malfunction and trans- YES Evaluation of all mal-lents not tested in ac- functions and transients cordance with 4.2.1 shall was performed by the be tested and compared to Waterford 3 Nuclear Oper-best estimate or other ations Engineering group available information and using the sst available shall meet the acceptance information or a tabletop criteria of 4.2.l(B). analysis by operations experienced personnel. A-24
APPENDIX A ANSI 3.5 1985 SIMULATOR CERTIFICATION CHECKLIST CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION NTI-601, Computer Real Timo Test, was ovaluated by simulator personnel using acceptanco critoria developed by them. O A-25
I APPENDIX A r ANSI 3.5 1985 SIMULATOR CERFIFICATION CitECKLIST CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION SECTION 4.3 A. Matbeustical equations YES A Simulator Operating may be simplified to meet Limits (SOL) alarm is real timo simulation included on the instruc-requirements. In.addi- tor station to alert the tion, it is sometimos instructor if paramotors possible to creato events exceed the known model on a simulator which boundaries. progress beyond plant design limits. Examples of such events includo primary containment fail-ure, gross coro damage, and reactor coolant sys-tem two-phase flow. In order to avoid nega-tivo training which could result frote simulator operation during such O' events, edttinistrative controls or other means shall be provided to alert, the instructor when certain parameters ap-proach values indicativo of events beyond the implemented model or . known plant behavior. Conditions to be consid-ered are:
- 1. Primary conta'.nment pressure greator than desigt. limit.
- 2. Reactor coolant system pressure greater than design limit.
- Fuel temperature histories indicative of gross fuel fail-ure.
A-26
APPENDIX A
-~
ANSI 3.5_1985 SIMULATOR CERTIFICATION CHECKLIST CONFORM GUPPORTING REQUIREMENT (Y/N) DOCUMENTATION
- 4. Reactor coolant system pressure versus temperature relationship indica-tive of gross void-ing.
i A. It shall bo possible to YES Hardcopy transient data obtain hardcopy transient is availablo from the data L5 the form of ei- instructor station on a thor plets or printouts Gould 8 pon recorder and for critical paramoters as video printouts of during the evolutions of monitor screens. Data is 3.1.1 (normal plant evo- also available from an lutions) and the malfunc- Indopondent PC based data tions of 3.1.2 (plant collection and plotting /- malfunctions). printing program that interfaces with the host simulation computer. (v} B. This monitoring capabill- YES The Gould pon recorder ty shall provide suffi- and the instructor sta-clont parametric and time tion monitors updato at a resolution to determino rate of 4 timos a second. compliance w!th the per- the PC based data acqui-formance critsrla of sition system can gather section 4 (Porformance up to 60 points at Criteria), twice a second ratos. I
^~
1 l __ -
- APPENDIX A r~ ANSI 3.5 1985 SIMULATOR CERTIFICATION CHECKLIST '
'~ #'
CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION SECTION 5 A. Simulators design control YES The Waterford 3 simulator provides a means for underwent an acceptanco initial and ongoing veri- test performed by 11cen-fication of simulator sod plant personnel when performance for use in it was delivered from the operator training. Simu- vendor. As any modifica-Ictors constructed within tions were made to the the guidelinos of this simulator or its models, standard shall be based the changes were testod ; on actual or predicted by licensed personnel. - plant configuration and The Performance Tests performance, developed for the certif-ication effort continue to monitor the simula-tor's performance against plant performance. ( SECTION 5.1 A. The simulator design data YES The Waterford 3 simulator forms the basis for ex- was accepted as ready for 1 sting simulator configu- training prior to the ration. This data base reference plant having may include predicted been in commercial opera-plant performanco until tion for 18 months, t}ie reference plant has Predicted plant perfor-
- been in commercial opera- mance was included in the tion for 18 months, simulator design data.
After this period, avail- As modifications and able actual plant config- updates to the simulation uration data shall be models are performed, the included in the simulator actual plant data is used design data, to updato the design data base and replace the predicted plant perfor-mance if needed. L f l s,,) A-28
APPENDIX A (~ ANSI 3.5 1985 SIMUI.ATOR CERTIFICATION CIIECKLIST CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION SECTION 5.2 A. The simulator update VES A review of the simulator design data forms the design data base as it basis for future simula- pertains to plant modifi-tor design changes. This cations and other related data base shall include changes was performed available plant data after 18 months of simu-within 18 months after lator operations. An the reference plant is in updato data base was commercial operation or established and the simu-within 18 months of the lator was modified to simulator operational include those items. A date, whichever is later. yeerly review was then Reference plant modifica- initiated to establish tions shall be reviewed the update data base to at least once por year be included in the fol-and the simulator update lowing calendar year. design data shall be 7- revised as appropriato ( based on engineering and
' training value assess-ment.
B. Student feedback should YES Student foodback is in-be evaluated as part of cluded into the review the review process, process in two ways. The first is through comments to the instructors, who will then generate Prob-lem Reports to be evalu-ated by a Problem Review Committee. The second is through a detailed ques-tionnaire that is given to each student at least semi-annually for their direct comments to the simulator staff. An evaluation is then given of those comments with the results fed back to the student. A-29 l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ m_. -
l APPENDIX A p_ ANSI 3.5 1985 SIMULATOR CERTIFICATION CHECKLIST CONFORM SUPPORTING REQUIREMENT (Y/N) DOCUMENTATION I SECTION 5.3 A. The simulator shall bo YES The modifications includ- o modified as required ed in the simulator up-within 12 months follow- dato data base are sched-ing the annual ostablish- uled to be irtorporated mont of the simulator in the calendar year tho updato design data refor- data base was establish-onced in 5.2 (simulator ed. If items were not , updato design data). fully incorporated due to ] Simulator modifications hardwaro availability or ! may procedo reference manpower loading, those plant modifications based items woro incorporated on the training value, as soon as possible in the next calendar year. Any items presently be-yond the 12 month doad-lino are included in the
~'T (V resolution schedulo in Appendix E.
)
- 8. Testing shall be conduct- YES __
An Acceptance Test Proco- l ed and a report prepared dure was performed before ' for each of the following the Watorford 3 simulator occasions: was declared ready for training. After overy
- 1. Completion of ini- significant model re-tial construction, placement since t. hat timo, an model specific
- 2. If almulator design ATP has boon run. A now changes roFult in set of Performance Testa l significant almula- on all ANSI 3.5 related !
tor configuration or areas was run prior to l performanco varia- this certification sub- i tions. mittal. C. When.a limited change is YES A chango specific perfor-mado, a specific perfor- mence test ic required mance test on the affect- after overy modification ed systems and components to the simulator and its ' shall be performed, models. j E \ [)\ A-30 l i L
.. . . _- - -= _ _.. _ _ _ . _ _ _ _ _ . _ . _ _ . _ . . _ . . _ . _ _ _ _ _ .
l APPENDIX A l ANs! 3.5 1985 SINULATOR CERTIFICATION CHECKLIST i CONFORM SUPPORTING REQUIRENENT (Y/N) DOCUNENTATION ; h 1.- Verify overall-simu- YES An integrated system l
-lator.model comp- benchmark test is being !
leteness and inte- developed to provide a ; gration. means for determining the impact a specific change has on the overall mod-els. This test will be run each time.a new simu-lator training-load is developed. 2.- . Verify simulator YES The steady state perfor-performance against mance tests referenced in the steady state ANSI'3.51will be perform- l criteria of.4.1~ exi once a year as part of ! (steady state opera- the annual testing.. tion). 3.- Verify simulator YES The transient tests ref-performance against erenced in Appendix B of
; the transient crite- ANSI 3.5'will be~perfor-ria of 4.2 (tran- med once a year as part-sient operation) for of the annual tests.
a benchmark set of transients. 4 4 9N S L A-31 r ' i.; _ .._;_---.----- - --a- - " -
I I l APPENDIX A () Exceptions to ANS/ ANSI 3.5, 1985 Requirements The Waterford 3 Training Department of ENTERGY Operations Inc. , interprets the term "to take exception to" to mean the Waterford SES Unit # 3 reference plant simulator will never meet a specific requirement of ANSI 3.5, 1985. The following exceptions to ANSI 3.5, 1985 are taken: ; 1.- Waterford 3 takes exception to the requirement of section 3.3.3(7) Normal Plant Evolutions " Startup, Shutdown ~and Power Operation with less than rull Reactor Coolant riow." Waterford 3 Technical _ Specification 3/4.4.1, Reactor Coolant Loops and Coolant Circulation, prohibits operation with less than full reactor coolant flow. Therefore, the Waterford 3 i reference plant simulator will not be used for training on normal plant evolutions with less than full RCS flow.
- 2. Waterford 31 takes exception to the requirement of section- l 3.1.2.5(L) Malfunctions - Control Rod railure including '
Uncoupled Rods. F
-- /~T .The lack of positive reactivity insertion associated with an (J uncoupled CEA in a subcritical reactor can not be observed by an operator using normal plant indications during start-up. Only with-the use of a-temporarily installed reactivity computer can this s emall . reactivity perturbation be seen.
Therefore,. the Waterford 3 reference plant simulator will not be used. for training on evolutions with uncoupled con-trol element assemblies.- 4 e 1 A-32 L l' l, _.J._ _..-.,._.._,u .a. ,...J;_,_... .,._...._.._.-,_.-,..m.._...-,_..,.-
O APPENDIX B SIMULATOR CONTROL ROOM LAYOUT PLANT CONTROL ROOM LAYOUT MINOR HARDWARE EXCEPTION LIST O O 1
I ! M/ENDIX M i t- { sIwu1Aton CONTROL ROON LAYOUT u i STAM "
...- j roast,t !
-, y pm 9'uMtee mos=4 f psafios ,
i .
- 1
/
ertu erre aWin ante I l e c . t3taff 4 4 7 e- e e -
~
J N () *
^
e F : i _
""*8 COMMUtt'C4110N DESK
} ,
D
~ ;
e o o o @ , e ,4 6 e_ _ e 3 e O, O e e b' -
- hk kN - -
ac t sas - f recuputta stoon ~i'
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W I' 4 'i 9tHER DLOOR$) . e t 3 i {
- .. .i B-1 O
L> c l
. .,.......,.a.,-.,-.m --..,4.2.._w..-- .,,.,me..,y.,_,. ,.,.#,Lo,_..w.- , - , , , , _ , , . . . . . , , . . , ,w.,
p .,,r..,,~., ..w.
,,v,, ,,,,.y .. -v--mv-.,,7
APPENDIX B PLANT CONTROL ROOM IA OUT h W Fwtc 4-a gg, &&we Wno0W /' g 9 0 - / cPanAnown g A g g q ( w mw.AnfA g.4 b._ 4 ,. t _ [ ' h gTgNfg imLET is [ $$ .y.!
"en a -
e
.W E CP 6 [ g
- 1. CONT ROL R00M
% CP4 Floor EL %,co' S rnowv g T P5 CP 4 CP.I E* P*
[ b b C b
~ reewt b ps ca.11 ep.c CF- 50 _ l V -
couPuTER Lor 4R (FM O NV i l l @ st
- JL -
- __ e .a I 1 6 9 Y.
-! C6 n
1 y' e _ n 50, 6 7 3 : b s e %
- N _
9.- d 5y 1. 2
- b E 0, g+*
g - . g* rR 7 1 _ L P R - Roforonce LOU-1564-G-134 n B-2 V
APPENDIX B A d SIMULATOR VERSES CONTROL ROOM HARDWARE MINOR EXCEPTIONS
- 1) (CP-15) Main The original devic.9 is no longer Transformer availablo from the manufacturor. A Differential closest substitution of sito, shapo Negative Phaso and color was used in the design of Sequencer the simulator. This has no impact on the function of the panol and is considorod a minor difloronco.
- 2) (CP-14) Radiation The almulator has only one typo, a Recorders throo channel recorder. The plant has three difforent typos, a 1 channel, 2 channel, and a 3 channel of a different model. The original types of recorders are no longer available and the closest substitute was used in the design of the simulator. Each recorder is configured with scalos and pens only ior those channels used.
- 3) (CP-52) Radiation This panol has the same situation as Recorders Item 2 (CP-14).
{ '
- 4) (CP-35, CP-3, CP-6, The control room CRTs aro mounted CP-36) CRT PMC flush in the control panol. The monitors, Radiation simulator CRTs protrude 2-3" from the Display monitor panel face. The CRTs are the same type and provido all of the samo information as in the control room.
This is considered a :ainor difforence.
- 5) (CP-35) The simulator and control room have HERCO/Koyboard 'V' different paint shados of groen, shaped mounting This has no impact on the function of panel the panel and is considered a minor difforence.
- 6) (CP-1) DEH Turbino The Westinghouso Logo is missing duo control panoi to copyright problems on duplication of the panel for the simulator. This has no impact on the function of the panel and is considorod a minor difforence.
- J B-3 l
l l
APPENDIX B
,- m i)
- 7) (CP-2) Channel The switch handle is grey in the Select Control Lovel plant and black in the simulator.
Switch This is a minor difference and does not impact the function and recognition of the switch.
- 8) (CP-2) CEA Drivo The plant has an additional group 7 Mechanism Controller and 8 engraved into the label plato.
Group Select Switch The extra groups are not used in the plant. This is a minor difference.
- 9) (various) Valve The plant has soveral different Percentage open labels on the same model meter used Motors to indicato valvo position. The labels vary from "4" to " Position %
Open" to " Percent Open" dependent on when the meter was purchased. The zero to 100% scales are exactly the i same on each. As the motors are ' repaired or replaced in the plant, a substituto motor may be installed, and the label may change at any given position. This is a minor difference 73 that has no impact on the function or ( i reading of the meter. The simulator Kl staff will Dat try to koop up with the exact label in any given location due to the minor nature of the discrepancy. l
- 10) (Various) In the control room and in the ,
International simulator, the dual scale models of Instrument Dual those motors have a contor lined Scale Panel Meters scale of major and minor divisions with labols on each sido. The sido labels have the numbers for each major division beside the scale and the units on the outsido edge. After repair or calibration some of tho ; motors that have the same scale on , both-sides may be assembled with the ! units on the insido and the numbers for the major divisions on the outside. This is a minor difference and has no impact on the reading of the motor. The simulator staff will agi try to koop up with which meters have boon roassembled this way sinco it is subject to change after the l' % l Q B-4 l i
l APPENDIX B () next repair or calibration.
- 11) (Various) Small During plant modifications a few diamotor conduits small diamotor (less than 1")
conduits were added around the walla of the control room. The simulator did not require their use, therefore, empty conduits were not added. Because of their small size their omission will not be noticeable. Conduits with a diamator of larger than 2" are considered more noticeable and are installed to match the plant configuration. This was doomed a minor difference with no impact on the simulator environment. p s v l 1 r B-5
O APPENDIX C PERFORMANCE TEST LIST PERFORMANCE TEST EXAMPLES O O
r APPENDIX C 7
-w PERFORMANCE TEST LIST t '~') PERFORMANCE PERFORMANCE TEST CERT. ANS-3.5 MALP TEST NUMBER DESCRIPTION REQ'D REF. USED NTI-601 COMPUTER REAL TIME TEST YES A3.1 NTI-602 NORMAL OPERATION TEST YES A3.2 NTI-603.01 45% ACCURACY TEST YES B2.1 603.02 80% ACCURACY TEST YES B2.1 603.03 100% ACCURACY TEST YES B2.1 603.04 100% STABILITY TEST YES B2.1 NTI-604.01 MANUAL REACTOR TRIP YES B2.2(1) 604.02 SIM. TRIP OF ALL FDW PUMPS YES B2.2(2) 604.03 SIM. CLOSURE OF ALL MSIVs YES B2.2(3)
(~~'T 604.04 SIM. TRIP OF ALL RCPs YES B2.2(4)
'~
604.05 TRIP ANY RCP YES B2.2(5) 604.06 MAIN TURBINE TRIP YES B2.2(6) 604.07 MAX RATE POWER RAMP YES B2.2(7) 604.08 MAX LOCA WITH LOP YES B2.2(8) 604.09 MAX UNISOLABLE MS LEAK YES B2.2(9) 604.10 SLOW RCS DEPRESS W/NO HPSI YES B2.2(10) 604.11 REACTOR TRIP FOLLOWED BY YES 3.1.1(4) RECOVERY TO RATED POWER NTI-610.01- CCW PUMP (S) TRIP YES 3.1.2(8) CC01 610.02 ACCW PUMP TRIP YES CCO2 610.03 CCW PUMP BEARING SEIZURE YES 3.1.2(8) CC03 610.05 COOLING TOWER FAN (S) TRIP YES 3.1.2(8) CC05 ( C- 1
l APPENDIX _C PERFORMANCE TEST LIST PERFORMANCE. PERFORMANCE TEST CERT. ANS-3.5 MALP TEST NUMBER DESCRIPTION REQ'D REF. USED 610.06 RCP SEAL CLR OTLT VLV FAILS YES 3.1.2(8) CC06 610.07 LOSS OF CCW TO CEDM CLRS YES 3.1.2(8) CC07 610.08 LOSS OF COOLING WTR TO DG YES 3.1.2(8) CCO B - 610.09 LOSS OF CCW TO CNTMT FAN CLR YES 3.1.2(8) CC09 610.10 LOSS OF CCW TO SDC HX YES 3.1.2(7) CC10 610.12 CCW SURGE TNK LVL SIG FAILS YES 3.1.2(8) CC12 610.15 LOSS OF CCW TO LPSI PMP CLRS YES 3.1.2(8) CC15 610.16 CCW UNISOLABLE LEAK IN CNTMT- YES- 3.1.2(8) CC16 610.17 RUPTURELOF CCW PMP-DISC PIPE YES 3.1.2(8) CC17 610.18 _CCW TUBE LEAK IN CNTMT FAN YES 3.1.2(8) CC18-COOLERS 610.19 AUX CCW PMP DISC HDR RUPTURE YES 3.1.2(8) CC19 610.21 :CCW LINE BREAK IN AUX BLDG YES 3.1.2(8) CC21 NTI-612.01 REACTOR FUEL CLADDING FAILS YES 3.1.2(14) CR01 NTI-613.01 CNTMT SPRAY PUMP (S) FAIL TO_ YES 3.1.2(23) CS01 AUTOSTART- ,~ NTI-614.01- CHARGING PUMP TRIP YES 3.1.2(18) CV01 614.02 .CHRG PUMPS FAIL.TO AUTOSTART YES 3.1.2(18) CV02
'614.03' CHRG PUMP SEAL LUBE PUMP YES 3.1.2(18) CV03 MOTOR FAILS 614.05 LTDN BCK' PRESS REG VLV FAILS YES 3.1.2(18) CV05 614.06 -LTDN HX TCV FAILS SHUT YES -3.1.2(18) CV06 614.14 CVCS.-LTDN LEAK IN CNTMT- YES 3.1.2(1) CV14-614.15 CVCS LTDN LEAK OUTSIDE CNTMT- YES 3.1.2(1) CV15- ;j a
C-2 i
i APPENDIX C PERFORMANCE TEST LIST PERFORMANCE PERFORMANCE TEST CERT. ANS-3.5 MALF TEST NUMBER DESCRIPTION REQ'D REF. USED 614.16 CHRG LINE LEAK INSIDE CNTMT YES 3.1.2(1) CV16 NT1-615.01 CW PUMP TRIP YES 3.1.2(5) CWO1 NTI-616.01 FDR BRKR TRIP IN SWITCHYARD YES 3.1.2(3) ED01 616.02 LOSS OF MAJOR STATION XFMR YES 3.1.2(3) ED02 616.04 LOSS OF 6.9KV BUS (ES) YES 3.1.2(3) ED04 616.05 LOSS OF 4.16KV BUS (ES) YES 3.1.2(3) ED05 616.06 LOSS OF 400VAC BUS (ES) YES 3.2.2(3) ED06 616.07 LOSS OF 125VDC BUS (ES) YES 3.1.2(3) ED07 616.10 LOSS OF 208/120V BUS (ES) YES 3.1.2(3) ED10 NTI-617.03 MAIN GEN LOAD REJECTION YES 3.1.2(16) EG03 (~) 617.04 MAIN GEN OUTPUT BKR FAILS TO OPEN ON AUTOTRIP YES 3.1.2(22) EG04 (_/ 617.05 EXCIT.BKR FAILS TO AUTOTRIP YES 3.1.2(22) EGOS 617.07 MAIN GEN AUTOVOLTAGE REG YES 3.1.2(22) EG07 FAILS TO MANUAL 617.08 FAILURE OF DG TO AUTOSTART YES 3.1.2(3) EG08 617.09 FAILURE OF DG TO LOAD YES 3.1.2(3) EG09 617.10 DG OVERSPEED TRIP YES 3.1.2(3) EG10 617.11 DG TRIP ON DIFF PROTECTION YES 3.1.2(3) EGil 617.18 H2 SEAL OIL PMP TRIP (H2) YES 3.1.e(22) EG10 617.19 H2 SEAL OIL PMP TRIP (AIR) YES 3.1.2(22) EG19 617.20 STATOR COOLANT HIGH COND. YES 3.1.2(15) EG20 NTI-619.01 CONDENSATE PUMP TRIP YES 3.1.2(9) FWO1 619.03 FEEDWATER PUMP OVERSPD TRIP YES 3.1.2(9) FWO3 i C-3 l
APPENDIM C PERFORMANCE TEST LIST
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PERFORMANCE PERFORMANCE TEST CERT. ANS-3.5 MALF TEST NUMBER DESCRIPTION REQ'D REF. USED 619.04 FDW PMP TURB SPD CNTRL FAIL YES 3.1.2(9) FWO4 619.06 MTR DRVN EMERG FDW PMP TRIP YES 3.1.2(10) FWO6 619.07 EMER FDW PMPS AUTOSTART FAIL YES 3.1.2(10) FWO7 619.08 LOSS OF AUX FDW PUMP YES 3.1.2(9) FWO8 619.10 CONDENSER VACUUM PUMP TRIP YES 3.1.2(5) FW10 619.12 FDW PUMP TURBINE HIGH VID YES 3.1.2(9) FW12 619.14 CNDSR HW LVL CNTRL VLV FAIL YES 3.1.2(S) FW14 619.19 FDW HTR BYPASS VLV FAILURE YES 3.1.2(9) FW19 619.20 SU FDW REG VLV FAILURE YES 3.1.2(9) FW20 619.21 CONDENSER AIR IN LEAKAGE YES 3.1.2(5) FW21 (' 619.29 EMER FDW PIPE LEAK YES 3.1.2(23) FW29 ( 619.30 EMER FDW PMP SUCT HDR LEAK YES 3.1.2(23) FW30 619.36 FDW PIPE BREAK OUTSIDE CNTMT YES 3.1.2(20) FW36 619.37 FDW PIPE BREAK OUTSIDE CNTMT YES 3.1.2(20) FW37 619.38 FDW PIPE BREAK INSIDE CNTMT YES 3.1.2(20) FW38 NTI-621.01 SA/IA CROSSOVER VLV FAILS YES 3.1,2(2) IA01 I 621.02 IA CNTMT ISOL VLV FAILS TO YES 3.1.2(2) IA02 CLOSE ON CIAS 621.03 RUPTURE AIR SUPPLY TO STEAM YES 3.1.2(2) IA03 BYPASS VALVES 621.04 RUPTURED AIR SPLY TO RAB YEF 3.1.2(2) IA04 621.05 IA CMPRSR DISCH LINE RUPTURE YES 3.1.2(2) IA05 NTI-622.04 STEAM BYPASS VLV LEAKAGE YES 3.1.2(17) MSO4 622.05 ATMOS STM DUMP VLV FAILS YES 3.1.2(17) MS05
- C-4
, , ..e-, - , .g-->-.. v ---r-,-e- - -~ve , e
i r AEPJHDIX..C ! PERFORMANCE TEST LIST O PERFORMANCE PERFORMANCE TEST CERT. ANS-3.5 MALF TEST NUMBER . DESCRIPTION REQ'D REF. USED l 622.09 S/G STM FLOW XMTR FAILURE YES 3.1.2(22) MSO9 ' 622.10 MS-FLOW XMTR FAILURE HI/LO YES 3.1.2(22) MS10 ; 622.11 MS LINE BREAK INSIDE CNTMT YES 3.1.2(20) MS11 l
- 622.12 MS LINE BREAK OUTSIDE CNTMT YES 3.1.2(20) MS12 i AFTER MSIV l
622.13 MS LINE BREAK OUTSIDE CNTMT YES 3.1.2(20) MS13 BEFORE MSIV l 622.21 MS LINE BREAK DWNSTRM OF YES 3.1.2(20) MS21 IFT-0300AS/BS IN CNTMT , t 622.22 TURBINE IST STAGE PRESSUllE YES 3.1;2(22) MS22 XMTR FAILS NTI+623.01 SAFETY INSTRMHT CH FAILURE YES 3.1.2(21) N101 , 623.03-- CNTRL CH-INSTRMNT FAILURE YES 3.1.2(21) NIO3-623.05 SU INSTRUMENT CH FAILURE YES 3.1.2(21) NIO5 : 623.07 SU CH FAILS TO DE-ENERGIZE YES 3.1.2(21) NIO7 '!
~
NTI-624.01' LOSS OF PMC PRI CMPTR CMPLX YES 3.1.2(20) PC01 NTI-625.01 CPC CHANNEL (S) FOIL YES 3.1.2(11) PWO1 ! 625.02- RX PWR CB FAILS TO DROP CEAS YES 3.1.2(11) PWO2 625.03 RX PWR:CB FAILS TO SB/RB YES 3.1.2(11) PWO3 625.06 RAIL CEAC CHANNEL (S) LOSS OF YES 3.1.2(11) PWO6 CPO2 CRT CH. 1,2 I ;NTI-626.01 LOSS OF ALL RCPS YES 3.1.2(4) RCO) , 626.03 RCP SHAFT SEIZURE YES: 3.1.2(4) RC03 626.04 RCP SHEARED SHAFT YES 3.1.2(4) RC04 l 626.05 .RCP LOSS OF LUBE OIL' YES 3.1.2(4') RC05 C-5
AP_PIMPlX_.C PERFORMANCE TEST LIST PERFORMANCE PERFORMANCE TEST CERT. ANS-3.5 MALF TEST NUMBER DESCRIPTION REQ'D REF. USED 626.08 RCP LOWER SEAL FAILURE YES 3.1.2(4) RC08 626.09 RCP MIDDLE SEAL FAILURE YES 3.1.2(4) RC09 626.11 CODE SAFETY FAILURE OPN/CLSD YES 3.1.2(1) RC11 626.12 CODE SAFETY RELIEF VLV LEAKS YES 3.1.2(1) RC12 626.14 PZR SPRAY VALVE FAILURE YES 3.1.2(18) RC14 626.15 PZR CNTRL LT FAILS HI/LO YES 3.1.2(18) RC15 626.16A RCP SPEED XMTR FAILS A - P YES 3.1.2(22) RC16 626.16B RCP SPEED XMTR FAILS Q - FF YES 3.1.2(22) RC16 626.17 SI SYS PRESS INTLK FAILURE YES 3.1.2(17) RC17 626.18 RCS COLD LEG CNTRL TT FAILS YES 3.1.2(22) RC18 () 626.19 626.20 RCS COLD LEG SFTY TT FAILS RCS HOT LEG SFTY TT PAILS YES YES 3.1.2(22) RC19 3.1.2(22) RC20 626.21 RCS HOT LEG CNTRL TT PAII.S YES 3.1.2(22) RC21 626.22 PZR CPC SFTY PT FAILS HI/LO YES 3.1.2(22) RC22 626.23 RCS COLD LEG PIPE RUPTURE YES 3.1.2(1) RC23 626.24 RCS HOT LEG PIPE RUPTURE YES 3.1.2(1) RC24 626.25 RCS LEAK INTO CNTMT YE3 3.1.2(1) RC25 626.27 PZR INSTRMNT LINE BREAK YES 3.1.2(1) RC27 NTI-627.01 CEDM MG SET FAILURE YES 3.1.2(12) RD01 627.02 DROPPED CEA YES 3.1.2(12) RD02 627.03 CEAS FAIL TO MOVE IN MAN GP YES 3.1.2(13) RD03 627.04 CEAS FAIL TO MOVE IN MAN ID YES 3.1.2(13) RD04 627.05 ROD EJECTION YES 3.1.2(12) RD05 i C-6
APPENDIX C r 'g
^
PERFORMANCE TEST LIST , ('") PERFORMANCE PERFORMANCE TEST CERT. ANS-3.5 MALF TEST NUMBER DESCRIPTION REQ'D REF. USED 627.06 CEA GRP UNCNTRLD INSERTION YES 3.1.2(12) RD06 627.08 DROPPED CEA WITH NO ALARMS YES 3.1.2(12) RDOB 627.09 CEA REG GRP UNCNTRLD WITHDRW YES 3.1.2(12) RD09 , 627.10 CEAS MOVE OUT WHEN INWARD YES 3.1.2(12) RD10 MOVEMENT REQUIRED IN AUTO 627.11 CEAS MECHANICALLY STUCK YES 3.1.2(12) RD11 627.12 CEA UNCNTRLD WITHDRAWAL YES 3.1.2(12) RD12 627.13 CEA DRIFT YES 3.1.2(12) RD13 627.14 FAILURE OF CNTRL/SD BANKS TO YES 3.1.2(12) RD14 TRIP 627.21 CEA UPR ELEC LIMIT FAILURE YES 3.1.2(12) RD21 ( ); -027.24 RX TRIP BRKR FAILS TO OPEN YES 3.1.2(24) RD24 NTI-629.02 RPS AUTO TRIP FAILURE YES 3.1.2(24) RP02 029.03 RX TRIP WITH NO AUTO TURBINE YES 3.1.2(19) RP03 TRIP 629.04 ESFAS TRIP GENERATED YES 3.1.2(23) RPO4 629.05 ESPAS CH FAILS TO TRIP YES 3.1.2(23) RP05 629.06 RPS MATRIX RELAY FAILURE YES 3.1.2(17) RP06 629.07 RPS BISTABLE RELAY FAILURE YES 3.1.2(17) RP07 NTI-630.01 SBC QUICK OPEN SIG FAILS YES 3.1.2(17) RX01 630.04 MFV FLOW CNTRL VLV FAILURE YES 3.1.2(9) RXO4 630.05 S/G LEVEL SETPOINT DRIFT YES 3.1.2(22) RX05 630.07 PZR PRESS C11TRLR FAILS OFF YES 3.1.2(18) RXO7 630.08 PZR LEVEL CNTRLR FAILS OFF YES 3.1.2(18) RXOB f C-7
{ MPENDIX C , { PERFORMANCE TEST LIST PERFORMANCE PERFORMANCE TEST CERT. ANS-3.5 MALF- + TEST NUMBER DESCRIPTION REQ'D REF. USED l 630.09 S/G LEVEL CNTRL FAILURE YES 3.1.2(22) RXO9 ! 630.10 -PZR BU HTRS FAIL YES 3.1.2(18) RX10 - 630.11 PER PROP HTRS FAIL ON/OFF YES 3.1.2(18) RX11 i 630.14 PZR PRESS CNTRL 100X/Y FAILS YES 3.1.2(18) RX14-NTI-631.01 S/G TUBE LEAK. YES 3.1.2(1) SG01 631.04 MS LINE PRESS XMTR FAILS YES 3.1.2(22) SG04 631.05' S/G. LEVEL XMTR FAILURE YES 3.1.2(22) SG05 NTI-632.01: SI-PUMP TRIP YES 3.1.2(22) SIO1- l 632.04 AIR BINDING IN SI SYSTEM YES 3.1.2(7) SIO4 , 632.08 LPSI PUMP SUCT LINE RUPTURE YES 3.1.2(7) .SIO8- .
'632.11- SDC HX TUBE LEAK =YES 3.1.2(7) Sill -
, NTI-633.01 TURBINE LOAD CNTRL DMD FAILS -YES 3.1.2(17) TC01.
'NTI-634.01 TCCW PUMP TRIP YES 3.1.2(6) 'TP01 I
634.04 TCCW HX A OUTLET HDR LEAK YES 3.1.2(6) TPO4 l 634.05' LOSS OF WTR TO HW COOLERS _YES 3.1.2(6)- TP05 - 634.06 LOSS OF TCCW CLG TO IA/SA YES 3.1.2(6) TP06-COMPRESSORS
'NTI-635.06- TURBINE TRIP YES- 3.1.2(15) TUO6
>NTI-640.01 LOSS OF 1 FDW HTR EVENT YES 3.1.2(17) 640.03 EFAS ACTUATION 9 POWER EVENT YES 3.1.2(17).
640.09 LOSS'OF CONDENSER VAC EVENT YES_ 3.1.2(15) 640.10- LOSS OF ALL NORMAL AC EVENT YES 3.1.2(3) 640'.21 S/G TUBE' RUPTURE W/ LOOP YES 3.1.2(1&3)- C'- 8
bPPENDIX C PERFORMANCE TEST LIST PERFORMANCE PERTORMANCE TEST CERT. ANS-3.5 MALF TEST NUMBER DESCRIPTION REQ'D REF. USED NTI-645.003 CHARGING PUMP OPERABILITY YES 3.1.1(10) CHECK 645.004 BORIC ACID PUMP OPERABILITY YES 3.1.1(10) CHECK 645.007 TURBINE INLET VALVE CYCLING YES 3.1.1(10) JST 645.010 ECCS THROTTLE VALVES POSITION YES 3.1.1(10) VERIFICATION 645.011 HIGH PRESSURE SAFETY YES 3.1.1(10) INJECTION PUMP PRESERVICE OPERABILITY CHECK 645.024 REACTOR COOLANT SYSTEM WATER YES 3.1.1(10) INVENTORY BALANCE 645.035 CONTAINMENT SPRAY PUMP YES 3.1.1(10) OPERABILITY CHECK 645.068 EMERGENCY DIESEL GENERATOR YES 3.1.1(10) OPERABILITY VERITICATION 645.090 SHUTDOWN KARGIN YES 3.1.1(10) 645.101 STARTUP CHANNEL TUNCTIONAL YES 3.1.1(10) TEST STARTUP CHANNEL 1 AND 2 645.102 SAFETY CHANNEL NUCLEAR YES 3.1.1(10) INSTRUMENTATION FUNCTIONAL TEST 645.107 PLANT PROTECTION SYSTEM YES 3.1.1(10) CHANNEL A B C D FUNCTIONAL TEST NTI-647.010 REACTOR TRIP ON TURBINE TRIP YES 3.1.1(10) CHANNEL A B C D FUNCTIONAL TEST 647.017 ANTICIPATED TRANSIENT SYSTEM YES 3.1.1(10) CHECK C-9
. -- .. - - _ - - . - .=
APPENDI4_C
,e w PERFORMANCE TEST LIST tN'J PERFORMANCE PERFORMANCE TEST CERT. ANS-3.5 MALF TEST NUMBER DESCRIPTION REQ'D REF. USED t
NTI-650.01 CRITICAL BORON CONCNTRTION YES 3.1.1(9) 650.02 GROUP WORTH TESTS YES 3.1.1(9) 650.03 CEA SYMMETRY TESTS YES 3.1.1(9) 650.04 ISOTHERMAL' TEMP COEFF TEST YES 3.1.1(9) 650.05 POWER DEFFECT TEST YES 3.1.1(9) 650.06 KEHON WORTH TEST YES 3.1.1(9) 650.07 XENON 03CILLATION TEST YES 3.1.1(9) 650.08 DECAY HEAT TEST YES 3.1.1(9) 650.09 FLUX COUPLING TO NI TEST YES 3.1.1(9) O f l C - 10 C' 1 l l
r l WATERFORD 3 SES SINtfLhTOR NO: NTI-603.04 - PERFORMANCE TEST PROCEDURE REV O r STEADY STATE TEST PAGE: 1 OF 10
. i STEADY STATE STABILITY TEST Ji- 100%-FULL POWER..
DATE: 07/16/90 s ANS-3.5 REQUIRED YES s. CONTENTS
.g 1.0 PURPOSE U 2.0 ' REFERENCES.
3.0 INITIAL CONDITIONS , 4.0 DATA ACQUISITION. r 5.0 ACCEPTANCE CRITERIA j 6.0 ' TES
T. PROCEDURE
.7.0; TEST PROCEDURE RESULTS 8.0 ' ATTACHMENTS 1
PREPARED BY/DATE bl 9 /lmA4 s-- / 7.m. fe,- i
~~> - // - 4 REVIEWED BY/DATE ,
;O AP RevED eY,eATE a -- / 4 .s r-<-eSIMULATOR SUPERVISOR
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k) WATERFORD 3 SES SIMULATOR NO: NTI-603.04 PERFORMANCE TEST PROCEDURE REV: 0 , STEADY STATE TEST PAGE: 2 OF 10 STEADY STATE STABILITY TEST 100% FULL POWER 1.0 PERFORMANCE TEST PURPOSE The purpose of this test is to prove Waterford 3 SES bimulator stability at 100% Full Power Steady State conditions as required by ANSI /ANS-3.5
2.0 REFERENCES
2.1 ANSI /ANS-3.5 American National Standard, Nuclear Power Plant Simulators for Use in Operator Training
,.s a. Section 4.1 - Steady State Operation
'/
\
(s/ b. Section B2.1 - Steady State Performance Tests (Appendix B) 3.0 INITIAL CONDITIONS The Simulator will be initialized into 100% Power, EOL, Steady State conditions for the performance of this test. 4.0 DATA ACOUISITION Use SPVS File __ for collection of the specified dats points and frequency of rample. Attachment 8.5 identifies data collected. 5.0 ACCEPTANCE CRITERIA The. following acceptance criteria shall be used to determine the acceptability of this performance test 5.1' The Simulator's computed values for Steady State, Full Power, Aut omatic Control Operation with the typical Waterford 3 SES Control Configuration shall be stable, AND not vary by more than 2 two (2) percent of initial value over a sixty (60) minute time period.
,1 v
WATERFORD 3 SES SIMULATOR NO: ITI'I-603. 04 PERFORMANCE TEST PROCEDURE REY: O STEADY STATE TEST PAGE: 3 0F 10 6.0 TEST PROCEDURE INITIALS 6.1 Reset the Simulator into 100% Tull Power, EOL, Steady State conditions IC- . 6.2 Place the Simulator in Run. 6.3 Initiate SPVS data collection, in accordance with Data Acquisition, Att. 8.5, and record Test Start Time = 6.4 Trend SPVS calculated variables, AND verify Control Board indicators track parameters listed in Data Acquisition, Att. B.5 6.5 Perform No control manipulations for one hour. Record Test Stop Time = I) C/ 6.6 Snapshot IC as Steady State Stability Test, Temporary IC- , then terminate this test. 6.7 Complete Attachments as necessary. O PERFORMED BY: DATE:
{- if i WATERFORD 3 SES SIMULATOR NO: IrrI-603.04 PERFORMANCE TEST PROCEDURE REV: O STEADY STATE TEST PAGE: 4 OF 10 7.0 TEST PROCEDURE RESULTS INITIALS 7.1 As determined by test results, annotate the following:. 7.1.1 Test cc.mpleted Satisfactorily. HQTFm Problems ddontified during the conduct-of this test procedure will be logged on Attachment 6.3 of this test procedure and resolved in accordance with NTP-015. 7.1.2 Af ter pr, clems are corrected, and ()
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the applicable procedure steps are retested, this test procedure is considered complete. 7.1.3 The test results are unsatisf actory. Complete retest of this t.st procedure is required following correction of problems. TEST STARTED: / (Date end Time) TEST COMPLETE: / (Date and Time) TEST PERFORMED BY: DATE: TEST REVIEUED BY: DATE: [ TEST ACCEPTED BY: DATE: b SIMULATOR SUPERVISOR
WATERFORD 3 BES SIMULATOR Not NTI-603.04 PERFORMANCE TEST PROCEDURE REV: O STEADY STATE TEST PAGE 5 0F 10 8.0 ATTACHMENTS 8.1 Test Procedure Report 8.2 Test Procedure Remarks 8.3 Test Problems Report 8.4 Continuation Sheet 8.5 Data Acquisition Sheet s O O ln __ -_. - _ _ _ _ _ _ _ _ _ - - _ - _ _ - _ _ _ _ _ - _ - - _ _ - _ _ _ _ - _ _ _ _ l
r ._
-t
~ j-+.; ,
Kr WATERFORD 3 SE8 8IMULATOR No s . NTI-603.04_ PERFORMANCE TEST PROCEDURE REV: 0 ' STEADY STATE TEST PAGE:~6 OF 10'
+
ATTACEMENT 8.1 -I TEST PROCEDURE REPORT Performance: Test
Title:
Performance Test. Number:. . 4 Date Test Conducted:: i Procedure. synopsis:= l 3 s
. !%,i r
. If .any conditions below- arey ' es,: initial-.the appropriate statement and append a copy to this Attachment.
a TIf any. test exceptions -or' modifications were made 0 during the performance of Ethis test, append : 1 L Attachment 8.2 :(Procedure Remaiks Report) ..
.- If any problems were noted 'during the- performance of this test, append Attachment 8 3 (Test Problems Report)..
,q I. I; PERFORMED BY:
- DATE:
l 1 I-
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J:(M i- ' i _j -;WATERFORD 3 SE8-SIMULATOR NO : - -NTI-603.04 i PERFORMANCE TEST = PROCEDURE -REV: 0 STEADY STATE TEST PAGE 7 OF- 10 i
-h ATTACHMENT 4.2 -
t e TEST PROCEDURE REMARKS 3 , Include all test orocedure remarks and comments below. j L
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WATERFORD 3 SES SIMULATOR NO: NTI-603.04 PERFORMANCE TEST PROCEDURE REV: O STEADY STATE TEST PAGE: 8 OF 10 ATTACHMENT 8.3 TEST PROBLEMS REPORT SIMULATOR PROBLEM PROBLEM REPORT DESCRIPTION: WRITTEN: O O PERFORMED BY: DATE:
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PERFORMANCE TEST PROCEDURE .REV: 0 STEADY STATE TEST- PAGE::- 9 0F 10. , k
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ATTACEMENT.8.4
,i goNTINUATION SHEET Attachment # Page of. =-
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~ PERFORMANCE TEST PROCEDURE - REV : - 0 STEADY STATE TEST ~ PAGE: 10 OF 10 j
ATTACRMENT 8.5 DATA ACOUISITION , Using'SPVS,; snapshot the f'ollowing data points:
-DescriDtion Point ID Primary Systems Data PPS Linear Power . __
Log Power: Channels : Core-Thermal Power CEA-Position, Tcold" (All Loops) Thot- - (All Loops)
'Tave:
. Boron, concentration-t(f- - : )+ ' Pressurizer:
~
' ' ' ' tPressure _
Temperature LLevel. Secondary Systems Data:
!SteamiGenerators!'
Level'
=
Pressure-- . Tsteam Steam Flowrate Feed Flowrate
-Feed Temperature Blowdown ~Flowrate '
Turbine 1 Generator MWe-Condenser Vacuum t PERFORMED BY: DATE:
,, 7 _ __
t i 56 '.' 3 , "!
. ;-W h- .WATERFORD. 3. SES SIMULATORE . NO:. NTI-604.04
- PERFORMANCE TEST'- PROCEDURE REV: 0 4 TRANSIENT ~ TEST PAGE: 1.OF 11 L~ .
-c i: _ .
b SIMULTANEOUS.- TRIP OF ALL RCPs TEST DATE: 07/26/90 ANS-3.5- REQUIRED: :YES i
' CONTENTS i
[Jl [- 1.0
-2.0 P'JRPOSE
- R3FERENCES-
~
m 7
- 3. 0 INITIAL CONDITIONS 4.O DATA ACQUISITION:
U 5. 0. ACCEPTANCE-CRITERIA +..
,5 {l. , , . .. .
(' . 6.O TEST' PROCEDURE-7.0 TEST PROCEDURE RESULTS 80 : ATTACHMENTS' ~.
- i';
. PREPARED BY/DATE NfN k Y O k REVIEWED BY/DATE
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2 7d APPROVED BY/DATE W /- e [~d988
' SIMULATOR SUPERVISOR 9:
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OV WATERFORD 3 SES SIMULATOR NO: NTI-604.04 FERFORMANCE TEST PROCEDURE REV: 0 TRANSIENT TEST PAGE: 2 OF 11 SIMULTANEOUS TRIP OF ALL RCPs TEST 1.O PERFORMANCE TEST PURPOSE This test proves Waterford 3 Simulator calculated parameters, overall completeness and model integration when compared to available transient Waterford 3 SES conditions, as required by ANSI /ANS-3.5. 2.0 EEFERENCES 2.1 ANSI /ANS-3.5 American National Standard, Nuclear Power Plant Simulators for Use in Operator Training
- a. Section 4.2.1 - Transient Operation
- b. Section B2.2 - Transient Performance Tests n (Appendix B)
(.) 3.0 INITIAL CONDITIONS The Simulator will be initialized into 100% Power, Xenon equilibrium conditions for the performance of thic test. 4.0 DATA ACOUISITION Use SPVS File for collection of the specified data points and frequency _of sample. Attachment 8.5 identifies data collected. 5.0 Accentance Criteria: The following acceptance criteria shall be used to determine the acceptability of this performance test: 5.1 The simulator's critical parameters, as listed in Section 4.0, will demonstrate similarity with "best estimate" Waterford 3 design calculations or Waterford 3 data applicable to the scope of simulation. 5.2 The simulator will cause observable changes in parameters to correspond in direction to those from actual plant data or best estimate analysis of the
-A transient, and shall not violate physical laws of
() nature.
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- 3 PERFORMANCE TEST PROCEDURE- REV ' O-
' TRANSIENT TEST PAGE: 3 OF ~ 11 -- .
5 ~. O ~ ACCEPTANCE CRITERIA: 5.3 The - simulator will n'ot : fall; to cause an alarm c or y -automatic petion if:the Waterford 3 stati'on would have-causedian alarm'or automatic action,-andLconversely, _ - f the' simulator will not cause an automatic action-if the , M' -. reference plant.would not:cause an alarm, or automatic
.. actuation.
5.4- ..If no. approved.Waterford:3' actual plant data or best estimate analyses are available, comparisons against-1 design calculations willibe made and will-be' judged-by - PWR operations experienced-personnel against the-above . criteria. u - T
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l WATERFORD 3 SES SIMULATOR Not NTI-604.04 PERFORMANCE TEST PROCEDURE REV 0 TRANSIENT Tr.8T PAGE: 4 OF 11 6.0 TEST PROCEDURE INITIALS 6.1 Reset the simulator to 100% Full Power steady state conditions, IC- _. 6.2 Start time =_ . 6.3 Place the Simulator in Run, wait fifteen (15) minutes, and verify the following parameter trends are stable:
- Reactor Power
- RCS Coolant Temperatures
. Pzr Pressure and Level
- Steam Generator Levels
- Main Steam Flow
- Main Feed Flow Turbine Generator MWe 6.4 Initiate SPVS data collection, in accordance with Data Acquisition, Att. 8.5 6.5 ManualPf Trip all RCPs simultaneously.
6.6 Continue data collection until parameter trends are stable, wait an additional 10 minutes, then terminate this transient test. 6.7 Stop time = . Test Duration was . 6.8 Complete Attachments as necessary. O PERFORMED BY: DATE: ___m. _ _______ _____ _______._ _ _________ _ _ _____________ __________ ________ ____ ____ _ _ _ _ __
l; 1 WATERFORD 3 SES SIlfULATOR NO: NTI-604.04 PERFORMANCE TEST PROCEDURE REV: 0 TRANSIENT TEST PAGE: 5 OF 11 7.0 TEST PROCEDURE RESULTS INITIALS 7.1 As determined by test results, annotate the following:, 7.1.1 Test completed Satisfactorily. 1 Problems identified during the g conduct of this test procedure will be g logged on Attachment 8.3 of this test ; procedure and resolved in accordance ; i with NTP-015. , 7.1.2 After problems are corrected, and I the applicable procedure steps are ( retestad, this test proceduta is considered complete. 7.1.3 The test results are unsatisf actory. Complete retest of this test procedure is required following correction of problems. TEST STARTED: .. .
/
(Date and Time) TEST COMPLETE: / (Date and Time) TEST PERFORMED BY: DATE: TEST REVIEWED BY: DATE: O TEST ACCEPTED BY: SIMULATOR SUPERVISOR DATE: 1
7x. s- WATERFORD 3-SES SIMULATOR NO: ITTI-604. 04 PERFORMANCE TEST PROCEDURE REV: 0 TRANSIENT TEST PAGE: 6 0F 11 8.0 ATTACHMENTS 8.1 Test Procedure Report 8.2 Test Procedure-Remarks 8.3 Test Problems Report 8.4 Continuation Sheet 8.5 Data Acquisition Sheet _(~ d O v
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{ V)( WATERFORD.3 SES; SIMULATOR NO: ' N'I'I-604. 04 ' PERFORMANCE TEST PROCEDURE REV:1 0 , t TRANSIENT TEST PAGE: 7 OF 11 :-)
+
ATTACHMENT S.1 s _ IEST PROCEDURE REPORT , Performance. Test Title': 7 Performance Test Number: , Date'. Test Conducted: Procedure Synopsis:- I t
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- 3 i
(If -any conditions below are.yes, initial the" appropriate statementiand' append'a copy to this= Attachment.
- - If: any test exceptions or- modifications were ~made during. the- performance of this test, fappend '
Attachment 8.2.(Test Procedure Remarks). If:lany. problems. were noted during the performance. lof this test,: append Attachment 8.3:-(Test Problems-
'aeport).
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PERFORMED BY: DATE: w- m- g r mea y, a- -i-9s% -- - g +- - - m et-t'?77T*---g yg.-1-v-s '-*y- y y- + mg
WATERFORD 3 SES BIMULATOR NO: NTI-604.04 PERFORMANCE TEST PROCEDURE REV: 0 TRANSIENT TEST PAGE: 8 OP 11 ATTACHMENT 8.2 TEDT PROCEDURE REMARKS Include all test'orocedure remarks and comments below, O O PERFORMED BY: DATE:
.x ); WATERFORD 3 SES SIMULATOR NO: NTI-604.04 PERFORMANCE TEST PROCEDURE REV: 0 TRANSIENT TEST PAGE: 9 OF 11 ATTACHMENT 8.3 TEST PROBLEMS REPORT Simulator Problem Problem Report
Description:
Written:
. _,Y ,es 1 NY PERFORMED BY: DATE:
,~s s ) WATERFORD 3 SES SIMULATOR' NO: NTI-604.04 PERFORMANCE TEST PROCEDURE REV: 0 TRANSIENT TEST PAGE: 10 OF 11 ATTACEMENT 8.4 CONTINUATION SHEET Attachment # Page of f~)
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PERFORMANCE TEST PROCEDURE REV 0 , TRANSIENT TEST PAGE: 11 OF- 11 ATTACRMENT 8.5 1 DATA ACOUTSITIQ1{
, Using SPVS , File , collect the following data points simultaneously vs.; time with~a resolution of 0.5 seconds:
Descricti~on Point ID .;
- PRIMARY SYSTEMS DATA: ;
PPS Linear Power' ., 4 Source-Range Power ' q; , Tcold' (Loop l') Thot: (Loop 1) Tave- (Loop 1-)- ' 4 Pressurizer: < g .; Pressure- , 4 Temperature-A , Level . SECONDARY SYSTEMS DATA:-
- Steam Generators:- .
Level- (Loop 1)- a Pressurez .(Loop 1) 2 Steam Flowrate: (Total) 4 Feed'Flowrate ,
.(Total) !
+
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'i PERFORMED BY: DATE:
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-y:7-vi :; WATERFORD 3 SES SIMULATOR NO: NTI-619.37- + ,Qi j* "
- b PERFORMANCE TEST PROCEDURE REVt: 0 ,
MALFUNCTION TEST PAGE: 1:OF 19
+
- FW PIPE BREAK OUTSIDE CONTAINMENT ., !
MALFUNCTION.:-FW37 DATE: 08/15/90 t ANS-3,5- REQUIRED:-- YES
- TYPE:- GENERIC b
-CONTENTS-3 3 '
1
-1.0 TEST-' PURPOSE ry 2 .' O LREFERENCES ',
13.02 ' INITIAL CONDITIONS L4.0 DATA' ACQUISITION _:.5.0 -ACCEPTANCE CRITERIA
- 6. O' . TEST PROCEDURE- !
'7.0'
~
TEST PROCEDUREJRESULTS m
- 8. 0- ATTACHMENTS
-i
, PREPARED.BY/DATE M _ d 7.cJV/f8' r
l REVIEWED)BY/DATE (J 5:
, APPROVED.BY/DATE gp Y 4f $-23'95 -i
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/ SIMULATOR SUPERVISOR v
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() WATERFORD 3.8E8 SIMULATOR NO: NTI-619.37
,e PERFORMANCE TEST PROCEDURE REV 0 s
MALFUNCTION TEST PAGE: 2 OF.19 V FW PIPE BREAK OUTSIDE CONTAINMENT MALFUNCTION: FW37 1.0 TEST PURPOSE > _ The . . purpose of this test is to verify proper simulator response to-an FW pipe break outside-containment. h - 2 '. 0 REFERENqEE 2 .1- ~ ANSI /ANS-3.5 American National Standard, Nuclear Power Plant Simulators for Use in~ Operator Training
-2.2- Malfunction,Cause and Effect Document c 2.3 Waterford 3 Plant Data
, 2 .'4 -Waterford 3.~ATP -I
<l- V} :' -
- 3.O INITIAL ~ CONDITIONS
-TheLSimulator will be initialized into a 100%: power condition l for this performance test.
- The initiating. event for this s ",
test:is a_ break:between FW-184A(B) and penetration-#3(#4). 4.01 -DATA-ACOUISITION. n a Thatdata to be:collectediduring_the performance of this test via SPVS_is annotated?on Attachment 8.5 of this procedure. SiO ACCEPTANCE CRITERIA:
-The-following acceptance criteria shall be used to determine
=the-acceptability of this: performance-test: I 5.1 The ' Gimulator's critical- parameters, as listed in =
Section L 4.0, will' demonstrate cimilarity with "best N '
.' estimate", Waterford_ 3' Design- Calculations, or; ;
Waterford-3 ! data-applicable to the scope of simulation. 1 [s
'5.2- Ther~ Simulator'-will
. cause observable changes in parameters.to correspond in direction-to those from actual . plant- data, or best estimate analysis of the -
< _ transient. ~ Those changes shall not violate physical laws of nature. t: -(%] . k 4
G h WATERFORD 3 BES SIMULATOR Not NTI-619.37 PERFORMANCE TEST PROCEDURE REV: 0 MALFUNCTION TEST PAGE: 3 0F 19 5.3 The Simulator shall not fail to cause an alarm or automatic action if Waterford 3 would have caused an alarm or automatic action. Conversely, the Simulator shall not cause an alarm or automatic action if the reference plant would not cause an alarm or sutomatic actuation. 5.4 If no approved Waterford 3 actual plant data or best ectimate analyses are available, then comparison against Design calculations shall be made and will be judged by P.W.R. Operations Experienced Personnel against the above criteria. O
o E WATERFORD 3 SE8 8INULATOR NO: NTI-619.37 PERFORMANCE TEST PROCEDURE REV: O q MALFUNCTION TEST PAGE: 4 OF 19
-6.0- TEST PROCEDURE INITIALS 6.1- Reset the . simulator to 100% full power,
-steady state conditions,-IC-- .
6.2 Place'the simulator in run. 6.3 Insert malfunction FW37A 9 10%, 10% BREAK OFr LINE 2FW20-12A BETWEEN FW-184A & PENETRATION NO. 3. .
'l 6.4 Verify;the following-actions occur p FW pumps A and B discharge header pressure flowers,slightly. (CP-1, FWIPI2101A & B)
-FW pumps 1 flow to S/G 1 rise. (CP-1, ,
t -FWIFI2000A) V. SG 1 STEAM /FW LFLOW- SIGNAL. DEV - annunciates.- (CP-1, F, T-17). , FW> pumps flow-to S/G'2. lowers slightly.
.(CP-1,'FWIFI2000B) l
-S/G 1 level lowers, then returns to normal j
' level .1 (CP-8, SGILI1113)-
- 1
-i FWCS-responds to higher speed and higher i
? level position, S/G 2 level responds, S/G lj-level' .may L lower slowly. (Rx Trip may not -occur).- _ (CP-1,, FWSI2010A &- B, FWLT1500-& 16) t CD hotwell level lowers, > make-up opens and-level responds lowering-slowly.
' (CP-1, CDILI1900) i HOTWELL LEVEL HI/LO.- annunciates. ;
, (CP-1, F; G-11) : 1 HOTWELL LEVEL LO-LO - annunciates. !
- y)(
(CP-1, F, H-11)L i a A HOTWELL EMERGENCY MAKE-UP VALVE OPEN - annunciates.-(CP-1, F, H-12)
a. f~k ( )j WATERFORD 3 SE8= SIMULATOR: No t -- NTI-619.37 PERFORMANCE TEST PROCEDURE REV 0
- MALFUNCTION-- TEST PAGE: 5 0F 19 6.0 TEST' PROCEDURE (cont.)- INITIALS 9
At Low Hotwell. Level Condensate Pump Trip Setpoint,-the'Rx trips, on a Loss of Main JFeedwater.-(CP-2, RXTRIP) r i EFAS'-'l'&L2 initiate RTO L on - the FWCS occurs, causing S/G 1 , level to lower faster, with S/G 1 pressure lowering. L .(CP-8, SGILI1113 & SGIPI1115AS) { I '
-EFW flows to S/G 1:& 2 as level lowers. *
'(CP-8, EFWIFI8330A2) '
SIAS ; and- CIAS - may actuate on -low Pzr-
. , pressure.-
<k[ ~RCS-loop 1 Delta T > loop'2' Delta T.
.(CP-7, RCITIO102CB, HB, CA & HA)
.MSIS actuates on~ low S/G pressure, j C/G Delta - P isolates EFW to ~ S/G- 1 and- .
- level-starts 1to decrease.:
Plant-- : stabilizes lat some- lower temperature.
' 6.5 LVerify EFAS logic after MSIS only feeds- 7
.S/G 2.
6.6~ Reset' the? simulator to : 100% ; full power, steady state conditions,- IC-~ . j 6.7 - Place - the simulator::in ' run. ,
-- 6.8~ Insert malfunction FW37A 0L100%, 100% BREAK OFF :LINE 2FW20-12A- BETWEEN ' FW-184 A &
PENETRATION.NO.-3. [f.
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I WATERFORD 3 SES BIMULATOR NO: NTI-619.37 PERFORMANCE TEST PROCEDURE REV 0 MALFUNCTION TEST PAGE: 6 OF 19 6.0 TEST PROCEDURE (cont.) INITIALS 6.9 Verify the following actions occur: FW pumps A and B discharge header pressure lowers RAPIDLY. (CP-1, FWIPI2101A & B) FW pumps flow to S/G 1 rise rapidly. (CP-1, FWIFI2000A) SG 1 STEAM /FW FLOW SIGNAL DEV - annunciates. (CP-1, F, T-17) Pressurizer pressure lowers rapidly and may actuate SEAS and CIAS. Rx trip on low Pressurizer pressure. (CP-2, RCIPIO102) (' s S/G 1 level lowers rapidly, trips the
\ reactor / turbine and initiates EFAS 1 & 2 (CP-8, SGILI1113 & CP-2, RXTRIP)
S/G 2 level lowers and steadies out after EFAS initiation. (CP-8, SGILI1123) S/G 1 pressure lowers to zero, prompting MSIS actuation. (CP-8, SGIPIl013) RCS loops 1 & 2 Cold Leg temperatures rise rapidly then lower and steady out. (CP-7, RCITIO102CA & B) RCS loops 1 & 2 Hot Leg temperatures lower rapidly then rise and steady out. (CP-7, RCITIO102HA & B) 6.10 Verify EFAS logic after MSIS only feeds S/G'2. 6.11 S/G 1 blows dry terminating Plar.t cooldown. 6.12 Roset the simulator to 100% full power, steady state conditions, IC- . ( 6.13 Place the simulator in run. l 1
i s WATERFORD 3 BES SIMULATOR NO: NTI-619.37 PERFORMANCE TEST PROCEDURE REV: 0 MALFUNCTION TEST PAGE: 7 OF 19 6.0 TEST PROCEDURE (cont.) INITIALS 6.14 Insert malfunction FW37B 0 10%, 10% BREAK OF LINE 2FW20-12B BETWEEN FW-184B & PENETRATION NO. 4. 6.15 Verify the following actions occur: P4 pumps A and B discharge header pressure lowers. (CP-1, FWIP12101A & B) FW pumps flow to S/G 2 rise. (CP-1, FWIFI2000B) SG 2 STEAM /FW FLOW SIGNAL DEV -
,. annunciates. -(CP-1, F, U-17)
A FW pumps flow to S/G 1 lowers slightly. (CP-1, FWIFI2000A) S/G 2 level lowers, then returns to normal level. (CP-8, SGILI1123) FWCS responds to higher speed and higher level position, S/G 1 & 2 level responds, (A Reactor trip may not occur). (CP-1, FWSI2010A:& B, FWLT1500 & 16) CD hotwell level lowers, make-up opens and level responds lowering slowly. (CP-1, CDILI1900) HOTWELL LEVEL HI/LO - annunciates. (CP-1, F, G-11) HOTWELL LEVEL LO-LO - annunc'stes. (CP-1, F, H-11) HOTWELL EMERGENCY MAKE-UP VALVE OPEN - annunciates. (CP-1, F, H-12)
< ~3 - At Low Hotwell Level Condensate Pumps Trip -i ) Setpoint, the Rx trips on loss of Main Feedwater. (CP-2, RXTRIP)
EFAS - 1 & 2 initiate.
1 I
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-( )3 WATERFORD 3 SES SIMULATOR NO: NTI-619.37 PERFORMANCE TEST PROCEDURE- REV 0
. MALFUNCTION TEST PAGE: 8 OF 19 f
6.0 TEST PROCEDURE (cont.) INITIALS
~
RTO3on the _ FWCS causes S/G 2 level to !
, ' lower ' faster,..With S/G- 2 -pressure lowering. (CP-8, SGILI1123 & SGIPI1125AS)'
EFW flows to S/G 1 and 2 as level' lowers. (CP-8, EFWIFI8330A1) 1 c i
- SIAS - and c CIAS may - actuate on. low Pzr pressure.-
RCS loopi2 Delta T > loop 1 Delta T. (CP-7,;RCITIO102CB, HB,.CA & HA)=
- q LMSIS acc.UStas-on low S/G pressure.
i, . Iu/, ' S/G--De)ta F isolates EFW l to S/G 2 and
, levels sta c .o decrease.
Plant stabilizes 'af ter_ S/G 2 : blows l dry at
-some lower temperature.
6.16 _ Verify: EFAS - logic .after MSIS - only feeds -k S/G 1.- -l
. '6.17 J ResetT- the s i m u l a t o r t o . 1 0 0 %-- f u l l power, steady. state. conditions,-IC , .
6,18' Place the simulator in run.
- 6. '19 : . Insert malfunction FW36B 0.100%,100% BREAK OF -LINE 2FW20-12Bi BETWEEN FW-184B '&
, . PENETRATION-NO. 4. f k f
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WATERFORD 3 8E8-SIMULATOR. Not~ NTI-619.37 PERFORMANCE-TEST PROCEDURE REV: 0 MALFUNCTION TEST- PAGE: 9 OF 19 1 6.0'- TEST PROCEDURE (cont.)- INITIALS
- 6.20.-' Verify th'e'following actions occur:
3 FW pumps discharge header pressure lowers
' RAPIDLY. (CP-1, FWIPI2101A & B)
- FW pumps flow to S/G 2 rise rapidly.- U
;(CP-1, FWIFI2000A) =;
i
-S/G 2 feed flowilowers to zero. (CP-1-,
FWIFR1121) SG .2 ' STEAM /FW O CJ SIGNAL- DEV - .
'annunciates.: (CP-1,
',;U-17)
M Pressurizeri pressure lowers rapidly ~ may , i V', . actuate- SIAS' and CIAS. Rx Trips -on low Per
; pressure.: (CP-2,JRCIPIO102).
, . - 1 S/G .- 2 level olowers L rapidly,- - trips the
- leactor/ turbine and; initiates EFAS 1i& 2
-(CP-8FSGILI1123 &LCP-2,JRXTRIP) s S/Gil; level, lowers -and steadies i out af ter'
, EFAS{ initiation.-- (CP-8h SGILI1113) {
S/G 2: pressure lowers'tolzero,: prompting _
-MSIS-' actuation. (CP-8,' SGIPIl023)-
-.4.-
. ' RCSiloops 1 & 2 Cold Leg:.. temperatures rise :
-X (rapidly:then' lower and. steady out.
L[; # , ' (CP-7 ', .RCITIO102CA' &. B) - [ i < <- . . M' LRCS 1copo 1 &-2 Hot Lag . temperatures lower
')' t 1 rapidly then.risesand-steady out. - <
q '
-(CP-7F RCITIO102HAL&;B)-
\ . .. . . .
.c L T_ 5.21 Verify'EFAf logic after MSIS only~ feeds E , 'i S/G 1. .
i
- 6.22 S/G 2. blows d: y, terminating Plant cooldown.
%;Q . NQj . 6. 23, . Plsnt _ cooldown . to be commenced by plant
. operator.
!bd) . .. .- - ,,
O WATERFORD 3 SED SIMULATOR NO: NTI-619.37 PERFORMANCE TEST PROCEDURE REV: 0 MALFUNCTION TEST PAGE: 10 OF 19 6.0 TEST PROCEDURE (cont. INITIALS 6.24 Terminate f.his test of malfunction FW37. 6.25 Complete Attachments as necessary. O PERFORMED BY: DATE: l
WATERFORD 3 BES SIMULATOR NOt NTI-619.37 PERFORMANCE TEST PROCEDURE REV: 0 MALFUNCTION TEST PAGE: 11 0F 19 7.0 IEST PROCEDURE RESULTS Il4ITIALS 7.1 As determined by test results, annotate the following: 7.1.1 Test coupleted Satisfactorily. Problems identified during the conduct of this test procedure will be logged en Attachment 8.3 of this test procedure and resolved in accordance ; with NTP-015. , c 7.1.2 After problems are corrected, and
! the applicable procedure steps are retested, this test procedure is considered complete.
7.1.3 The test results are unsatisf actory. Complete retest of this test procedure is required following correction of problems. TEST STARTED: / (Date and Time) TEST COMPLETE: / (Date and Time) TEST PERFORMED BY: DATE: TEST REVIEWED BY: _, DATE: TEST ACCEPTED BY: DATE: SIMULATOR SUPERVISOR __ _ ______m______.__________.._._____________.____.___._____.________.,_m_.m __ -
l O WATERTORD 3 SES SIMULATOR 14 0 : liTI-619.37 PERFORMA! ICE TEST PROCEDURE REVt 0 MALTUllCTIOli TEST PAGEt 12 OF 19 8.0 ATTACHMENTS 8.1 Test Procedure Report 8.2 Test Procedure Remarks 8.3 Toot Problems Report 8.4 Malfunction Testing Report 8.5 Data Acquisition Sheet 8.6 Continuation Sheet O O i
-.._..__.m-._ _ _ _ .___. _ _ _ _ _ _ _ _ _ _ _ _ _ . _ - __.-..__-__._m___&-.-. -_u_-- .m___m _.. _.- _.__.__ .__ -- -
p t WATERFORD 3 DES SIMULATOR 11 0 : 11TI-619. 37 PERFORMANCE TEST PROCEDURE REV 0 MALFUNCTIO!1 TEST PAGE: 13 OT 19 ATTACHMEllT 8.1 TEST PROCEDURE REPORT Performance Test
Title:
Performance Test 11 umber: Date Test Conducted: Procedure Synopsis: If any conditions below are yes, initial the appropriate statement and append a copy to this Attachment.
- If eny test exceptions or modifications were made during the performance of this test, append Attachment 8.2 (Test Procedure Remarks).
- If any problems were noted during the performance of this test, append Attachment 8.3 (Test Problems Report).
+ If any malfunctions were used in this test, append Attachment 8.4 (Malfunction Testing Report).
PERFORMED BY: DATE:.
O WATERFORD 3 SES SIMULATOR 11 0 NTI-619.37 PERFORMANCE TEST PROCEDURE REV: 0 tiLTUNCTION TEST PAGE: 14 OF 19 ATTACHMENT 8.2 TEST PROCEDURE REMARKS Include all test nrocedure remarks and comments below. O O , PERFORMED BY: DATE:
O WATERFORD 3 SED SIMULATOR 11 0 : liTI-619. 37 PERPORMAllCE TEST PROCEDURE REV: 0 MALPUliCTIOff TEST PAGE: 15 OT 19 ATTACHMEliT 8. 3 TEST PROBLEMS REPORT Simuistor Problem Problem Report Descriptioni Written: O O : PERFORMED BY: DATE: _ _ _ _ - - . _ _ _ _ 'W$
- ' * -me WATERFORD 3 SES SIMULATOR NO: NTI-619.37 PERFORMANCE TEST PROCEDURE REV 0 MALFUNCTION TEST PAGE: 16 OF 19 ATTACHMENT 8.4 MALFUNCTION TESTING REPORT This att-c.hment provides data concerning tr.a types of malfunctions, simulator severity range and rates, options used, with initial and final conditions.
MALFUNCTION DESCRIPTION ANSI /ANS 3.5 NUMBER APPLICABLE ,-~, MALFUNCTION RATE AS TESTED INITIAL AND AND RANGE OPTIONS OPTION FINAL CONDITIONS 1 %). PERFORMED BY: DATE:
WATERFORD 3 SES SIMULATOR NO: NTI-619.37 PERFORMANCE TEST PROCEDURE REV: 0 MALTUNCTION TEST PAGE: 17 OF 19 ATTACHMENT 8.5 DATA ACOUISITION
=Using SPVS file , collect the following data points simultaneously vs. time with a resolution of 60 seconds:
DescriDtion Point ID FW Pump Discharge Header Pressuro FW Pump Discharge Header Pressure _ FW Pumps Flow to S/G 1 1 SG 1 STEAM /FW FLOW SIGNAL DEV
.' FW Pumps Flow.to S/G 2 S/G 1 Level S/G 2 Level HOTWELL LEVEL HI/LO HOTWELL LEVEL LO-Lo HOTWELL EMERGENCY MAKE-UP VALVE OPEN S/G 1 Pressure ETW Flow to S/G 2 RCS Loop 1 T RCS Loop 2 T
. CONDENSATE PUMP A TRIP / TROUBLE CONDENSATE PUMP B TRIP / TROUBLE CONDENSATE PUMP C TRIP / TROUBLE
- FWPT A' TRIP CD PUMP LOST
%J.
PERFORMED BY: DATE: l
.t + m v v n
O WATERFORD 3 SES DIMULATOR 11 0 : NTI-619.37 PERFORMANCE TEST PROCEDURE REV: 0 MALFUNCTION TEST PAGE: 18 0F 19 ATTACHMENT 8.5 DATAJCOUISITION Using SPVS file __ , collect the following data points simultaneously vs. time with a resolution of 60 secondo: Descrintion Point ID FWPT B TRIP CD PUMP LOST S/G Feedwater Flow Pressurizer Fressure S/G 2 Pressure S/G 2 STEAM /FW FLOW SIGNAL DEV O i PERFORMED BY: DATE:
7s I WATERFORD 3 SES SIMULATOR No: NTI-619.37 PERFORMANCE TEST PROCEDURE REV: 0 MALFUNCTION TEST PAGE: 19 OF 19 ATTACHMENT 8.6 CONTINUATION SHEET Attachment # - Page of /N 1__) C' 't PERFORMED BY: DATE:
O APPENDIX D PERFORMANCE TEST ABSTRACTS O O l
APPENDIX D (,, PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-601 PERFORMANCE TEST TITLE : MEASUREMENT OF MODEL REAL-TIME OPERATION INITIAL CONDITIONS : Simulator is initialized in the current Training Load at the EOC cotidition and left in FREEZE. The Maintenanco PC is required to perform this test and utilizes the simulation Timing . Study Display. TEST SYNOPSIS : The simulator is placed in RUN and operated for 15 min. to ensure stable conditions. Malf unction RC01, Less of All RCPs is then inserted and the simulator is allowed to run an additional 15 min. The PROMAC system is used to analyze the Gould Master Synchronization Task to determine the active simulator frame and whether all executivo programs were completed on time in the previous framo. Slipped frames are displayoJ on a D Timing Study Tableau [V Simulator analysis. for DATA COLLECTION : Data is collected via a cable connection betwoon the Maintenance PC and the Gould simulation computer. Data is recorded by the PROMAC system and stored on the PC hard disk for analysis, display, printout, and downloading to an archive floppy disk. TRANSIENT INITIATOR : There is no transient per so; however, Malfunction RC01 is entered via the Instructor's Station to exercise the simulation model as part of this test. TERMINATION CRITERIA: The test is terminated after a total Problem Time of 30 minutes has elapsod. EVALUATION RESULTS : The test determined that the number of frame slips over a 30 minuto period was
- 21. .
EVALUATION CRITERIA : The test acceptance critoria specified a slip rate of 51 slipped frame por minute D-1 V(3
APPENDIX D 7-
'\ PERFORMANCE TEST ABSTRACTS over a 30 minute period. j PLANT DATA REFERENCES : Not applicable DISSENTING OPINION ;
RESOLUTION : Not applicable TESTED BY : W. A. Lowranco 02/08/91 i REVIEWED BY , D. E. Barr 02/13/91 ' TEST ACCEPTED BY : W. L. Smith 02/13/91 l q Q l i
APPENDIX D : PERFORMANCE TEST ABSTRACTS
- PERFORMANCE TEST NUMBER NTI-602 PERFORMANCE TEST TITLE : PLANT STARTUP TO FULL POWER AND SHUTDOWN TO COLD CONDITIONS INITIAL CONDITIONS : 125'F, 150 psia, solid, no vacuum, End of Life TEST SYNOPSIS : Using plant procedures, the simulator will be started up to full power and stabilized to equilibrium xenon. The simulator will then be shutdown to cold conditions also using plant procedures.
DATA COLLECTION : Control Board indications and plant procedure calculations TRANSIENT INITIATOR : None TERMINATION CRITERIA : Successful completion of the plant startup and uhutdown EVALUATION'RESULTS : Multiple problem reports were generated g during the execution of this test.
-(
N - Problem areas included: secondary makeup, extraneous alarms, boron dilution monitor scales, low . decay heat, RCS mixing of Boron, temperature responses, CEA control, and ASI problems. Equilibrium xenon at 100% power was never achieved due to .ASI problems. Engineering analysis noted' that- the overall documentation of the test was weak. The test will' be rerun after correcting the problems. EVALUATION CRITERIA s Evaluation was- performed by PWR experienced engineering and operations personnel using . table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None-DISSENTING OPINION
-RESOLUTION: None TESTED BY : Wayne L. Smith (with others) 2/22/91 REVIEWED BY : Mark D. Phillippe 2/26/91 -
TEST ACCEPTED BY : Wayne L. Smith- 2/26/91
;i D-3 L
L
l APPENDIX D PERFORMANCE TEST ABSTRACTS PER5'ORMANCE TEST NUMBER NTI-603.01 PERFORMANCE TEST TITLE : STEADY STATE ACCURACY TEST, 45% POWER INITIAL CONDITIONS : Simulator is initialized in the curront Training Load at 45% power, equilibrium Xenon, steady-stato conditions and operated for 15 minutos to ensure that the IC is stab 111:od. TEST SYNOPSIS : At the end of 15 minutos, primary and secondary process paramotors are chocked for stability. SPVS data collection is initiated and a secondary calorimetric is performed in accordance with NE-05-201. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : There is no transient initiated during performance of this tost. TERMINATION CRITERIA: The test is terminated when the serandary
\ calorimetric has been completed.
EVALUATION RESULTS : The test data were collected over a period of 18 minutos and indicated no deviations in critical parameters. The secondary calorimetric performod using NE-5-201 indicated an average secondary power lovel of 48.76%. EVALUATION CRITERIA : The test results were reviewod by PWR oxperienced engincoring and operations personnel, in lieu of Waterford 3 actual plant data or a best estimato analysis, and no problems woro noted. However, it was dotormined that a standard set of data points were nooded to provide Reactor powur information to the SPVS data collection program. PLANT DATA REFERENCES : Not applicable DISSENTING OPINION RESOLUTION : Not applicable D-4 i _ _____.____._:m_-_ _ _ _ - - . - - - _ - - _ - - - - - - - - ___
APPENDIX D PERFORMANCE TEST ABSTRACTS TESTED BY : Mike Asher 09/26/90 REVIEWED BY : Mark D. Phillippo 10/19/90 TEST ACCEPTED BY : W. L . Stai t h 11/15/90 O O o-s b . . . _
APPENDIX D ,a (j PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-603.02 PERFORMANCE TEST TITLE t STEADY STATE ACCURACY TEST, 80% POWER INITIAL CONDITIONS : Simulator is initialized in the curront Training Load at 804 power, equilibrium Xenon, steady-stato, End of Cycle conditions and operated for 15 minutos to ensure that the IC is stabilized. TEST SYNOPSIS : At the end of 15 minutes, primary and secondary process paramotors are checked for stability. SPVS data- collection is initiated and a secondary calorimetric is performed in accordance with NE-05-201. DATA COLLECTION : Control Board indications and SPVS data collection p.ogram TRANSIENT INITIATOR : Thore is no transient initiated during performance of this tost. O TERMINATION CRITERIA: The test is terminated when the secondary V calorimetric has been completed. EVALUATION RESULTS : The tost data were collected over a period of 23 minutos and indicated no deviations in critical parameters. The secondary calorimetric performed using NE-5-201 indicated an average secondary power level of 85.38%. EVALUATION CRITERIA : The test results were reviewed- by PWR experienced engineering and operations . personnel, in lieu of Waterford 3 actual plant data or a best estimato analysis, and no problems woro noted. However, it . was determined that a standard set of data points were needed to provide Reactor power information to the SPVS data collection program. There were also minor dif forences between ~ he data points used by NE-5-201 and SPVS.for feodwater temperature and SG pressure. PLANT DATA REFERENCES : Not applicable O v D-6
APPENDIX D PERFORMANCE TEST ABSTRACTS DISSF*lTING OPINION RESOLUTION : Not applicable TESTED BY : Mike Asher 09/27/90 REVIEWED BY : Mark D. Phillippe 11/08/90 TEST ACCEPTED BY : W. L. Smith 11/08/90 O o n.,
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFOllMANCE TEST NUMBER NTI-603.03 PERFORMANCE TEST TITLE : STEADY STATE ACCURACY TEST, 100% POWER INITIAL CONDITIONS : Simulator is initielized in the curront Training Load at 100% powor, equilibrium Xenon, steady-stato conditions and operated for 15 minutos to ensure that the IC is stabilized. TEST SYNOPSIS : At the end of 15 minutos, primary and secondary process paramotors are chocked for stability. SPVS data collection is initiated and a secondary calorimotric is performed in accordance with NC-05-201. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR Thoro is no transient initiated during performanco of this tost. [} U TERMINATION CilITEllIA: The test is terminated when the secondary calorimetric has boon completed. EVALUATION RESULTS : The test data woro collected over a period of 16 minutes and indicated no deviations in critical paramotors. The secondary calorimetric performed using NE-5-201 indicated an average secondary power level of 99.92%. EVALUATION CRITERIA : The test results woro reviewod by PWR experienced ongincoring and operations personnel, in lieu of Waterford 3 actual plant data or a best estimato analysis, and no problems were noted. Ilowever, many secondary plant data points woro suspect in the SPVS data collection filo and Simulator Problem Reports woro genoruted to correct the discropancies. PLANT DATA REFERENCES : !?ot applicable DISSENTING OPINION RESOLUTION : Not applicable D-8
APPENDIX D PERFORMANCE TEST ABSTRACTS TESTED BY : Mike Asher 11/07/90 REVIEWED BY : Mark D. Phillippo 11/14/90 TEST ACCEPTED BY : W. L. Smith 01/24/91 O E' D-9
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-6U3.04 PERFORMANCE TEST TITLE : STEADY STATE STABILITY TEST, 1004 FULL POWER INITIAL CONDITIONS : Simulator is initialized in the curront Training Load at 100% power, equilibrium Xenon, steady-stato conditions and placed
, in lju_tj, TEST SYNOPSIS : No control manipulations are purformod for 1 hour as SPVS data collection is conducted. Control board indicators representing the same process paramotors ne ;ho SPVS data points are also monitored to ensure that they track consistent ly with the data being collected by SPVS.
DATA r.0LLECTION : Control Doord indications and SPVS c'ata collection program TRANSIENT INITIATOR : Thoro is no transient initiated during pcrformanco of this tost. TERMINATION CRITERIA: The test is terminated after 1 hour of simulator operation. EVALUATION RESULTS : The test data woro collected over a period of 59 minutos and indicated no deviations in critical paramotors. EVALUATION CRITERIA : The simulator computed values for steady stato, full power, automatic control operation with the typical Waterford 3 SES cont.rol configuration shall be stable and not vary by more than 2% of the initial values over a 60 minuto porlod. Soveral data points were suspect in tho SPVS data collection file and Simulator Problem Reports woro generated to correct the discropancies. PLANT DATA REFERENCES : Not. applicable DISSENTING OPINION RESOLUTION : Not applicable n D-10 (]
esema mi i APPENDIX D PERTORMANCE TEST ABSTRACTS TESTED BY Mike Asher 10/11/90 REVIEWED DY : Mark D. Phillippo 11/16/90 TEST ACCEPTED BY : W. L. Smi t.h 01/24/91 O O D- u
APPENDIX D (G) PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-604.01 PERFORMANCE TEST TITLE : REACTOR TRIP TEST INITIAL CONDITIONS : Simulator is initialized in the curront Training Loat at 100% powor, equilibrium Xenon, steady-stato conditions and oporated for 15 minutos to ensure that the IC is stabilized. TEST SYNOPSIS : At the end of 15 minutes, primary and secondary process paramotore are checked for stability. SPVS data collection is initiated. Tno canctor is manually tripped and no further control manipulations are pe riormod. When primary and secondary process paramotors have stabilized, data collection is continued for an additional 10 minutos. DATA COLLECTION : Control Board indications and SPVS data collection ptsgram TRANSIENT INITIATOR The transient is initiated by a manual [' Hoactor trip. TERMINATION CRITERIA: The test is terminated 10 minutos after primary and secondary parameters have stabilized. EVALUATION RESULTS : Data woro collected for approximately 24 minutes. No problems woro notede other than a continuous hCS cooldown due to heat removal via the steam-driven Main Foodwater Pumps and the Gland Steam System. EVALUATION CRITERIA : Data comparison was performed by PWR experienced engineering and operations personnel using their exportenco and any other available references, in lieu of approved Waterford 3 actual plant data or best estimato anal&os. , PLANT DATA REFERENCES Not applicable DISSENTING OPINION ' RESOLUTION : Not applicable D-12 , m I i { L
.---r- + -"
APPENDIX D ('- ( PERFORMANCE TEST ABSTRACTS TESTED BY : Hubert C. Crummoy 08/01/90 REVIEWED BY : Mark D. Phillippe 11/08/90 TEST ACCEPTED BY : W. L. Smith 11/08/90 4 4 e
\
D-13
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-604.02 PERFORMANCE TEST TITLE SIMULTANEOUS TRIP OF MFW T FPS TEST INITIAL CONDITIONS : Simulator is initialized in the current Training Load at 1004 power, equilibrium Xenon, steady-state conditions and operated for 15 minutes to ensure that the IC is stabilized. TEST SYNOPSIS : At the end of 15 minutes, primary ar.d secondary process parameters are checked for stability. SPVS data collection is initiated. Both Main Feedwater Pumps are simultaneously tripped and no further control manipulations are performed. When primary and secondary process parameters have stabilized, data collection is continued for an additional 10 minutes. b.%TA COLLECTION : Control Board indications and SPVS data collection program b b TRAN01ENT INITIATOR : The transient is initiated by manually tripping both Main Feedwater Pumps. TERMINATION CRITERIA: The test is terminated 10 ininutes af ter primary and accondary parameters have stabilized. EVALUATION RESULTS : Data were collected for approximately 48 minutes. No problems were noted. EVALUATION CRITERIA : The simulator data comparison was judged by PWR experienced engineering and operations personnel using their experience and any other available references in lieu of approved Waterford 3 actual plant data or best estimate analyses. PLANT DATA REFERENCES : Not applicable DISSENTING OPINION RESOLUTION : Not applicable TESTED BY : Hubert C. Crummey 07/31/90 REVIEWED BY : Mark D. Phillippe 10/16/90 A) ( D-14
APPENDIX D PERFORMANCE TEST ABSTRACTS TEST ACCFPTED BY : W. L. Smith 10/22/90 O i O l D-15 l \
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-604.03 PERFORMANCE TEST TITLE SIMULTANEOUS CLOSURE OF MSIVs TEST INITIAL CONDITIONS : 100t power, steady stato
'i'EST SYNOPSIS : From 100% power, manually shut both Main Steam Isolation Valves. Verify plant roSpoRBo.
DATA COLLECTION : Control Board indications and SPVS data collection program TTO\NSIENT INITIATOR : Manual closure of both MSIVs TERMINATION CRITERIA Paramotor trends are steady EVALUATION RESULTS t The test. har not boon performed. EVALUATION CRITERIA None PLANT DATA REFERENCESt Nono (If Applicable) O DISSENTING OPIN10N RESOLUTION: (If Applicable) None TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a D-16 1 \ _ _ _ _ _ - _ _ _ _ _ _ _ - _ . ._-____- _______________-_ - .-_ - - . - _ - -
APPENDIX D PERFORMANU TEST ABSTRACTS PERFORMANCE SEST m:6: DER NTI-604.04 PERFORMANCE TEST TITLE : DIMULTANEOUS TRIP OF ALL RCPs TEST 1NITIAL CONE'TIONS : Simulator is initialized in the current Training Load at 100% power, equillW1um Xenon, steady-state conditionL and operated for 15 minutos to ensure that the IC is stabilized. TEST SyNOPSls : At the end of 15 minutti4, pti b ry and . secondary procisa paramo1ero are checked for stability. SPVS datt collection is initiattd. All fout RCPs are
'imultaneously tripped and no further
, control manipulations are phr[ormed. When primary and secondary process parat.iotors have utabilized, data collection is ; continued for an additional 10 minutos. e-3 DATA COLLECTION t Control Board indications and SPVS data collection program TRANSIENT INITIATOR : The transient is initiated by Simu4taneously tripping all RCPs. TERMINATION CRITERIA: The test is terminated 10 minutos atter - y primary and secondary paramotors have stabilized. EVALUATION RESULTS : Data were collected for opproximately 25 minutos. No problems wer noted. FVALUATION CRITERIA : Data comparison was performed by PWR exportonced engineering and operationa J personnel using Lhoir experience and any other available references, in lieu of approved Waterford 3 ectual plant data or best estimate analysou. PLANT DATA REFERENCES : Not applicablo DISSENTING DPINION RESOLUTION : Not applicablo TESTED BY : Hubert C. Crummoy 08/01/90 REVIEWCD BY Mark D. Phillippe 11/08/90 TEST ACCEPTED BY : W. L. Smith 11/A8/90 D-17 1
a APPENDIX D PERFORMANCE TEST ABSTRACTS PERT'ORMANCE TEST NUMBER NTI-604.05 - PERFOr.MANCE TEST TITLE : TRIP ANY RCP TEST INITihL CONDITIONS : Simulator is initMalized in the current Training Load at 100% power, equilibrium Xenon, steady-state conditions and j operated for 15 minutes to ensure that i the IC is stabilized. ; TEST SYNOPSIS : At the end of 15 minutes, primary and 4 secoraary process parameters are checked 1 for stability. SPVS data collection is initiated. RCP 2A is manually tripped and no further control manipulations- are ,s performed. When primary and secondary
- process parameters have stabilized, data collection is continued for an additional i 10 minutes. !
DATA COLLECTION Control Board indications and SPVS data ' collection program. TRANSIENT INITIATOR , The transient is initiated by tripping ne RCP. 7ERMINATION CRITERIA: 'P . e test is terminated 10 minutes after l
- p. f ary and secondary parameters have l s t Vh .' i zod .
1 EVALUATION RESULTS Data. w're collected'ior-spproximately 24 'i ! minR4k. No problems were noted. 1 EVALUATION CRITERIA : Data comparison - was ' performed by PWR oxperienced . engineering and operations . perhonnel using their experience and any ' other available references, in lieu of : approved Waterford 3 actual plant data or best estimate analyses. PLANT DATA REFERENCES : .Not applicable .
- DKSSENTING OPINION RESOLUTION
- Not applicable
$" , TESTED BY : Hubert C. Crummey 08/02/90
- REVIEWED BY : Mark D.:Phillippa 11/08/90 3
TEST ACCEPTED BY : W. L. Smith 11/08/90 b D-18 t. P
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APPENDIX D PERFORMANCE TEST ABSTRACTS PURFORMANCE TEST NUMBER : NTI-604.06 PERFORMANCE TEST TITLE : LOSS OF LOAD INITIAL CONDITIONS : 60% power, steady state TEST SYNOPSIS : From 60% power, manually trip the Main Turbine. Verify plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : Manual trip of main turbine TERMINA? ION 4 RITERIA : Parameter trends are stable EVALUATION RESULTS : The test has not been performed. EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicable) O DISSENTING OPINION RESOLUTION: (If Applicable) None TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a D-19
>"DIA p
PERFORP, ST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-604.07 PERFORMANCE TEST TITLE : MAXIMUM RATE POWER RAMP TEST INITIAL CONOITIONS : Simulator is initialized in the current Training Load at 100% power, equilibrium Xenon, steady-state conditions. A reactivity calculation is performed to determine the reactivity associated with a 25% power decrease and the RCS is borated over a 5 minute period. The simulator is reset to 100% power and placed in R_U_ff. TEST SYNOPSIS : Reactor Power Cutback is placed in the auto-actuate mode. The Generator load control is set to drop load to 75% over a 5 minute period with MW feedback in service, and a load reductinn is initiated. When load has been reduced to 75%, primary and secondary process parameters are checked fer stability and no control manipulations are performed for 10 minutes. Another reactivity f] is calculation is performed for raising power to 100% and a dilution is initiated via Remote Function CV-93 to maintain a Tavg/ Tref mismatch of < 0.5 degrees F. The Generator load control is set to raise load to 100% over a 5 minute period and a load increase is initiated. Primary and secondary parameters are monitored for stability over a 10 minute period. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : The transient is initiated by lowering Generator load at a rate of 5% per minute. TERMINATION CRITERIA: The test-is terminat-d 10 minutes after primary and secondary parameters have stabilized at 100% power. EVALUATION RESULTS : Data were collected for approximately 63 minutes. No problems were neied. EVALUATION CRITERIA : Data comparison was performed by PWR b-20
APPENDIX D PERFORMANCE TEST ABSTRACTS experienced engineering and operations personnel using their experience and any other available references, in lieu of approved Waterford 3 actual plant data or best estimate analyses. PLANT DATA REFERENCES : Not applicable DISSENTING OPINION RESOLUTION : Not applicable TESTED BY : Hubert C. Crummey 08/01/90 REVIEWED BY : Mark D. Phillippe 11/08/90 TEST ACCEPTED BY : W. L. Smith 11/08/90 D-21
t APPENDIX D
) PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-604.08 PERFORMANCE TEST TITLE : LOCA RESPONSE WITH LOSS OF ALL OFFSITE POWER INITIAL CONDITIONS : 100% power, steady state TEST SYNOPSIS : From 100% power, initiate a Loss of Offsite Power and a Loop 1A Cold Leg Rupture. Verify plant response.
DATA COLLECTION Control Board indications and SPVS data collection program TRANSIENT INITIATOR : ED01A, B, C, and D, Loss of Offsite Power RC23A, Loop 1A Cold Leg Rupture TERMINATION CRITERIA : Parameter trends are stable. EVALUATION RESULTS : The test has not been performed due to problem reports scheduled to be worked. EVALUATION CRITERIA : None PLANT DATA REFERENCEb None A (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a D-22 l
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-604.09 PERFORMANCE TEST TITLE : EXCESS STEAM DEMAND INITIAL CONDITIONS : Simulator is initialized in the current Training Load at 100% power, equilibrium Xenon, steady-state conditions and operated for 15 minutes to ensure that the IC is stabilized. TEST SYNOPSIS : At the end of 15 minutes, primary and secondary process parameters are checked for stability. SPVS data collection is initiated. Malfunction MS11A (MSLB Inside CNTMT) is inserted at 100% severity. When primary and secondary process parameters have stabilized, data collection is continued for an additional 10 minutes. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : The transient is initiated by a Main IO Steamline Break inside the Containment O Building. TERMINATION CRITERIA: The test is terminated 10 minutes after primary and secondary parameters have stabi: zed. EVALUATION RESULTS : Data were collected for approximately 25 minutes. All recorded parameters responded correctly with tne exception of Containment ambient temperature which read 212 degrees F at 30 psia (Tsat , 250.34 d.gn9s F). A Problem Report was initiated . this discrepancy. EVALUATION CRITERIA : Data comparison was performed by PWR experienced engineering and operations personnel using their experience and any other available references, in lieu of approved Waterford 3 actual plant data or best estimate analyses. V) D-23
, . _ _ . . . , _ . . _ . , . _ _ . . . . . _ . _ . _ . , _ _ . . . _ . __ . . , . _ _ . . . . . . _ _ _ . _ . , _ - _ _ . . _ ~
..A-4 i
APPENDIX-D-- PERFORMANCE TEST ABSTRACTS , PLANT' DATA REFERENCES Not applicable-DISSENTING OPINION- ._ . i RESOLUTION : Not applicable-
- TESTED!BY- George M. Vaux,_Jr. 08/29/90 -
REVIEWED BY ._ Mark D. Phillippe 11/16/90 T E S T -' A C C E P T E D B Y:- , t W. L.-Smith - '11/26/90 _m ;
- 1
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APPENDIX D
) PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-604.10 PERFORMANCE TEST TITLE : SLOW RCS DEPRESSURIZATION TO SATURATION, NO HPSI INITIAL CONDITIONS : Simulator is initialized in the current Training Load at 100% power, equilibrium Xenon, steady-state conditions and operated for 15 minutes to ensure that the IC is stabilized.
TEST SYNOPSIS : At the end of 15 minutes, primary and secondary process parameters are checked for stability. SPVS data collection is initiated. Malfunction SIO2A, B, and C (HPSI Pump Auto-start Failure) are inserted. An Event Trigger is created to insert Malfunction RC01 (Loss of all RCPs) when RCS pressure reaches 1621 psia. Malfunction RCl2A (PRZR Safety Valve Leakage) is inserted at 10 % severity. No additional control manipulations are performed, and the test (3 is continued until the RCS Subcooling x_/- Monitor indicates < 0 degrees F subcooling. The Subcooling Monitor is then verified against the Steam Tables. Data collection is continued for 10 minutes after primary and secondary parameters have stabilized. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : The transient is initiated by a 10% look , on PRZR Safety Valve RC-0317A. TERMINATION CRITERIA: The test is terminated 10 minutes after primary and secondary parameters have stabilized. EVALUATION RESULTS : Data were collected for approximately 30 minutes. All recorded parameters responded correctly. EVALUATION CRITERIA : Data comparison was performed by rWR experienced engineering and operations personnel using their experience and any l f~%
) 9_25 l
i i
l APPENDIX D PERFORMANCE TEST ABSTRACTS other available references, in lieu of approved Waterf ord 3 actual plant data or best estimate analyses. PLANT DATA REFERENCES : Not applicable DISSENTING OPINION RESOLUTION : Not applicable TESTED BY : Hubert C. Crummey 08/07/90 REVIEWED BY : Mark D. Phillippe 01/22/91 TEST ACCEPTED BY : W. L. Smith 01/22/91 O
.-. .. . - . . - . . . . . . - . - - . . . - - - - -. .~ . -. - - - ..
'f APPT,NDIX D PERFORMANCE TEST ABSTRACTS
- PERFORMANCE TEST NUMBER -
NTI-604.11 I
- PERFORMANCE-TEST TITLE : REACTOR TRIP FOLLOWED BY RECOVERY TO RATED-POWER
'INITIALnCONDITIONS : 100% power, eteady state. ,
TEST SYNOPSIS : The test has not been written. - DATA COLLECTION : Control. Board indications and SPVS data-collection program'
. TRANSIENT. INITIATOR 1 None TERMINATION CRITERIA : None J EVALUATION RESULTS.: The test has not been performed. .
EVALUATION CRITERIA 1- None i PLANT DATA
REFERENCES:
None (If. Applicable) t
' DISSENTING. OPINION- -
RESOLUTION ' None
,(If Applicable)
TESTED BY:: n/a-REVIEWED ' BY: 't' - n/a '
= TEST ACCEPTED BY' L n/a "
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- APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-610.01 PERFORMANCE TEST TITLE : CCW PUMP (S) TRIP, MALFUNCTION CC01 INITIAL CONDITIONS : Simulator is initialized in the current Training Load at 100% power, equilibrium Xenon, steady-state conditions.
TEST SYNOPSIS : SPVS data collection is initiated. Malfunction CC01A (CC Pump A Trip) is inserted. Correct component and system responses are verified and recorded and the CCW system is allowed to stabilize. The Standby (AB) CCW Pump is started and system response is then verified again. Malfunction CC01B (CC Pump B Trip) is then inserted and component and system response is again verified. The CCW system is allowed to re-stabilize and Malfunction CC01C (CC Pump AB Trip) is then inserted. System and component response is then verified for a total loss of CCW flow. Data collection is f' continued until all parameter trends have stabilized. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR The transient is initiated by a trip of CCW Pump A. TERMINATION CRITERIA: The test is terminated after all parameters have stabilized. EVALUATION RESULTS : Data were collected for approximately 54 minutes. All recorded parameters responded correctly with the following exceptions: CCW Pump stator temperature did not follow amperage. CNTM Fan Cooler response was questionable. CNTMT ambient temperature points were not functional. ( D-28 I
APPENDIX D C's (j PERFORMANCE TEST ABSTRACTS RCP stator temperature response was questionable.- Problem Reports were written on all the above discrepancies. EVALUATION CRITERIA : Data comparison was performed by PWR experienced engineering and operations personnel using their experience and any other available references, in lieu of approved Waterford 3 actual plant data or best estimate analyses. PLANT DATA REFERENCES : Not applicable DISSENTING OPINION RESOLUTION : Not applicable TESTED BY : Hubert C. Crummey 09/22/90 REVIEWED BY : Mark D. Phillippe 01/21/91 TEST ACCEPTED BY : W. L. Smith 01/22/91 ( D-29
y APPENDIX-D . I PERFORMANCE TEST ABSTRA NS r PERFORMANCE TEST NUMBER :- NTI-C10.02
' PERFORMANCE TEST TITLE- : ACCW PUMP TRIP, MALFUNCTION CCO2
-i INITIAL CONDITIONS : Simulator'is initialized in the current !
Training Load at 100% power, equilibrium ! Xenon, steady-state conditions. TEST SYNOPSIS :
' -SPVS data collection 11s initiated. ' ACCWl Train A is placed in _ service and External-Parameter EP03 Ambient-Air Temperatureit- t 33 ft) is: raised to'107Jdegrees-F.L ACCW operation Tis verifledf-by observingL that -1 the WetlCooling-Towersfans have started.
MalfunctionsCC02A (ACCW Pump' A Trip)---is inserted. Correct component and: system responses are verifiedsand recordedyand the ACCW.systemiis allowed to stabilize. Malfunction CCO2B (ACCW PumptByTrip)"is then - inserted and = component f and s ys t.em . ; response is - again -verified., The iACCW systemi is. allowed to, re-stabilize and datar collection; is ' continued 3until all [:; parameter trends have stabilized. q QA .
.. DATA COLLECTION :: Control Board indicationsDand SPVS data collection-program. '
TRANSIENT INITIATOR': The transient.is initiated by a trip of ACCW= Pump A.- TERMINATION? CRITERIA: The test __ _is terminated ~ after iall e
' parameters-have' stabilized; EVALUATION RESULTS- : -Data-were:c.ollectedifor approximately 38 .
' minutes.1 . "All recorded parameters.
responded correctly with the exception of
, ACCW header flow meters, which continued to_ indicate system iflow with the respective ACCW pump tripped. A Problem'-
Report _w as written on the above ; discrepancy'. t
-EVALUATION CRITERIA -: l Data comparison ~ -'.was performed _ by PWR experienced engineering and ' operations personnel using their experience and any other ' available references,- in lieu of
, approved Waterford 3 actual plant data or J
D-30
. a.
APPEND 7X D' l
;- PERFORMANCE TEST ABSTRACTS best estimate analyses.
, PLANT DATA REFERENCES Not applicable r
DISSENTING OPINION RESOLUTION- : Not applicable P
--TESTED BY- : Mike Asher- 08/24/90 '
REVIEWED.BY , t - Mark D...Phillippe .- 10/18/90 TEST ACCEPTED BY t. . W . , L'. Smith. 10/19/90
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APPENDIX D () fm PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-610.03 PERFORMANCE TEST TITLE : CCW PUMP BEARING SEIZURE, MALFUNCTION CCO3 INITIAL CONDITIONS : Simulator is initialized in the current Training Load at 100% power, equilibrium Xenon, steady-state conditions. TEST SYNOPSIS : SPVS data collection is initiated. Malfunction CC03A (CC Pump A Bearing Seizure) is inserted. Correct component and system responses are verified and recorded and the CCW system is allowed to stabilize. The Standby (AB) CCW Pump is started and the system parameters are allowed to return to their pre-trip values. Malfunction CC03B (CC Pump B Bearing Seizure) is then inserted and component and system response is again verified. The CCW system is allowed to re-stabilize and Malfunction CC03C (CC Pump AB Bearing Seizure) in then f_3 inserted. System and component response V is then verified for a total loss of CCW flow, Data collection is continued until all parameter trends have stabilized. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : The transient is initiateo by a bearing failure and mechanical seizure of CCW Pump A. TERMINATION CRITERIA: The test is terminated after all parameters have stabilizad. EVALUATION RESULTS : Data were collected for approximately 38 minutes. All recorded parameters responded correctly with the following exceptions: CNTM Fan Cooler response was questionable. CNTMT ambient temperature points were not functional. 1 s D-32 (] I
- - - - - - - - - - . . - 64 .----.
APPENDIX D PERFORMANCE TEST ABSTRACTS RCP stator temperature response was questionable. , Problem Reports were written on all the above discrepancies. EVALUATION CRITERIA : Data compatison was performed by PWR experienced engineering and operations personnel using their experience and any other available references, in lieu of approved Waterford 3 actual plant data or best estimate analyses. PLANT DATA REFERENCES : Not applicable DISSENTING OPINION RESOLUTION : Not applicable l TESTED BY : 11ubert C. Crummey 09/22/90 REVIEWED BY : Mark D. Phillippe 10/17/90 TEST ACCEPTED BY : W. L. Smith 10/17/90 0 D-33
APPENDIX D (3 () PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-610.05 PERFORMANCE TEST TITLE : COOLING TOWER FAN (S) TRIP, MALFUNC"'1N CC05 INITIAL CONDITION 4 : Simulator is initialized in the current Training Load at 1001 power, equilibrium Xenon, steady-stato conditions. TEST SYNOPSIS : SPVS data collection is initiated. Malfunction CC05A (Cooling Tower A Fans Trip) is inserted. Correct componont and system responses are veriflod and recorded and the CCW system is allowod to stab 41zo. The simulator is then resot and SPVS data collection re-started. Malfunction CC05B (Cooling Tower Fans B Trip) is then inserted and component and system response-is again veriflod. The CCW system is allowed to re-stabilize and-data collection is continued until all parameter trends have stabilized. DATA COLLECTION : Control Board indications and SPVS data v collection program TRANSIENT INITIATOR : The transient is initiated by a trip of CCW Cooling Tower A Fans. TERMINATION CRITERIA: The tost- is terminated after all paramotors have stabilized. EVALUATION RESULTS- Data woro collected for approximately 58 minutos. All _ recorded parameters responded correctly with the exception of RCP stator temperatures, which did not rise as CCW temperature increased. A Problem Report was written on the above discropancy. EVALUATION CRITERIA- Data comparison was performed by PWR L experienced engineering and operations personnel using their experience and any other available references, in lieu of approved Watorford 3 actual plant data or best estimato analysos. PLANT DATA REFERENCES : Not applicable
) D-34
l APPENDIX D PERFORMANCE TEST ABSTRACTS DISSENTING OPINION RESOLUTION : Not applicable TESTED BY : Hubert C. Crummey 09/22/90 REVIEWED BY : Mark D. Phil11ppo 10/16/90 TEST ACCEPTED BY : W. L. Smith 10/19/90 O o D->s
APPENDIX D k PE RFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-610.06 PERFORMANCE TEST TITLE : RCP SEAL CLR OUTLET VLV FAILURE OPEN/ CLOSED, MALFUNCTION CC06 INITIAL CONDITIONS : Simulator is initialized in the current Training Load at 100% power, equilibrium Xenon, steady-stato conditions. TEST SYNOPSIS : SPVS data collection is initiated. Malfunction CC06Al (Seal Cooler Viv CC679A Fails Open) is inserted and system response is verified (valve is normally open). Malfunction RC29A (RCP 1A Seal Cooler Leak From RCS) is then inserted at 50% severity. Component and system response are verified. The simulator is reset and the test ir repeated using Malfunctions CC06B1 through D1 and RC29B through D. After Malfunction RC290 has b(en tested, the simulator is reset and Malfunction CC06A2 (Seal Cooler Viv CC679A Fails Closed) is inserted. RCP (g) seal degradation is verified to occur U within 30 minutes of loss of seal cooling. The simulator is reset and the test repeated using Malfunctions CC06B2 through D2. DATA COLLECTION : Control-Board indications and SPVS data collection program TRANSIENT INITIATOR : The transient is initiated by a failure of the RCP seal cooler package. TERMINATION CRITERIA: The test is terminated after all parameters have stabilized. EVALUATION RESULTS : Data were collected for approximately 37 minutes. All recorded parameters responded correctly. EVALUATION CRITERIA : Data comparison was performed by PWR experienced engineering and operations personnel using their experience and any other available references, in lieu of approved Waterford 3 actual plant data or best estimate analyses. D-36
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, - 1
-APPENDIX D. .;
' PERFORMANCE TEST-ABSTRACTS-PLANT DATA'
REFERENCES:
Not applicable ; LDISSENTING OPINION-RESOLUTION- l' Not applicable-
> TESTED BY : Mike Asher 10/25/90 REVIEWED ' BY- - Mark D. Phillippe 11/12/90
-TEST. ACCEPTED.BY W. L. Smith -11/15/90 0
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APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-610.07 l'ERFORMANCE TEST TITLE : LOSS OF CCW TO CEDM COOLERS, MALFUNCTION CC07 INITIAL CO:iDITIONS : Simulator is initialized in the current Training Load at 100% power, equilibrium Xenon, steady-state conditions. TEST SYNOPSIS : SPVS data collection is initiated. All CEDM Coolers are verified to be operating. Malfunction CC07A (Loss of CCW to CEDM Cooler A) is inserted and system response is verified. The test is repeated using Malfunctions CC07B through D. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : The transient is initiated by a loss of CCW to CEDM Cooler A. C.N, TERMINATION CRITERIA: The test is terminated after verifying (_/ the simulator response to Malfunction CC07D. EVALUATION RESULTS : Data were collected for approximately 30 minutes. CCW flow could not be completely . stopped to the CEDM Coolers, and temperature changes occurred too rapidly. A' Problem Report was written to correct the simulator response. EVALUATION CRITERIA : Data comparison was performed by PWR experienced engineering and operations personnel using their experience and any other ' available references, in lieu of approved Waterford 3 actual plant data or best estimate analyses. D-38
APPENDIX D PERFORMANCE TEST ADSTRACTS PLANT DATA REFERENCES : Not applicable DISSENTING OPINION RESOLUTION : Not applicable TESTED BY : llubert C. Crummoy 08/20/90 REVIEWED BY : Mark D. Phillippe 10/18/90 TEST ACCEPTED BY : W. L. Smith 10/19/90 0 0 D->e
APPENDIX D r~N ( ). PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-610.08 PERFORMANCE TEST TITLE : LOSS OF CCW TO EDG, MALFUNCTION CC00 INITIAL CONDITIONS : Simulator is initialized in the current Training Load at 100% power, equilibrium Xenon, steady-state conditions. TEST SYNOPSIS : SPVS data collection is initiated. Emergency Diesel A is started and loaded, and CCW system response is verified. Malfunction CC08A (Loss of Cooling Water to Diesel Generators) is inserted and the Diesel is verified to trip in approximately 10 minutes. The test. is repeated by starting and loading EDG B and inserting Malfunction CC08B. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : The transient is initiated by a loss of /) V CCW to EDG'A. TERMINATION CRITERIA: The test is terminated after verifying the simulator response to Malfunction CC08B. EVALUATION RESULTS : Data were collected.for approximately 44 minutes. No problems were identified. EVALUATION CRITERIA : Data comparison was performed by PWR experienced engineering. and operations personnel using their experience and any , other available references, in lieu of approved Waterford 3 actual plant data or best estimate analyses. PLANT DATA REFERENCES : Not applicable DISSENTING OPINION RESOLUTION : Not applicable
-TESTED BY : Hubert C. Crummey -09/23/90 REVIEWED BY : Mark D. Phillippe 10/16/90 TEST ACCEPTED BY : W. L. Smith 10/17/90 l D-40 m
t APPENDIX D
'.Q - .
PERFORMANCE TEST ABSTRACTS
- PERFORMANCE-TEST NUMBER : NTI-610.09 PERFORMANCE TEST TITLE : LOSS OF CCW TO-CNTMT FAN COOLERS INITIAL CONDITIONS : 100% power, steady state TEST SYNOPSIS : From 100% power, fail. the temperature-control valve for CCW to the containment fan coolers. Verify plant response. ,
DATA: COLLECTION : Control Board indications and SPVS data y collection program TRANSIENT INITIATOR : CC09A and .CC098, Loss of CCW oto Containment Fan Coolers-TERMINATIONiCRITERIA : Containment-air temperature stabilizes EVALUATION RESULTS - The test has not been performed. EVALUATION CRITERIA : None ' w .. PLANT-DATA
REFERENCES:
None-( h (If-Applicable)'
\_/
DISSENTING OPINION
~
-RESOLUTION - .None
.(If Applicable)
TESTED BY- .n/a REVIEWED BY n/a
-TEST ACCEPTED BY : n/a f l
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= APPENDIX D p)T 1( PERFORMANCE TEST ABSTRACTS L
. PF.RFORMANCE-TEST NUMBER NTI-610.10 ;
. PERFORMANCE TEST TITLE : LOSS OF CCW TO SDCHX, MALFUNCTION CC10 INITIAL CONDITIONS : Simulator is initialized-in the current Training Load at Cold Shutdown, Solid Plant' conditions.
TEST SYNOPSIS : SPVS data collection is- initiated. Malfunction CC10A.(Loss of CCW to SD HX) is inserted and RCS heatup and , pressurization- are verified. The simulator. la = reset and- the_ test .is repeated by inserting Malfunction CC10B.
' DATA-. COLLECTION : Control Board indications and SPVS data collection program ,
- TRANSIENT INITIATOR -
The transient-is initiated by a loss of CCW to-SDCHX A. _.: TERMINATION-CTITERIA' The test is - terminated. af ter verifying O. : the simulator response- to Malfunction V- CC10B.- EVALUATION RESULTS :- -Data were-collected for approximately 28 minutes. No problems were identified.
- EVALUATION CRITERIA : Data comparison: was performed by PWR experienced engineer.ing and opera tions --
personnel using their experience and any othereavailable reierences, in lleu- of'
+
. approved Waterfordi3_ actual plant data or a T .best estimate analyses. g PLANT DATA REFERENCES :~ Not applicable-1 DISSENTING OPINION l RESOLUTION- Not applicable TESTED BY- .
Hubert C.-Crummey- 08/20/90 !, REVIEWED BY : Mark <D, Phillippe .12/13/90 i' TEST ACCEPTED BY. : W. L. Smith 12/20/90 i i
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APPENDIX D PERFORMANCE TEST ABSTRACTS
-PERFORMANCE TEST NUMBER. I NTI-630.12 PERFORMANCE TEST TITLE : CCW SURGE TANK LEVEL SIGNAL FAILURE !
HI/LO, MALFUNCTION CC12 1
' INITIAL CONDITIONS : Eimulator is' initialized in-the current Training Load at 100%-power, equilibrium Xenon, steady-state conditions.
TEST SYNOPSIS : This test checks-the 6 -level transmitters associated with- the- CCW Surge Tank.- Various control actions-are initiated by each level transmitter depending on its failure mode. A small CCW leak is used to initiate makeup. The following is a-list' lof the malfunctions, level transmitters,- , and expected ~ control actions tested. during performance of.this-procedure:
.CC12Al- LS*/ 010S :H1' Closes normal makeup valve CMU-226.;
ICC12A2- :LS7010S Lo Opens normal makeup valve CMU-226. =l
#~h CC12B1 LS7011AS Hi- Closes makeup valve CMU-538A.
- -Q CC12B2 LS7011AS Lo Opens CMU-538A and starts Makeup
. Pump A.-
CC12Cl- LS7011BS Hi Closes. makeup valve CMU-538B. CC12C2 LS7011BS Lo LOpens CMU-5388 and ' starts MakeupL Pump B. JO CC12D1 LS7012S Hi- -No-effect. CC12D2. LS7012S Lo. Opens-normal makeup: valve CMU-226. e, CC12E1 LS7013AS Hi -No-effect. O CC12E2: LS7013AS Lo Isolates'CCW-Train-A. CC12F1 -LS7013BS.Hi No effect. q _CC12F2 LS7013BS Lo : Isolates CCW Train B. DATA COLLECTION =: Control Board Indications and SPVS data collection program (i D-43 i_
APPENDIX D PERFORMANCE TEST ABSTRACTS TRANSIENT INITIATOR There is no transient associated with this test. TERMINATION CRITERIA: The test is terminated after verifying the simulator response to Malfunction CC12F2. EVALUATlaN RESULTS ? Aside from minor data collection problems, there were no discrepancies noted during performance of this test. EVALUATION CRITERIA : Da t.a comparloon was performed by PWR experienced engineering and operations personnel using their experience and any other available referencas, in lieu of approved Waterford 3 actual plant data or best estimate analyses. PLANT DATA REFERENCES : Not applicable DISSENTING _ OPINION RESOLUTION : Not applicable Mike Asher- 09/19/90 O' TESTED BY REVIEWED BY
- Mark D. Phillippe 12/17/90 TEST ACCEPTED BY : W. L. Smith 01/24191 D-44
APPENDIX D PERFORMANCE TEST ABSTRACTS , ! PERFORMANCE TEST NUMBER NTI-6IO.15 PERFORMANCE TEST TITLE : LOSS OF CCW TO LPSI PUMP COOLERL, MALFUNCTIOh CC15 INITIAL CONDITIONS : Simulator is initialized inn the currt nt Training Load at 100% power, equilibur,9 Xenor., steady-state a:onditions. TEST SYNDPSIS : SPVS dota col.]ection is initiated. L'!SI Ptunp a le started. Malfunction CC15A (Loss of CCW to LPSI Pump Coolee A)-is innrted and system response is verified.
'1 h e simulator is reset, LPSY Pump B is started, and the test is repeated using Msifunc+. ion CC15B.
DhTA COLLECTION : Control Board indications and SPVS data collection pro 1 ram
'IRANSIENT INIT'I ATOR : There Ja no transient asuoi.tated with this Malfunction Test.
TERMINATION CRITERIAt The test 19 terminated af ter verifying ( the simulator response to Malfunction
=L CC15B.
EVALUATION RESULTS : Data were collected for approximotely 10 minutes. There were no p r o b l w.4s noted during performance of this test. EVALUATION CRITEP.IA : Data comparison was performed by PWR experienced engineering and operations personnel using their experience and any other avulloble references, in lieu of approved Waterford 3 actual plant data os best estimate analyses. PLANT DATA REFERENCES : Not app 11 cable DISSENTING OPINJON RESOLUTION : No*. applicable TSSTED B1 : Hubert C. Crum:ney 08/20/90 REVIEWED llY : Mark D. khillippo 10/18/90 TEST ACCEPTED BY : W. L. Smith 10/19/90 D-45
APPENDIX D PERFORMANCE TEST ABSTRACTS ?- PE RFORMANC - TEST NUMBER : NTI-610.16 PEHFOIOENCE TEST TITLE : CCW LEAK IN CNTMT (O TO 100% OF FLOW AT PRESS), MALFUNCTION CC16 INITIAL CONDITIONS : Simulator is initialized in the current Training Load at 100% power, equilibrium Xenon, steady-state conditions. TEST SYNOPSIS : SPVS data c.ollection is initiated. Malfunction CC16 (CCW Unisolable Leak In Containment) is lasrQw at 10 % w ynt )- e-(10t of CCW fio.. ,, r,d 3, stem robgobae is [4: verified. Tne sli,L4 atar is reset and
' Mal f unc tior. CC16 is inserted (. 100%
severity. Pp tem resp;nse f r< again f-verified w j :. .s specific emphasis on CCW )
;f bood'r isole.t. ion valve p^%1tionaa and Di'y Cou; " ,,7 Tower operatloaal responce. RCP f tempA4 'ure responst is alJo verigied during W e ueste DATA COLLECTION ; CoM.rcl Board iodi', ations and SDVS data ct e ction program 3 TRANSIENT INITIATOR : There la no transisint associatm with f I
this Malfunction Test. [ TERMINATION CRITERIA: The test is terminated af ter verjiying the almulator response to Malfunction CC16 at 100% severity. EVALUATION RESULTS : Data were collected for approximatelv 18 minutes. There were several comra ats generated regarding valve responses not addressed in the test procedure; however, it was later determined that the valves responded correctly based on actual simulator conditions. The test procedure .' will be revised to address these concerns. There were no Problem Reports generated during this test, f I EVALUATAON CRITERIA : Data comparison was performed by PWR experienced engineering and operations
, personnel using their experience and any other available references, in lieu of 's
; approved Waterford 3 actual plant data or D-46 1
p-APPENDIX D p.-~ i s ,) PERTORMANCC TEST ABSTRACTS b M t. e s t i m a t e a n a l y s e s . PLANT DATA REFERENCES : Not applicable DISSENTING OPINION , RESOLUTION Not applicable TESTED DY : Hubert C. Crummoy 08/20/90 REVIEWED BY : Mark D. Phillippe 10/18/90 TEST ACCE)TED BY t W. L. Smith 10/19/90
=
4 l
APPENDIX D g v) PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-610.17 PERFORMANCE TEST TITLE : RUPTURE OF CCW PUMP DISCHARGE PIPE (0 - 1004), MALTUNCTION CC17 INITIAL CONDITIONS : Sieulator is initialized in the current Training Load at 100% power, equilibrium Xenon, steady-state conditions. TEST SYNOPSIS : SPVS data collection is initiated. Malfunction CC17A (Rupture of CCW Dischargo Piping) is inserted at 10% severity (104 line rupture on CCW Pump A), and system responso is veriflod. The simulator is roset and Malfunction CC17A is inserted at 90% soverity. System responso is again verified with specific emphasis on CCW header isolaition valvo positions, Dry Cooling Tower, and CCW Train B operational response. The simulator is agair roset and Malfunction CC17B is inserted at 10% severity (10% line rupture on CCW Pump B). System (D C/ response to the Train B leak is verified. The simulator is roset and Malfunction CC17B inserted at 100% sovority. System responso is again verified with specific emphasis on CrW header isolation valvo positions, Dry Cooling Tower, and CCW Train A operational response. The simulator is roset and the CCW System is aligned with the Train B and Train AB CCW Pumps in operation. Malfunction CC17C is inserted at 10% severity (104 line rupture on Pump AB) and system responso is veriflod. The simulator is roset and Malfunction CC17C is inserted at 90% severity. System responso is again verified with specific emphasis on CCU header isolation valvo positions, Dry Cooling Tower, and CCW Trains A and B operational responso. DATA COLLECTIO5 : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : There is no transient associated with this Malfunction Test, [J D-48
i APPENDIX D PERFORMANCE TEST ABSTRACTS TERMINATION CRITERIA: The test is terminated after verifying the simulator responso t.o Malfunction CC17C at 90% severity. EVALUATION RESULTS : Data were collected Ior Adontifled critical paramotors. There were several Problem Reports generated regarding the response of flowrate, pressure, and temperature fur the RCP seals and CCW headers. EVALUATION CRITERIA : Data comparison was performed by PWR experienced engAncoring and operations personnel using their exporlence and any other available references, in lieu of approved Waterford 3 actual plant data or best estimato analysos. PLANT DATA REFERENCEE : Not applicablo DISSENTIFG OPINION RESOLUTION Not ap,n'icable TESTED BY : Miko Asher 08/21/90 O~ REVIEWED BY : Mark D. Phillippe 12/10/90 TEST ACCEPTED BY : W. L. Smith 12/20/90 D-49 4
i l APPENDIX D
,Q Q PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUldSER NTI-610.18 PERFORMANCE TEST TITLE : CCW TUBE LEAK IN CNTMT FAN COOLERS (0-100%), MALFUNCTION CC18 INITIAL CONDITIONS : Simulator is initialized in the current Training Load at 100t power, equilibrium Xenon, steady-stato conditions.
TEST SYNOPSIS : This test checks the 2 CCW cooling coils in each of the 4 CNTMT Fan Cooler Units. A leak rate of 10% severity is inserted f ust, followed by a simulator roset and then a 100% soverity leak. CCW System rotponso is evaluated as well as Far Choier responso and CNTMT responso. DATA COLLECTION : Contr al Board indications and SPVS data ccille,ction program TRANSIET7 INITIATOR : Th0ro is no transient associated with _ th:.5 tost, f C TERMINATION CRITERIA: The vest is terminated af ter verifying the simulator response to Malfunction CC18H. EVALUATION RESULTS : A gonorAc problem was identifiod in that none of the CNTMT Fan Cooler drain ilow SWitC?ses indicated leakage flow during test tr.g. A Problem Report was generated. EVALUATION CRITERIA : Data lomparison was performed by PWR ex;--8 9nced engineering and operations pers onel using their experience and any ot%r available references, in lieu of
- mpr >ved Waterford 3 actual plant data or best estimato analyses.
PLANT DATA REFERENCES : Not applicable DISSENTING OPINION RESOLUTION : Not applicable TESTED BY : Mike Asher 08/21/90 REVIEWED BY : Mark D. Phillippe 10/18/90 TEST ACCEPTED BY : W. L. Smith 01/19/90 D-50
i i r APPENDIX D s rj PERFORMANCE TEST ABSTRACTS I PERFORMANCE TEST NUMBER NTI-610.19 ' PERFORMANCE TEST TITLE : AUX CCW PUMP DISH HDR RUPTURE (1-100% OF FLOW) a f INITIAL CONDITIONS : 100% power, steady state ! TEST SYNOPSIS : From 100% power, isolate the dry cooling , tower-for the tested loop. Then insert the .'ux CCW pump discharge header rupture at 1M and 90% rates. Verify plant responte. DATA COLLECTION 3- Control Board indications and b'1V data collection program TRAdSIENT: INITIATOR- CC19A. and B, Aux CCW Pump Discharge Header Rupture
' TERMINATION CRITERIA's ACCW temperature control. valve opens to -;
lower CCW temperatures EVALUATION RESULTS : The test has not been performed due to l
-[ problem reports scheduled to be worked.
EVALUATION CRITERin.- None , PLANT DATA
REFERENCES:
None t (If Applicable) DISSENTING. OPINION
-RESOLUTION: None
.(If Applicable)
-n/a TESTED BY :
y REVIEWFD BY : n/a
. TEST ACCEPTED BY : n/a r
P I
APPENDIX D () PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-610.21 PERFOP.MANCE TEST TITLE : CCW LINE BREAK IN THE AUXILIARY BUILDING (0-100% OF 20" LINE), MALFUNCTION CC21 INITIAL CONDITIONS : Simulator is initialized in the current Training Load at 100% power, oquilibrium Xenon, steady-stato conditions. TEST SYNOPSIS : SPVS data collection is initiated. Malfunction CC21A (Rupture of CCW Pump A Discharge Piping) is inserted at 10% severity, and system response is verified. The simulator is roset and Malfunction CC21A is inserted at 90% severity. System responso is again verified with specific emphasis on CCW header isolation valve positions, Dry Cooling Tower, and CCW Train B operational response. The simulator is again reset and Malfunction CC21B is 7 inserted at 10% severity (10% line I rupture on CCW Pump B). System response x to the Train B leak is verified. The simulator is roset and Malfunction CC21B inserted at 90% soverity. System response is again verified with specific emphnsis on CCW header isolation valvo positions, Dry Cooling Tower, and CCW Train A operational responso. The simulator is reset and the CCW System is aligned with the Train B and Train AB CCW Pumps in operation. Malfunction CC21C is inserted at 10% severit.y (10% line rupture on Pump , AB) and system response is verified. The simulator is reset and Malfunction CC21C is inserted at 90% severity. System response is again verified with specific emphasis on CCW header isolation valve positions, Dry cooling Tower, and CCW Trains A and B operational response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR There is no transient associated with this Malfunction Test. ( D-52
APPENDIX D O 'd PERFORMANCE TEST ABSTRACTS TERMINATION CRITERIA: The test is terminated after verifying the simulator response to Malfunction CC21C at 90% sovority. EVALUATION RESULTS : Data were collected for identiflod critical paramotors. RCP seal roturn temperature was not responsive to degradation of CCW flow. A Problem Report was generated. EVALUATION CRITERIA : Data comparison was performed by PWR experienced engineering and operations personnel using their exporlonce and any other available references, in lieu of approved Watorf ord 3 actual plant data or best estimate analysos. PLANT DATA REFERENCES : Not applicable DISSENTING OPINION RESOLUTION : Not applicablo
, TESTED BY : Mike Asher 08/21/90 ld REVIEWED BY TEST ACCEPTED BY Mark D. Phillippo W. L. Smith 12/17/90 01/24/91 f
i
i I l APPENDIX D I (, PERFORMANCE TEST ABSTRACTS l PERFORMANCE TEST NUMBER NTI-612.01 ' PERFORMANCE TEST TITLE : REACTOR FUEL CLADDING FAILS, MALFUNCTION CR01 INITIAL CONDITIONS : Simulatar is initialized in the current Training Load at 100% power, equilibrium Xenon, steady-stato conditions. TEST SYNOPSIS : Malfunction CV17 (Lotdown HX Tubo Leak To CCW System) is inserted at 10% soverity. CVC System responso is verified and Mr.l ? unction CR01 is inserted at 10% (1000 Ctrios) is inserted. Process and Area Radiation Monitor responses are vorified and the simulator is reset. Malfunction CV17 is again inserted at 10% severity and Malfunction CR01 is re-inserted at 100% soverity (10,000 Curios). Radiation Monitoring System responso is re-verified, b1 DATA COLLECTION : Control Board indications and SPVS data V collection program TRANSIENT INITIATOR : There is no transient associated with this test.
. TERMINATION CRITERIA: The test is terminated af ter the plant has stabilized at olevated radiation levels.
EVALUATION RESULTS : No increase in activity was noted on the CNTMT Area Radiation Monitor. A Problem Report was generated. 6 VALUATION CRITERIA : Data comparison was performed by PWR oxperienced engineering and operations personnel using their experion;c and any other available references, " lieu of approved Waterford 3 actual pisnt data or best estimato analysos, r~x !Q n-54
APPENDIX D () PERFORMANCE TEST ABSTRACTS PLANT DATA REFERENCES : Not applicable DISSENTING OPINION RESOLUTION : Not applicablo TESTED BY : Georgo M. Vaux 10/17/90 REVIEWED BY : Mark D. Phillippo 10/22/90 TEST ACCEPTED BY : W. L. Smith 10/26/90 O e O o-ss i _____ _m_.--m_ -I '
APPENDIX D n PERFORMANCE TEST ABSTRACTS , PERFORMANCE TEST NUMBER : NTI 613.01 PERFORMANCE TEST TITLE : CONTAINMENT SPRAY PUMP (S) FAIL TO AUTOSTART, HALFUNCTION CS02 INITIAL CONDITIONS : 100% Power, Steady-State TEST SYNOPSIS : Malfunction CS02A (Loss of CS Pump A) is insorted followed by Malfunction RC23 (RCS Cold Log Rupturo). CS Pump A is veriflod not to start. CS Pump A is started manually and system performance is monitored. The simulator is reset and the test is repeated using Malfunction CS02B. , DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : The transient is initiated by insortion of Malfunction RC23 (RCS Cold Leg Rupture). [ TERMINATION CRITERIA : The test is terminated when paramotor tends have stabilized following testing of CS02B. EVALUATION RESULTS : The " Containment Spray Pump Unavailable" annunciator did not come in for either CS Pump malfunction. Containment pressure reduction ra',e did not increase when the second CS Pump was manually started. Problem Reports were generated for each deficiency. EVALUATION CRITERIA Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None DISSENTING OPINION RESOLUTION: Nono TESTED BY : Mike Asher 08/24/90 REVIEWED BY : Mark D. Phillippe 11/08/90 TEST ACCEPTED BY : Wayne L. Smith 11/08/90 O i) D-56 l l O e , , ,
APPENDIX D ( PERTORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI 614.01 PERFORMANCE TEST TITLE : CHARGING PUMP TRIP, MALPUNCTION CV01 INITIAL CONDITIONS : 100% Power, Steady-Stato TEST SYNOPSIS : Charging Pump A is place in service and the Backup Charging Pump Selector Switch is aligned to B-AB. Malfunction CV01A (Charging Pump A motor failure) is inserted. Charging Pump A and CVC System responso cre verified. The simulator is roset and the test is repeated using Halfunction CV01B. The elmulator is again reset and the test repeated using Malfunction CV01C. i DATA COLLECTION : Control Board indications and SPVS data i collection program ' TRANSIENT INITIATOR 4 The transient is initiated by tripping the operating Charging Pump. O TERMINATION CRITERIA The tost is terminated when paramotor U tends have stabilized following testing of CVOIC. EVALUATION LESULTS : No problems were identiflod during I performance of this test. E /ALUATION CRITERI A : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA REFIXENCES: Nono (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : Mike Asher 09/06/90 REVIEWED BY : Mark D. Phillippe 10/16/90 TEST ACCEPTED BY : Wayne L. S:nith 10/19/90 ( D-57 W --ag -- + - m y-----7--g,-- ---;- +
4 e a APPENDIX D ; PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI 614.02 : PERFORMANCE TEST TITLE CHARGING PUMPS FAIL TO AUTO START, E MALFUNCTION CV02 e INITIAL CONDITIONS : 100%-Power, Steady-State i TEST SYNOPSIS : The Backup Charging Pump Selector Switch is aligned to A-B and the Letdown Flow , Controller is placed in manual at 66gpm. Malfunction CV02A (Charging Pump A auto- .
~
start f ailure) is inserted. Charging Pump B and.CVC System response are verified. t The simulator is reset and the test is
- repeated using Malfunction CV02B. The simulator is again reset and the test ;
, repeated.using Malfunction CV02C.
DATA COLLECTION 1 Control Board indications and SPVS data , collection program TRANSIENT INITIATOR The transient is initiated by raising
- letdown flow and allowing PRZR level to
\
fall to the Backup Charging Pump auto-start setpoint. TERMINATION CRITERIA-t The test is terminated wher. parasaeter. - tends 'have stabilized following testing of CV02C. m EVALUATION RESULTS No problems were- identifled~ during. j pcrformance of this test.
- EVALUATION CRITERIA : - Evaluation was performed by PWR experienced engineering - and operations ,t personne1' using table top analysis in '
lieu of plant data or-best estimate data. ! PLANT DATA
REFERENCES:
None
-DISSENTING OPINION-L DESOLUTION: None p
TESTED BY 1 Hubert C. Crummey 09/06/90 REVIEWED BY :-- Mark D.-Phillippe 10/16/90 TEST ACCEPTED.BY : Wayne L. Smith- 10/19/90 I D-50 l-
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APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI 614.03 PERFORMANCE TEST TITLE : CHARGING PUMP SEAL LUBE PUMP MOTOR FAILS, MALFUNCTION CV03 INITIAL CONDITIONS : 100% Power, Steady-State TEST SYNOPSIS : Malfunction CV03A (Charging Pump A Seal Pump failure) is inserted and CVC System response is verified. The simulator is reset and the test is repeated using Malfunction CV03B. The simulator is again reset and the test repeated using Malfunction CV03C. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : The transient is initiated by a thermal overload trip of Charging Pump A seal water pump. TERMINATION CRITERIA : The test is terminated when parameter tends have stabilized following testing d of CV03C. EVALUATION RESULTS : No problems were identified during performance of this test. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : Mike Asher 10/28/90 REVIEWED BY : Mark D. Phillippe 11/05/90 TEST ACCEPTED BY : Wayne L. Smith 11/15/90 D-59 l _________L _ - .
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI 614.05 PERFORMANCE TEST TITLE : LETDGWN BACK PRESSURE REGULATING VALVE FAILURE OPEN/ CLOSED, MALFUNCTION CV05 INITIAL CONDITIONS : 100% Power, steady-State '~ TEST SYNOPSIS : Malfunction CV05A1 (CVC-123A falls open is inserted and CVC System response is verified. The cimulator is reset and the test is repeated using Malfunction CV05A2. The test sequence is repeated using Malfunctions CV05B1 and CV05B2. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : The transient is initiated by falling open Backpressure Regulating Valve CVC-123A. TERMINATION ",RITERIA : The test is terminated when parameter tends have stabilized following testing of CV05B2. EVALUATION RESULTS : No problems were identified during
, performance of this test.
EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) SISRWT ' PINION
..LUTION: None tIf Appl. le)
TESTED BY : Hubert C. Crummey 09/06/90 REVIEWED BY : Mark D. Phillippe 10/16/90 TEST ACCEPTED BY : Wayne L. Smith 10/17/90 i D-60
APPENDIX D F '( PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMDER : NTI 614.06 PERFORMANCE TEST TITLE : LETDOWN TEMPERATURE CONTROL VALVE FAILS CLOSED, MALFUNCTION CV06 INITIAL CONDITIONS : 100% Pcwor, Steady-State TEST SYNOPSIS : Malfunction CV06 (CC-636 f ails closed) is inserted and CVC System responso is veriflod. Remoto Function CVR42 is inserted to open bypass valvo CC-632 and lotdown temperature responso is verified. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : The transient is initiated by falling closed the Letdown HX Temperature Control Valve. TERMINATION CRITERIA : The test is terminated when paramotor trends have stabilized. EVALUATION RESULTS No problems were identiflod during performance of this test. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engincoring and operations personnel using table top analysis in lieu of plant data or best estimato data. PLANT DATA
REFERENCES:
Nono (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : Mike Asher 09/06/90 REVIEWED BY : Mark D. Phillippe 10/16/90 TEST ACCEPTED BY : Wayne L. Smith 10/17/90 D-61 l
'I
~
APPENDIX D ! O Q PERFORMANCE TEST ABSTRACTS
- PERFORMANCE TEST NUMBER : NTI 614.14 PERFORMANCE TEST TITLE- CVCS LETDOWN LEAK INSIDE CONTAINMENT (1-100% PIPE SHEAR), MALFUNCTION !
CV14 INITIAL CONDITIONS : . 100% Power, Steady-State l TEST SINOPSIS : Malfunction CV14 (Leak downstream of ! Regen. HX) is inserted at 2% severity and : CVCS response is verified. The simulator. : is reset and CV14 is inserted at 100% ) severity. System- response is again: verified. ; DATA' COLLECTION : Control Board indications-and SPVS data '! collection program , l TRANSIENT INITIATOR t The transient is initiated by a leak on !
, the- letdown piping. downstream of the -:
Regenerative Heat Exchanger. - TERMINATION CRITERIA':. The test is -terminated when parameter; trends have stabilized. ! EVALUATION-RESULTS : . No problems were_ _identifled during. performance of this test. EVALUATION CRITERIA : Evaluation was_ - performed ~ by PWR - experienced' engineering and operations personnel using . table top analysis in : =- lieu of plant data'or best estimate. data. ,
- PLANT DATA.
REFERENCES:
None (If Applicable) DISSENTING-OPINION
-RESOLUTION: - None (If, Applicable)-
TESTED.BY _ George M. Vaux 11/15/90 REVIEWED BY. - Mark D. Phillippe 12/11/90- -t
-TEST ACCEPTED BY s. ' Wayne L. Smith- . 12/20/90 {
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i APPENDIX D r I PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI 614.15 PERFORMANCE TEST TITLE : CVCS LETDOWN LEAK OUTSIDE CONTAINMENT (1-100% OF LINE LEAK), MALFUNCTION CV15 INITIAL CONDITIONS : 100% Power, Steady-Stato TEST SYNOPSIS : Malfunction CV15 (Loak betwoon FI-202 and CVC-132) is inserted at 10% sovarity and system / component responses are veriflod. The simulator is reset and CV15 is inserted at 100% soverity. System / component responso is again verified. DATA COLLECT 1PN : Control Board indications and SPVS data collection program TRANSIENT INITIATOR The transient is initiated by a leak on the letdown piping outside the Containment Building. TERMINATION CRITERIA : The test is terminated when paramotor (9 LJ trends have stabilized. FVALUATION RESULTS : A problem was identiflod concerning the response of the Lotdown Flow Control and Backprosauro Regulating Valves. A Problem Report was generated to document this discrepancy. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engincoring and operations personnel using table top analysis in lieu of plant data or best estimato data. PLANT DATA
REFERENCES:
Nono (If Applicable) DISSENTING OPINION RESOLUTION: Nono (If Applicable) TESTED BY - Mike Asher 09/07/90 REVIEWED BY : Mark D. Phillippo 10/17/90 TEST ACCEPTED BY : Wayne L. Smith 10/26/90 ! D-63 (v)
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE I'EST NUMBER NTI 614.16 PERFORMANCE TEST TITLE : CHARGING LINE LEAK INSIDE CONTAINMENT (1-1004 OF FLOW), MALFUNCTION CV16 INITIAL CONDITIONS : 1004 Power, Steady-State TEST SYNOPSIS : . Malfunction CV16 (Leak at Penetration
#27) is inserted at 10% severity and system /componont and Containment responses are verified. The CNTMT Sump is pumped to verify Radiation Monitoring System response. The simulator is reset and CV16 is inserted at 100% severity.
System / component response is again verified. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : The transient is initiated by a leak on the charging line at Penetration #27 !O. - inside the CNTMT. M TERMINATION CRITERIA .. The test is terminated when parameter trends have stabilized and PRER level is slowly dropping. EVALUATION RESULTS I A problem was identiflod concerning the response o f -- CNTMT airborne activity- - A , Problem Report was generated-to document this discrepancy. EVALUATION CRITERIA : Evaluation was performed by. PWR experienced engineering - and operations personnel using table top analysis in lieu of plant dath or best estimate data. PLANT DATA.
REFERENCES:
None , DISSENTING OPINION RESOLUTION: None
-TESTED BY- Mike Asher . 09/07/90 REVIEWED BY : Mark D. Phillippe 10/17/90 TEST ACCEPTED BY : Mayne-L. Smith 10/17/90 D-64
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI 615.01 PERFORMANCE TEST TITLE : CW PUMP TRIP, MALFUNCTION CWO1 INITIAL CONDITIONS : 100% Power, Steady-State TEST SYNOPSIS : Malfunction CWO1A (CW Pump A Trip) in inserted and system / component is verified. The simulator is reset and the test is repeated for CWO1B, C, and D. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : The transient is initiated by a tripping one of the four operating Circulating Water Pumps. TERMINATION CRITERIA : The test is terminated when paramotor trends have stabilized. EVALUAT!ON RESULTS : No problems were identified during performance of this test. EVALUATION CRITERIA : Evaluation was performod by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimato data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : Hubert C. Crummoy 09/07/90 REVIEWED BY : Mark D. Phillippo 10/16/90 TEST ACCEPTED BY : Wayne L. Smith 10/19/90 D-65 l l
( APPENDIX D i PERFORMANCE TEST AUSTEACTS PERFORMANCE TEST NUMBER NTI- ti16. 01 PERFORMANCE TEST TITLE : Feedor Breaker Trip in Switchyard INITIAL CONDITIONS : 100% power, any timo in core cycle, equilibrium xenon TEST SYNOPSIS : Trip all 4 switchyard breakers one at time and verify proper indications and alarms. Roset simulator, trip all four treakers simultano:)usly and verif y proper indications and alarms. DATA COLLECTION : Observation of control board indications and alarms , SPVS data collection program. , TRANSIENT INITIATOR : ED01 (A,B,C,D), Fooder Breaker Trip in , Switchyard TERMINATION CRITERIA : Observation of alarms indications and plant responso complete. (')
'(,/
EVALUATION RESULTS No problems were noted, all indications and alarms responded as required. An indication problem was noted on the PMC point display but this was determined to , be the proper response. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data nr best estimate cata. PLMIT DATA
REFERENCES:
None. DISSENTING OPINION RESOLUTION : None. - l (If Applicable) e TESTED BY : Mike Asher 9-7-90 i REVIEWED DY : Mark D. Phillippo 12-11-90 TEST ACCEPTED Dy : Wayne L. Smith 12-20-90 l t D-66 L
APPENDIX D ( PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER t NTI-616.02 PERFORMANCE TEST TITLE : LOSS OF MAJOR STATION TRANSFORMER INITIAL CONDITIONS : 100% power, any timo in core cyclo, equilibrium xenon TEST SYNOPSIS : From 1004 power, major transformers c.ro l faulted and system responses are verified. I DATA COLLECTION Control Board observation and SPVS data collection program l TRANSIENT INITIATOR ED02 A-F, Main /Startup/ Unit Auxiliary Transformer Fault TERMINATION CRITERIA : Verification of system indications and alarm actuation. EVALUATION RESULTS : All alarms, indications and controls responded properly, no problemo woro notod. Some minot differences in (x paramotor trends woro identiflod for information purposes. EVALUATION CRITERIA : Evaluation was performed by PWR oxperienced engineering and operations personnel using table top analysis in lieu of plant data or best estimato data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : Nono. (If Applicable) TESTED BY : Hubert C. Crummoy 9-7-90 REVIEWED BY : Mark D. Phillippe 10-21-90 TEST ACCEPTED BY : Wayne L. Smith 10-26-90 Il D-67 U i
APPENDIX D () PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-616.01 PERFORHANCE TEST TITLE : LOSS OF 6 9 KV BUS (ES) INITIAL CONDITIONS : 100% power, any +1mo in core cycle, equilibrium xenon TEST SYNOPSIS : From 100% power, actuate malfunction for 6.9 kv bus fault, verify generator fault alarm followed by generator trip and verify subsequent system responses. DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR : ED04 A-B, 6.9 KV 3A1/381 fault TERMINATION CRITcAIA : Verification of post trip conditions with stable plant paramotor trends. EVALUATION RESULTS : All alarms, indications and controls responded properly. Other than main Foodwater was not lost as expected by the (^] LJ test proceduro, no problems were noted. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best ostimato data. PLANT DATA REFERFNCES: None. (If Applicable) DISSENTING OPINION RESOLUTION : None. (If Applicablo) TESTED BY : Mike Asher 9-7-90 REVIEWED BY : Mark D. Ph1111ppo 10-17-90 TEST ACCEPTED BY Wayne L. Smith 10-17-90 D-68 e --__----_--.-_-.-____-.____u_ - . - . - - - - - - - _ - - . - - - - _ . . - . _ _ - - _ . - _ - _ - - - - . - _ - - - __ - - _ _ _ - . _ _ . . -
b APPENDIX D Q PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-616.05 PERFORMANCE TEST TITLE : LOSS OF 4.16 KV BUS (ES) INITIAL CONDITIONS : 100% power, any time in coro cycle, equilibrium xenon TEST SYNOPSIS : from 100% power, actuato a 4.16 kv bus f ault and verify proper system responsos. DATA COLLECTION : Control Board observation and SPVS data collection TRANSIENT INITIATOR : ED05 A-G, Various 4.16 Bus Faults T90J41 NATION CRITERIA : Verify system response and load de-energization. EVALUATION RESULTS : All alarms, indications and controls responded properly with the exception that MCC 3B22 did not doonorgize on the loss of bus 3B2, no other problems were gi noted. A few minor plant parameter trend LJ differences were noted for information. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in 1!ou of plant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None. (If Applicable) TESTED BY : Hubert C. Crummey 9-7-90 , REVIEWED BY.: Mark D. Phillippe 10-16-90 TEST ACCEPTED BY : Wayne L. Smith 10-26-90 t i I D-69
APPENDIX D
,c v) PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-616.06 PERFORMANCE TEST TITLE : LOSS OF 480 VAC BUS (ES)
INITIAL CONDITIONS : 100% power, any timo in core cycle, equilibrium xenon TEST SYNOPSIS : With normal electrical distribution in operation, actuate 400 VAC bus f aults and verify proper load doenergization and system response. DATA COLLECTION Control Board observation and SPVS data collection program TRANSIENT INITIATOR ED06 A-K, Various 480 VAC Bus Faults TERMINATION CRITERIA : Verify system response and propor load doenergization. EVALUATION RESULTS : All alarms, indications and controle responded properly, no problems were noted. A question was raised on tho responso of a secondary bus, however, (^)\ b this was determined to be beyond the scope of simulation. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None. (If Applicable) TESTED BY : Mike Asher 9-8-90 REVIEWED BY : Mark D. Phillippe 10-16-90 TEST ACCEPTED BY : Wayne L. Smith 11-2-90 l
.O N] p.70
APPENDIX D gs y) PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-616.07 PERTORMANCE TEST TITLE : LOSS OF 125 VDC BUS (ES) INITIAL CONDITIONS : 100% power, any time in coro cycle, equilibrium xenon TEST SYNOPSIS : With the electrical distribution system in a normal lineup, actuate malfunctions ' to cause 125 VDC bus short circuit and subsequent loss, verify propor system response and load doenorgization. DATA COLLECTION : Control Board observation and SPVS data > collection program TRANSIENT INITIATOR : ED07 A-c, Loss of 125 VDC Bus TERMINATION CRITERIA : Verification of proper loss of loads. EVALUATION RESULTS : All alarms, indications and controls responded properly, no problems were noted. A request was made to expand the (~'} test to verify which alarms and (_- components lose indication for each DC bus. EVALUATION CRITERIA Eva,1,uatiott was performed by PWR oxperienced engineering and operations personnel using table top analysis in lieu of plant data or best estimato data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None. i (If Applicablo) l TESTED BY : Hubert C. Crummey 9-0-90 1 REVJLWED BY : Mark D. Phillippe 10-16-90 TEST ACCEPTED BY : Wayne L. Smith 10-19-90 l D-71
f i APPENDIX D FERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-616.10 ' , PERFORMANCE TEST TITLE : LOSS OF 208/120V BUS (ES) INITIAL" CONDITIONS : 100% Power, Any Time in Core Life, Equilibrium Xenon-Conditions TEST SYNOPSIS : Insert Malfunctions ED10A, ED10B, and I ED10C individually at to 100% power . conditions with normal electrical line ups. Verify propor systero response and ; load deenergization. DATA COLLECTION t Board Observation attd SPVS data- .I collection. TRANSIENT INITIATOR Malfunctions ED10A-C, Loss of 208/120V - Buses 387A, 3078, and 3AB-1 TERMINATION CRITERIA : Verification of proper loss of loads. EVALUATION RESULTS : Loss of 387ALS could not be demonstrated ' by board indications. A Problem Report O. was written for this condition. Loss of PDP 3hB-1 was . indicated by proper
' response _ of alarms, indicators, _and ;
u atrols. EVALUATION CRITERIA : Evelyation -was performed by- PWR experienced engineering and operations personnel = using table top = analysis in lieu of plant data or best estimate data. PLANT.. DATA
REFERENCES:
None. (If. Applicable).
,l DISSENTING OPINiUN ;
RESOLUTION: Wone . .
-(10 Applicable)
TESTED BY - H. C. Crummey, 9/8/90 REVIEWED BY : Mark D. Phillippe, 1/25/91 TEST ACCEPTED BY.t Wayne L.' Smith,.1/26/91 i D-72
l APPENDIX D
.( ) PERFORMANCE TEST ABSTRACTS 3 PERFORMANCE TEST NUMBER : NTI-617.03 PERFORMANCC TEST TITLE : MAIN GENERATOR LOAD REJECT 50N (100%
= FULL LOAD) )
IN. TI Ab ( ONDITIONS : 100% power, steady stato TEST SYNOPSIS : From 2004 power, initiato a 10% generator load rejection. Tho increase the rejection to 50%. Verify plant response. DATA COLLECTION : Control Donrd indications and SPVS data collection program TRANSIENT INITIATOR : EG03, Generator Load Rojection at 10% and ; 50n TERMINATION CRITERI A : Simulator stabilizes EVALUATION RESULTS t The test has not boon performod due to problem reports acheduled to be worked.
,_s EVALUATION CRITERIA : Nono t )
(_ / PLANT DATA
REFERENCES:
Nono (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicablo) Tf;GTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a D-73 l
i.
,i APPEIO)IX D
/b PERFORMANC's TEST ADSTRACTS f()
PERFORMANCE TEST NUMfMJ/ : KM - 617. 0 4 PERFORMANCE TEST TITLE : MAJN GENERATOR OUTPUT BREAKER FAILS TO OPEN ON A TRIP INITIAL CONDITIONS : 100% power, any time in core cycAe, equilibrium xenon TEST SYNOPSIS : Follo @ng a manual turbine trip, the ' failure of eclected generator output breakers is verified and system : esponses verified. DATA COLLECTION : Control Joard observation and SPVS data collection program . TRANSIENT INITIATOR Manual trip of the main turbine. TERMINATION CRITERIA : Plant stabilizen in te post trip condition. EVALUATION RESULTS : All alarms, indicationo and controle responded properly. C EVALUATION CRITERIA Evaluaticn was performed by PWR - experienced engineering and operations personnel using table top analysis in lieu of pl nt data or best estimate data . PLANT E.4TA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOL'/ TION : None. (If Applicable) , TESTED BY : Hubert C. Crummoy 9-8-90 REVIEWED BY : Mark D. Phillippe 10-17-90 TEST ACCEPTED BY : Wayne L. Smith 10-17-'s0 D 74 '
fh APPENDIX D PERFORMANCE TEST ABSTRACTS . PERFORMANCE TEST NUMBER NTI-617.05 PERFORMANCE TEST. TITLE EXCITATION BREAKER FAILS TO AUTO TRIP ;
$ INITIAL CONDITIONS : 100% power, any- time in core cycle, equilibrium xenon TEST SYNOPSIS :, Following. a r.anual -trip of the main turbinei the failure to automatically- ,
trip the exciter field breaker -is y verified and the system' responses a' e : verifled. DATA COLLECTION - Control Board observat!.cn and SPVS data collect. ion
-TRANSIENT INITIATOR : . Manual trip of the main turbine.
TERMINATION' CRITERIA Plant stabilizes in a post trip condition ! with stable parameter trends. . EVALUATION RESULTSl: All alarms, indicators- and controls D responded properly, no problems were i d noted. EVALUATION. CRITERIA: : Evaluation- was performed by M l.
-experienced: engineering -:and operations d personne1E using table top -analysis- in: :
l lieu of plant data or best estimate data., j FLANT-DATA'PEFERENCES: None. (If ~ Applics.ble) _
-~ DISSENTING OPINION ,;
' RESOLUTION I__ _.None. i (Iff. Applicable) '
~ TESTED-BY : Hubert C. Crummey 9-8-90 ;
= REVIEWED:BY :- Mark D. Phillippe 10-17-90' '
l TEST ~: ACCEPTED:BY :- Wayne L. Smith 10-17-90 a
'~
-;.-.. ;-. . - - , - . , - . . ~ , . . - - -
a e., c
APPENDIX D a j PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-617.07 PERFORMANCE TEST TITLE : MAIN GENERATOR AUTO VOLTAGE REGULATOR FAILS TO MANUAL INITIAL CONDITIONS : 60% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : From 80% power, the generator load is raised and lowered with the voltage regulator failed to manual to verify no response, then manual adjustments are made for generator voltage to '11ri f y proper system response. DATA COLLECTION Control Board observation / manipulation-and SPVS data collection program TRANSIENT INITIATOR : EG07, Generator Voltage Regulator transfers to manual, in coniunctioO with manual manipulations of generator laad. TERMINATION CRITERIA : Verification of proper system response. (/ EVALUATION RESULTS : All alarms, indications and controls responded properly, no problems were noted. EVALUATION CRITERIA : Evaluation was performed by-_ PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None. (If Applicable) TESTED BY : Hubert C. Crummey 9-9-90 REVIEWED BY : Mark D.-Phillippe 10-17-90 TEST ACCEPTED BY : Wayne L. Smith 10-17-90
APPENDIX D () PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-617.08 PERFORMANCE TEST TITLE : FAILURE OF EDG TO AUTOSTART INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : With malfunction actuated at 100% power, a SIAS is manually initiated and failure of the EDG is verified, the diesel is manually started. After simulator reset the same sequence is followed but a loss of off site power is simulated to verify no response of the affected EDG, DATA COLLECTION : Control Board observation / manipulation and SPVS data collection program TRANSIENT INITIATOR : EG80 A(B). EDG A(B) Fails to Autostart TERMINATION CRITERIA : Verification of, diesel generator manual start and loading. EVALUATION RESULTS : All alarms , indications and controls [~)/ (_ responded properly, no problems were noted. Engineering had a concern for SPVS generator voltage although control board indications were normal EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personne) using table top analysis in lieu of riant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None. (If Applicable) TESTED BY : Mike Asher 9-9-90 REVIEWED BY : Mark D. Phillippe 10-16-90 TEST ACCEPTED BY : Wayne L. Smith 10-18-90 () D-77
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-617.09 PERFORMANCE TEST TITLE : FAILURE OF EDG TO LOAD INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : From full power, a loss of off site power is actuated and with the malfunction active the emergency diesel response is verified. DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR : EG 09A(B), EDG A(B) output Breaker Fails to Autoclose TERMINATION CRITERIA : System responses verified and plant parameter trends stable for doenergized safety bus. EVALUATION RESULTS : All alarms, indications and controls Q V responded noted. properly, The performance test will be no problems were revised to remove an improper step. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None. (If Applicable) TESTED BY : George M. Vaux 9-25-90 REVIEWED BY : Mark D. Phillippe 1-25-91 TEST ACCEPTED BY : Wayne L. Smith 1-28-91 ( D-78
APPENDIX D (~'T l PERFORMANCE TEST ABSTRACTS j ix.-) i PERFORMANCE TEST NUMBER : NTI-617.10 PERFORMANCE TEST TITLE : EDG OVERSPEED TRIP 1 INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : The emergency diesel generators are loaded parallel to the grid, an overspeed malfunction is actuated and system responses are verified. Then the same sequence is repeated, only with a loss of bus voltage being used to start the diesel and system response is verified on the overspeed trip. DATA COLLECTION : Control board observation / manipulation and SPVS data collection program TRANSIENT INITIATOR t EG10 A(B), EDG A(B) Overspeed Trip TERMINATION CRITERIA : Plant parameter trends are stable.
}
(_/ EVALUATION RESULTS : All alarms, responded indications and controls properly, mo problems were noted. Some SPVS data points were questionable and will be changed for future runs. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations l personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None. (If Applicable) l TESTED BY : Hubert C. Crummey 9-9-90 L REVIEWED BY : Mark D. Phillippe 10-16-90 i TEST ACCEPTED BY : Wayne L. Smith 10-18-90 L r"N i
) D-19
APPENDIX D I ,f y -' ()f PERFORMANCE TEST ABSTRACTS
-PERFORMANCE TEST-NUMBER : NTI-617.11 PERFORMANCE TEST TITLE : EDG TRIP ON DIFFERENTIAL PROTECTION s
1NITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : The diesel generator is manually loaded parallel to the grid, EDG trip
-malfunction is actuated and proper system response verified. After simulator reset, the. same basic sequence is followed-except the diesel is loaded in emergency due-to a loss of bus voltage and system response is then verified.
DATA COLLECTION : Control board observation / manipulation and SPVS data collection program
-TRANSIENT INITIATOR':
EGil A(3), EDG A(B) Differential Trip TERMINATION CRITERIA _: Plant parameter trende stable. EVALUATION-RESULTS _ All alarms, ir..hcations and - controls V responded : properly, no problems were 3-noted. Suspect SPVS data points will be corrected before future tests. LEVALUATION CRITERIA : Evaluation was performed by PWR-experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None. , (If Applicable) TESTED BY :- Mike Asher 9-9-90 i REVIEWED BY :- Mark D. Phillippe - 10-16-90 TEST l ACCEPTED BY : Wayne L. Smith' 10-18-90 D-80
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE' TEST NUMBER : NTI-617.18 PERFORMANCE TEST- TITLE : HYDROGEN SEAL OIL PUMP (H2 SIDE) TRIP INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : , From 100% power, the seal oil pump. trip malfunction is actuated and proper system responses are verified. DATA-COLLECTION : Control Board observation-and SPVS data collection program
' TRANSIENT INITIATOR :
EG 18, H2 Seal Oil Pump Trip TERMINATION CRITERIA : -Plant parameter trends are stable.
-EVALUATION RESULTS-: All alarms and- controls responded properly, the H' seal oil : cooler temperature responded in the ; wrong direction. A Problem Report was written.
No other problems'were noted. EVALUATION CRITERIA = 1 Evaluation was performed - by - PWR experienced- engineering and operations personnel using table top- analysis in
, lieu of plantL data or best estimate data.
. PLANT DATA'
REFERENCES:
None.- l(If' Applicable)- DISSENTING OPINION-RESOLUTION : None.
~(If Applicable):
TESTED BY I ~ -Mike Asher- 10-23-90 REVIEWED BY - -Mark D.-Phillippe 11-6-90 TEST ACCEPTED BY : Wayne L. Smith 11-14-90 l s
; D-81
APPENDIX D
..g-q--
!sm ,-) PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-617.19 i PERFORMANCE TEST- TITLE : HYDROGEN SEAL OIL PUMP -( AIR SIDE)
TRIP INITIAL' CONDITIONS : 100% power, steady state TEST SYNOPSIS : From 100% power, trip the Hydrogen Seal Oil Pump. -Verify plant response.
-DATA COLLECTION : Control Board indications and - SPVS data
(
-collection program
. TRANSIENT INITIATOR : EG19A and EG19B, Hydrogen Seal Oil Pump.
Trip TERMINATION-CRITERIA : Parameters are stable
' EVALUATION RESULTS : _ The test has not been performed due to l problem reports scheduled to be worked.
- EVALUATION-CRITERIA:: None
/h-b /:
PLANT DATA
REFERENCES:
(If-Applicable) None DISSENTING OPINION. RESOLUTION: None (If Applicable); _ TESTED-BY : n/a
-REVIEWED BY :- n/a- .
-TEST _ ACCEPTED BY :
n/a: s I l D-82 (_)- L
APPENDIX D y j PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-617.20 PERFORMANCE TEST TITLE : Stator Coolant High conductivity INITIAL CONDITIONS : 100% power, any time in cycle, equilibrium xenon TEST SYNOPSIS : Insert a 10% high conductivity and varify no effect. Insert 50% high conductivity and verify proper alarms. Insert 95% high conductivity and verify turbine runback accompanied by a turbine trip wjthin 45 seconds. DATA COLLECTION : Control panel observation and SPVS data collection program. TRANSIENT INITIATOR : Malfunction EG20, Stator Coolant High Conductivity (100% = 10.0 micro mho) TERMINATION CRITERIA : Turbine trip 45 seconds after initiation of final severity.
/ EVALUATION RESULTS : Test was satisfactory. All alarms, \> automatic actions and indications were as per test instructions.
EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None.
.(If Applicable)
TESTED BY : Mike Asher 11-15-90 REVIEWED BY : Mark D. Phillippe 12-10-90 TEST ACCEPTED BY : Wayne L. Smith 12-20-90 (3 ( ,/ D-83
I APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-619.01 PERFOPJ4ANCE TEST TITLE : CONDENSATE PUMP TRIP INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : From 100% power, 2 condensate pump trips on lo/lo hotwell level are sequentially actuated and_ system response is verified. DATA COLLECTION : Control Board Observation and SPVS data , collection program TRANSIENT INITIATOR FW01 A-C, CD-ILS-1900(3,4) Fails LO/LO TERMINATION CRITERIA : Plant parameter trends stable in a post. trip condition. EVALUATION PESULTS : . All alarms, indications and controls responded properly,: no problems were noted.- SPVS -digital points will be changed for next test. r
-: EVALUATION-CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel - using table top - analysis in.
lieu of plant data or best estimate data. - PLANT' DATA
REFERENCES:
None. (If Applicable): DISSENTING OPINION RESOLUTION : None.
.(If Applicable) ,
TESTED.BY : Mike Asher 8-8-90 REVIEWED BY : Mark D.-Phillippe 10-18-90 TEST ACCEPTED BY : Wayne L. Smith 10-19-90 [\ .. D-84 . U/ - . 4 W* wmw -r v t _ , , - - - - _ - _ - - - , - - ..u-__ - . - _ - _ - - . . . - - - _ _ _ - _ - _ - - - - . _ - - - . - _ - - -
- ; +
g , .]
, f APPENDIX D~- l ff :
.Q ~ PERFORMANCE TEST ABSTRACTS -
-PERFORMANCE TEST NUMBER" NTI-619.03
= PERFORMANCE TEST TITLE FEEDWATER-PUMP OVERSPEED TRIP'
. INITIAL CONDITIONS : . 100% power, any- time in core cycle,- .i equilibrium xenon .
. . t TEST SYNOPSIS-_: From- 100%. power, the malfunction for i overspeed trip is actuated , a reactor power cutback and proper system response '
is verified.
- DATA COLLECTION-:- Control Doard observation and SPVS data collection program ;
TRANSIENT INITIATOR FWO3 A(B), A(B) Feedwater Pump.Overspeed
~ '
Trip: i
-TERMINATION CRITERIA..- Plant parameter trends.' stabilize at post b
-reactor power cutback-_ conditions. _,
LVALUATION4RESULTS-.: All . alarms _ and l controls" responded as-
' expected, feed: pump : speed. response - was -
~
': P) . : incorrect f and _ ,a- spurious -Rx; . trip- r
' P%> :. ' occurred, otherwise allLindications were proper; no_'other problems-were.noted. EVALUATIONICRITERIA - Evaluation ~_. was' _ performed _ by ' PWRl 1
- experienced:. engineering:.7and . operations.
i personnel: _ using table H tope analysis :'n
- lieu of- plantrdata .or best= estimate: data .. <
.None.
--PLANT DATAL
REFERENCES:
;(Ifi Applicable)- s
' DISSENTING. OPINION
- RESOLUTION : None.
(If-- Applicable)- TESTED BY :- ~ Mike Asher 8-90
' REVIEWED BY 2
' Mark :D. Phillippe - 10-18*90 :
-TEST ACCEPTED:BY 1, ._Wayn_e. L. Smith '10-19-90
- ( D-85 rt . , " . - , . .+.e
- ..J.----- ,,,-%..- -- __________________i_______________.__I
APPENDIX D (m): PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-619.04 PERFORMANCE TEST TITLE : FEEDWATER PUMP TURBINE SPEED CONTROL FAILURE INITIAL CONDITIONS : 80% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : , From 80% power, a speed control malfunction is actuated, first - at- 10% severity then at 100%. severity and system response is. verified. DATA COLLECTION Control Board observation and SPVS data collection program TRANSIENT INITIATOR FWO4 'A(B), A(B) Feedwater Pump. Speed-Control Fails to _% Severity. TERMINATION CRITERIA : Plant param0ter trends and proper' system-response is verified.
. EVALUATION RESULTS : All alarms and- controls responded f] proparly, feed pump . speed response -was L/ questionable at 100% severity, no-other problems -were noted. The procedure ,
required major pen and ink changes, a new revision will be made before rerunning. EVALUATION CRITERIA : Evaluation 'was. performed by PWR experienced engineering and operations personnel using table top analysis = in
.11eu.of; plant data or best estimate data.
PLANT DATA
REFERENCES:
- None. (If Applicable)
~
DISSLNTING OPINION. RESOLUTION :: None.
-(If-Applicable) t TESTED BY : Mike Asher 9-3-90 REVIEWED BY : Mark D. Phillippe 10-18-90
. TEST ACCEPTED BY : Wayne-L. Smith 10-19-90 I
i D-86 l i -
.a- -
APPENDIX D
) PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-619.06 PERFORMANCE TEST TITLE : MOTOR DRIVEN EMERGENCY FEEDWATER PUMP TRIP INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : From 100% power, a loss of feedwater accident is actuated with only the selected emergency feedwater pump in operation, subsequently the pump trip malfunction is actuated and system response is verified. Both motor driven emergency feedwater pumps are tested in this manner.
DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR : Main feedwater pumps are manually tripped, unaffected Emergency feedwater pumps are tripped and FWO6A(B), A(B) Emergency Feedwater Pump Overcurrent _\_s (} Relay Fault TERMINATION CRITERIA :- P?nnt parameter trends stabilize in post Rx. trip condition. EUALUATION RESULTS : All alarms, indications and controls responded proptrly, no problems were noted. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None. (If Applicable) TESTED BY : Mike Asher 8-9-90 REVIEWED BY : Mark D. Phillippe 10-18-90 TEST ACCEPTED BY : Wayne L. Smith 10-19-90 D-87 [\ >) l
APPENDIX D PERFORMANCE TEST ABSTRACTS
. PERFORMANCE TEST NUMBER : NTI-619.07 PERFORMANCE TEST TITLE : EMER FDW PMPS AUTOSTART FAIL INITIAL CONDITIONS : n/a TEST SYNOPSIS : The test has not been written DATA COLLECTION
- Control Board indications and SPVS data collection program TRANSIENT INITIATOR : FWO7, Emergency Feedwater Pumps Fall to Autostart TERMINATION CRITERIA : n/a EVALUATION RESULTS : The test has not been performed.
EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION \ RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a 1
APPENDIX D () PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-619.08 PERFORMANCE TEST TITLE : LOSS OF AUXILIARY FEEDWATER PUMP INITIAL CONDITIONS : Mode 2 entry condition TEST SYNOPSIS : With auxiliary feedwater in service, the auxiliary feedwater pump is tripped by a faulty overcurrent relay and proper system response is verified. DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR : FWO8, Faulty Overcurrent Relay Trips Auxiliary Feedwater Pump TERMINATION CRITERIA : Proper system response is verified. EVALUATION RESULTS-: All alarms, indications and controls responded properly no problems were noted. Pen and ink changes to the procedure will be incorporated into a new r~' revision before rerunning. Qg EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None. (If Applicable) TESTED BY : Mike Asher 8-9-90 REVIEWED BY : Mark D. Phillippe 10-18-90 TEST ACCEPTED BY : Wayne L. Smith 10-19-90
,O D-89 G i
I
--APPENDIX D p
. PERFORMANCE TEST ABSTRACTS d m
PERFORMANCE TEST NUMBER NTI-619.10 _ PERFORMANCE TEST TITLEL: CONDENSER VACUUM PUMP TRIP
- INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium:xenoa >
TEST SYNOPSIS-1 From 100% power with a condenser vacuum ,
--leak _ inserted, each vacuum' pump: is
. tripped and fproper system response ~1s-verified.
DATA COLLECTION- Control Board Observation and SPVS data-collection program TRANSIENT INITIATOR : FW10,. Condensate . Vacuum Pump trip - on Overcurrent Due To Motor Fault TERMINATION CRITERIA : Condenser vacuum returns to normal following removal. of -vacuum . - pump trip: ~ malfunction. , EVALUATION'RESULTS : :All- alarms,- indications and- controls . responded properly,1 no problems were - noted. . EVALUATION CRITERIA l' Evaluation- was. performed by_ PWR
- experienced engineering- and operations personnel ;using : table . top : analysis in.
lieu of plant data 'or best estimar,e data. PLANT DATA' REFERENCES ' None.--
- (If: Applicable)_
DISSENTING OPINION: ' RESOLUTION None. ^
. (IfiApp11 cable)
TESTED BYJ:. Hub'ert C.-Crummey 9-23-90. REVIEWED ~BYi: Mark D. Phillippe_ '10-16 TEST ACCEPTED ~BY::'. Wayne,L. Smith 10-17 , .i.}' k( D-90
- _ _ .. .-_ _ . . _ _ _ . . = .
f APPENDIX D fN, .:
'Q PERFORMANCE TEST ABSTRACTS
' PERFORMANCE TEST NUMBER : NTI-619.12 PERFORMANCE TEST TITLE : FEEDWATER PUMP ~ TURBINE HIGH VIBRATION INITIALLCONDITIONS : 100%-power, steady state
-TEST SYNOPSIS : From 100% power, f ail a inboard feedwater pump turbine bearing on a ramp from 0 to 1004. Verify plant response -
DATA: COLLECTION : -Control Board indications and SPVS data collection program TRANSIENT. INITIATOR : FW12A. and FW12B, Main Feedwater Pump Turbine High Vibration TERMINATION CRITERIA Plant stabilizes
--EVALUATION RESULTS's A station mo"ication affects this malfunction. The test has not been performed,
' EVALUATION L CRITERI A - :' None i f
)
PLANT DATA
REFERENCES:
.None (If-Applicable)
DISSENTING OPINION RESOLUTION: None
.(If; Applicable)
' TESTED BY : n/a REVIEWED BY : n/a iTESTfACCEPTED BY : n/a I
i
- APPENDIX D
./}
(j; PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-619.14 l
-PERFORMANCE TEST TITLE : CONDENSER HOTWELL LEVEL CONTROL VALVE FAILURE OPEN/ CLOSED TNITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon '
TEST SYNOPSIS : , From 100% power, the various hi/lo , malfunctions are actuated and system b response is verified. DATA COLLECTION : Control Board Observation and SPVS data collection pro' gram TRANSIENT INITIATOR : FW 14 Al-B2, Various Condenser Hotwell Level Switch Failures Both High-and Low TERMINATION CRITERIA.: Proper system response is verified and-plant parameter trends are stable. '
-EVALUATION RESULTS: All alarms, indications iand controls e
,j cY responded properly, SPVS point for u hotwell level did not show a rise during emergency _ hotwell _ makeup, no ^ other problems were noted. 6 EVALUATION CRITERIA : Evaluation = was -performed _by-
-PWR experienced engineering and operations - ;
personnel -using.-l table top analysis in lieu of plant data or best estimate data.- l
-PLANT DATA
REFERENCES:
None. (If Applicable) L DISSENTING OPINION , . RESOLUTION : -None. L -(If Applicable)_ L L TESTED BY : Hubert C. Crummey 9-22-90 REVIEWED BY Mark D. Phillippe 10-16-90 [ . TEST ACCEPTED BY : Wayne L. Smith 10-18-90 , A- D . g
l APPENDIX D l ) PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-619.19 PERFORMANCE TEST TITLE : FEEDWATER HEATER BYPASS VALVE FAILS OPEN/ CLOSED INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : With systems in normal operation, heater train bypass vales are f ailed open and closed, the bypass valves are also opened normally to verify consistency of system response. This test includes all heater bypass valves. DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR : FW 19 Al-C2, Mechanical failure Causes Heater Bypass Valve to Fall Open or Closed TERMINATION CRITERIA : Plant parameter trends stabilize and system responses are verified. EVALUATION RESULTS : The high pressure bypass malfunction response was jncorrect, no other probl;ms were noted. A problem report was written on a problem opening the LP Heater bypass valve using the-handswitch. No problems with the low pressure heater bypass or intermediate pressure heater bypass ' uo malfunction were noted. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations , personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None. (If Applicable) TESTED BY : Hubert C. Crummey 8-17-90 REVIEWED BY : Mark D. Phillippe 11-14-90 TEST ACCEPTED BY : Wayne L. Smith 11-15-90 D-93 L
v 4 N APPENDIX D gQ. PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-619.20 PERFORMANCE TEST TITLE : START UP FEEDWATER REGULATING VALVE l FAILURE INITIAL CONDITIONS : Reactor power startup- in progress, any time in core cycle,-power conditions 4cw enough to ensure start up feedwater
. valves supplying steam generators TEST SYNSPSIS : From a-reduced power /-start up condition, the start up feedwater regulating v61ves are failed open/ closed and' system response is verified. This test is .
performed-on both sides of feedwater and i with the valves being failed both open then shut, j DATA-COLLECTION Control Board- observation and SPVS data f collection Program TRANSIENT INITIATOR : .FW 20 Al-B2, FW-166-A(B) Falls Open/ Shut 4 ['\
' TERMINATION CRITERIA : The reactor trips on either High Steam j Generator or Low Steam Generator level. !
EVALUATION RESULTS : .All alarms, indications and controls responded- properly, no problemn were ! noted. Pen and ink changes _w ill be o incorporated before rarunning. EVALUATION CRITERIA -
-Evaluation = was performed by- PWR
-experienced engineering and operations personnel using table top - antlysis :in - .
lieu of plantLdata or' best estimate data.- j
-PLANT DATA
REFERENCES:
None. (It' Applicable) > DISSENTING OPINION RESOLUTION None. (If Applicable)
-TESTED BY :- Mike Asher 9-3-90 REVIEWED BY : Mark D. Phillippe 10-18-90 TEST ACCEPTED 1Mr : Wayne L. Smith 10-19-90 1 g D-94
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE-TEST NUMBER =1 NTI-619.21
-PERFORMANCE TEST, TITLE -
CONDENSER AIR-IN LEAKAGE : INITIAL CONDITIONS : 100% power, steady state TEST SYNOPSIS - From 100% power, initiate a condanser air in leakage by initiating a 1 't around-a valve seat at a 10% and J0% rate. Verify. plant response. t DATA COLLECTION : ~ Control Board-indications and-SPVS-: data collection program TRANSIENT' INITIATOR FW21A, B, and C, _ Condenser Air In Leakage
-TERMINATION CRITERIA : Plant stabilizes. in a post trip-condition..
-EVALUATION RESULTS -The test has not been performed due to problem reports scheduled to be-worked.'
EVALUATION CRITERIA:- iNone Q h PLANT' DATA REFERENCES- None (If Applicable)- q
-DISSENTING OPINION
-RESOLUTION---
-None
~(If Applicable)- I TESTED BY n/a' '
REVIEWED BY n/a-TEST ACCEPTED BYt i n/a. t L 4 0 o-es
- . . . - _= . .
APPENDIX D ) PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-619.29 PERFORMANCE TEST TITLE : EMERGENCY FEEDWATER PIPE LEAK INITIAL CONDIT ONS : 100% power, steady state TEST SYNOPSIS : From 100% power, trip both feedwater pumps. After the Emergency Foodwater Pumps start, initiate the break malfunction at a 10% and 100% rate. Verify plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : FW29A and FW29B, Emergency Feedwater Line Leak TERMINATION CRITERIA : Plant stabilizes-EVALUATION RESULTS i The test has not been performed. EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a D-96
APPENDIX D yN fj PERFORMANCE TEST ABSTRACTS
-PERFORMANCE TEST NUMBER : NTI-619.30 , PERFORMANCE TEST TITLE : EMERGENCY FEEDWATER PUMP SUCTION HEADER LEAKAGE INITIAL CONDITIONS :- 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : ,
With the plant in a normal operating condition, the main feedwater pumps are manually tripped, once EFW is. in operation a pump suction leak is actuated and system response 'is verified. _ This test is performed a both 10% and 100% ' severity on both suction lines. DATA COLLECTION Cop
- tol Board observation and- SPVS data collection program-
. TRANSIENT-INITIATOR Manual trip of tho main feedwater pumps followed by FW 30 A(B), Leak on Line 3CD4-67A(B) Between FW-103A(B) and FW--
n- 106A(B).-
! \
V- TERMINATION CRITERIA : The system response is verified then the ability to isolate the- leak; is demonstrated with subsequent system-
-response-verifled.
EVALUATION RESULTS : Several-problem arous were noted-during
-the performance-.of this test,-CSP make up_
-did not- initiate, Auxiliary building' sumps-did not respond correctly.and-EFW -
pump flows were questionable. All alarms and cont _rols' responded properly. '
'FVALUATION CRITERIA : Evaluation was performed .by PWR
=- experienced engineering and operations- '
personnel using table top analysis- in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
' None.- 4 DISSENTING OPINION
-RESOLUTION : None.
TESTED BY : George M. Vcux 10-29-90 + REVIEWED BY : Mark D. Phillippe 11-2-90
-TEST ACCEPTED BY Wayne L. Smith 11-15-90 A D-97 (f
1
7 .,
~ APPENDIX D
[_V
- Q PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-619.36 PERFORMANCE TEST TITLE.: FEEDWATER PIPE BREAK OUTSIDE CONTAINMENT INITIAL CONDITIONS t 100% -power, any time in core cycle, equilibrium xenon TEST. SYNOPSIS : From full power. operation a 10% feed line break-is actuated and-system response is verified. this test is conducted on- .
both the A and B Steam Generator feed
' lines at both 10% and 100% severity. ;
DATA COLLECTION 1 Control Board Observation and SPVS? data l collection program
. TRANSIENT INITIATOR -- FW 36A(B), Break of Line 2FW20-12A(B)-
- Between.FW-101A(B) and FW 184A(B)
TERMINATION CRITERIA =: Plant parametes trendo stable following MSIS.- , bV [\ EVALUATION RESULTS .: All alarms,.' indications and' controls respondad . properly, 'no problems were
- noted.-
EVALUATION CR4.ERIA 1 Evaluation- - was performed by- PWR experienced; engineering- and: operations personnel. :using table top analysia 'in
- lieu of' plant data or. best estimate data.
' L.NT: DATA
REFERENCES:
- ' None. (If' Applicable) DISSENTING OPINION: ' i RESOLUTION.' : - - None.
- (If_ Applicable)
TESTED BY : --Hubert C. Crummey. 8-14-90'
-REVIEWED BY.1- -
Mark D.cPhillippe- 1'-25-91: '
.TSST ACCEPTED BY; Wayne.L.--Smith 1-26-91 D-98 - - - - - - - .e -.' -w.- .e .sr -+a y .-,.g., w < ,-
7-p - v, g-. m .r,, e
~ . - . - . . .. . - . _ - - - - . . . . .
APPENDIX D- 3 jq. ( ). PERFORMANCE TEST ABSTRACTS PERFORMANCE, TEST' NUMBER NTI-619.37 PERFORMANCE TEST TITLE : FEEDWATER PIFE BREAK OUTSIDE ' CONTAINMENT INI'?IAL CONDITIONS : 100% power, any time in - core cycle, equilibrium xenon TEST, SYNOPSIS-- ,
.From full. power,a feed line break is .;
actuated and system recponse is verified.-- This test is run on both Steam Generator feedwater lines at both 10% and 100% ! severity. DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT; INITIATOR FW 37A(B), Break of line 2FW20-12A(B) Between FW-184A(B)and Penetration No., 3(4)- . TERMINATION CRITERIA -
. Plant parameter trends stable following Steam Generator dry out.
V EVALUATION RESULTS : All alarms and controls responded. properly, some problems: with . Steam Generator pressure,_ Pressurizer pressure and timing problems were noted by Engineering-evaluation. EVALUATION CRITERIA : . Evaluation was performed by --PWR experienced . engineering and : operations personnel usint -table top - analysis' in lieu of' plant data' or best- estimate data.
--PLANT DATA
REFERENCES:
'None.
-(If Applicable)
; DISSENTING OPINION RESOLUTION : None..
- (If-Applicable)
TESTED BY't Hubert C. Crummey 8-14-90 1 REVIEWED BY : Mark D. Phillippe 25-91 TEST ACCEPTED BY : Wayne L. Smith 1-26-91 D-99
, ,. _ s. . - - . - _ +
l 4 f APPENDIX D j
~, .;
~I PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-619.38 PERFORMANCE TEST TITLB :: FEEDWATER PIPE BREAK INSIDE CONTAINMENT INITIAL CONDITIONS : J,00% - power, any time in core cycle, ,
equilibrium xenon TEST SYNOPSIS : From full pcwor operation a - f eed line-break is actuated and system-response is-verified. The break J,s tested on both
. Steam Generator- feed lines at both 10%
and 100% soverity. DATA COLLECTION : Control Board observation and SPVS data collection Program TRANSIENT INITIATOR- Line
.FW38A(B), Break of 2FW20-12A(B) between Penetration No. 3(4) and Steam Generator 1(2)
TERMINATION CRITERIA' . Plant. parameter trend - stable following= Steam Getserator dry out. O. V EVALUATION RESULTS r :All alarms and controla responded properly, several-. indications-
..(Containinent humidj.ty,-T average,:6.EFW flow) .- w e r e questioned by engineering _ ;
evaluation.- EVALUATION. CRITERIA- 1 Evalbatjon -was . performed by- -PWR experienced _ engineering and operations personnel using table - top analysis : in-lieu of pioit data tor best estimate data.
' PLANT DATA 'REFEREliCEd:- None. s (If Applicable)
DISSENTING OPINION hESOLUTION : None. (If Applicable)- TESTED'BY 'Miku Asher 8-15-90 l -REVIEWED BY : Mark-D. Phillippe 1-25-91 l- TEST.. ACCEPTED BY : Wayne L.ESmith 1-26-91' i: D-100 l- -i j
-- ~ .,_
APPENDIX.D PERFORMANCE TEST ABSTRACTS PRFIORMANCE TEST. NUMBER : NTI-621.01 PEhPORMANCE TEST TITLE : Station Air / Instrument Air , Crossover-Valve, SA 125, Fails Open
/ Closed INITIAL CONDITIONS : 100 T power, Equillbrium Xenon, End of Cycle l TEST SYNOPSIS : Fail'SA 125 closed, place an instrument air compressor in Full To Lock and veri-fy 1 instrument air pressure lowers. Then, fall SA 125 open, verify ' station air ?
pressure lowers while- . instrument air ! pressure -risen- to equalization of both air headers, j DhTA COLLECTION :- 1. Manual observation of control panols.
- 2. SPVS data collection program '
TRANSIENT INITIATOR : IA-01A :SA-125 Fall Shut , IA-01B SA 125-Fall Open I b
' _ TERMINATION CRITERIA : Station and instrument air prossure
.rest ored to normal and' parameter-trends stable.
.i EVALUATION RESULTS : All recorded parameterr venponded ;
-correctly,4 except when SA_ 125- failed-
~
_i open,. initially _both_ instrument and q station air pressures lowered- slightly _ when= the instrument' air pressure should
'have risen. All alarms and . controls- Q responded properly.
-EVALUATION CRITERIA-
- Evaluation' was performed by PWR experienced i..ineering and operations personnel ~ _ using table top analysis ~1n.
lieu of plant data or best estimate' data. L PLANT JATA
REFERENCES:
None.; D'ISSENTING-OPINION-RESOLUTION : None. TESTED-BY Mike AsLer 9-25-90 i -REVIEWED BY-: Mark D. Phillippe 10-16-90 L TEST ACCEPTED BY : Wayne L. Smith 10-17-90 D-101 e g y rr
Jt
?:
i APPENDIX.D-PERFORMANCE TEST ABSTRACTS
%./
PERFORMANCE TEST NUMBER NTI-621.02
- PERFORMANCE TEST TITLE : INSTRUMENT AIR CONTAINMENT ISOLATION VALVE IA-909 FAILS TO CLOSE ON CIAS 2 0 . INITIAL CONDITIONS 1 100% 1)ower , any time in core cycle, f equilibrium xenon-TEST SYNOPSIS : With--Instrument Air in normal operation,
- the f ailure is actuated along with; a .
manual CIAS. and system response is verified. ; DATA COLLECTION : Control Board observatio: .and -SPVS' data. collection program TRANSIENT INITIATOR _: IA 02, IA-909 Fails _to Cloae on I CIAS
' TERMINATION CRITERIA' - IA-909 'is: manually closed and system response is verified.
' EVALUATION RESULTS : All alarms,. indications and controls responded properly, no problems. -were
- noted. -
. EVALUATION CRITERIA : Evaluation :was! performed. by PWR 3' experienced engineering . and operations personnel J using table' top- analysis -in-
-lieu ' of plant' data or -best estimate data.
a
- PLANT; DATA
REFERENCES:
None. _(If Applicable)
-DISSENTING' OPINION- -
~
l -- .. RESOLUTION :: None. (If A'pplicable) \ TESTED'BY': 1 Mike Asher_ .9-9-90: Y - REVIEWED BYE:L Mark D. Phillippe
~
10-16-90 TEST. ACCEPTED BY._:- Wayne L. Smith 10-17-90 L.- s
-d I
's
N
-Q D-102
,--A 1,-m-, a.a-- ,m. , , .
l APPENDIX D ( ) PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NT!-621.03 PERFORMANCE TEST TITLE : STEAM BYPASS CONTROL VALVE AIR SUPPLY RUPTURE
't INITIAL CONDITIONS : 100% power, steady stat '
TEST SYNOPSIS : From 100% power, ruP*ture the instrument air supply to the utoam bypass control valves. Verify plant response. Manually trip the reactor. Verify plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : IA03A through IA03F, Rupturo Air Line to Steam Bypass Valve { TERMINATION CRI'INI A : Plant stabilizes in a post trip condition EVALUATION RESULTS The test has not boon performed. EVALUATION CRITERIA None PLANT DATA
REFERENCES:
Nono (If Applicable) , DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a D-103 (J
APPENDIX D PERFORMANCE TEST AUSTRACTS PERFORMANCE TES".' NU:4BER NTI-621.04 PERFORMANCE TEST TITLE : RUPTURED AIR SUPPLY LINE TO RAB (0-1004) INITIAL CONDITIONS : 100% power, any timo in coro cycle, Equilibrium xenon TEST SYNOPSIS : From 100% power, normal Instrument Air operations, an air line rupture is actuated and system response is veriflod. This tost includes both 15% and 100% overity. DATA COLLECTION : Control Board observation and SP'/S data collection program TRANSIENT INITIATOR : IA 04, Rupture of Line 71A2-33 Botween Valves IA-550 and IA-530, in the Reactor Auxiliary Building (0-100% of a 2" lino) TERMINATION CRITERIA : System responso is verified and plant paramotor trends st.able. EVALUATION RESULTS : alarms, and All indications controls responded proporly, no problems woro noted. Pon and ink changou to the proceduro will be incorporated before rerunning. EVALUATION CRITERIA : Evaluation was performed by PWR oxperienced engineering and operations personnel using table top analysis in lieu of plant data or best estimato data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : Nono. (If Applicable) TESTED BY : George M. Vaux 9-10-90 REVIEWED BY : Mark D. Phillippe 10-16-90 TEST ACCEPTED BY : Wayno L. Smith 10-17-90 ( D-104
..___..___.__m_____.-___________-__.__.--m __ __ - __
APPENDIX 0 ig PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-621.05 PERFORMANCE TEST TITLE : INSTRUMENT AIR COMPRESSOR DISCHARGE LINE RUPTURE INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : With the Instrument Air system in normal operation, a line break is actuated and system response is verified. This test includes both 10% and 100% severity breaks of both air compressor discharge lines. DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR : IA 05A(B), Break of Instrume it Air Comprassor A(B) Discharge Line ietween the Discharge check Valve and Manual Block Valvo, Upstream of the Receiver [] V TERMINATION CR/TERIA : System respont.e is verified and plant parameter trends are stable. EVALUATION RESULTS : All alarms, indications and controls responded properly, no problems were noted except for SPVS data point selection. Pen and ink changes will be incorporated before rerunning. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in , lieu of plant data or best estimate data. t PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None. (If Applicable) l ( TESTED BY : Hubert C. Crummey 9-10-90 1 REVIEWED BY : Mark D. Phillippe 10-16-90 l TEST ACCEPTED BY : Wayne L. Smith 10-18-90 D-105
'N v' '-T w w w
l l APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-622.04 PERFORMANCE TEST TITLE : STEAM DYPASS VALVE LEAKAGE INITIAL CONDITIONS : 804 power, steady state l TEST SYNOPSIS 3 From 80% power, initiate a steam bypass valve faulty seat leak at 10% and 100%. : Verify plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : MSO4A through MSO4F, Steam Bypass Valve Leak (0 - 100%) , TERMINATION CRITERIA : Plant stabilizes-- at- a higher reactor power. EVALUATION RESULTS : The test has not been. perf ormed due to , 1- problem reports scheduled to be worked. EVALUATION-CRITERIA : None , PLANT DATA
REFERENCES:
None (If_ Applicable)
' DISSENTING OPINION RESOLUTION: None.
-(If Applicable)
TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a l-L o._, s....,.=m~- - ~ . . ~ . . . . . . . . , _,..._m_, m., .,,~ ,-- ,___ _ mm,,, ,.-..m. ,...m___-....,_m--.----..._..
APPENDIX D ( PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-622.05 PERFORMANCE TEST TITLE : ATMOSPHERIC GTEAM DUMP VALVE FAILS INITI AL CONDI"' IONS : 100% and 80% power conditions, steady state. Anytime in Core life. TEST SYNOPSIS Actuat.ed malf unctions f ailing atmospheric steam dump valves open at 80% power. System response in reactor power, steam flow, secondary makeup, and T average is verified. Activated malfunctions f ailing atmospheric steam dump valves closed following a manual trip from 100% power. Verify that cooldown shifts to the unaffected steam generator. DATA COLLECTION : Control board observation and SPVS data collection program. TRANSIENT INITIATOR : MS05A1, A2, B1, and B2 Atmospheric Steam Dump Valve Tails TERMINATION CRITERIA : Plant parameters stabilize with high ( cocondary make-up rate and mismatch
\
between reactor power and turbine power for the valves failed open. Plant parameters stabilize for cooldown conditions for the valves failed closed. EVALUATION RESULTS : Engineering comments included problems with pressurizer level, T average, steam flow rates, and response times between loops. All other alarms, controls, and plant parameters responded properly. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimato data. PLANT DATA
REFERENCES:
None DISSENTING OPINION RESOLUTION: None TESTED BY : H. C. Crummey 8/22/90 REVIEWED BY : Mark D. Phillippe 10/18/90 TEST ACCEPTED BY : Wayne L. Smith 10/19/90 D-107 G
l l APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-622.09 PERFORMANCE TEST TITLE S/G STEAM FLOW TRANSMITTER FAILURE INITIAL CONDITIONS : 60% and 10M power conditions, steady state, and anytime in core life. TEST SYNOPSIS : From 100% power conditions, failed each steam transmitter to 50% of range and verified that the feedwater system recovered feedwater flow and S/G level. From 60% power conditions, failed each steam transmitter to 100% of range and verified that the system recovered feedwater flow and S/G level. DATA COLLECTION : Control Board observation and SPVS data collection program. TRANSIENT INITIATOR : MSO9A and MSO98 S/G Steam Flow Transmitter Failure at 50% and 100% of scale.
~
t TERMINATION CRITERIA : Plant stabilizes with feedwater flow and S/G 1evial normal. EVALUATION RESULTS : All alarms, controls, and plant parameters responded as expected. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : Mike Asher 8/22/90 REVIEWED BY : Mark D. Phillippe 10/18/90 TEST ACCEPTED BY : Wayne L. Smith 10/19/90 O Q D-108 1
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-622.10 PERFORMANCE TEST TITLE : MS FLOW TRANSMITTER FAILURE INITIAL CONDITIONS : 80% power conditions, steady stato, and any time in coro life. TEST SYNOPSIS : The main steam flow transmitters are failed high and low using the malfunctions. Other than the reading on the indicators, thoro should be no af fect on the plant due to those malfunctions. DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR MS10A1, A2, B 1, and B2 Main Steam Flow Transmitter Failuro TERMINATION CRITERIA : Plant paramotor trends remain stable at conditions prior to the initiation of the malfunction. h V EVALUATION RESULTS : The SPVS data points selected for the transmitter readings did not change either high or low. Control board indications, alarms, and plant paramotors responded as expected. EVALUATION CRITERIA t Evaluation was performed by PWR-exporlonced engineering and operations personnel using tablo top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: Nono (If Applicable) TESTED BY : H. C. Crummey 8/22/90 REVIEWED BY : Mark D. Phillippo 10/18/90 TEST ACCEPTED BY : Wayne L. Smith 10/19/90 D-109 1
APPENDIX D i PERFORMANCE TEST ABSTRACTS wi PERFORMANCE TEST NUMBER NTI-622.11 PERFORMANCE TEST TITLE : MS LINE BREAK INSIDE CONTAINMENT INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : From 100% power, a 10% break then a 100% break of each steam line in containment is actuated and proper system response is verified. DATA COLLECTION Control, Board observation and SPVS data collection program TRANSIENT INITIATOR MS11 A(B), Main Steam Line 2MS40-163A(B) Breaks Inside Containment TERMINATION CRITERIA : Plant stabilizes in post trip condition. EVALUATION RESULTS : All alarms and controle responded properly, some minor PMC temperature indication did not respond, otherwise no (_s) problems wnre noted. %J EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None. ' (If Applicable) TESTED BY : Hubert C. Crummey 8-23-90. REVIEWED BY : Mark D. Phillippe 1-18-91 TEST ACCEPTED BY : Wayne L. Smith 1-22-91 D-110 [] u-
- n. APPENDIX D PERFORMANCE TEST ABSTRACTS PERTORMANCE TEST NUMBER NTI-622.12 .
PERFORMANCE TEST TITLE : MS LINE BREAK OUTSIDE CONTAINMENT AFTER MSIV > , INITIAL CONDITIONF : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS s, From 1001% power, a 10% then a 100% line ' break is actuated on each steam line and proper system response is verified. DATA COLLECTION : Control Board observation and SPVS deita collection program TRANSIENT INITIATOR MS12 A(B), Main Steam Line 2MS40-6A(B) Break TERMINATION CRITERIA : Plant stabilizes in post trip condition. EVALUATION RESULTS : All control board alarms, indications and controls responded as expected, engineering analyJis shows an unexplained O. steam spike to be investigated, no other problems were noted. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
.None. -
-(If Applicable)
DISSENTING OPINION ' RESOLUTION : None. (If: Applicable) TESTED BY : ' Mike Asher 8-22-90 REVIEWED BY : Mark D. Phillippe 1-22-91 TEST ACCEPTED BY' Wayne L. Smith 1-22-91 D-111 4 l c ; - -. - - .. ~ . _ -- ---- - - . -
t i APPENDIX D
/ .
( PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-622.13 PERFORMANCE TEST TITLE : MS LINE BREAK OUTSIDE CO)TAINMENT BEFORE MSIV + INITIAL CONDITIONS : 100% power, any time in cote cycle, : equilibrium xenon TEST SYNOPSIS From 100% power, a 10% break then
- 1004 line break on each main steam lins is actuated to verify proper syst63 response.
DATA COLLECTION.: Control Board Observation and SPVS-data collection program TRANSIENT INITIATOR : MS13 A(B), . Main Steam Line 2MS40A(B) , Break Before MSIV TERMINATION CRITERIA-1 Plant stabil11.es in a post trip condition. EVALUATION RESULTS : All alarms, indicat; ons and controls O V responded properly, n,; problets were noted. Pen and ink chanves will be-incorporated before the test is rerun. . EVALUATION CRITERIA : Evaluation was . performed by PWR es:perienced engineering and operations peraonnel -usang table - top- analysis in liet of. plant data or best estimate data. PLANT DATA
REFERENCES:
None.
.(If Applicable)
~
DISSENTING OPINION L RESOLUTION : None.
.(If' App 11 cable) i TESTED BY : Mike Asher 8-23-90
!; REVIEWED BY Mark D. Phillippe- 1-18-91
- l. . TEST ACCEPTED BY : Wayne L. Smith 1-22-91
/. t . D-112
l APPENDIX D o PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-622.21 PERFORMANCE TEST TITLE : MAIN STEAM LINE BREAK DOWNSTREAM OF IFT-033AS/BS INSIDE CONTAINMENT INITIAL CONDITIONS : 100% power, any time in core cyclo, equilibrium xenon
'9ST SYNOPSIS : From 100% power, a 10% then a 100% steam line break is actuated for each rteam line and proper system response is verified.
DATA COLLECTION : Control Board Observation and SPVS data collection program
" JNITI ATOR MS21 A(B), Main Steam Line 2MS40-163A(B)
Break TERMINATION CRITERIA Plant stabilizes in post trip condition. EVALUATION RESULTS : With the exception of minor PMC containment Temperaturo indications, all alarms, indicators and controls responded as expected. Engineering analysis (_} G indicates somo RCS temperature and S/G pressure trends are questionablo, th9so trends will be investigated. Pen and ink changes will be incorporated before the test is rerun. EVALUATION CRITERIA : Evaluation was performed by PWR experienend engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None. (If Applicable) TESTED BY : MJko Asher 8-23-90 hEVIEWED BY : Mark D. Phillippo 1-22-1,1 TEST ACCEPTED BY : Wayne L. Smith 1-22-91 D 113 1
I APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-622.22 PERFORMANCE TEST TITLE : TURBINE FIRST STAGE PRESSURE TRANSMITTER (S) FAIL INITIAL CONDITIONS : 80% power conditions, steady state, and any time in core life. TEST SYNOPSIS : The malfunction is inserted to fall the first stage turbine pressure at various levels. The CEAs will attempt to compensate for a perculved mismatch in T average and T reference if the proper reactor regulating group is controlling. DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR : MS22A, B, C, D, E, F, and O Turbine "irst Stage Pressure Transmitter Failure variable from 0 - 100%
, TERMINATION CRITERIA : Plant parameter trends change to provide L the control measures indicated as needed by the pressure transmitters.
EVALUATION RESULTS : Problems were encountered with a PMC point used for indication. Two of the malfunctions did not respond per the test and caused a reactor trip. Engineering analysis had questions about data point behavior for T average, T reference, and first stage turbino pressure. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None DISSENTING OPINION RESOLUTION: None TESTED BY : George M. Vaux, Jr. 9/10/90 REVIEWED BY : Mark D. Phillippe 10/21/90 TEST ACCEPTED BY : Wayne L. Smith 10/26/90 (3 g D-114 1 i ________mm____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-623.01 PERFORMANCE TEST TITLE i SAFETY INSTRUME.1T CHANNEL FAILURE INITIAL CONDITIONS : Critical Boron, Shutdown Banks Parked and 60t power, steady state, any time in core life TEST SYt!OPSIS : The malfunction f ails the safety channels at various severities for just critical and 60% power conditions and verifles the affect on control systems. DATA COLLECTION : Control Board indication and SPVS data collection. TRANSIENT INITIATOR : N101A through NI0lL Safety Instrument Channel Failure at adjustable severity TERMINATION CRITERIA : Proper parameter response is observed. EVALUATIU< ESULTS : The test will be rewritten before the next runr.ing to improve the ease of [ running and reviewing the test. Problems ( were noted in some alarms. All other alarms, indications, and controls responded properly. EVALUATION CRITERIA : Evaluation was parformed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : H. C. Crummey 9/11/90 REVIEWED BY : Mark D. Phillippe 11/2/90 TEST ACCEPTED BY : Wayne L. Smith 11/15/90 tQ g D-115
APPENDIX D ( PERFORMANCE TEST ABSTRACTS PERFORMA!!CE TEST NUMBER : 1;TI-623.03 PERFORMANCE TEST TITLE : CONTROL CHANNEL INSTRUMENT FAILURE INITIAL CONDITIONS : 60% power, steady stato conditions TEST SYNOPSIS : Proper paramotor response is verified following insertion of the malfunctions failing the detector output signals. DATA COLLECTION : Control Board observation and SPVS data collection program. TRANSIENT INITIATOR : NIO3A and NIO3B, Control Channel 1 and 2 Instrument Failure variable to 0 - 100% of range TERMINATION CRITERIA Observation of proper paramotor response. EVALUATION RESULTS : Engineering noted a typo problem with a verification stop. Otherwise all alarms, indications, and plant paramotors responded as proper. EVALUATION CRITERIA Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimato data. PLANT DATA
REFERENCES:
Ncne (If Applicable) DISSENTING OPINION RESOLUTION: Nono (If Applicable) , TESTED BY : George M. Vaux, Jr. 9/11/90 REVIEWED BY : Mark D. Phillippe 10/10/90 TEST ACCEPTED BY : Wayne L. Smith 10/18/90 () D-116
APPFtIDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-623.03 PERFORMANCE TEST TITLE : SU INSTRUMENT CHANNEL FAILURE (0 - 100% OF SCALE) INITIAL CONDITIONS : Suberitical, shutdown banks parked, critical boron concentration TEST SYNOPSIS : From the suberitical condition, insert the malfunction at it, 40%, 80%, and 100%. The insert the malfunction in both channels at 100%. Verify plant responso. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR NIO5A and NIO58, Startup Instrument Channel Failuro TERMINATION CRITERIA : Paramotor trends are stable. EVALUATION RESULTS : The test has not been perf ormed due to problem reports scheduled to be worked. EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicablo) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a ' TEST AFCEPTED BY : n/a D-117
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-623.07 PERFORMANCE TEST TITLE : STARTUP CHANNELS FAIL TO DE-ENERGIZE ON STARTUP INITIAL CONDITIONS : Critical, stable, power = 900 cps, appro:t . BE-74 TEST SYNOPSIS : From 8E-74 power, insert the malfunction. Raise the power level to 1E-64 and verify plant reaponse. Remove the malfunction and veri f plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANc,IENT INITIATOR : NIO7A and NIO78, Startup Channels Fall to De-energize on Startup TERMINATION CRITERIA : Verification of plant response EVALUATION RESULTS : The test has not been perf ormed due to problem reports scheduled to be worked. EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a D-118 I
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-624.01 PERFORMANCE TEST TITLE : LOSS OF PRIMARY PMC COMPUTER COMPLEX INITIAL CONDITIONS : 100% power, steady stato TEST SYNOPSIS : From 1004 power, verify that the CP-2 BISIS panel is functioning. Insert the PMC malfunction. Verify plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR PC01, Loss of PMC Train A TERMINATION CRITERIA : Verification of plant responso EVALUATION RESULTS : The test has boon performed. However, a review of the results has not been performod. EVALUATION CRITERIA None PLANT DATA
REFERENCES:
Nono (If Applicablo) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : Arthur N. Vost, Jr. 1/15/91 REVIEWED BY : n/a TEST ACCEPTED BY : n/a . . _ . . . _ . , _ _ . _ _ _ ..-_.m- - - - - . - - - . - _ . - - - - - - - - - - - _ - _ - - - - - - - - - - - - - - - - - - --- ------- " ' '
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APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-625.01 PERFORMANCE TEST TITLE : CPC CNANNEL(S) FAIL . INITIAL CONDITIONS : 100% power, steady stato conditions, anytimo in coro lifo TEST SYNOPSIS : The response of the Reactor Protection System is veriflod fcr a f ailure of a CPC channel. i DATA COLLECTION : Control Board observation i TRANSIENT INITIATOR : PWO1A, B, C, and D, CPC Channel (s) Fall TERMINATION CKITERIA : Verification of proper system response to the malfunction. . EVALUATION RESULTS : All alarms, indications, and plant paramotor responded as required. EVALUATION CRITER.TA : Evaluation was performed by PWR , experienced engineering and operations
/ personnel using table to9 analysis in C]' lieu of plant data or best estimato data.
PLANT DATA
REFERENCES:
Nono (If Applicable) DISSENTING OPINION RESOLUTION: Nono (If-Applicable) TESTED BY : Mike Asher 9/19/90 REVIEWED BY : Mark D. Phillippo 10/16/90 TEST ACCEPTED BY : Wayne L._ Smith 10/17/90 t O
' D. m
i APPENDIX D ! PERFORMANCE TEST ABSTRACTS i PERFORMANCE TEST NUMBER NTI-625.02 ' i PERFORMANCE TEST TITLE : REACTOR POWER CUTBACK FAILURE TO DROP CEAS L INITIAL CONDITIONS : 100% power, any time in core cycle, , j equilibrium xenon > i TEST SYNOPSIS. . At 100% power, a feed pump is manually tripped with -reactor power cutback i I ~1nhibited from dropping CEAS and system e response is verifled. DATA COLLECTION:s Control Board observation and SPVS data collection program i L TRANSIENT INITIATOR s' --PWO2, Reactor Power Cutback Failure to
. Drop CEAs TERMINATION CR' < ERI A : Plant paratneter trends stable.
EVALUATION RESULTS : All alarms and controls responded as
,- expected, "Large Load Rejection" pushbutton did not light, otherwise, no ;
.other problems.were noted EVALUATION' CRITERIA . Evaluation was performed by PWR experienced engineering and operations personnel using table- top analysis in lieu of plant data or best estimate data.
PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION
' RESOLUTION : None. '.
_(If Applicable) , TESTED BY : Mike Asher- 24-90 REVIEWED BY : Mark D. Phillippe 1-22-91 TEST ACCEPTED BY : Wayne L. Smith I-22-91 1 i a
i
-l APPENDIX D (
PERFORMANCE TEST ABSTRACTS l PERFORMANCE TEST NUMBER : NTI-625.03 l' PERFORMANCE = TEST TITLE : REACTOR POWER CUTBACK FAILURE TO SETBACK / RUNBACK j INITIAL CONDITIONS : 100% and 60% power, any time in core _, cycle, equilibrium xenon , TEST SYNOPSIS : From 100% power, a feed pump is manually i tripped, the failure to setback / runback is monitored and system response 4 verified. the same test is run from 60% . power with the addition of removing:the malfunction and verifying proper system . response.. . DATA COLLECTION Control Board Observation and SPVS data I collection program 1 TRANSIENT INITIATOR PWO3, Reactor Power Cutback Failure to Initiate a Runback / Setback in conjunction with the manual tripping of a feed pump
- TERMINATION CRITERIA : Verification od system response complete o and system' parameter trends stable.
EVALUATION RESULTS : All alarms and indication responded i properly, The reactor cutback system failed to reset as required, no other problems were noted.- EVALUATION CRITERIA Evaluation was' performed by PWR experienced engineering and operations , personnel using table top _ analysis -in. lieu of plant data or best estimate data. , PLANT DATA
REFERENCES:
None. . _(If Applicable)_ DISSENTING OPINION RESOLUTION : None. (If Applicable) TESTED:BY : Mike Asher 8-24-90 REVIEWED BY : Mark D. Phillippe 1-18-91 TEST ACCEPTED BYlt Wayne L. Smith 1-22-91 D-122
APPENDIX D ( PERFORMANCE TEST ADSTRACTS PERFORMANCE TEST NUMBER : NTI-625.06 PERFORMANCE TEST TITLE : FAIL CEAC CllNL(S) LOSS OF CP-2 CRT CH. 1, 2 INITIAL CONDITIONS : 100% power, steady stato conditions TEST SYNOPSIS : Reduce power to 954 with CEAC failed. Vorify that RPI on CRT does not change. Verify appropriate lights and indicators. Set CEAC inoperativo flags on all CPCs. Ropoat for remaining CEACs. DATA COLLECTION : Control Board indication arid SPVS data collection progeam TRANSIENT INITIATOR : PWO6A, PWO6B rail CEAC channel A, B Loss of CP-2 TERMINATION CRITERIA : Verify proper responso of plant parameters to the insortion and removal of the malfunction. C EVALUATION RESULTS : All alarms, indications, and plant paramotors responded as expected. y EVALUATION CRITERIA : Evaluation was performod by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or boat ostimato data. PLANT DATA
REFERENCES:
Nono (If Applicable) DISSENTING OPINION RESOLUTION: Nono (If Applicable) TESTED BY : Mike Asher 8/24/90 REVIEWED BY : Mark D. Phil11ppo 11/5/90 TEST ACCEPTED BY : Wayno L. Smith 11/15/90 l D-123 1
APPENDIX D CN y) PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-626.01 PERFORMANCE TEST TITI~ : LOSS OF ALL REACTOR COOLANT PUMPS 100% power, any time in core cycle, INITIAL CONDITIONS : : equilibrium xenon TEST SYNOPSIS : From 100% power, a simultaneous loss of 4 all reactor coolant pumps is actuated and system response is verified. DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR RC01, Loss Of All RCPs TERMINATION CRITERIA Natural circulation is established with stable plant' parameter trends. EVALUATION RESULTS : All alarms, indications and controls responded as expected, no problems were noted. Engineering analysis had a 7s question on the T hot response. x- EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : Wnne. (If Applicable) TESTED BY Hubert C. Crummey 8-23-90 REVIEWED BY : Mark D. Phillippe 1-21-91 TEST ACCEPTED BY : Wayne L. Smith 1-2?'s1 l.( D-124
4 i APPENDIX D ' () PERFORMANCE TEST ABSTRACTS i PERFORMANCE TEST NUMBER NTI-626.03 PERFORMANCE TEST TITLE RCP SHAPT SEIZURE INITIAL CONDITIONS : 100% power, steady state conditions, any ' time in core life i TEST SYNOPSIS The malfunction is introduced from 100%
, power and plant response is verified for the shaft seizuro, turbine trip, and i reactor trip.
l DATA COLLECTION 4 Control Board indication and SPVS ' data , collection program TRANSIENT INITIATOR t RC03A, B, C, and D, RCP Shaft seizure TERMINATION CRITERIA Begin recovery from reactor trip EVALUATION RESULTS - Problems were encoua t,ered with RCp Stator i Temperature, Hi vibration alarms, and RCP delta P during the running of the test. t All other alarms,: indications, 'and plant (} EVALUATION CRITERIA : parameters responded as required.
--Evaluation was - performed _by PWR experienced engineering and operations personnel -using table top analysis in lieu of plant data or best estimate data.
PLANT DATA'
REFERENCES:
None- i (If Applicable) ! DISSENTING ~ OPINION . RESOLUTIONt None ' (If Applicable) p TESTED _BY George Vaux, Jr. - 8/30/90 L REVIEWED BY : Mark D. Phillippe 10/18/90 TEST. ACCEPTED BY : Wayne L. Smith- 10/19/90 , L D-125
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t APPENDIX D PERFORMANCE TEST ABST" ACTS PERFORMANCE TEST NUMBER NTI-626.04 PERFORMANCE TEST TITLE REACTOR COOLANT PUMP SHEARED SHAFT INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon !
\
TEST SYNOPSIS At 1004 power, a sheared shaft ! malfunction is . actuated and system : response verified. [ DATA COLLECTION Control Board observation and.SPVS data-collection program TRANSIENT INITIATOR RC04 A-D, RCP sheared shaft ,
~ TERMINATION-CRITERIA Plant parameter trends atabilize . post trip.-
EVALUATION RESULTS : Alarms: and controls responded as expected, problems with ' pump amps and differential presrure were noted. , Engineering analysis had questions about O the reverse flow response and the current behavior of the pump motors. EVALUATION CRITERIA Evaluation was performed - by PWR
, experienced engineering and operations t personnel using table top analysis in ,
liet of plant data or best estimate data. ' PLANT DATA _
REFERENCES:
None. t (If. Applicable) ; DISSENTING OPINION RESOLUTION : None. (If Applicable) TESTED BY : George'M. Vaux 8-30-90 REVIEWED BY- Mark D. Phillippe 1-21-91
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APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-626.05 ' PERFORMANCE TEST TITLE RCP LOSS OF LUBE OIL INITIAL CONDITIONS : 1004 power, steady state, any time in core life TEST SYNOPSIS : The malfunction is inserted from 100%
, power, the system responds to the loss of lube oil, loss of the reactor coolant pump, reactor trip, and turbine trip.
DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : RCOSA, B, C, and D, RCP Loss of Lube Oil TERMINATION CRITERIA : Beginning recovery from reactor trip EVALUATION RESULTS : Problems were encountered with the RCP2A motor stator temperature during -the running of the test. No other problems with alarms, indications, and plant , O b parameters- were reported. analysis had multiple problems with Engineering interpreting the SPVS data points and with the stator winding temperature. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations , personnel using table - top analysis in lieu of plant data or best estimate data. PLhNT DATA REFEREHCES: None (If Applicable) , DISSENTING OPIW10N RESOLUTION: , ne (If Applicablo) TESTED BY : Mike Asher 8/23/90 REVIEWED BY : Mark D._Phillippe _ 10/18/90 - TEST ACCEPTED BY : Wayne L. Smith 10/19/90 D-127 js l l h .- . -_. ~ . - . . _ . . - . _ _ . . . _ _..~.____._.__..u-. - - . _ .
APPENDIX D b PERFORMANCE TEST ABSTRACTS s PERFORMANCE TEST NUMDER NTI-626.H PERFORMANCE TEST TITLE : RCP LOWER SEAL FAILURE INITIAL CONDITIONS : 100% power, atandy state, any time in core life TEST SYNOPSIS : The malfunction is invoked at 100% powcL and the responses of the seal pressure, temperature, and bleedoff flow are verified. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT TNITIATOR : RCOBA, B, C, and D, RCP Lower S -- 4 Failure TERMINATION CRITERIA : Plant stabilizes EVALUATION RESULTS i All alarms, indications, and plant parameters responded as expected. A problem with the test procedure wi.11 be O. 'O corrected before the test is rerun. EVALUATION CRITERIA : Evaluation was performed by PWR l experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) , DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY t Mike Asher 8/23/90 REVIEWED BY : Mark D. Phillippe 10/10/90 TEST ACCEPTED BY t Wayne L. Smith 10/19/90 D-128
APPENDIX D PERFORMANCE TEST fiBSTRACTS PERFORMANCE TEST NUMBER : NTI-626.09 PERFORMANCE TEST TITLE : RCP MIDDLE SEAL FAILURE INITIAL CONDITIONS : 100% power, steady state, any time in core life TEST SYNOPSIS : The malfunction is invoked at 100% power, the seal pressures, bleedoff flows, and temperature responsus aro verified. DATA COLLiCTION : Control Board indications and SPVS data collection program > TRANSIENT INITIATOh RC09A, B, C, and D, RCp Middle Seal Failure TERMINATION CRITERIA : Plant stabilizes EVALUATION RESULTS : All alarms, indications, and plant parameters respond as expected. No problems were reported. C) k/ EVALUAT10N CHITERIA : Evaluation was performed by experienced engineering and operations PWR personnel using table top analysis in lieu of plant data or best estimato data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OFINION RESOLUTION: None (If Applicable) TESTED BY : Mike Asher 0/23/90 REVIEWED BY : Mark D. Phillippe 10/18/90 TEST ACCEPTED BY : Wayne L. Smith 10/19/90 D-129
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-626.11 PERFORMANCE TEST TITLE : CODE SAFETY FAILURE, OPEN/ CLOSED INITIAL CONDITIONS : 100% power, steady state, any time in core life TEST SYNOPSIS For the fall open malfunction, plant response is verified for the loss in pressurizer level, reactor trip, and quench tank responde. For the fall closed malfunction, the reactor trips are bypassed _ and the pressuriser backup heaters are failed on. This sequence initiates a cycle of pressurizer pressure rising and falling as the relief valve cycles. . DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR RC11A1, B1 Safety Valve Fails Open RC11A2, B2 Safety Valve rails Closed
/ TERMINATION CRITERIA t Reactor trends stabilize EVALUATION RESULTS Problems were reported with the relief valve indication response and the pressure response. A prob 1::, with the test procedure will be correc;,cd before the test is rerun. All other alarms, indications, and plant parameters responded as expected.
EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION None (If Applicable) TESTED BY : George M. Vaux, Jr. 8/31/90 REVIEWED BY : Mark D. Phillippe 10/18/90 TEST ACCEPTED BY : Wayne L. Smith 10/19/90 b v D-130 _ ___-__m--______m-u m. .
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-626.12 PERFORMANCF TEST TITLE : CODE SAFETY RELIEF VALVE LEAKS INITIAL CONDITIONS : 100% power, steady state TEST SYNOPSIS : From 100% power, initiate the valve stem failure at 10% and 100%. Verify plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : RC12A and RC12B, Code Safety Relief Valve Leaks (0 - 100%) TERMINATION CRITun . : Plant parameters are steady. EVALUATION RESULTS : The test has not been performed.
~
EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) , TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a O t] D-131
APPENDIX D (Qf PERFORMANCE TEST ABSTRACTS PERtv.1MANCE TEST NUMBER NTI-626.14 PERFORMANCE TEST TITLE : PRESSURIZER SPRAY VALVE FAILURE OPEN/CLOSE INITIAL CONDITIONS : 100% power, steady state, any time in core life TEST SYi.OPSIS : For the spray valve failing open, the plant parameters are verified during the depressurization and subsequent reactor ' trip. For the valve falling closed, the pressurizer heaters are manually turned on, the pressure increases,. and the reactor trips. DATA COLLECTION : Control Board indications :.nd SPVS data collection program TRANSIENT INITIATOR : RCl4A1, B1 Spray Valve kalls Open RC14A2, B2 Spray Valve Fails-Closed TERMINATION CRITERIA : Plant stabilizes af ter trip with pressure
,F. slowly decreasing or held steady by
( safeties. EVALUATION RESULTS : All alarms, indications, and plant parameters responded as expected. Problems with the test procedure will be corrected before the test is rerun. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel asing table top analycis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : George M. Vaux, Jr. 8/31/90 REVIEWED BY : Mark D. Phillippe 10/18/90 TEST ACCEPTED BY : Wayne L. Smith 10/19/90 D-132 l
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORE::CE TEST ltUMBER : NTI-626.1$ PERIORMANCE TEST TITLE : PRESSURIZER CONTROL LT FAILS HI/LO ~ INITIAL CONDITIONS : 100% power, steady state, any time in core-life TEST SYNOPSIS : The plant control response is verified
, for the level transmitter failure-in the pressurizer.
DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR RC15A1, B1, and C1, LT Fails High RC15A2, B2, and C2, LT Fails Low TERMINATION CRITERIA . Plant stabilizes EVALUATION-RESULTS : All alarms, indications, and plant-parameters responded as expected. Problems with the test procedure will be corrected before the test is rerun.
.\ EVALUATION CRITERIA : _ Evaluation . was performed by PWR
-experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data..
PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION - RESOLUTION: -None (If Applicable) TESTED BY : H.-C. Crummey- 9/10/90 REVIEWED BY : Mark'D. Phillippe 10/18/90 TEST ACCEPTED BY : Wayne L. Smith '10/19/90 D-133
1 APPENDIX D ( ,) PERFORMANCE TEST ABSTRACTS PFRFORMANCE TEST NUMBER : NTI-626.16A PERFORMANCE TEST TITLE : RCP SPEED TRANSMITTER FAILS INITIAL CONDITIONS : 100% power, steady state TEST SYNOPSIS : From 100% power, the RCP Speed Transmitter is failed at 10% and 100%. Plant response is verified. This test is only for RC16A through RC16P, RC160 through RC16FF will be tester. by NTI-626.16B. DATA COLLECTION : Control Board indication s and SPVS data i collection program TRANSIENT INITIATOR : RC16A through RC16P, RCP Speed Transmitter Falls (0 - 100%) TERMINATION CRITERIA : The plant is stable. EVALUATION RESULTS : The test has been run but not evaluated, r; [ EVALUATION CRITERIA : None
' PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED-BY : Arthur N. Vest, Jr. 1/19/91 REVIEWED BY : n/a TEST ACCEPTED BY : n/a ( D-134 l
- - - - J
APPENDIX D PERFORMANCE TEST ABSTRACTS a PERFORMANCE TEST NUMBER : NTI-626.16B PERFORMANCE TEST TITLE : RCP SPEED TRANSMITTER FAILS INITIAL CONDITIONS : 100% power, steady state TEST SYNOPSIS : From 100% power, the RCP Speed Transmitter is failed at 10% and 100%. Plant response is verified. This test is only for RC160 through _ RC16FF. RC16A through RC16P will be tested by NTI-626.16A. DATA COLLECTION : Control Board-indications and SPVS data collection program TRANSIENT INITIATOR : RC160 through RC16FF, RCP Speed Transmitter Falls (0 - 100%) RMINATION CRITERIA The plant is stable. EVALUATION RESULTS : The test has not been run. EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a
I APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-626.17 PERFORMANCE TEST TITLE : SAFETY INJECTION SYSTEM PRESSURE INTERLOCK FAILURE HI/LO INITIAL CONDITIONS : 125*F, drained to hot leg, no secondaries, and 100% power, steady state TEST SYNOPSIS : From low power, fail the interlock high. From 100% power, fall the safety injection interlock low. Verify plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : RC17Al through RC17D2, SI System Pressure Interlock Fails Hi/Lo TERMINATION CRITERIA : Parameter trends are stable. EVALUATION RESULTS : The test has not been performed. EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a D-136 1
APPENDIX D PSRFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-626.18 PERFORMANCE TEST TITLE : RCS CO'd LEG CONTROL TT FAILS INITIAL CONDITIONS : 100% power, steady state, any time in core life TEST SYNOPSIS : With the malfunction inserted at various levels, plant response to temperature control is verified. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : RC18A, B, C, and D, RCS Cold Leg Control Temperature Transmitter Falls 0 - 100% TERMINATION CRITERIA : Plant stabilizes EVALUATION RESULTS : All alarms, indications, and plant parameters responded as expected. Problems with t'Te test procedure will be updated before the test is rerun. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : George M. Vaux, Jr. 9/14/90 REVIEWED BY : Mark D. Phillippe 11/6/90 TEST ACCEPTED BY : Wayne L. Smith 11/15/90 D-13?
, _ 4 . ,, . - . _ . _ _ - . _ _ _ . _ _ . .. _ . . . _ . _ . _ . . _ . _ . . . _ . _ _ . _ - _
\
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE OEST NUMBER : NTI-626.19 PERFORMANCEffEST TITLE I' RCS COLD LEG SAFETY-TT FAILS INITIAL r,0NDITIONS : 100% power, steady state, any - time .in core life
- TEST-SYNOPSIS : From.- 100% power, -
fall each T. cold l transmitter . at 10% and 100% severity. Verified- proper plant _ response with no-operator action.
' DATA COLLECTION-t- -Control Board indlcations and SPVS - data collection _ program _
'i TRANSIENT INITIATOR .RC19A. through- RC19H( RCS ~ Cold Leg Safety Temperature Transmitter Fails-tTERMINATION CRITERIA : Plant remains in_ stable' condition.
EVALUATION RESULTS : All alarms, indications,, -and. plant variables. responded as expected.. ^.
'[- EVALUATION ~ CRITERIA : Evaluation was. . performed. by PWR=
experienced engineering .and _ operations - personnel using table top analysis 'in ; lieu of plant data or best estimate data.- ' I PLANT DATA
REFERENCES:
None
'(If.Applicab)e)
DISSENTING OPINION: RESOLUTION: None (If- Applicable) TESTED BY :- Mike Asher 9/3/90 REVIEWED BY : Mark D. Phillippe 11/13/90
-TEST ACCEPTED BY : -
Wayne L. . Smith- 11/15/90 J Y
- . , . , -,, -,,--7 -
APPENDIX D
,~
) -PERFORMANCE TEST ABSTRACTS v
PERFORMANCE TEST NUMBER NTI-626.20 PERFORMANCE TEST TITLE : RCS HOT LEG SAFETY TT FAILS INITIAL CONDITIONS : 100% power, steady state, any time in core life TEST SYNOPSIS : From 100% power, f all each Safety Hot Leg temperature transmitter first to 10% and then to 100% severity. Verify proper plant response with no operator action. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : RC20A through RC20H, RCS Hot Leg Safety Temperature Transmitter Falls (0 - 100%) TERMINATION CRITERIA : Plant remains stable EVALUATION RESULTS : Problems were encountered on some of the PMC points. All other alarms, indications and plant parameters l$ responded as expected. Problems with the (/ test procedure will be corrected prior to the test being rerun. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : Mike Asher 9/3/90 REVIEWED BY : Mark D. Phillippe 11/2/90 TEST ACCEPTED BY : Wayne L. Smith 11/15/90 l) D-139 U
L APPENDIX-D r fy ()- PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-626.21 ' PERFORMANCE TEST TITLE : RCS HOT LEG CONTROL TT FAILS-Il1ITIAL CONDITIONS : 100% power, steady state, any time in ; core life TEST SYNOPSIS From 100% power, initiated the hot leg control temperature transmitter failure at 10% and 100% severity._ At 100%- severity the CEAs insert until a reactor trip occurs. _ Verify alarms, indications, and controls respond properly. DATA COLLECTION : Control--Board indications and SPVS data cellection nrogram TRANSIENT INITIATOR : RC21A and RC21B, RCS Hot Leg Control Temperature Transmitter Faels (0 - 100%) TERMINATION CRITERIA : Plant remains stable for 10% severity, and plant trips for 100% severity. EVALUATION RESULTS t All alarms, indications, and . plant \ parameters- responded -as expected. Problems with the test-procedure will be corrected prior to the test-being rerun. EVALUATION CRITERIA : Evaluation _ was- : performed by- PWR experienced engineering - ~ and - operations personnel using- table . top _ analysis in lieu of_ plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable)
- DISSENTING OPINION RESOLUTION: None (If Applicable)
TESTED BY :- H. C. Crummey 9/3/90 REVIEWED BY : Mark D. Phillippe. 11/2/90
-TEST. ACCEPTED BY : Wayne L. Smith 11/15/90' D-140
APPENDIX D h PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-626.16 PERFORMANCE TEST TITLE : PRESSURIZER CPC SAFETY PT FAILS HI/LO INITIAL CONDITIONS : 100% power, steady state TEST SYNOPSIS : From 100% power, f ail the pressurizer CPC safety pressure transmitter high and low. Verify plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : RC22Al through RC22H2, Pressurizer CPC Safety Pressure Transmitter Fails Hi/Lo TERMINATION CRITERIA : Plant remains stable. EVALUATION RESULTS : The test has not been performed due to problem reports scheduled to be worked. EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a D-141
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER. NTI-626.23 PERFORMANCE TEST TITLE : RCS COLD LEG PIPE RUPTURE (DOUBLE ENDED BREAK) INITIAL CONDITIONS : 100% pcwer, steady state TEST SYNOPSIS : From 100% power, insert the RCS cold leg double ended rupture. Verify plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : RC23A and RC23B, RCS Cold Leg Pipe Rupture TERMINATION CRITERIA : Plant and containment stabilize. EVALUATION RESULTS : The test ha. not been performed due to problem reports scheduled to be worked. EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a D-142 i
APPENDIX D () PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-626.24 PERFORMANCE TEST TITLE : RCS HOT LEG PIPE RUPTURE (DOUBLE ENDED BREAK) INITIAL CONDITIONS : 100% power, steady stato TEST SYNOPSIS : From 1004 power, insert the Hot Log rupture malfunction. Verify plant responso. DATA COLLECTION Control Board indications and SPVS data collection program TRANSIEb INITIATOR : RC24A and RC24B, RCS Hot Log Pipo Rupture TERMINATION CRITERIA : Plant and Containment cool down and stabilize EVALUATION RESULTS : The test has not been performed due to problem reports scheduled to be worked. EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
Nono (If Applicable) DISSENTING OPINION RESOLUTION: Nono (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a () D-143 l P
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-626.25 PERFORMANCE TEST TITLE : RCS LEAK INTO CONTAINMENT INITIAL CONDITIONS : 100% power, steady state TEST SYNOPSIS : From 100% power, initiate the RCS leak at 100% and 10% rate. Verify plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR RC25, RCS Leak into Containment (0 - 100%), 100% = approx. 113 sq. in. TERMINATION CRITERIA : Plant and containment continue to cool down and stabilize. EVALUATION RESULTS : The test has not been performed due to problem reports scheduled to be worked. EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RE:'LUTION:
. None (If Applica':le)
TESTED BY : n/a REVIEWED BY : n/a TEST. ACCEPTED BY : n/a . _I. l
APPENDIX D r i PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-626.27 PERFORMANCE TEST TITLE : PRESSURIZER INSTRUMENT LINE BREAK (7/32" LINE) INITIAL CONDITIONS : 100% power, steady state, any time in core life TEST OYNOPSIS : At 100% power, insert pressurizer instrument line break malfunction. Plant controls respond to the slow loss of pressure and level. DATA COLLLcTION . Control Board indications and SPVS data collection program TRANSIENT INITIATOR : RC27, 7/32" Pressurizer Instrument Line Break TERMINATION CRITERIA : Plant remains stable EVALUATION RESULTS : Engineo.ing analysis questioned the containment sump response. All other O alarms, indications, and plant parameters V respond as expect ed. Minor problems with the test proceaure will be corrected prior to rerunning the test. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top anclysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : Mike Asher 10/12/90 REVIEWED BY : Mark D. Phillippe 10/22/90 TEST ACCEPTED BY : Wayne L. Smith 10/26/90 D-145
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-627.01 PERFORMANCE TEST TITLE : CEDM MG SET FAILURE INITIAL CONDITIONS : 100% Power, any time in cycle, equilibrium xenon TEST SYNOPSIS : From 100% power, insert the failure of one MG set then the other and verify response. The order of malfunctions insertion is reversed and response again verified. DATA COLLECTION : Control Board observation and SPVS data collection program TRAN3IENT INITIATOR : Malfunction RD01A(B), CEDM MG Set Failure. TERMINATION CRITERIA : Plant stabilizes in post trip condition. EVALUATION RESULTS : All cc.ntrols, alarms and indications responded as expected. No problems were noted. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (It Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : George M. Vaux 9-10-90 REVIEWED BY t Mark D. Phillippe 10-17-90 TEST ACCEPTED 7: : Wayne L. Smith 10-17-90 D-146 1 1
l APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-627.02 PERFORMANCE TEST TITLE : DROPPED CEA INITIAL CONDITIONS : 100% Power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : From 100% power, selected CEAs are dropped individually and in pairs to verify response. DATA COLLECTION : Control board observation and SPVS data collection program TRANSIENT INITIATOR : RD02, Dropped CEA (1-91, up to any two selectable) TERMINATION CRITERIA : Plant parameter trends stable following verification of proper response. EVALUATION RESULTS : All alarms indications and controls responded correctly, no problems were noted. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) , TESTED BY : Hubert C. Crummoy 9-10-90 REVIEWED BY : Mark D. Phillippe 10-18-90 TEST ACCEPTED BY : Wayne L. Smith 10-19-90 ( D-147
i i APPENDIX D f ' PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST-NUMBER NTI-627.03-PERFORMANCE TEST TITLE : CEAs~ FAIL TO MOVE IN MANUAL (GROUP) ; INITIAL CONDITIONS : Low power, with Group 6 inserted for control
- i TEST SYNOPSIS : From the low power condition, insert-the-
' malfunction to fail motion on the CEAs in - I manual, Try to maneuver- the CEAs- ' involved. Repeat for the other groups. t
^ Verify plant response.
, DATA COLLECTION : Control Board indications and SPVS data collection program ,
TRANSIENT INITIATOR : RD03A through'RD03J, CEAs Fall to Move in Manual TERMINATION CRITERIA : Verification of plant response EVALUATION RESULTS_-3 The test'has not been performed due -to problem reports scheduled to-be worked.
,G if EVALUATION CRITERIA : None PLANT. DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None-(If--Applicable)- TESTED BYE: n/a
-REVIEWED BY : n/a TEST ACCEPTED BY _
n/a l-l D-148
.(
-APPENDIX D >
PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST-NUMBER J NTI-627.04 CEAs Fall to Manual Individual
-PERFORMANCE TEST TITLE :
INITIAL CONDITIONS : 100% power, any time in cycle, equilibrium xenon
. TEST SYNOPSIS : Check CEA motion as per procedure.
, Insert malfunction and verify .CEAs will-not move in Manual Individual but will
. move in other manual modes.
DATA COLLECTION : Control panel observation-and SPVS data-collection program
. TRANSIENT INITIATOR : Malf unction RD04, CEAs Fall to. Move in Manual Individual -(selectable 1-91, any combination up to four CEAs)_
TERMINATION CRITERIA : Verification- of no ' response to manual. ' Individual control.
-EVALUATION RESULTS s' No problems were encountered. All alarm A -and indications. responded as required.
d EVALUATION CRITERIA : Evaluation was performed by _ PWR experienced engineering and- operations personnel _ using table top analysia in . lieu of plant data or best estimate data.-
' PLANT DATA
REFERENCES:
-Nona.
(if applicable)-
)
~ DISSENTING OPINIONE -
-RESOLUTION : None- '
-(if applicable)
TESTED BY : ' George M.-Vaux 10-14-90 REVIEWED BY-': Mark D. Phillippe- 10-22-90 TEST ACCEPTED BY : Wayne L. Smith 10-26-90 -i
4 I l l APPENDIX D ! 7 i PERFORMANCE TEST ABSTRACTS v PERFORMANCE TEST NUMBER : NTI-627.05 PERFORMANCE TEST TITLE : ROD EJECTION (UP TO 2 RODE) INITIAL CONDITIONS : SE-4% power, CEAs parked 100% power, steady state TEST SYNOPSIS : From SE-4% power, eject first one and then 2 CEAs by failing the rod housing. Repeat at 100% power. Verify plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : RDOS, CEA Ejection (Selectable 1 - 91), up to 2 rods TERMINATION CRITERIA : Plant stabilizes in a post-trip LOCA condition EVALUATION RESULTS : The test has not been performed due-to _, problem reports scheduled to be worked.
/ \
$,_) EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a , TEST ACCEPTED BY : n/a O D-150 NJ
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-627.06 PERFORMANCE TEST TITLE : CEA Group Uncontrolled Insertion INITIAL CONDITIONS : 100% power, any time in cycle, Equilibrium Xenon TEST SYNOPSIS : Inserted malfunction and observed insertion of affected CEAS. DATA COLLECTION : Control panel observation and SPVS data collection program. TRANSIENT. INITIATOR : Malfunction RD06, CEA Group Uncontrolled Insertion TERMINATION CRITERIA : Verify the plant trends stable either post trip or at a reauced power level. EVALUATION RESULTS : The Shutdown Banks and Part Length CEAs had to be selected prior to the uncontrolled insertion and the Part Length CEA insertion trip setpoint is not .e as por the test procedure. all alarms and Response of the regulating CEAs were as por the test, indication were as required. EVALUATION CRITERIA : Svaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA REFEREMCES: None ' (if applicable) DISSENTING OPINION RESOLUTION : None (if applicable) TESTED BY.: George M. Vaux 11-15-90 REVIEWED BY : Mark D. Phillippe 12-10-90 TEST ACCEPTED BY : Wayne L. SMth 12-20-90 D-151
,1.
-APPENDIX D
.I^6 sj PERFORMANCE TEST ABSTRACTS
. PERFORMANCE TEST NUMBER : =NT1-627.08
- PERFORMANCE TEST TITLE : LROPPED CEA, WITH NO ALARMS ( ANY TWO SELECTABLE) (1-91)
INITIAL. CONDITIONS :- 100%. power, steady state ! TEST SYNOPSIS From 100%' power, drop one and then two 5
-CEAs using the malfunction. Verify plant response'.
DATA' COLLECTION:: . Control Board -indications and SPVS data -
.n collection program
-TRANSIENT INITIATOR-' -
RD08, Dropped - CEA, with No Alarms, Any- i two selectable, CEAs 1 through 91 TERMINATION-CRITERIA ~. Plant- . stabilizes with possible reactor trip
. EVALUATION RESULTS : The-test has not been parfarmed.
EVALUATION CRITERIA :
. , 'None
'l\l) .
PLANT DATA
REFERENCES:
None ~ L(If Applicable)
--DISSENTING OPINION-
- RESOLUTION:- None~
_(If Applicable)- TESTEDIBYL n/a
' REVIEWED DY- ~
n/a
. TEST ~ ACCEPTED BY':..
-n/a: 1 w
r 4 e
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-627.09 PERFORMANCE TEST TITLE : CEA REGULATING GROUP UNCONTROLLED WITHDRAWAL (MS-AS) INITIAL CONDITIONS : Critical boron, Shutdown anc Part-length CEAs parked, CEA group to be tested at 100 inches withdrawn TEST SYNOPSIS : From the initial conditions, a continuous uncontrolled group withdrawal is initiated to the upper electrical limit and response veriflod. , DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR : RD09A-F, Regulating Group 1-6 Uncontrolled Withdrawal TERMINA* ION CRITERIA : Selected group stops at the upper electrical limit, plant paramotor trends stabilize and response is veriflod. O V EVALUATION RESULTS : All alarms, indicators and controls responded correctly. Several problems in simulator initial condition setup were encountered resulting in test: proceduro changes. EVALUATION CRITERIA : Evaluation was performed by PWR nxperienced engineering and operations personnel using table top analysis in lieu of plant data or best estimato data. PLANT DATA REFEREPCES: Nono (If Applicable) DISSENTING OPINION RESOLUTION: Nono (If Applicable) TESTED BY : George M. Vaux 10-29-90 REVIEWED BY : Mark D. Phillippo 11-13-90 TEST ACCEPTED BY : Wayne L. , Smith 11-15-90 D-153
APPEND 1X D 'in
) PERFORMANCE TEST ABSTRACTS v.
PERFORMANCE TEST NUMBER : NTI-627.10 PERFORMANCE TEST TITLE : CEAS MOVE OUT WHEN INWARD MOVEMENT REQUIRED IN AUTO MODE INITIAL CONDITIONS : 45t power, any time in core cycle, steady state conditions TEST SYNOPSIS : , With the desired group at a intermodlate position and CEDMCS in Auto Sequential, Tave is raised and malfunction response - is verified. DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR : RD10A-F, Regulating Group 1-6 Withdraws When Insert is Required TERMINATION CRITERIA : Plant response is verified following an Auto Withdrawal Prohibit signal initiation.
~T EVALUATION RESULTS : All alarms, indicators and controls (d responded correctly. No problems were noted. Initial Tave was lower than plant data, this required additional dilution to initiate insertion signal.
EVALUATION CRITERIA : Evaluation was ~ performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best ostimate data. PLANT DATA
REFERENCES:
None ' (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : Mike Asher 9-26-90 REVIEWED BY : Mark D. Phillippe 10-16-90 TEST ACCEPTED BY : Wayne L. Smith 10-1 -90 [') D-154 v
APPENDIX D
.( ,
PERFORMANCE TEST ABSTRACTS
- PERFORMANCE TEST NUMBER : NTI-627.11 PERFORMANCE TEST TITLE s' CEAs Mechanically Stuck
-INITIAL CONDITIONS : 100% power, any time in cycle, equilibrium xenon TEST SYNOPSIS : Insert ' malfunction to stick a CEA 'in groups A, B, Part Length and regulating. <
Verify that the af fected CEAs do not move i in response to CEDMCS commands. Trip the reactor and verify the CEAs do not insert into the core. DATA COLLECTION : Control panel observation and SPVS data collection program.
; TRANSIENT INITIATOR RD11, CEAs Mechanically stuck (selectable 1-91)
-TERMINATION CRITERIA : Remove malfunction following a reactor trip and verify CEAs fully insert.
(~) 3,s.) EVALUATION RESULTS No problems were encountered. All alarms and indications responded as required. EVALUATION CRITERIA Evaluation was- performed by PWR experienced engineering _ and operations personnel using' table- top analysis in
-lieu of -plant data or best (stimate data. -
PLANT DATA ~
REFERENCES:
None
-(if applicable)'
DISSENTING-OPINION
-RESOLUTION : None '
+
.(if applicable)
-TESTED BY : Mike Asher 9-17-90
' REVIEWED BY : Mark D. Phillippe 10-17-90 TEST ACCEPTED BY : Wayne L. Smith 10-17-90
'D .V D-155
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI 627.12 PERFORMANCE TEST TITLE : CEA Uncontrolled Withdrawal INITIAL CONDITIONS : SE-4% Power, CEis parked, Any time in Cycle TEST SYNOPSIS : Diluted group P (SD A and SD B) to 120 inches (DNBR and LPD trips in override). Inserted CEA Uncontrolled withdrawal malfunction (s). Verified CEA withdrew and would not stop uutti upper mechanical stop. DATA COLLECTION : Observation of control panels and SPVS data collection program. TRANSIENT INITIATOR RD12, CEA Uncontrolled Withdrawal (Selectable 1-91, any.up to 4) TERMINATION CRITERIA : Verification of CEA at the upper mechanical stop, t' EVALUATION RESULTS : Test was untisfactory. All indications C and alarms functioned as per test, no problems were observed. EVALUATION CRI'.'ERI A : Evaluation us performed by PWR experienced engineering and operations personnel using .able top analysir in lieu of plant datr. or best estimate data. PLANT DATA
REFERENCES:
None (if applicable) DISSENTING OPINION . RESOLUTION : None (if applicable) TESTED BY : George M. Vaux 11-7-90 REVIEWED BY : Msrk D. Phillippe 14-90 TEST ACCEPTED BY : Wayne L. Smith 1-15-91 D-156 s
APPENDIX D PERFORMANCE TEST ABSTHACTS PERFORMANCE TEST NUMBER NTI-627.13 PERFORMANCE TEST TITLE : CEA DRIFT (+10% OF POSITION) 1 OR 2 RODS INITIAL CONDITIONS : 5E-4% power, CEAs parked TEST SYNOPSIS : From SE-4 % power, select any rod using the malfunction. Repeat with 2 CEAs. Verify plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR RD13, CEA Drift, 1 - 91 selectable, up to 2 CEAS TERMINATION CRITERIA : Parameter trends are stable EVALUATION PESULTS : The test has not been performed due to problem reports scheduled to be worked. EVALUATION CRITERIA : Ncne PLANT DATA
REFERENCES:
None (If Applicable} DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY :- n/a R2 VIEWED BY : n/a TEST ACCEPTED BY : n/a
n , - APPENDIX D i PERFORMANCE TESP ABR' TRACTS PERFORMANCE TEST NUMBER NTI-627.14 PERFORMANCE TEST TITLE : FAILURE OF CONTROL / SHUTDOWN BANKS TO TRIP INITIAL CONDITIONS : 100% power, any time in core cycle, equJlibrium xenon TEST SYNOPSIS : From the initiat venditions a manual reactor trip 's initiated and malfunction response verified, the CEDM MG sets are subsequently tripped and the trip of the subject CEA group verified. JATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR : RD14A-J, CEA Group T/ ails to Trip TERMINATION CRITERIA : Plant parameter trends are stable, post trip with all '"*- inserted. EVALUATION RESULTS : All alcrms, indications and controls p responded correctly. No problems were d noted. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION ' RESOLUTION: None (If Applicable) TESTED BY :- Hubert C. Crummey 9-13-90 REVIEWED BY : Mark D. Phillippe 10-17-90 TEST ACCEPTED BY : Wayne L. Smith 10-17-90 i D-158
l f v , APPENDYX D 1 .tFORMANCE TEST ABSTRACTS
- PERFORMANCE TEST NUMBER NTI-627.21 I PERFORMANCE TEST TITLE
- CCA UPPER ELECTRICAL LIMIT FAILURE
-INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST FLOPSIS : Individual CEAs or CEA groups are inserted, the malfur.ction is inserted an.1 l the CEA or group is withdrawn to ita ;
mechanical stop. DAT'. COLLECTION- Control Board observation and SPVS , data collection program TRANSIENT INITIATOR : RD21, CEA Upper Electrical Limit Failure (selectable 1-91) TERMINATION CRITERIA : Individual CEAs or groups withdraw to their mechanical stops, plant parameter trends are stable and response is verified. ,
.Q EVALUATION RESULTS : All controls, alarms and indicatioris if responded properly.
noted. No problems were , EVALUATION CRITERIA Evaluation was. performed by PWR experienced engineering and operations , personnel using table top analysis in lieu of plant data or best estimate data. 21'LANT DATA-.
REFERENCES:
None (If Applicable) t DISSENTING OPINION- 't RESOLUTION:- None (If Applicable). } TESTED BY : George M. Vaux- 10-14-90.- REVIEWED BY : 10-22-90
. Mark D. Phillippe
- TEST' ACCEPTED BY Wayne L. Sinith 10-26-90 I
\<
. . . - , - -;-_._.-..=__ -_.,_....-___,_._.,_.._-,;-.-_._.-,__..._,-,,....-.,.,,._.-,-_-.- -
APPENDIX D ' PERFORMANCG TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-627.24 PERFORMANCE TEST TITLE : REACTOR TRIP BREP.KERS FAIL TO OPEN INITIAL CONDITIONS : 100% power, any time in core cyclo, equilibrium xenon TEST SYNOPSIS With the malfunction selected, a manual r rear: tor trip in initiated and plant response verified. , DATA-COLLECTION 11 control Board observation and SPVS' data i collection program + TRANSIENT INITIATOR : RD24A-h, Reactor Trip Breaker TCB_1-8 Falls to Open . TERMINATION CRITERIA : PJ ant parameters stabil,1ze in post trip condition with selected trip breaker - closed. EVALUATION RESULTS : All alarms, indications and controls responded correctly. No problems were > noted. EVALUATION CRITERIA Evaluation- was performed .by PWR experienced engineering and cperations personne4 using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION
.. RESOLUTION: None (If Applicable)
TESTED BY't Hubert C.'Crummey. 9-13-90 : REVIEWED BY..: _ Mark D. Phillippe 10-17-90 TEST ACCEPTED BY : Wayne L. Smith 10-17-90 D-160
t APPENDIX D () PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-629.02 PERFORMANCE TEST TITLE : RPS AUTOMATIC TRIP FAILURE INITIAL CONDITIONS : 15% power, turbine generator ready to synchronize, end of cycle TEST SYNOPSIS : Actions are taken to cause an automatic reactor trip and the selected channel , failure to trip is verified. DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR .RP02A-D, Reactor Protection System : Channel A-D Automatic Trip Failure. '
-TERMINATION. CRITERIA : Upon removal of the malfunction, a normal i reactor trip response is varified.
1 EVALUATION RESULTS : All alarms, indications and controls responded correctly. No problems were noted. EVALUATION CRITERIA ; Evaluation was performed by. .PWR. experienced engineering and operations - personnel using . table top analysis in Aleu of plant data or best estimate data. ,. , PLANT DATA
REFERENCES:
None (If~ Applicable) DISSENTING OPINION.. . RESOLUTION: None _(If Applicable)-
.l TESTED BY : Hubert C. Crummoy 9-19-90
. REVIEWED BY : Mark-D. Phillippe- 10-17-90
'TES7 KCCEPTED BY : Wayne L. Smith 10-17 l t
i
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-629.03 PERFORMANCE TES'I TIT?? Reactor Trip with No Automatic Turbine Trip INITIAL CONDITIONS : 100 % power, Equilibrium Xenon, End of Cycle TEST SYNOPSIS : , Reactor was manually tripped using manual push buttons. Automatic turbino trip failed to initiato and a MSIS terminated the transient. DATA COLLECTION : 1. Manual observation of control panels.
- 2. SPVS data collection program.
TRANSIENT INITIATOR : RP-03 Reactor Trip with No automatic Turbine Trip. .
~
Manual Reactor Trip Push Buttons. TERMINATION CRITERIA : Main gonorator trip on 86 relay following a MSIS. f EVALUATION RESULTS All recorded parameters responded i correctly. All alarms and controls responded proporly. No prrblems noted. EVALUATION CRITORIA Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
Nono (if applicable) DISSENTING OPINION ' RESOLUTION : None (if applicable) l TESTED BY : Goc.rgo M. Vaux Jr. 9-19-90 REVIEWED BY Mark 0, oh!1H;po 11-14-90 L TEST ACCEPTED BY : Wayne L. Smith 11-16-90 l l ( D-162
- ~ , _
- n. , -
I l APPENDIX D ( PERFORMANCE TEST ABSTRALTS PERFORMANCE TEST NUMBER : NTI-629.04 PERFORMANCE TEST TITLE : ESFAS TRIP GENEPATED INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : Two channels of ESFAS are sequentially actuated by malfunction insertion and plant response is verified. Each ESFAS trip (SIAS,CIAS,etc)is tested. DATA COLLECTION : Control Board Observation and SPVS data collection program TRANSIENT INITIATOR : RPO4Al-B7, Channel A-B ESFAS Trip Generated TERMINATION CRITERIA : ESPAS automatic actions are verified and plant parameter trends are stable. EVALUATION RESULTS : All alarms, indications and controls responded correctly except for the
.O following, CSAS failed to actuate V following a manual SIAS actuation. No other' problems were noted. DNBR trips caused bistable lights to extinguish and some bistable lights were not verified, this is proper logic and not a simulator discrepancy.
EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None
-(If Applicable)
TESTED BY : Mike Asher 9-19-90 REVIEWED BY : Mark D. Phillippe 10-18-90 TEST ACCEPTED BY : Wayne L. Smith 10-25-90 l O-v D-163
APPENDIX D PERFORMANCE TEST ABSTRACTS i] PERFORMANCE TEST NUMBER NTI-629.05 PERFORMANCE TEST TITLE : ESFAS CHANNEL PAILS TO GENERATE A TRIP INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS t, From 100% power with selected malfunctions insertod, various accidents are initiated and ESFAS trips are verified not to actuate. DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR : RP05Al-D7, ESFAS Channel Fails to Generate A Trip TERMINATION CRITERIA : Plant parameter trends are stable and appropriate actions are verified. EVALUATION RESULTS All alarms, indications and controls
/* responded correctly, with the exception d of 4 minor problems with misc. etatus lights, trip lights, etc.
EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : Mike Asher 9-21-90 REVIEPED BY , Mark D. Phillippe 10-17-90 TEST ACCEP'.ZD BY : Wayne L. Smith 10-26-90 l- , l i ( D-164 l l l l
-. . . . - -.--.- .--- - - - - - - - _ - - - - . . ~ . -
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-629.06 j PERFORMANCE TEST TITLE : RPS MATRIX RELAY FAILURE j i INITIAL CONDITIONS : 15% power, turbine generator ready to ' synchronize l TEST SYNOPSIS : From 15% power, malfunctions are I sequentid11y inserted and the plant response is verified. DATA COLLECTION-1 Control Board observation and SPVS data collection Program TRANSIENT INITIATOR : RP06A-X, Reactor Protection System Matrix Relay Fails TERMINATION CRITERIA Plant parameter trends are stable and proper actions are verified. EVALUATION RESULTS : All alarms, indications and controls responded correctly. No problems were noted. (Q-
/ EVALUATION CRITERIA : Evaluation was experienced engineering and operations performed by PWR personnel using table -top analysis in lieu of plant data or best astimate data.
. PLANT DATA
REFERENCES:
None (If App 11 cable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : Mike =Asher .
.9-24-90 REVIEWED BY s' Mark D. Phillippe 11-1-90 TEST ACCEPTED BY : Wayne L. Smith 11-15-90 D-165
.__-.-.._.._.__.____.___.__.______...___._m-- _ - _ ._ .
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-629.07 PERFORMANCE TEST TITLE : RPS BISTABLE RELAY FAILURE INI'tIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon , TEST SYNOPSIS : Two channels of RPS bistables are f ailed,
, conditions are initiated for a reactor trip and plant response is verified.
DATA COLLECTION : Control Board observation and SPVS data collection program , TRANSIENT INITIATOR RP07A-D, Reactor Protection 3ystem j Bistable fail to open : TERMINATION Cx1TERIA : Plant parameter trends stabilize in a post trip condition, cutomatic actions , are verified. : EVALUATION RESULTS : All Alarms, indications and controls , responded correctly except for the High bQ linear power bistable lights did not come on. No other problems were noted. EVALUATION CRITERIA : Evaluation was performed by . PWR experiencad engineering and operationc personnel using table top analysis in lieu- of plant data or best estimate data.
. PLANT DATA REFERENCES - None (If-Applicable)
DISSENTING OPINION ' RESOLUTION: None (If" Applicable) TESTED BY : . Mike Asher 9-27-90 REVIEWED ~BY :: Mark D. Phillippe 10-16-90 TEST ACCEPTED BY : Wayne L. Smith 10-17-90 , D-166
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-630.01 PERFORMANCE TEST TITLE : SBCS QUICK OPEN SIGNAL FAILS ON/OFF INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS The reactor is manually tripped with SBCS f ailed on then f ailed of f, plant response is verified. DATA COLLECTION : Control Board observation and SPVS data collection program TRANSIENT INITIATOR : RX01A(B), Steam Bypass Control System Quick Open Falls On(Off) TERMINATION CRITERIA : Plant parameter trends stabilize and automatic actions are verified. EVALUATION RESULTS : All alarms, indications and controls responded correctly. No problems were noted. EVALUATION CRITERIA Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in llou of plant data or best estimato data. PLANT DATA REFERENCES 1 None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) , TESTED BY : Mike Asher 9-19-90 REVIEWED BY : Mark D. Phillippe 10-22-90 TEST ACCEPTED BY : Wayne L. Smith 10-26-90 D-167
APPENDIX D ( PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-630.04 PERFORMANCE TEST TITLE : MAIN FEED REGULATING VALVE FLOW CONTROL FAILURE INITIAL CONDITIONS : 80% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : Each feedwater regulating valve flow controller is sequentially failed at 10% then 90% and system responses are verified. DATA COLLECTION : control Board observation and SPVE cata collection program TRANSIENT INITIATOR : RXO4 A(B), Main Feedwater Regulating Valve Flow Controller Falls (0-100% severity) ' TERMINATION CRITERIA : Plant parameter trends stabilize and automatic actions are verified. EVALUATION RESULTS : All indications and controls responded
]v correctly, two alarms did not actuate.
No other problems were noted. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations . personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOIITION: None (If Applicable) l TESTED BY : 9-20-90 George M. Vaux REVIEWED BY : Mark D..Phillippe 10-22-90 TEST ACCEPTED BY : Wayne L. Smith 10-26-90 t
/ D-168 l
l
.g , - - -w -
_ _ . -____.-_-..______-._..__.._.__.._.-_._._._.__-_..___..__..._._.m..-._ i APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST FUMBER : NTI-630.05 ' PERFORMANCE TEST TITLE : STEAM GENERATOR LEVEL SETPOINT DRIFT ; INITIAL CONDITIONS : 804 power, c. iy time in coro cycle, ! equilibrium xenon TEST SYNOPSIS : Each steam generatcr level controller is sequentially failed at 10% then 90% and plant response is verified and steam genera *or levels are restored in manual Control. DATA COLLECTION : Control board observation and SPVS data collection program TRANSIENT INITIATOR RX0SA(B), Steam Generator A(B) Level Controller fails to (0-100%) Severity
- TERMINATION CRITERIA : Plant parameter trends stabilize and automatic actions are verified, EVALUATION RESULTS All alarms, indications and controls O responded correctly.
noted. No problems were .' EVALUATION CRITERIA : Evaluatien was performed by PWR experienced engineering and operations personnel using table top analysis in , lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable)- , DISSENTING OPINION RESOLUTION: None S (If Applicable) , TESTED BY : Mike Asher 9-21-90 REVIEWED BY : Mark D. Phillippe 10-22-90 TEST ACCEPTED'BY : Wayne L. Smith 10-26-90 D-169
.. ~ . - . . . . _ . - . . - _ . - . - - . - - . . - - . - - - - ~ . . ~ . - . - - . ~ .
b l i APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-630.07 PERFORMANCE TEST TITLE : PRESSURIZER PRESSURE CONTROLLER FAILS OFF INITIAL CONDITIONS : 80% power, steady state TEST SYNOPSIS : From 80% power, initiate tne pressurizer
, pressure controller malfunction failed off. Initiate -a ' steam leak. Verify plant response.
DATA-COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : RXO7A and RXO7B, Pressurizer Pressure Controller Falls Off- _ MSO4A, MS-319A Faulty Seat Leak by at 10% , TERMINATION CRITERIA l' Verification of plant' response EVALUATION RESULTS : The test has not been performed.
.f EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
- None-(If Applicable) - DISSENTING OPINION
. RESOLUTION: None
.(If Applicable)
TESTED BY : n/a-REVIEWED BY - n/a TEST ACCEPTED BY-t' n/a . -i l D-170
APPENDIX D O t PERFORMANcd TEST ABSTRACTS v/ PERFORMANCE TEST NUMBER NTI-630.00 SERFORMU!CE TEST TITLE : PRESSURIZER LEVEL CONTHOLLER FAILS OFF INITIAL CONDITIONS : 00t power, steady stato TEST SYNOPSIS : From 00% power, fail the pressurizor , , lovel controller. Verify plant responso. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR RX00A and RX000, Pressurizer Lovel Controller Fails Off TERMINATION CRITERIA : Paramotor trends are stable. EVALUATION RESULTS : The test has not boon performed. EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a ( D-171
l APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-630.09 PERFORMANCE TEST TITLE : STEAM GENERATOR LEVEL CONTROL FAILURE INITIAL CONDITIONS
- 80% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : Each steam generator level controller is sequentially failed to 10% then 90% and plant response verified.
DATA COLLECTION : Control Board observation and SPVS data collection TRANSIENT INITIATOR : RXO9A(B), FWIFICllll Steam Generator A(B) Level Controller Falls to (0-100% Severity TERMINATION CRITERIA : Plant parameter trenda stabilize and automatic actions are verified. EVALUATION RESULTS : All alarms, indications and controls O responded correctly. No problems were noted. Suggestion to include narrow range steam generator level indication was made by OA&ID. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using ta.;le top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) , OISSENTISG OPINION F.ESOLUTION: None ) (If Applicable) TESTED BY : Mike Asher 9-21-90 REVIEWED BY : Mark D. Phillippe 10-22-90 TEST ACCEPTED BY : Wayne L. Smith 10-26-90 D - l *12
i APPENDIX D PERFORMANCE TEST ABSTRACTS l PERFORMANCE TEST NUMBER NTI-630.10 PERFORMANCE TEST TITLE 1 PRESSURIZER BACKUP HEATERS FAIL INITIAL CONDITIONS : 100% power, any time in core cycle, L equilibrium xenon TEST SYNOPSIS : The failur9 of pressurizer backup heater
, operation ',oth on and of f _in automatic and manual control is verified.
DATA COLLECTION Control Board operation and SPVS data collection program TRANSIENT INITIATOR RX10Al-C2, Pressurizer Backup, Heater , Bank 1-4 Falls On/Off ' TERMINATION CRITERIA Plant parameter trends stabilize and automatic actions are verified. i EVALUATION RESULTS : All alarms, indications and controls responded correctly. No problems were noted. Reactor trips and subsequent load ' rejections resulted in 3 sections of the O- test boing skipped, t EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : George M. Vaux 9-20-90 it REVIEWED BY : Mark D. Phillippe 10-22-90 TEST ACCEPTED BY : Wayne L. Smith 10-26-90
APPENDIX D m _ PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-630.11 l PERFORMANCE TEST TITLE : PRESSURIZER PROPORTIONAL HEATERS I FAIL ON/OFF {
. INITIAL CONDITIONS : 100% power, any time in core cycle, .
equilibrium xenon t TEST SYNOPSIS : Each pressurizer proportf onal heater bank is failed on and off, plant response is verified. DATA COLLECTION : . Coritrol Board observation .nd SPVS data collection program TRANSIENT INITIATOR RX11Al-BS, Proportional Heater Bank 1(2) Fails On/Off
- TERMINATION CRITERIA : Plant _ parameter trends stabilize and
- automatic actions are verified.
EVALUATION RESULTS : All alarms, indications and controls responded correctly. No problems were
- noted.
V(T. EVALUATION CRITERIA : Evaluation was by. PWR experienced engineering performed and ' operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None
.(If-Applicable)_ .
DISSENTING OPINION RESOLUTION: None , (If Applicable) L TESTED BY : Mike Asher 9-20-90 1 REVIEWED BY : - Mark D.-Phillippe 10-22-90 TEST ACCEPTED BY : Wayne L. Smith 10-26-90 !i i
- LO.
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I APPENDIX D PERF*)RMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-630.14 PERFORMANCE TEST TITLE : PRESSURIZER PRESSURE CONTROLLER 100X/Y FAILS INITIAL CONDITIONS : n/a TEST SYNOPSIS : The test has not boon written. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : RX14, Pressurizer Prosauro Controller Fails TERMINATION CRITERIA : n/a EVALUATION RESULTS : The test has not boon performed. EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
Nono (If Applicablo) DISSENTING OPINION RESOLUTION: Nono (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEbf ACCEPTED BY : n/a D-175
1 l APPENDIX D PERFORMANCE TEST ABSTRACTS l PERFORMANCE TEST NUMBER NTI-631.01 i PERFORMANCE TEST TITLE i S/G TUBE LCAK (0-100%, 100% = 15 TUBES) INITIAL CONDITIONS : 100% power, any time in core cycle, equilibrium xenon TEST SYNOPSIS : At 100% power, a 14 then 10% severity , tube leak is initiated and system response is verified. 1 DATA COLLECTION : Control Board observation and SPVS data collection TRANSIENT INITIATOR SG01, Steam Generator Tube Leak TERMINATION CRITERIA : it severity, plant stabilizes with decreasing pressurizer level and stable , parameter trends. 10% severity, plant stabilizes post trip with stable parameter trends. O EVALUATION RESULTS : All alarms indications responded as expected, no problems were noted. Engineering analysis questioned and controls - the timing of the trip response. ' Procedure corrections will be made before the test is rerun. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations i personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None. (If Applicable) DISSENTING OPINION RESOLUTION : None.
.(If Applicable)
TESTED BY : George M. Vaux S-27-90 REVIEWED BY : Mark D. Phillippe 1-21-91 TEST ACCEPTED BY : Wayne L. Smith 1-22-91 l D-176
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APPENDIX D o k,) PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER NTI-631.04 PERFORMANCE TEST TITLE : MAIN STEAM LINE PRESSURE TRANSMITTERS FAIL (1 - 100% OF RANGE) INITIAL CONDITIONS : 100% power, steady state, and Modo 2 entry, 2000 ppm Boron TEST SYNOPSIS : At 100% power, insert the 25% . pressure channel failure and verify proper response for each 4 channels for 2 steam generators. At Mode 2 insert 100% failure for each 4 channels for 2 steam generators and verify proper response. DATA COLLECTION : Control Board indications TRANSIENT INITIATOR : SG04A through EG04H, Main Steam Line Pressuro Transmitters Fall TERMINATION CRITERIA : Plant is stable [D
's /
EVALUATION RESULTS : All alarms, indications, parameters responded as expected. and plant The test procedure will be changed before the test is rerun to make the execution ' easier. EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA REFERENC;3: None (It Applicablo) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : Mike Asher 9/27/90
' REVIEWED BY : Mark D. Phillippe 10/16/90 TEST ACCEPTED BY : Wayne L. Smith 10/17/90
\ m
) D-177
k APPENDIX D ( PERFORMANCE TEST ADSTRACTS PERFORMANCE TEST NUMBER NTI-631.05 PERFORMANCE TEST TITLE : SG LEVEL TRANSMITTER FAILURE (1 - 1004 OF RANGE) INITIAL CONDITIONS i 100% power, steady state, any time in core life TEST SYNOPSIS : Initiated the SG 1evel transmitter f ailure at 25, 60, and 90% of range for 4 channels and verified system response. DATA COLLECTION : Control Board indications and SMS data collection program TRANSIENT INITIATOR SG05A, B, C, and D, Steam Generator Level Transmitter Failure TERMINATION CRITERIA Plant remains stable EVALUATION RESULTS : Engineering analysis questioned the feedwater level response. All other alarms, indications, and plant parameters ('i responded as expected.
<j' EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data.
PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING *WlNION RE&oLUTION: None (If Applicab1e) TESTED BY : H. C. Crummey 9/28/90 REVIEWED BY : Mark D. Phillippe 10/19/90 TEST ACCEPTED BY : Wayne L. Smith 10/19/90 D-178 [) m
i e APPENDIX D , PERFORMANCE TEST ABSTRACTS i PERFORMANCE TEST NUMBER I NTI-632.01 PERFORMANCE TEST TITLE : SI PUMP TRIP l 1 t INITIAL CONDITIONS : 100% power, steady state, any time in ! core life 5 TEST SYNOPSIS From_ 100% power, a Loop 1A Cold Leg a
, rupture is initiated to generate a Safety Injection actuation. Each SI pump, HPSI and LPSI, is tripped and plant response is verified. >
i DATA COLLECTION Control Board indications and SPVS data { collection program TRANSIENT INITIATOR : SIO1A through 8101E, Safety Injection Pump Trip 1 TERMINATION CRITERIA t Verification that total SI flow reduces t EVALUATION RESULTS All alarms, indications, and plant parameters associated with the Safety Injection system responded as expected. EVALUATION CRITERIA- _ Evaluation was _ performed by._ PWR experienced engineering and operations . personnel using table _ top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None-
.(If. Applicable) -
DISSENTING OPINION RESOLUTION: None (Ifl Applicable)-
"t TESTED BY : Mike'Asher 10/24/90 I REVIEWED BY _
Mark D. Phillippe 11/7/90 : TEST ACCEPTED BY : Wayne L. Smith 11/15/90 < b 7 _ . - - - _ . _ _ _ _ _ -_ . . - _ . _ . - . . _ _ . . _ , _ _ . . , . . _ , . _ . _ . . . - . . .,,.u.-,_.__..._,-.___,_, -,..,,....-.,._.,,,_....,_,,,_.-_,.a
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-632.04 PERFORMANCE TEST TITLE : AIR BINDING IN SI SYSTEM INITIAL CONDITIONS : Shut down cooling conditions, dreined to the top of the Ifot Leg TEST SYNOPSIS : With SDC in place, the malfunction is initiated. Plant response is verified for the loss of SDC. The test is repeated for both loops. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : SIO4A and SIO4B, Air Binding in SDC due to open Suction Header Relief valve TERMINATION CRITERIA : RCS temperature rise due to loss of SDC flow i lVALUATION RESULTS : Engineering analysis had questions about the temperature and pressure response of the A side. No other problems were found V on the A side. The E Mde response is considered unsatisfactory e.nd a problem report has been written to correct this. EVALUATION CRITERIA : Evaluation was performed by PWR experienced enginedring and operations personnel using cable top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: Hono (If Applicable) TESTED BY : George M. Vaux, Jr. 9/23/99 REVIEWED BY : Mark D. Phillippe 10/19/90 TEST ACCEPTED BY : Wayne L. Smith 10/26/90 D-180 __ .- - - - - - ~ - - - - - - - - '
I APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-632.08 PERFORMANCE TEST TITLE : LPSI PUMP SUCTION LINE RUPTURE INITIAL CONDIT3ONS : LOCA initiated from a 100% power condition
.EST SYNOPSIS : With a Loop 1A cold Leg Rupture in progress from 100% power, the LPSI pump suction lines are given a 10% and 90%
rupture. Plant response is verified. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR SIO8A and SIOBB, LPSI Pump Suction Line Rupture TERMINATION CRITERIA : Penetration area sump level rises EVALUATION RESULTS : All alarms, indications, and plant parameters for the suction line rupture event responded as expected, b d EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) , TESTED BY : George M. Vaux, Jr. 10/25/90 REVIEWED BY : Mark D. Phillippe 11/14/90 TEST ACCEPTED BY : Wayne L. Smith 11/1S/90 D-101
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-632.11 PERFORMANCE TEST TITLE : SHUTDOWN HEAT EXCHANGER TUBE LEAK INITIAL CONDITIONS : Shutdown, SDC in service, 125'F q TEST SYNOPSIS : WitP SDC in_ service, introduce activity into the primary system with the Reactor i Fuel Cladding Failure malfunction. Introduce the Shut Down Cooling Heat Exchanger leak raalfunction at 10% and 90% , . severity and verify plant response. 1 DATA COLLECTION : Control Board indications and SPVS-data collection program TRANSIENT INITIATOR : SIllA and S111B, Shutdown Heat Exchanger Tube Leak ; TERMINATION CRITERIA t CCW activity and outlet temperature rises EVALUATION RESULTS : All alarms, indications, and plant parameters responded as expected. . A l- change to the test procedure will be l- incorporated prior to the test being rerun. EVALUATION CRITERIA : Evaluation- was performed by PWR experienced - engineering and operations personnel using table top analysis in lieu of plant data or.best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : Mike Asher 10/26/90 . REVIEWED BY : Mark D. Phillippe 11/14/90 TEST ACCEPTED BY : Wayne L. Smith 11/13/90 l
.D-182
APPENDIX D PERFORMANCE TEST ABSTRACTS l PERFORMANCE TEST NUMBER NTI-633.01 ! PERFORMANCE TEST TITLE : TURBINE LOAD CONTROL DEMAND FAILURE INITIAL CONDITIONS : ~f0% power, steady state TEST SYNOPSIS : From 60% power, activate the malfunction at the 10% rate and the 90% rate. Verify
, plant response.
DATA COLLECTION : Control Board AndAct,t tons . and SPVS' data collection program-TRANSIENT INITIATOR- TC01, Turbine Load Control Demand Failure (0 - 1004) # TERMINATION-CRITERIA :- Parameter trends are stable-EVALUATION RESULTS : The test has not - been performed due to - problem-reports scheduled to be worked. EVALUATION CRITERIA None (~ PLANT DATA
REFERENCES:
None - )
\ (If Applicable) -l DISSENTING OPINION -
RESOLUTION: None-
-(If Applicable)
- TESTED BY 1 n/a .
REVIEWED BY. - n/a
- TEST ACCEPTED 1BY n/a, ,
D-183
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APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER t NTI-634.01 PERFORMANCE TEST TITLE : TCCW PUMP THIP INITIAL CONDITIONS 1 80% power, steady state TEST SYNOPSIS : From 904 power, the malfunction trips the running TCCW pump and the response is
, verified. The standby pump is then manually secured and the system response
.ie verified.
DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT; INITIATOR : TP01A and TP01B, TCCW Pump Trip TERMINATION CRITERIA : Cooled equipment temperatures rising-1 EVALUATION RESULTS : Several pieces of the cooled equipment did not respond to the loss of coolant. A problem report was written. All of the remaining alarms, indications, and plant p rameters responded as expected. EVALUATION CRITERIA 1 Evaluation was performed .by PWR' i experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
~Jne
, (If Applicable)- DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : Mike Asher 9/26/90 i REVIEWED BY : Mark D. Phillippe 10/16/90 j- TEST ACCEPTED BY : Wayne L. Smith .10/12/90
- f. ,
D-184 i
,e
APPENDIX D r (x PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-634.04 PERFORMANCE TEST TITLE : TCCW HX OUTLET HEADER LEAK INI'l'I AL CONDITIONS : 80% power, steady state TEST SYNOPSIS : From 80% power, the loak malfunction is initiated at rates of 10% and 90% for both heat exchangers. Plant response is verified. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : TPO4A and TPO4B, TCCW Heat Exchanger Outlet Header Leak TERMINATION CRTTERIA : Cooled .:quipment temperatures rise and the automatic condensate maxoup valve modulates EVALUATION RESULTS : Problem reports were written on no temperature increase on some cooled (y' equipment and the response of the surgo tank along with the TCCW pumps. The test is scheduled to be rerun when problems are corrected. EVALUATION CRITERIA t Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis .i n lieu of plant data or best estimato data. PLANT DATA
REFERENCES:
None (If Applicable) DId2ENTING OPINION RESOLUTION: None (If App 11able) TESTED BY : George M. Vaux, Jr. 9/27/90 REVIEWED BY : Mark D. Phillippo 10/16/90 TEST ACCEPTED BY t Wayne L. Smith 10/19/90 fJ D-185
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-634.05 PERFORMANCE TEST TITLE : LOSS OF COOLING WATER TO HYDROGEN COOLERS INITIAL CONDITIONS : 80% power, steady state TEST SYNOPSIS : From 80% power, insert the malfunction establishing hydrogen cooler inloakage. Verify plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : TPOSA, B, C, and D, Loss of Cooling Water to Hydrogon Coolers TERMINATION CRITERIA : Parameter trends are steady. EVALUATION RESULTS : The tost has not boon performed. EVALUAT20N CRITERIA None O PLANT DATA
REFERENCES:
(If Applicable) Nono DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a O "->es l
t APPENDIX D y/ PERFOi?MANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-634.06 PERFORMANCE TEST TITLE LOSS OF TCCW COOLING TO IA/SA COMPRESSORS INITIAL CONDITIONS : 80% power, steady state TEST SYNOPSIS : From 80% power, insert a 6" break into the coolant supply line for the compressors. Verify plant response. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : TP06, Loss of Con 11ng to Instrument Air / Service Air Compressors TERMINATIOh CRITERIA : Pr.rameter trends are stable EVALUATION RESULTS : The test has not been performed due to problem reports scheduled to be worked. 7 JVALUATION CRITERIA : Nono u/ PLANT ,OATA
REFERENCES:
?
(if Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a
)
() D-187
APPENDIX D () PERFORMANCE TEST ARSTRACTS PERFORMANCE TEST NUMBER : NTI-635.06 PERFORMANCE TEST T!TLE : TURBINE TRIP INITIAL CONDITIONS : 100% 7ower, steady state TEST SYNOPSIS : The tast has not been written, DATA COLLECTION t Control Board indications and SPVS data collection program TRANSIENT INITIATOR 1 TUO6, Turbine trip TERMINATION CRITERIA : None EVALUATION RESULTS : The te' has not been performed. EVALUATION CRITERIA : Mene .r"N O PLANT DATA RCFERENCES: None (If'Aepl' able)
. DISSENTING OPINIC'l RESOLUTION: None (If Applicable)
TESTED BY : n/a REVIEWED BY : n/a " TEST' ACCEPTED BY : n/a (%.)D D-188
. . - . .. - - - -.- . . , - . - . . , , - - . . - - . . - . . - . - . _ . . . - . ~
t
- APPENDIX D V
O PERFORMANCE TEST ABSTRACTS 1 PERFORMANCE TEST NUMBER NTI-640.01 - PERFORMANCE-TEST- TITLE.: LOSS OF ONE FEEDWATER HEATER EVENT INITIAL-CONDITIONS : 100% power, steady state TEST SYNOPSIS . From 100% power,- bypass all #1- High Pressure heaters and isolate #1 Feedwater >
, Heater Trains. Verify plant response.
I DATA COLLECTION-: Control 30ard indicationa and SPVS data j collection program
. TRANSIENT INITIATORc: Manual - bypass _ and isolation of hers ter trains - using controls and remote functions ;
TERMIN! ION-CRITERIA : Parameter trends are stable
'EVALuafION RESULTS : The test results were unsatisfactory.
The procedure values will be changed and , the test will be rerun.
' EVALUATION CRITERIA : Evaluation was periormed by PWR A experienced engine.ering and operations personnel -using table top analysis in lieu of plant Aata or best estimate data.
-PLANT: DATA
REFERENCES:
None l(If Applicable)
- DISSENTING : OPINION
. RESOLUTION: -None f(If' Applicable) '
TESTED BY : Mike Asher 10/4/90 '
. REVIEWED BY : Mark D. Phillippe -11/7/90 .
TEST-ACCEPTED BY := Wayne L. Smith 11/15/90 ' Y is. - - -. - . '.. _ . . _. .- .- . . _ - .
r APPENDIX-D W : 4 PERFORMANCE TEST ABSTRACTS PERFORM 3LNCE TEST NUMBER--: NTI-640.03
' PERFORMANCE TEST TITLE : EFAS ACTUATION AT POWER EVENT
. INITIAL CONDITIONS : 100% power, steady state f TEST SYNOPSIS : From 100% power, place the feedwater controls --in manual and' j nitiate Emt.,rgency
, -Teed .-- Vorify plant response to the over--
-feed condition.
~
DATA COLLECTION : Control Board ind1 cations and SPVS data :
. collection' program '
TRANSIENT INITIATOR i Ste;: ting the Train A EFW pump and locking the normal feedwater controls into manual- ' TERMINATION CRITERIA : Parameterstrends are stable.
~
- EVALUATION RESULTS :- The :. test results were determined - to be unsatisfactory. The test ~will be revised and rerun. : Engineering! analysis ,
questioned the response of:theEcriticalE parameters. EVALUATION CRITERIA.: Evaluation was performed by PWR
' experienced engineering and operations personnel .using. table top analysis in lieu of plant data or best' estimate data.
PLANTEDATA
REFERENCES:
None (If Applicable)- L
- DISSENTING OPINION-RESOLUTION: -None (If . ~Applj cable)
TESTED BYi: Mike Asher- 10/1/90 , u , REVIEWED BY-- Mark D'. Phillippe- 10/25/90 !~ TEST ACCEPTED BY :- -Wayne L. Smith 10/26/90 a f ITY o-190-1 V.
.i1 VI H ;, .
-APPENDIX D ;g 4,
PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER - NTI-C40.09 PERFORMANCE TEST TITLE-: LOSS OF CONDENSER VACUUM EVENT INITIAL CONDITIONS : 100% power,. steady state, End of Cycle TEST SYNOPSIS From 100% power, trip all of the Cire i pumps on- overcurrent. -Verify ' plant response. DATA COLLECTION.: Control Board indications and SPVS data collection program TRANSIENT INITIATOR : CWO1A, B, C, and D, Overcurrent trip _of-Circ pr ps-TERMINATION CRITERIA :- Parameter trends are stable. 4 EVALUATION RESULTS : The test results were deta ained to be-
-ut. satisfactory. The test will- be rewritten and.reperformed.
, . . EVALUATION CRITERIA : Evaluation _ was- performed by- _PWR q i 'O experienced engineering and operations :
, (/ ' _ personnel using tabic top analysis in ' lieu of plant data or best estimate data.- PLANT DATA REFERENCES ' None (If Applicable) DISSENT 1NG-OPINION
. RESOLUTION ' None L (If-Applicable)-
l L TESTED BY : Mike-Asher 10/2/90 ' REVIEWED BY : Mark D.'Phillippe 11/12/90-TEST' ACCEPTED--BY - :- Wayne L.__ Smith 11/15/90-t i i
, - --,- -c-
U1
.i APPENDIX D- .' .Q Q
PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-640.10 +
- PERFORMANCE TEST TITLE :- LOSS OF ALL NORMAL AC EVENT INITIAL CONDITIONS : 100% power, End of Cycle j
. TEST SYNOPSIS : -From--100% power, .with some- control-systems-in-manual and some reactor trips-- t
'in override, initiate a loss of all normal AC power. Verify plant response..
-DATA CnLLECTION :. Control Board indicaaions-and-SPVS-data collection program TRANSIENT--INITIATOR :~ ED01A, B, C, and 3, - Loss of Of f aite- Power -
EG01, Negative Phase Sequence
'. TERMINATION CRITERIA : ; Pararneter - trends - are stable . -
EVALUATION RESULTSL ' =The_ _ test was- determined to- be
-: unsatis f actory. The test: will -be s
-rewritten and-rerun.
[\i
^
EVALUATION CRITERIA-:- Evaluation was . performed-experienced engineering .and f operations by. PWR personnel using table top- analysis 'in lieu of plant data or best estimate. data. LPLANT DATAf
REFERENCES:
None (IfJApp11 cable) DISSENTING-OPINION RESOLUTION' None ('if Applicable) TESTED-BY : George'M. Vaux, Jr. 10/3/90 ' " REVIEWED BY.':. Mark D..Phillippe 11/11/90-
. TEST ACCEPTED BY:: Wayne L. Smith- 11/15/90 ,
D-192 ( - *b,,v ,+ - ,
.g ^
'_Tk' APPENDIX D- -
g, l j r PERFORMANCE TEST ABSTRACTS ,
~ : PERFORMANCE TEST NUMBER-1 NTI-640.21-
-PERFORMANCE-TEST,-TITLE- S/G TUBE- RUPTURE- WITH LOSS OF OFFSITE POWER-EVENT INITIAL' CONDITIONS 100% power, End of Cycle 1
TEST-SYNOPSIS ~t From 100%- power, = initiate a SG #1 tube 4
, rupture at 10% _ severity. _ Initiate a less Lof of fsite power event to coincide with a t
, reactor trip.. Verify plant response. ;
J eD. ' DATA COLLECTION-- Control Board Lindications and SPVS data
'ce11ection program
. TRANSIENT .INITI ATOR' :--
-SG01A, SG #1 Tube Rupture 9:1041 severity 4 ED01A,.B, C, and D, Lossiof Offaite Power- -
coinci' dent-with reactor _ trip
= TERMINATION CRITERIA -Parameter. trends-are stable.-
EVALUATION:RESULTSl:' - The ? test Lwas . not - completed. The test . procedure ~will be review-and' revised.as-necessary;before. rerunning. EVALUATION CRITERIA 1: Evaluation- . was- performed by= . PWR . experienced; engineering and operations personnel usingl table top ' analysis in-lieu of . plant' data .or .best estimate data.-
,PLANTEDATAJ
REFERENCES:
'None
.(If' Applicable)
-DISSENTING OPINION RESOLUTION: None
L(IfTApplicable).
-TESTED BY. : Eke'Asher --10/17/90.
REVIEWED BY.Ji- Mark D.'Phillippe 112/07/90
- TEST ACCEPTED BYD : Wayne L. Smith 12/20/901 <
4 4 i
., . 4, . - , * . _ . . , . . - . . , . . . _ . _ __~ _.m ._m . _ _ .______i . _ _
APPENDIX L () PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-645.003 PERFORMANCE TEST TITLE : CHARGING PUMP OPERABILITY CHECK INITIAL CONDITIONS : 100% power, steady state TEST SYNOPSIS : From 100% power, run the surveillance test OP-903.003, Charging Pump Operability Check. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : None TERMINATION CRITERIA : Completion of the surveillance test EVALUATION RESULTS : Problems were noted with the PMC data points used in the surveillance test. Engineering analysis recommended a problem report be written on this point. The surveillance test was performed satisfactorily. ID (/ EVALUATION CRITERIA : Evaluation was performed by PWR experienced engineering end operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable; DISSENTING OPliiION RESOLUTION: None (If Applicable' , TESTZD BY : R. J. Ciminel 2/15/91 REVIE'/ED BY : Mark D. Phillippe 2/25/91 TEST ACCETTED BY : Wayne L. Smith 2/26/91 [") \_s' D-194
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-645.004 PERFORMANCE TEST TITLE : BORIC ACID PUMP OPERABILITY CHECK INITIAL CONDITIONS : 100% power, steady state TEST SYNOPSIS : From 100% power, run surveillance test OP-903-004, Boric Acid Pump Operability Check. DATA CC ~'CTION : Control Board indications TRANSIENT INITIATOR : None TEPJ4T. NATION CRITERIA : Completion of che surveillance test EVALUATION RESULTS : The surveillance test was run satisfactorily. No problems were reported. VALUAM ON CRITERIA : Evaluation was performed by PWR experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : R. J. Ciminel 2/15/91. REVIEWED BY : Mark D. Phillippo 2/25/91 TEST ACCEPTED BY : Wayne L. Smith 2/26/91 , D-195 1
- - - . - _ _ . - . - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - - - - ^ ' ' ' ' ^ '
APPENDIX D PERFORMANCE TEST ABSTRACTS PEliFORMANCE TEST NUMBER : NTI-645.007 PERFORMANCE TEST TITLE : TURBINE INLET VALVE CYCLING TEST INI"IAL CONDITIONS : 100% power, steady state
'12cT SYNOPSIS : From 100% power, run surveillance test OP-903-007, Turbine Inlet Valvo Cycling Test.
DATA COLLECTION : Control Board indications TRANSIENT INITIATOR : None TERMINATION CRITERIA : Completion of the surveillance test EVALUATION RESULTS : The surveillance test was run satisfactorily. Engineering analysis questioned why all of the valves were not tested. EVALUATION CRITERIA : Evaluation was performed by PWR experjenced engJneering and operations O personnel using table top analysis in \d lieu of plant data or best ostimate data. PLANT DATA
REFERENCES:
Nono (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : R. J. Ciminel- 2/15/91 REVIEWED BY : Mark D. Phillippe 2/25/91 , TEST ACCEPTED BY : Wayne L. Smith 2/26/91 D-196
APPENDIX D I t,) PERFORMANCE TEST ABSTRACTS l PERFORMANCE TEST NUMBER : NTI- 15.010 PERFORMANCE TEST TITLE : ECC3 THROTTLE VALVES POSITION l VERIlICATION INITIAL CONDITIONS : 100% power, steady state TES1 SYNOPSIS : From 100% power, run surveillance test OP-903-010, ECCS Throttle Valves Position Verification DATA COLLECTION : Control Board indications TRANSIENT INITIATOR : None TERMINATION CRITERIA : Completion of the surveillance test EVALUATION RESULTS : The surveillance test was run satisfactorily. A problem report was written on the response of the ECCS valve positions. EVALUATION CRITERIA : Evaluation was performed by PWR (,_T experienced engineering and vperations k_) personnel using table top analysis in lieu of plant data-or best estimate data. PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable)
-TESTED BY : R. J. Ciminel 2/15/91 REVIEWED BY : Mark D. Phillippe 2/25/91
' TEST ACCEPTED BY : Wayne L. Smith 2/25/91 D-197
APPENDIX D iA ( ) PERFORMANCE TEST ABSTRACTS
<j PERFORMANCE TEST NUMBER : NTI-645.011 PERFORMANCE TEST TITLE : HIGH PRESSURE SAFETY INJECTION PUMP PRESERVICE OPERABILITY CHECK INITIAL CONDITIONS : 100% power, steady state TEST SYNOPSIS : From 100% power, run surveillance test OP-903-011; High Pressure Safety Injection Pump Preservice Operability Check.
DATA COLLECTION : Control Board indications TRANSIENT INITIATOR : None i TERMINATION CRITERIA : Completion of the surveillance test EVALUATION RESULTS : The surveillance too v, was run satisfactorily. A problem with the available remote functions to operate in-plant valves was reported. EVALUATION CRITERIA : EvalGation was performed by PWR (-)5 (_ experienced engineering and operations personnel using table top analysis in lieu of plant data or best estimate data,
' PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : R. J. Ciminel 2/15/91
~
REVIEWED BY : Mark D. Phillippe- 2/25/91 TEST ACCEPTED BY : Wayne L. Smith 2/26/91 (~}.
%./
D-198
;v
' APPENDIX D i PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-645.024 PERFORMANCE-. TEST TITLE : REACTOR COOLANT- SYSTEM t'ATER INVENTORY BALANCE INIT'IAL CONDITIONS : 100% power, steady state ,
TEST SYNOPSIS From 100% power, run surveillance test OP-903-024. DATA COLLECTION : Control Board indications TRANSIENT INITIATOR None TERMINATION CRITERIA's -Completion of the surveillance test '
. EVALUATION RESULTS The test has not been'run.
EVALUATION CRITERIA 11 None PLANT DATA
REFERENCES:
None' (If Applicable)
"Q.
v. DISSENTING OPINION RESOLUTION: None
- (If Applicable)
TESTED BY : n/a- ~ REVIEWED BY.: n/a *
-TEST ACCEPTED BY-: n/a q
+
d []- D-199 v
_. . . - _ . ._ __ _.._._.. _ _.._ . _ . . _ - - _ . . . - . _ . _ . ~ . _ . . . _ _ . .-. . . . APPENDIX D [ PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-645.035 , PERFORMANCE TEST TITLE : CONTAINMENT SPRAY PUMP OPERABILITY CHECK INITIAL' CONDITIONS : 100% power, steady state TEST SYNOPSIS : From 100% power, run surveillance test OP-903-035, Containment Spray Pump Operability Check.- DATA COLLECTION Control Board indications i TRANSIENT INITIATOR- None o o TERMINATION CRITERIA 1 CompJetion of the surveillance test i l--
. EVALUATION RESULTS :- The surveillance test was run satisfactorily. No problems were reported.
EVALUATION CRITERIA' - Evaluation .was, performed by- PWR
. experienced engineering and -operations f 4/ :
fl personnel using table top analysis in lieu of plant data or best estimate data. L' E PLANT DATA
REFERENCES:
- None (If Applicable) DISSENTING-OPINION , RESOLUTION: None (If Applicable)- 4. TESTED BY : 'R. J. Ciminel 2/15/91 j' REVIEWED BY :- fr.Ik D. Phillippe 2/25/91 [, -TEST ACCEPTED BY : Weyne L. Smith 2/26/91 l-p D-200 l.'.____2_.__________________________._...m .m_ . . _ , , , , , , . , , _ , - , e._ _r y 7 , - __.p
. _ - . _ . - . - . . . - . = - - - - - . . ~ . - . - - - - . . .
. - . ~ . - . . ,
k .e APPENDIX D-PERFORMANCE TEST ABSTRACTS
'PE'LFORMANCE TEST NUMBER : NTI-645.068 PERFORMANCE TEST TITLE': Emergency Diesel Generator Operability Verification
. INITIAL CONDITIONS I 100% power, st.c3dy state TEST SYNOPSIS : From 100% power, run surveillance test OP-903-068,- Emergency Diesel Generator '
Operability Verification. I DATA COLLECTION : Control Board indications TRANSIENT INITIATOR s None-TERMINATION CRITERIA :. Completion-of the surveillance test i EVALUATION.RESULTS : The- surveillance- test was run satisfactorily. No. problems were l reported. . EVALUATION CRITERIA : Evciuation was . performed by. PWR experienced engineering and : operations Ll O -"artom.91 - using table top ~ analysis in 4'.eu of olant data or best estimate data. L PLANT DATA'REFERENC"Si None ,
-(If Applicable) ;
l L- DISSENTING OPINION-
- j. -RESOLUTION: .None p L(If; Applicable)
L TESTED BY : R. J. Ciminel- -2/15/91 t REVIEWED BY-: Mark D. Phillippe. 2/25/91' i TEST ACCEPTED BY :' 2/26/91 Wayne L.: Smith l i b.
%W D-201
9 L .
- - - = . _ . . - _ . - . . . _ - . - . .. - , , ., . .-.- - -- ..
-APPENDIX D Af f] -
PERFORMANCE TEST ABSTRACTS e
-PERFORMANCE TEST NUMBER t' NTIr6451.090 PERFORMANCE TEST TITLE SHUTDOWN MARGIN INITIAL ~ CONDITIONS : 100% power, steady state-TEST SYNOPSIS From 100% power, run surveillance test , OP-903-090, Shutdown margin.
I-I
- DATA COLLECTIud : Control Board indications
,(-
~
. TRANSIENT INITIATOR None SERMINATION CRITERIA. Completion of the surveillance test EVALUATION RESUITS The surveillance test was not run, '
EVALUATION CRITERif , None Fl#Fc DATA =REFERENCFS None
- (1f. Applicable)
. - DISSENTING OPINION .
RESOLUTION: None j_ l(If Applicable) 1 TESTED BY-: n/a REVIEWED BY 1- n/a: n/a
~
TEST-ACCEPTED-BY : W (- u l 4
-~ -
L-
~l 'D-202 a
, . - . . . , ~ . . . , . , . , , , . . . e....-., , ., ,
APPENDIX D PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-645.101 PERFORMANCE TEST TITLE : STARTUP CHANNEL FUNCTIONAL TEST STARTUP CHANNEL 1 AND 2 INITIAL CONDITIONS : 1001, power, steady state TEST SYNOPSIS : From 100% power, run surveillance test OP-903-101. DACA COLLECTION : Control Board indications TRANSIENT INITIATOR : None TERMINATION CRITERIA : Completion of the surveillance test EVALUAT'ON RESULTS : The surveillance test was not run.
- EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicabic) DISSENTING OPINION ON RESOLUTION: None (If Applicable) TESTED BY , n/a REVIEWED BY : n/a
'TCOT ACCEPTED BY : n/a
. _ _ . . _ . - . ~ . . _-.. .. ....._. -- . . ._ _ _ _ _ - . _ . - _
i 1 I l APPENDIX D-
]
I PERFORMANCE TEST ABSTRACTS ; PERFORMANCE TEST NUMBER : NTI-645.102 PEilFORMANCE TEST TITLE SAFETY CHANNEL NUCLEAR INSTRUMENTATION. FUNCTIONAL TEST INITIAL CONDITIONS : 100% power, steady state - TEST SYNOPSIS : From 100% power,. run surveillanc>s test > OP-903-102. DATA COLLECTION 3-: Control Board indications-TRANSIENT INITIATOR : None TERMINATION CRITERIA :- -Completion of the surveillance test EVALUATION RESULTS : The surveillance test was not run. '
' EVALUATION CRITERIA : None PLANT-DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION (~} s_- RESOLUTION ' None (If Applicable); TESTED 4BY : n/a
-REVIEWED'BY -
n/a TEST ACCEPTED-BY : n/a l H l
.{. D-204-f
. _ m _ . _ _ _ . . _ . . . _ _ . . . . _ _ . . _ _ _ _ . _ _ _ _ _ , _ . . . _ _ , . . _ . .. _ . _ _ . . . - . _ .
APPENDIX D , t PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-645.107-
. PERFORMANCE TEST -TITLE : PLANT PROTECTION'GYSTEM CHANNEL A B C D FUNCTIONAL TEST INITIAL CONDITIONS- 100% power, steady state TEST SYNOPSIS : From 100% power, run surveillance test
, OP-903-107. -
-DATA COLLECTION Control Board indications TRANSIENT INITIATOR:: None
_-TERMINATION CRITERIA : Completion-of the surveillance test ~
~
EVALUATION RESULTS . The surveillance test was not run. i
-EVALUATION CRITERIA : None- ,
PLANT DATA REFERENCES - None
;(If Applicable)
DISSENTING OPINION L . RESOLUTION: :None l (If! Applicable)- TESTED BY : -n/a REVIEWED BY.: n/a-TEST ACCEPTED BY : n/a l-
- I o'.
l u< _ 1 D-205 s
. . _ . _ _ _ __.;__ u- .
. . ~ . - _..- ~.... . _.. .. - _ - - - . . . , . - ,
. APPENDIX D- i
-,R l([. PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER.: NTI-647.010 PERFORMANCE TEST TITLE : REACTOR TRIP ON TURBINE TRIP CHANNEL .
A B C D FUNCTIONAL TEST INITIAL CONDITIONS.: 100% power, steady state TEST SYNOPSIS : From 100% power, run surveillance test OP-904-010. DATA COLLECTION : Control Board indications TRANSIENT INITIATOR : None
' TERMINATION CRITERIA Completion of the surveillance test EVALUATION RESULTS : The surveillance test was not run.
.i EVALUATION-CRITERIA None PLANT DATA.
REFERENCES:
None (It' App 11 cable) Y (.s-' h. DISSENTING OPINION-RESOLUTION: None
.(If Applicabla) l TESTED BY : n/a REVIEWEDLBY : n/a
' TEST. ACCEPTED BY : n/a i-L o
s he p-
... _ , - . _ . _ . _ . . . . , _ _ . _ _ _ . _ _ _ _ _ _ . _ _ _ __ ._. __m _ _ _
1 t if
. APPENDIX D..
p< h - PERFORMANCE TEST ABSTRACTS PERFORMANCE: TEST NUMBER : NTI-647.017 PERFORMANCE TEST TITLE : ANTICIPATED TRANSIENT SYSTEM CHECK a INITIAL CONDITIONS : 100% power, steady state , TEST SYNOPSIS : From 100% power, run surveillance test- : OP-904-017. DATA' COLLECTION : Control Board indications TRANSIENT INITIATOR None TERMINATION CRITERIA f Completion of the surveillance test EVALUATION RESULTS : The surveillance test was not run.
' EVALUATION-CRITERIA None
~ PLANT DATA
REFERENCES:
None ; _(If Applicable)
. DISSENTING OPINION i RESOLUTION: None aO .(If: Applicable)-
TESTED BY : n/a REVIEWED BY : -n/a
' TEST - ACCEPTED BY: I- n/a
.(
k , e 6 i 1 Pa h
~
p D-207-l3
. - . - . - - . -. -- , - . .. - ,, , . v I
APPENDIX D
,n -
PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-650.01 PERFORMANCE TEST TITLE : CRITICAL BURON CONCENTRATION INITIAL CONDITIONS : SE-4% power, 100% power, f or BOC , MOC, and EOC TEST SYNOPSIS : At the power levels, compare the simulator critical beron concentrations / with the values given in the Plant Data Book for that cycle. DATA COLLECTION- Control Board indications and SPVS data collection program TRANSIENT INITIATOR : None TERMINATION CRITERIA : None EVALUATION RESULTS : The test has not been performed, EVALUATION CRITERIA : None (~ PLANT DATA
REFERENCES:
None N (If Applicable) DISSENTING OPINION RESOLUTION: None .- (If Applicable) TESTED BY : n/a REVIEWED BY - n/a TEST ACCEPTED BY : n/a D-208
APPENDIX D
- ,Q j-- PERFORMANCE TEST ABSTRACTS PERFORMANCE' TEST NUMBER : NTI-650.02-PERFORMANCE TEST _ TITLE : GROUP WORTH TEST INITIAL CONDITIONS : SE-4% power TEST SYNOPSIS At the power level, borate all of: the CEAs out of the core Insert all of CEAs
, _w hile maintaining is-sr and temperature.
Compare the rod worths with the Plant Data Book for this cycle. DATA COLLECTION : Control Board Indications and-SPVS data collection program TRANSIENT INITIATOR : none TERMINATION CRITERIA : none EVALUATION RESULTS- The_ test has not been perforr9d. EVALUATION CRITERIA None . PLANT DATA'
REFERENCES:
None
.( (If_ Applicable)
DISSENTING OPINION RESOLUTION: None
.(IfzApplicable)
TESTED BY : n/a
' REVIEWED:BY : n/a TEST ACCEPTED BY : n/a 0
l
=c '
? 4 w e v =
we'
T APPENDIX D-i/~ 4 PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-650.03 PERFORMANCE TEST TITLE : -CEA SYMMETRY TESTS INITIAL CONDITIONS : n/a TEST SYNOPSIS : The test has not been written. DATA COLLECTION.:, Control Board indications and SPVS data collection program . TRINSIENT lNITIATOR : n/a TERMINATION' CRITERIA n/a EVALUATION RESULTS- The test has not been performed. EVALUATION CRITERIA : 'None , Li PLANT DATA
REFERENCES:
None
-_(If Applicable).
DISSENTING OPINION RESOLUTION: None
- Os '(If Applicable)
TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : 'n/a i i i J
l l i APPENDIX D
.p, . PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : 'NTI-600.04 PERFORMANCE TEST TITLE-1 ISOTHERMAL TEMPERATURE COEFFICIENT TEST -
INITIAL CONDITIONS : 5 E -4% power, BOC, MOC and EOC conditions, all rods out, normal operating. pressure and temperature
. TEST SYNOPSIS : From initial conditions,. reactor power is held constant using boration &_ dilution _
as , temperature is lowered 10. degrees. The boron change is then used to, calculate. the isothermal temperature coefficient. DATA COLLECTION 1. SPVS_ data collection Program TRANSIENTJ-INITIATOR't No transient is actuated during this test. TERMINATION CRITERIA-:- Comparison of calculated _ value of isothermal temperature coef ficient to the , plant data book value.
\
EVALUATION RESULTS BOC, -8E-4%; MOC, --3E-4%; Eoc, <-6E-4%; all satisfactory, problems-were reported on the value for- BOC. Engineering analysis _ _ determined -_that _'the value was satisfactory EVALUATION CRITERIA : Evaluatjon was. performed by- PWR-experienced engineering. and- operations personnel using- table top ' analysis 'in lieu of-plant data or best estimate data. . PLANT-DATA
REFERENCES:
'None.
-(If Applicable)-
4 DISSENTING OPINION RESOLUTION : None.
-(If Applicable)
TESTED BY : George M. Vaux 10-16-90 REVIEWED BY : Mark D. Phillippe 1-21-91 TEST ACCEPTED BY : Wayne L. Smith 1-24-91 T D-211
-[Q .
hj); E i. L. APPENDIX D ..py. ; s,.) ;. PERFORMANCE TEST ABSTRACTS .} PERFORMANCE TEST NUMBER : NTI-650.05 3M'
' r .st PERFORMANCE TEST TITLE POWER DEFECT TEST > 1 INITIAL CONDITIONS : 100% power, BOC, MOC, and EOC &
l TEST SYNOPSIS : From 100% power, borate the reactor to - 50% power. Calculate the power defect and compare to the Plant Data Book. p% DATA COLLECTION : Control Board indications and SPVS data collection program [ TRANSIENT INITIATOR : TERMINATION CRITERIA : none none m. EVALUATION RESULTS : The test has not been performed. 1 EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None (If Applicable) DISSENTING OPINION RESOLUTION: None (If Applicable) [ n/a TESTED BY : P.EVIEWED BY : n/a TEST ACCEPTED BY : n/a E i Erd tulig l i i 1 l
$ D-212 l
l m
?
-APPENDIX D '
.f 3 PERFORMANCE TEST ABSTRACTS
.6
'(s .!?
1
-PERFORMANCE TEST NUMBER : NTI-650.06 PERFORMANCE TEST TITLE' -XENON WORTli TEST INITIAL CONDITIONS SE-4% power, and 100% powor, steady state TEST SYNOPSIS 14 From-5E_1% power, ramp the simulator to 100% power over a 1 hour period. Verify
~
plant - re;ponse during a 60 hour xenon oscillation. From 100% power,. trip the reactor. Observe the xenon transient for a 40 hour cycle. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR none ' TERMINATION CRITERIA :- none
-EVALUATION-RESUtTS :. The test has not been per'iormed.
- - EVALUATION -CRITERI A' :'. None
;p) .k._, - PLANT. DATA:
REFERENCES:
' None
_(If Applicable) DISSENTING OPINION
- RESOLUTION: Ncne
~(If Applicable)
' TESTED BY_. n/a REVIEWED BY : ~ n/a:
TEST' ACCEPTED BY~: n/a- ..I{ o
- L'
[- D-213 L _. ~ ._ , _. _ -- _
-. -- .._.-- - -.. .~ ~. - ... _ . . .-- . - . - . . ~
.~3 5 APPENDIXTD
- v i jtg.
PERFORMANCE TEST I.BSTRACTS u; PERFORMANCE TEST: NUMBER NTI-650.07
- PERFORMANCE TEST- TITLE : XENON OSCILLATION TEST-INITIAL CONDITIONSit- n/a '-i TEST--SYNOPSIS : The test has not been written.
DATA COLLECTION :~ Control Board indications and SPVS data.
- colJ ection program
-TRANSIENT INITIATOR 1 none
. TERMINATION CRITERIA : none '
EVALUATION RESULTS The test has not been performed. EVALUATION ~ CRITERIA None PLANT DATA REFERENCES None (If Applicable). . DISSENTING-OPINION ~
. RESOLUTION - None (If Applicable)-
TESTE.D BY- n/a
- REVIEWED BY :- n/a-TEST ACCEPTED BY : n/a 0
.. l a
D-214 j; 1..., - . . - . . .....: . . - . . .. : . .. - :. . - . . . . - - . - . _ . . - . . - . . . - . = . . . -
APPENDIX D PERFORMANCP. TEST ABSTRACTS PERFORMANCE TEST NUMBER : IITI- 6 5 0. 08 PERFORMANCE TEST TITLE : DECAY HEAT TSST INITIAL CONDITIONS : 100% power, BOC, MOC, and ECC TEST SYNOPSIS : From 100% power for each time in core life, trip the reactor. Perform a secondary calorimetric to determine the decay heat. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR : Manual trip TERMINATION CRITERIA : none EVALUATION RESULTS : The test has not been performed. EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None O (If Applicable) V DISSENTING OPINION RESOLUTION: None (If Applicable) TESTED BY : n/a REVIEWED BY : n/a TEST ACCEPTED BY : n/a
APPENDIX D f)) ( PERFORMANCE TEST ABSTRACTS PERFORMANCE TEST NUMBER : NTI-650,09 PERFORMANCE TEST TITLE : FLUX COUPLING TO NI TEST INITIAL CONDITIONS : n/a TEST SYNOPSIS : The test has not been written. DATA COLLECTION : Control Board indications and SPVS data collection program TRANSIENT INITIATOR n/a TERMINATION CRITERIA n/a EVALUATION RESULTS : The test has not been performed. EVALUATION CRITERIA : None PLANT DATA
REFERENCES:
None
-(If Applicable)
DISSENTING OPINION ['s /
) RESOLUTION:
(If Applicable) None TESTED BY : n/a REVIEWED BY : n/a TEET ACCEPTED BY : n/a I l (g D-216 l l l 1,
A 0 MPENDIX E CERTIFICATION DISCREPANCIES AND SCllEDULE OF RESOLUTION O : O O ,
--i------ - - _ . _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ ,
l l APPENDIX E (y SECTION A (' ') CERTIFICATION DISCREPANCIES AND SCHEDULE OF RESOLUTION The following listing contains the cur ' open problem reports and simulator change packages ident&1ted during the simulator performance test period. These problem reports have been compared with all present open reports to identify and close outdated items. Problem reports written prior to January 1990 are included in this appendix only if directly related to simulator certification via an ANSI requirement. NOTE: Problem reports without scheduled completion dates do not necessarily relate to ANSI 3.5 requirements and will be scheduled for completion at a later date. NOTE: This addendum relates the assori: Led problem report to only one applicable ANSI .t.5 Ohecklist requirement. A problem report may be , elated to more than one requirement. NOTE: Problem reports with the priorities of B1 and B2 are enhancements and although related to an ANSI requirement, [] (,/ training quality is not affected and no completion date is scheduled. PROBLEM DESCRIPTION PRI SCHEDULE ANSI REPORT # DATE HEQ B 890155 Incorporate core data changes A2 5-17-91 5.3 A to CPC/CEAC model B 900004 Turbine Seal 011 A2 temperatures are too low B 900005 Condensate Storage Pool B1 makeup level control valve does not close at proper setpoint B 900007 Auxiliary Component Cooling B1 Water wet tower has improper evaporation rate B 900008 CP-13 lockout relay white B1 light - improper logic A
) E-1
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APPENDIX E fNg. ;B3 PORT #: DESCRIPTION EB1 SCHED ANS 3.5
- L7f '
D 900009 Feed pump-speed response B1 sluggish
.B:900014 Feedwater level control A2 '
temperature compensation program needs reinstallation & B.9000018 Generic Problem Report B1- , for switch-check items LBT900030 ' Incorrect feelwaterd 81
; temperature. response B:900034-' Shutdown Cooling boron A2 5-17-91 A3'.2 ,
. -response incorrect B 900036 . Shutdown Cooling heat .A2 exchanger temperature response; incorrect.
'B 900039' -Anrunciator D-M08~does not A2
- loc k -in -
B 900040 Heating-and-Ventilation. A2 ( response improper during
\
Shutdown Cooling operation B 900043 Air Handling Unit 12. B1 differential pressure improper B 900046 HydrogenLAnalyzer. improper B1 operation B1900047 .BD.303' Radiation Monitor B1 - 1
;1mproper. operation
;B-900049 : Improper Feed Pump speed B1
. indication following trip-1B5900055 ENI Start Upl recorder stays A2 energized on loss of Electrical Bus B 900056 Radiation Monitor pens on A2-
.CP-14.do not fail.to zero
}f -
E-2 I l -.
f 2-{- i < APPENDIX.E
,j q REPORT # DESCRIP_TlOff RAI. SCHED ANS-3.5-9%MI LBE900059_ Malfunctionidisplay-for_ B1 CR02 through~CR04 do not
- appear ' on Instructor -Station ' i
! tableau- ,
'B 900060: -Reactor Coolant-System Al- 8-30-91 A3.2 pressureispike while solid' B 900061.-Reactor Coolant System does A2- l not respond ~c.orrectly to lossLof heat sink, post trip B 900062 : Polisher' remote: functions B1 A3.2 e 1 are inadequate B 900063 . Charging and Letdown annun- B1- A3.2
'clator G-M04 alarms spurious]y- - t
,B 900064 ~ Plant _ Stack Radiatnan Mon. A2 6-28 A3.2 7
. alarms: spuriously 1during_
eShutdown-- i
;B:;900065' HighiStartLUp Rate.alarmax A2 6-28-91 A3.2-
, o(~') during. power _-reduction .
-B=900066 Shutdown. Cooling boron B1 A3.2 response _ improper-~
(Repeat'of B900034)
~
-B 900067 _ rressurizer; spray line.
B1; A3.2' temperature" dropping '
- B 1 9 0 0 0' 6 8' Post trip Reactor Coolant---
. A2 '8-30 '
A3.2
- 1 System cooldownoresponse !
B 900069?: Volume Control Tank vent' A2 6-28-91. -A3.2 % does not raduce tank press. , properly _ ?
~
Bi900072: Turbine DEH valve position - A2 L6-28-91 A3.2 runbacki on trip not working
' B;: 90007 3' Synchroscope. runs backwards B1 A3.2
- in_autosynch
'TB 900074- Plant monitoring; computer- B1 -
point change-u E-3 r t-i eIw'.- . - ~- r r- ,-.wwie,- +-v--- v-- ew,y-4t,- e,e---*-- + - * ,,%. + y+ 3 w
m.. . . ._ _. _ . _ . _ _ . _ . .. . ._ APPENDIX E REPORT # DESCRIPTION EEI. SCHED .ANS 3.5
}r~
CV> - Bi 900075 Low Steam Generator level A2 (Plant-Protection System surveillance): delay - B 900076 Setpoint-reset values'for A2
, trips and pretrips deviating B 900077 -High Steam Generator level A2 '
(Plant Protection System surveillance), Digital' volt meter indication B'900078 Improper containment Spray A2 flow following Loss-Of
-Coolant-Accident or-Main Steam Line Break B-900079+: Containment Loss of Coclant. A1 8-30-91 B2.2(8)
. Accident: containment-response 3.1.2(8)
. questionable. . 13.1.2(20). 1 (follow upfto.PR B 900078)
-B 900b801 lCCW pump amps go up with no RB1 3.1.2(8)
,_ change in stator temperature. '
k B1900081' Temperature change affects A2
'ECCW surge tank' level too greatly' B:900082 ACCW. wet tower flow with A2 5-17-91 3.1.2(8)
-pump = stopped BL900083 Reactor. Coolant, Pump stator B1 3.1.2(8)
; temperature response questionable- -
BL900084- Affected Steam Generator A1 5-17 3.1.2(9): Feed-Pump turbine goes to
- 3900; rpm post over-speed trip-B:900085i Plant' Monitoring Computer A2
; point change
.B 900086 Suspect Plant Monitoring B1 3.1.2(9) m
' Computer point, Emergency
-Feedwater discharge pressure
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m . __ __ _ . .. -. _ . _ _ _ _ _ _ _ . . . _ _ APPENDIX E
~A REPORT # DESCRIPTION PIsl SCHED -ANS 3.5-ij~
i B 900087 -Rupture of Emergency Feed- A1 5-17-91 3.1.2(9)- , water Pump suction line had no effect on~other pumps B-900088 Steam Generator WR level A2 5-17-91 3.1.2(9) oscillation-(same-problem 1 as B 900108) . B 900089 EFW 223A & EFW 224A control A2 5-17-91 3.1.2(9)- improper operation B 900090 Turbine Seal 011 pump does _B1 not auto start
' B 900091 Affected Condenser vacuum B1 should-be different from unaffected Condenser (Malfunction FW21A, b,-or C)
- B 900092 Vacuum hogging mode maintains A2= 5-27-91 3.1.2(5) 25" with 100% in-leakage B 900094: CCW flow response 1through B1 3.1.2(8)
',c response.through containment !y) ' fan coolers questionable -
B 900095 CD.173 can't be opened with Bll 3.1. 2 ( . -) hand switch-
' B'900097 Control-Element Drive-Mech- B1 3.1.2(8) anism temperature response to loss of-CCW questionable B 9000981 Reactor _ Coolant Pump _CCW- A2 17 3.1.2(8) low pressure alarm didn't
function
- B 900099 CCW discharge-: header flow- A2 5-17-91 3.1.2(8) and; pressure _ response not' correct to CCW'line break-B:900100 Containment--Sump temperature B2 3.1.2(8) response-incorrect-for CCW-leak B 9001011 ContainmentLFan Cooler drain A2 6-28-91 3.1.2(8)
-flow not' indicating-or Plant.
Monitoring Computer I f'% !j E-5 y L i
-i
, APPENDIX E
#r st 3 REPORT'# DESCRIPTION EB1 SCHED ANS 3.5- '
*N'll :
B 900102 Lack'of malfunctions to B2 ' simulate off-site' load fault
'B 900103 Reactor _ Coolant Pump 2A amps B1 3.1.2(4) oscillate with sheared shaft ,
Bl900104_ Reactor Coolant Pump Stator B1 3.1.2(4) temperatures do not rise with
' sheared shaft B 900105 Safety: valve position ind- A1 8-30-91 3.1.2(1) ication cycled during latter ,
stages.of valve fail open ,- malfunction
' B 900106 Core Protection Calculator A2 6-28-91 3.1.2(22) sensor failure light did not actuate B 900107 Improper Turbine Control A2-with #4 Governor valve '
failed: closed-B:900108 Steam Generator level, below A2 5-17-91 3.1.2(9)
' (_l_ _60% WR, response improper t N_/L (same-problem as B 900088)--
BL900109_-ACCW-pump would not exhibit B1 3.1.2(8) suction pressure cavitation B 900111 MCC 3B33 didn't.deenergize B1 3.1-.2(3) on loss of. bus 3B2 B 900112 Plant Monitoring Computer A2 6-28-91 3.1.2(3) points A-59504 and~A-59507 '
- are not reading correctly B 900113: PurificationLinlet pressure B1 3.1.2(1)
Plant-Monitoring Computer point.-(A39204) responded-incorrectly during Letdown-line break t i B 900114 Pk) response of Letdown Flow. A2 8-30-91 3.1.2(1) or Back Pressure controllers-with 100% break
, B 900115- 3" line break has less B1 effect than 2" break E-6
M E_ED DT X %
, REPORT # DESCRIPTIOB ERI SCHED ANS 3.5
)
B 900116 "15 %" light on CP-10 did B1 3.1.2(21) not light-B 900117 Plant Moa.itoring Computer A2 6-28-91 3.1.2(12) digital points D-34312, 33912, 34212 and 34042 did not change B 900119 Turbine controls did not A2 5-17-91 3.1.2(22) respond as specified by test B 900120 Turbine Seal Oil Backup pump A2 5-17-91 3.1.2(22) indicates "on" continuously for D58206 B 900121 Generator Air Side Seal Oil B1 3.1.2(22) heat exchanger temperature response incorrect B 900122 Malfunction RXO7A doesn't A1 5-17-91 3.1.2(18) fail controller B_900123 Malfunction RXO8A doesn't A1 5-17-91 3.1.2(18)
-. fal1~ controller x-) B 900124 Turbine Cooling Water system A1 6-28-91 3.1.2(6) needs flow and temperature balancing (see B 900156)
B 900126 Annunciators G0110 and A2 G0210 illuminated without malfunction active B 900127 Rods stop at upper electrical A2 5-17-91 3.1.2(12) limit vice mechanical stop B 900128 -Malfunction RDOE does not A2 5-17-91 3.1.2(12) affect Control Element Assembly operation until in manual group or auto-sequential B 900129 Containment Spray system A2 6-28-91 3.1.2(12) failed to actuate as per test B 900130- Improper Reactor Coolant A2 8-30-91 3.1.2(9) System alarm indication during test ,3, v) E-7 a
1
+
APPENDIX E fr s REPORT 4 DESCRIPTION ERI; SCHED ANS 3.5
.I B 900132- LCP 43 Controller Scale A2 change.
B'900133- Engineered Safety'_ Feature A2 6-28-91 3.1.2(23) - bistable-trip logic wrong
-(CP10) .
B-9001341 "RPS chan. Trouble" A2- 6-28-91 3.1.2(23)- Ann logic incorrect i B 900135: Emergency Fee'd Actuation - A2 ' 6-28-91 3.1.2(23) System' actuation-status lights-on CP10' logic incorrect B-900136- Improper-response to A2- 8-30-91 3.1.2(21) : malfunction NIO7 ' B 900137- Incorrect-indication for
.A2 6-28-90. 3.1.2(22)-
malfunction RC19D on-Plant ;
-Monitoring Computer- .c B.900138: Improper responsetto Low A2 '8-30-91 3.1.2(22)
Pressure; Safety Injection-pump B cavitation BL900139: Malfunction RP05 C06'and D66 A2 6-28-91 3.1.2(23)
-didinot work B 900140- Generator-Hydrogen seal oil A2L S-17-91 3.1.2(22) 4 differential pressure does not' respond as per-:-test' EB 900141; Incorrect Charging Pump; A2 UNID labe1J
-B 900142~-Generator Hydrogen? seal- EA2 28-91 3.1.2(22) ~
^
cooler temperatures do not respond!as per test B 900143 Improper radiation response A2 8-30-91 3.1.2(14) to malfunction CRO1-B 900144_ Containment i pressure response A1 8-30-91. 3.1.2(20)
-is--incorrect-tot malfunctien- -
, FW E-8
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i APPENDIX E (~N _ REPORT # DESCRIPTION EBI, ECI(Ep ANS 3.5 B 900145 No Amperage spike on Cire. A2 6-28-91 3.1.2(5) Water Pump A using malfunction CWO1 B 900146 Improper Pressurizer pres- A2 8-30-91 3.1.2(1) sure response to stuck open Safety Valve B 900147 Plant Monitoring Computer A2 6-28-91 3.1.2(22) point A-55105, did not change state for malfunction MS22 B 900148 Annunciator crywelf, A-G04 A2
& A-H04 do not respond.
B 900149 Boration Dilution Monitor A2 6-28-91 3.2(2) scalos incorrect B 900150 Qualified Safety Parameter A2 6-28-91 B2.2(8) Display System display improperly indicates CIAS when present
,_s B 900151 Turbine DEH valve test A2 6-28-91 3.2(2) buttons mislabeled J
B 900152 Condensate Storage Pool A2 6-28-91 3.1.2(9) level did not stabilize as per test B 900153 Malfunction EG03, load A1 8-30-91 3.1.2(18)- rejection, did not function as per test B 900154 Instrument air response to A1 8-30-91 3.1.2(2) SA-125 closure improper B 900155 Improper temperature A1 6-28-91 3.1.2(6) responst to Turbine Cooling Water pump trip B 900156 Turbine Cooling Water did A1 6-28-91 3.1.2(6) not respond as per test (see 3 900124) B 900157 Incorrect response of BAM- A1 141 to loss of 3B3-S (9 x_/ E-9 l l
APPENDIX E r-~g REPORT # DESCRIPTION ERI SCHED ANS 3.5 =ig B 900158 Malfunction FW38B, affected A1 0-30-91 3.1.2(22) Steam Generator pressure was abnormally low B 900159 Improper power response as Al per test NT1640.04 D 900160 Tripped Main Feed Water pump A1 6-28-91 3.1.2(22) discharge pressure too high B 900161 Wrong trip setpoint, Part A1 6-28-91 3.1.2(12) Length Control Element Assembly insertion B 900162 Improper Emergency Feedwater A1 8-30-91 3.1.2(9) flow response B 900163 Start Up channel High Voltage B1 3.1.2(21) low light (CP-12) did not light as per test SCP 121 Remove time delay from Start / A2 6-28-91 5.3 A Up Transformer to Auxiliary Transformer, add synchrocheck
- (~
's .
relay SCP 156 Allow auto / man control of A2 6-28-91 5.3 A
.SG flow after priority override SCP 232- QSPDS data base software A2 5-17-91 5.3 A revision SCP 257 Addition of liquid waste A2 5-17-91 5.3 A tank C SCP 480 Deluge system for charcoal A2 5-17-91 5.3 A filters SCP 517 Excore Channel addition A2 5-17-91 5.3 A to LCP-43 for App. R SCP 690 Rx Reg. input range change A2 5-17-91 5.3 A SCP 804 Add new-Demin. Water Tank A2 5-17-91 5.3 A alt. to CST SCP 1328 Gaseous Waste Management A2 5-17-91 5.3 A Radiation Monitor replacement
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1 APPENDIX.E y- g REPORT # DESCRIPTION ERI SCHEQ ANS 3.5-
\ hCP1654 Replace RCP+ seal cartridge A2 8-30-91 5.3 A with'new-design seal B 910036 l1A and-SA compressors do not A1 6-28-91 3.1.2(6) trip on11oss of TCW.
B 910037 RCP sheared shaft reverse A2 8-30-91 3.1.2(4)
. flow-and amperage. response .;
B 910038 -Sheared shaft. hot leg temp.-
' ~
A2_ 8-30-91 3.1.2(4) response. B 910039L RCS' temperature and pressure A1_ 8-30-91 -_3.1.2(20)_ > response following: a -100% MSLB.is questionable : B-.910040- . slow RCS depressurization A2 8-30-91 - B2.2.(10)_ saturation pressure: response B 910041: .MSIS signal _ delay time after- B2 3.1.2(20)
-a 100% MSLB-outside entmt B 910042- MS: flow n spike _ af ter 10% MSLB- A2 8-30 3.1.2(20) outside entmt-i
. ()\-
\_ Bf910043: ;10%-MSLBJinside entmt; S/G- A1 8-30-91 3.1.2(20)
-flow and; pressure-response
~
'B 910044 S/G Rad. activity _after a- :A1 .8-30-91 3.1.2(1) tube--leak -
Bl910045 : Response to:the magnitude A11 8-30-91 3.1'2(1)
.of a S/G1 tube leak-
, 'Bc910046 . Charging pump;1abel changes B2' >
.B1910047: 1Malf.iTC01 did not respond '
~
A1 6-28-91' ' 3.3.2(6).
-properly.
B 910049 Malf. RC 16 S-FF, invalid
. Al B:910050 CEA ejection-pressure resp. Al ~8-30-91: 3.1.2(12) !
isntoo= fast and-goes'too-far .4
-BJ910051 'CEAs move:in MS with'malf. ' All 5 27-91 3.1.2(13)
RD03 actuated'
'BL910052 RCS.LOCA response Ques- Al- 8-30-91 B2.2(8) tionable
'E-11
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4
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I P e APPENDIX E 4 f'r x REPORT # DESCRIPTION EB1 SCHED ANS'3.5- t 1 -- B: 910053- Wrongc units-on letdown. B2- t back pressure regulator B 910054' PMC cntmt ambient temp. A1 8-30-91 3.1.2(8) indicates-0
' B'910055 . Transfer panels do not A2 .
--match plant photo survey B 910056- Instrument-UNIDs missing B2 A3.2 l B>910057 CP-2 Train 2-tags missing B2 B 910058 Excessive loss of mass .A2 6-28-91 A3.2 .,
from condenserLhotwell ; during normal operation ! 3 O 4 u
~
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AP.PENDIX_E , j-(; REPORT # EESCRIPTION EB1 SCHEQ -ANS 3.5 . , A ll ' N/ SECTION'B PERFORMANCE TESTS AND CQMPLETION SCHEDULE-The ' following performance tests have been identified as i needing.to be performed. Criterja for tests to-be in this section ares ,
.o The test was judged unsatisfactory or not completed due to a severe problem, o The test has insuf ficient or incorrect data and therefore ,
requires revi,sion. o 'The test has only rocently been identified as part of the , certification program.
-NTI -
TITLE SCHEDULED . NUMBER , 6 04 ~. 0 3 Simultaneous Closure of All MSIVs 6-28-91 604'.06. Main Turbine Trip- 6-28-91 604'08. Max Break LOCA with Loss of Offsitt Power 8-30-91
- 604.11 Reactor Trip Followed by Recovery to Rated 6-28-91
. Power 610.09 Loss of CCW to-Containment Fan' Cooler 6-28-91 610.19 ACCW-Pump Discharge Header Rupture 6-28-91 616.10 -Loss of 208/120 volt-Bus (es)- 6-28-91
- 617.03' Main Generator Load Rejection 8-30-91 617.19 -Hydrogen _ Air' Side Seal Oil Pump 1 Trip 6-28-91 619.07 ' Emergency Foodwater Pumps-Auto Start-Failure 6-28-91
~
619.'12 Feedwater Pump Turbine High Vibration 6-28-91. 619.21. Condenser Air In Leakage 6-28 619.29' Emergency Feedwater Pipe Leak 6-28 621.03 Rupture-Air' Supply *to Steam Bypass Valves 6-28-91 622.04 : Steam Bypass Valve Leakage 6-28-91 623.05 .Startup Nuclear Instrument Channel Failure 6-28-91 o e-13
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APPENDIX E r , pL , REPORT.# DESCRIPTION - P_Ep SCHED ANS 3.5 623.07 Startup Nuclear Instrument Channel Fails to 6-28-91 De-energire 624;01 Loss of PMC Primary Computer Complex- - 6-28 626.12 - Code Safety Relief Valve Leaks 8-30-91 626.16- ; Reactor Coolant Pump Speed Transmitter Falls 6-28 -626.17 Safety Injection System Pressure Interlock 6-28-91 Failure 626.22 Pressurizer CPC Safety Pressure Transmitter. 6-28-91 Falls Hi/Lo 626.23 RCS_ Cold Leg. Pipe Rupture 8-30-91 626.24 RCS:, Hot-Leg Pipe Rupture 8-30-91 4 U 626.25L RCS Leak into Containment 8-30-91 62703 CEAs! Fall to Move in Manual Group 6-28-91' >
;627.05 - Cea Ejection 8-30-91L E(
6 2 7 .13 -~ - CEA Drift (10%) 6-28-91 "
;630.07 Pressurizer Pressure: Controller Fails'Off 6-28 #
i630.08 - Pressurizer Level-Controller Fails-Off 6-28-91 630.14 Pressurizer Pressure Controller 100X/Y Fails 6-28-91 633.01- Turbine Load Demand ~ Controller Fails- ' 6-28-91 634.05 Loss of: TCCW to Hydrogen Coolers! 6-28-91' 634.06 Loss of TCCW to IA/SA Compressors- 6-28-91 (635.06 Turbine Trip 6-28-91 645.024= Reactor Coolant' System WateryInventory 6-28-91
, _ Balance:
- 645.068 Emergency Diesel Generator Operability 6-28-91 Verification 645.090 Shutdown Margin 6-28-91 l
O E-14
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APPENDIX E ('] REP 6dT # DESCRIPTION EB1 SCHED ANS 3.5.
' ~ '
645.101 Startup Channel Functional Test Startup 6-28-91 Channel 1 and 2 645.102 Safety Channel Nuclear Instri.montatiri 6-28-91 Functional Test 645.107 Plant Protection System Channel Functional 6-28-91 Test 647.010 Reactor Trip,on Turbine Trip Channel 6-28-91 Functional Test 647.017 Anticipated Transient System Check 6-28-91 650.05 Power Defect Test 6-28-91 650.06 Xenon Wortin Test 6-28-91 650.07 Xenon Oscillat.'on Test 6-28-91 650.08 Decay Heat Test 6-28-91 650.09 Flux Coupling to Nuclear Instrumentation 6-28-91 LY
-( , E-15 v
-a- 'a-F AAs4 M't* i* E--+" +- *' -e'A-A'- ^ '4--" O '4'Md-"++444 + "- %44*'+ **'-sM4-MM+4A-Em-O4hAhed<W-2 4+4+'-'--48-* **#+ #** 4ha4a*aG P4 Id' A n 3- eA 44-4 4A 4c'm AJ4@Ms-- M4-=i=-
s APPENDIX F ANNUAL TESTING SCHEDULE
.4 e
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s APPENDIX F c _p y ) FIRST YEAR TEST LIST
- PERFORMANCE PERFORMANCE TEST CERT. ANS-3.5 MALF TEST NUMBER -DESCP.IPTION REQ'D REF. USED NTI-602 NORMAL OPERATION TEST YES A3.2 NTI-603.01 45% ACCURACY TEST YES B2.1 NTI-603.02 80% ACCURACY TEST YES B2.1 NTI-603.03= 100% ACCURACY TEST YES B2.1 NTI-603.04 100% STABILITY TEST YES B2.1 NTI-604.01 MANUAL REACTOR TRIP YES B2.2(1)
NTI-604.02 SIM. TRIP OF ALL FDW PUMPS YES B2.2(2) NTI-604.J3 SIM. CLOSURE OF ALL MSIVs YES B2.2(3) NTI-604.04- SIM. TRIP OF ALL RCPs YES B2.2(4) j,_.s NTI-604.05- TRIP ANY RCP YES B2.2(5)
)
s' NTI-604.06 MAIN TURBINE TRIP YES B2.2(6) NTI-604.07 MAX RATE POWER RAMP YES B2.2(7) NTI-604.08 MAX LOCA WITH LOP YES B2.2(8) NTI-604.09 MAX UNISOLABLE MS LEAK YES B2.2(9) NTI-604.10 SLOW RCS DEPRESS W/NO HPSI. YES B2.2(10) NTI-604.11 REACTOR TRIP FOLLOWED BY YES 3.1.1(4) RECOVERY TO RATED POWER NTI-610.01 CCW PUMP (S) TRIP YES 3.1.2(8) CC01 NTI-610.06 RCP SEAL CLR OTLT VLV FAILS YES 3.1.2(8) CC06 NTI-610.10 LOSS OF CCW TO SDC HX YES 3.1.2(7) CC10 NTI-610.17 RUPTURE OF CCW PMP DISC PIPE YES 3.1. 2 ( 8 )- CC17 NTI-612.01 REACTOR FUEL CLADDING FAILS YES 3.1.2(14) CR01
- NTI-614.01 CHARGING P ?TP YES 3.1.2(18) CV01
( F- 1 i
).
l g -APPENDIX F PERFORMANCE -PERFORMANCE-TEST CERT. ~ ANS-3.5 MALF 3- 1 TEST NUMELR DESCRIPTION- REQ'D REF.- USED NTI-614.06 LTDN HX TCV FAILS SHUT YES 3.1.2(18) CV06 l
~NTI-615.01 CW: PUMP TRIP YES 3.1.2(5) CWO1- y NTI-616.01 FDR BRKR TRIP IN SWITCHYARD YES 3.1.2(3); ED01 j
NTI-616.06 LOSS OF 480VAC BUS (ES) YES 3.1.2(3) ED06- 1 NTI-617.03 JUGtN GEN LOAD REJECTION YES 3.1.2(16) EG03-LNTI-617.08 FAILURE OF DG TO-AUTOSTART YES '3.1.2(3) EG08 NTI-617.18 H2 SEAL OIL PMP TRIP (H2) YES 3.1.2(22) EG18 NTI-619.01 CONDENSATE PUMP TRIP YES 3.1.2(9) - FW01' NTI-619.08 . LOSS OF AUX FDW PUMP YES 3.1.2(9) FWO8 NTI-619.19 FDW HTR BYPASS- VLV: FAILURE YES 3.1.2(9) FW19 NTI-619.'30 EMER FDW PMP SUCT HDR LEAK YES 3.1.2(9)- .FW30
-SA/IA CROSSOVER VLV FAILS YES- 3.1.2(2): IA01'
, i[J~T1 I :NTI-621.01 NTI-622.04 4 STEAM-BYPASS VLV LEAKAGE YES -3.1.2(17) MSO4-NTI-622.11 'MSILIFE BREAK INSIDE CNTMT YES 3.1.2(20) MS11 NTI-623.01- LSAFETY INSTRMNT CH FAILURE YES 3.1.2(21);NIO1-
~
NfI-625.01 CPC CHANNEL (S) FAIL YES 3.1.2(11) PWO1. t NTI-626.01, . LOSS OF ALL=RCPS YES' -_3.1.2(4). RC01-NTI-626.08 RCP. LOWER SEAL FAILURE EYES 3.1.2(4) :RC08-xNTI-626.14- PZR SPRAY VALVE-FAILURE YES. 3.1.2(18)1RC14. 3 NTI-626.18- RCS COLD LEG CNTRL TT FAILS YES 3.1.2(22) RC18 NTI-626.22 PZR CPC SFTY PT-FAILS HI/LO YES 3.1.2(22) RC22, NTI-626.27 PZRsINSTRMNT LINE BREAK YES . 3.1. 2 ( 1 ) . RC27 NTI-627.01 -CEDM M3-SET' FAILURE YES 3.1.2(12);RD01 1NTI-627.05 ROD EJECTION YES 3.1.2(12) RDOS F-2
APPENDIX F P/.RFORMANCE PERFORMANCE TEST CERT. ANS-3.5 MALF TEST NUMBER DESCRIPTION REQ'D REF. USED MTI-627.10 CEAS MOVE OUT WHEN INWARD YES 3.1.2(12) RD10 MOVEMENT REQUIRED IN AUTO NTI-627.14 FAILURE OF CNTRL/SD BA!!KS TO YES 3.1.2(12) RD14 TRIP NTI-629.02 RPS AUTO TRIP FAILURE YES 3.1.2(24) RP02 NTI-629.06 RPS MATRIX' RELAY FAILURE YES 3.1.2(17) RP06 NTI-630.01 SBC QUICK OPEN SIG FAILS YES 3.1.2(17) RX01 NTI-630.08 PZR LEVEL CNTRLR FAILS OFF YES 3.1.2(18) RX08 NTI-630.14 PZR PRESS CNTRI 100X/Y FAILS YES 3.1.2(18) RX14 NTI-631.01 S/G TUBE LEAK YES 3.1.2(1) SG01 NTI-632.01 SI PUMP TRIP YES 3.1.2(22) SIO1 NTI-634.01 TCCW PUMP TRIP YES 3.1.2(6) TP01 O F-3
7[ ., APPENDIX-F f SECOND YEAR, TEST LIST s/
! PERFORMANCE- PERFORMANCE TEST CERT. ANS-3.5 MALF TEST NUMBER DESCRIPTION. . REQ'D REF. USED NTI-602- NORMAL OPERATION TEST YES A3.2 NTI-603l01 45% ACCURACY TEST- YES B2.1
.NTI-603.02 80% ACCURACY TEST YES B2.1
*' NTI-603.032 100%' ACCURACY TEST --YES B2.1=
c NTI-603.04- 100% STABILITY TEST YES B2-.1 NTI-604.01 MANUAL' REACTOR TRIP YES B2.2(1)'- iNTI-604LO2. SIM. TRIP-OF ALL FDW PUMPS YES B2.2(2) lNTI-604.03 .SIM. CLOSURE OF-ALL MSIVs- YES B2.2(3)- L , NTI-604.04; : SIM.: TRIP OF ALL-RCPs: YES B2.2(4)
+ .
j_ NTI-604.05 TRIP ANY RCP YES 'B2.2(5) ENTI-604.06 . MAIN TURBINE TRIP YES. B2.2(6)' -
<NTI-604.07 MAX RATE POWER RAMP YES B2.2(7)
NTI-604.08 MAX LOCA'WITH' LOP YES B2.2(8) LNTI-604009 -MAX-UNISOLABLE'MS LEAK.- YES B2.2(9) 1NTI'-604.10i SLOW RCS' DEPRESS W/NO'HPSI YES 82.2(10) NTI-604.11 REACTOR-TRIP FOLLOWED BY. YES- .3.1.1 ( 4 ) - ,, RECOVERYLTO RATED = POWER 1hTI-610.02 ACCW' PUMP TRIP YES 3.1.2(8) CCO2
'NTI-610.07= LOSS OF COW TO CEDM CLRS YES- 3.1.2(8) CC07:
NTI-610.12- CCW' SURGE TNK LVL SIG FAILS: .YES '3.1.2(8) CC12 NTI-610.~18 CCWJTUBELLEAK IN CNTMT-FAN YESL 3.1.2(6) CC18 COOLERS
, lNTI-613.01 CNTMT SPRAY PUMP (S) FAIL TO ~YES 3.1.2(23) CS01 AUTOSTART
. . _ - - ~ - .-. . - _ . . . .
-APPENDIX F j PERFORMANCE: . PERFORMANCE TEST CERT. ANS-3.5 MALF.
-: TEST NUMBER- DESCRIPTION REQ'D TREF.- USED -l
-NTI-614,02 - CHRG PUMPS FAIL 70 AUTOSTART YES 3.1.2(18) CV02 1 NTI-614.14 CVCS LTDN LEAK--IN CNTMT YES- 3.1.2(1). CV14 o NTI-616.02 LOSS OF MAJOR STATION XFMR YES 3.1.2(3) ED02 TNTIi616.07- LOSS OF 125VDC BUS (ES) YES '3.1.2(3) ED07 NTI-617.04 MAIN GEN O TPUT BKR FAILS TO YES 3.1.2(22) EG04
-OPEN ON-AUTOTRIP NTI-617.09 FAILURE-OF DG TO LOAL YES 3.1.2(3) EG09
- NTI-617 ;.19 H2 SEAL OIL PMP-TRIP (AIR) .YES 3.1.2(22) EG19 NTI-619.03 FEEDWATER PUMP OVERSPD TRIP 1YES 3.1.2(9) FWO?-
NTI -619.10 ; -CONDENSER VACUUM PUMP TRIP YES 3.1.2(5) :FW10 NTI-6i9.20- SU FDW REG VLV FAILURE YES 3.1.2(9) FW20 -- NTI-619.J6L FDW PIPE BREAK OUTSIDE CNTMT- YES 3.1.2(20) FW36 ( NTI-621.02. IA ISOL VLV FAILS TO :YES 3.1.2(2) IA02 CLOSE ON CIAS
.NTI-621.05 IA:CMPRSR DISCH LINE RUPTURE LYES. 3.1. 2 ( 2 )-- IA05
'NTI-622;05 ATMOS.STM DUMP VLV FAILS: YES. 3.1.2(17) MS05 J NTI- 6 2 2 .~ 12 - MS:LINE BREAK OUTSIDE CNTMT, YES 3.1.2(20)~MS12~
AFTER'MSIV NTI-623.03 CNTRL CH INSTRMNT FAILURE- YES 3.1.2(21) NIO3 NTI-625.02- RX--PWR CB FAILS TO DROP CEAS YES' 3.1.2(11) PWO2-LNTI-626.03- -RCP-SHAPT' SEIZURE- YES 3.1.2(4) RC03 NTI-626.09 RCP; MIDDLE SEAL-FAILURE ~YES 3.1.2(4)- RC09 NTI-626.15- .PZR CNTRL LT FAILS HI/LO YES 3.1.2(18) RC15' NTI-626.19 RCS~ COLD LEG SFTY TT FAILS YES 3.1.2(22) RC19
'NTI-626.23 -RCS COLD LEG PIPE RUPTURE YES 3.1.2(l') RC23
_ .\ F-5
a APPENDIX F' IPERFORMANCE PERFORMANCE TEST- CERT. ANS-3.5 MALF
- TEST NUMBER DESCRIPTION REQ'D .REF. USED ,
LNTI-627.02 DROPPED CEA YES 3.1.2(12) RD02 2NTI-627.06- CEA GRP UNCNTP.LD INSERTION YES 3.1.2(12) RD06 s JfT1 627.11 ' CEAS MECHANICALLY STUCK YES 3.1.2(12) RD11 ll HTI-627.21 CEA UPR ELEC LIMIT FAILURE YES 3.1.2(12) RD21 NT4 6. -. 03- RX TRIP-WITH NO AUTO TURBINE. YES 3.1.2(19). RP03 . TRIP NTI-629.07- RPS BISTABLE-RELAY FAILURE -YES 3.1.2(17) RP07-NTI-630,04 MFV FLOW CNTRL'VLV FAILURE YES 3.1.2(9): RX04 NTI-630.09? S/G LEVEL CNTRL FAILURE YES 3.1. 2 ( 2 2 ) .- RXO 9
.NTI-631.04: MS LINE--PRESS XMTR FAILS YES- 3.1.2(22) SG04-NTIf632.04 AIR BINDING IN SI SYSTEM. YES 3.1.2(7) lSIO4_
, , sNTI-633.01' -TURBINE-LOAD CNTRL DMD-FAILG YES 3.1.2(17);TC01
\
NTI-634.04 :TCCW HX A OUTLET,HDR~ LEAK- _ YES 3.1.2(6) TPO4 t 4 k 1 e M h w q y - , ,. . , . - -- w a , , ,
APPENDIX F
,,~ .
() THIRD YEAR TEST LIST PERFORMANCE PERFORMANCE TEST CERT. ANS-3.5 MALF TEST NUMBER DESCRIPTION REQ'D REF. USED NTI-602 NORMAL OPERATION TEST YES A3.2 NTI-603.01 45% ACCURACY TEST YES B2.1 NTI-603.02 80% ACCURACY TEST YES B2.1 NTI-603.03 100% ACCURACY TEST YES B2.1
.NTI-603.04 100% STABILITY TEST YES B2.1 NTI-604.01 MANUAL REACTOR TRIP YES B2.2(1)
NTI-604.02 SIM. TRIP OF ALL FDW PUMPS YES B2.2(2) NTI-604.03 SIM. CLOSURE OF ALL MSIVs YES B2.2(3) NTI-604.04 SIM TRIP OF ALL RCPs YES B2.2(4) NTI-604.05 TRIP ANY RCP YES 42.2(5) NTI-604.06 MAIN TURBINE TRIP YES B2.2(6) NTI-604.07 MAX RATE POWER RAMP YES B2.2(7) NTI-604.08 MAX LOCA 6ITH LOP YES B2.2(8) NTI-604.09 MAX UNISOLABLE MS LEAK YEE B2.2(9) NTI-604.10 SLOW RCS DEPRESS W/NO HPSI YES B2.2(10) NTI-604.11 REACTOR TRIP FOLLOWED BY YES 3.1.1(4) RECOVERY TO RATED POWER NTI-610.03. CCW PUMP BEARING SE!ZURE YES 3.1.2(8) CC03 , NTI-610.00 LOSS OF COOLING WTR TO DG YES 3 1.2(8) CC00 NTI-610.15 LOSS OF CCW TO LPSI PMP CLRS YES 3.1.2(8) CC15 NTI-610.19 AUX CCW PMP DISC HDR RUPTURE YES 3.1.2(C) CC19 NTI-614.03 CHRG PUMP SEAL LUBE PUMP YES 3.1.2(18) CV03 MOTOR FAILS
- ) F-7
APPENDIX F O PERFORNA 'CE _. PERFORMANCE TEST CERT. ANS-3.5 MALP TEST NUMLER DESCRIPTION REQ'D REF. USED NTI-614.15 CVCS LTDN LEAK OUTSIDE CNTMT YES 3.1.2(1) CV15 NTI-616.04 . LOSS OF 6.9KV BUS (ES) YES 3.1.2(3) ED04 NTI-616.10 LOSS OF 208/120V BUS (ES) YES 3.1.2(3) ED10 NTI-617.05 EXCIT.BKR FAILS TO AUTOTRIP YEL 3.1.2(22) EGOS NTI-617.10. DG OVERSPEED TRIP YES 3.1.2(3) EG30 NTI-617.20 STATOR COOLANT HIGH COND. YES 3.1.2(15) EG20 NTI-619.04 FDW PMP TURB SPD CNTRL Ft!L YES 3.1.2(9) FWO4 NTI-619.12 FDW PUMP TURBINE-HIGH VIB YEE 3.1.2(9) FW12 NTI-619.21 CONDENSER AIR IN LEAKAGE YES 3.1.2($) FW21 J NTI-619.37 FDd PIPE BREAK OUTSIDE ChTMT YES 3.1.2(20) FW37 i NTI-621.03 RUPTURE AIR' SUPPLY TO STEAM YES 3.1.2(2) IA03 BYPASS VALVES ({]) NTI-622.09 S/G STM' FLOW XMTR FAILURE YES 3.1.2(22) MSO9 NTI-622.13 MS LINE BREAK OUTSIDE CNTMT YES 3.1.2(20) MS13 BEFORE MSIV' NT1-622.22' . TURBINE 1ST STAGE PRESSURE YES 3.1,2(22)-MS22 XMTR FAILS-NTI-623.05 SU INSTRUMENT CH FAILURE YES 3.1.2(21).NIO5 NTI-625.03. 'RX PWR CB FAILS TO SB/RB YES 3.1.2(11) PWO3 NTI-626.04 RCP SHEARED SHAFT YES 3.1.2(4) RC04 NTI-626.11' CODE SAFETY FAILURE OPN/CLSD YES 3.1.2(1) RC11 NTI-626.16A RCP. SPEED XMTR FAILS A - P YES 3.1.2(22) RC16
. NTI-626.16B RCP-SPEED XMTR FAILS O - FF YES 3.1.2(22) RC16 NTI-626.20 RCS HOT LEG SFTY TT FAILS YES 3.1.2(22) RC20
.NTI-626.24 RCS HOT LEG PIPE RUPTURE YES 3.1.2(1) RC24 gf3 .
F-8 1'-
--l
, , , , , .. .,,,,,,,,,,,,,,,,,,y -
APPENDIX F ; O PERFORMANCE PERFORMANCE TEST CERT. ANS-3 5 MALF TEST NUMBER DESCRIPTION REQ'D REF. USED NTI-627.03 CEAS FAIL TO MOVE IN MAN GP YES 3.1.2(13) RD03 NTI-627.08 DROPPED CEA WITH NO ALARMS YES 3.1.2(12) RD08 NTI-627.12 CEA UNCNTRLD WITHDRAWAL YES 3.1.2(12) RD12 NTI-627.24 RX TRIP BRKR FAILS TO OPEN YES 3.1.2(24) RD24 NTI-629.04 ESFAS TRIP GENERATED YES 3.1.2I23) RPO4 NTI-630.05 S/G LEVEL SETPOINT DRIFT YES 3.1.2(22) RX05 NTI-630.10 PZR BU HTRS FAIL YES 3.1.2(18) RX10 NTI-631.05 S/G LEVEL XMTR FAILURE YES 3.1.2(22) SG05 NTI-632.08 LPSI PUMP SUCT LINE RUPTURE YES 3.1.2(7) SIO8 NTI-634.05 LOSS OF WTR TO HW COO' '. d YES 3.1.2(6) TP05 i l
~
l _ , _ . . . , ., _ _ . _ . b. _ _ . _ _ _ -. ___ _ _ . .
l APPENDIX F
.v) FOURTH YEAR TEST LIST PERFORMANCE PERFORMANCE TEST CERT. ANS-3.5 MALF TEST NUMBER DESCRIPTION REQ'D REF. USED NTI-602 NORMAL OPERATION TEST YES A3.2 NTI-603.01 45% ACCURACY TEST YES B2.1 t.
NTI 603.02 80% ACCUhACY TEST YES B2.1 NTI-603.03 100% ACCURACY TEST YES 92.1 NTI-603.04 100% STABILITY TEST YES B2.1 NTI-604.01 MANUAL REACTOR TRIP YES B2.2(1) NTI-604.02 SIM. TRIP OF ALL FDW PUMPS YES B2.2(2) NTI-604.03 SIM. CLOSURE OF ALL MSIVs YES B2.2(3) NTI-604.04 SIM. TRIP OF ALL RCPs YES B2.2(4)
, NTI-604.05 TRIP ANY RCP YES B2.2(5) k_ NTI-604.06 MAIN TURBINE TRIP YES B2.2(6)
NTI-604.07 MAX RATE POWER RAMP YES B2.2(7) NTI-604.08 HAX LOCA WITN LOP YES B2.2(8) NTI-604.09 HAX UNISOLABLE MS LEAK YES B2.2(9) NTI-604.10 SLOW RCS DEPRESS W/NO HPSI YES B2.2(10) NTI-604.11 REACTOR TRIP FOLLOWED BY YES 3.1.1(4) RECOVERY TO RATED POWER NTI-610.05 COOLING TOWER FAN (S) TRIP YES 3.1.2(8) CC05 NTI-610.09 LOSS OF CCW TO CNTMT FAN CLR YES 3.1.2(B) CC09 NTI-610.16 CCW UNISOLABLE LEAK IN CNTMT YES 3.1.2(8) CC16 NTI-610.21 CCW LINE BREAK IN AUX BLDG YES 3.1.2(8) CC21 NTI-614.05 LTDN BCK PRESS REG VLV FAILS YES 3.1.2(10) CV05 NTI-614.16 OHRG LINE BREAK INSIDE CNTMT YES 3.1.2(1) CV16 F- 10 l
-____ -_ _ _ _ _ _ _ __ _ ___- ___ _ ___- _ - _w_____
l
., APPENDIX F PERFORMANCE PERFORMANCE TEST CERT. ANS-3.5 MALF i
- TEST NOMBER DESCRIPTION REQ'D REF. USED : ,
~NTI-616.05 LOSS OF 4.16KV BUS (ES) YES 3.1.2(3) ED05 j i
NTI-617.07' MAIN GEN AUTOVOLTAGE REG YES 3.1.2(22) EG07 FAILS TO MANUAL , i NTI-617.11 DG TRIP ON DIFF PROTECTION YES 3.1.2(3) EGil , NTI-619.06 MTR DRVN EMERG FDW PMP TRIP YES 3.1.2(10) FWO6 f
'NTI-619.07 EMER FDW PMPS AUTOSTART FAIL YES - 3.1.2(10) FWO7 f NTI-619 14 CNDSR HW LVL CNTRL VLV FAIL YES 3.1.2(5) FW14 NTI-619.29 EMER FLW PIPE LEAK- YES 3.1.2(9) FW29 i NTI-619.38 FDW PIPE BPLAK INSIDE CNTMT YES 3.1.2(20) FW30 ;
NTI-621.04 RUPTURED AIR SPLY TO RAB YES. 3.1.2(2) IA04 NTI-622.10 MSHFLOW XMTR FAILURE HI/LO YES 3.1.2(22) MS10 j
, , NTI-622;21 MS LINE BREAK DWNSTRM OF- YES 3.1.2(20) MS21 !
] IFT-0300AS/BS IN'CNTMT NTI-623.07. SU CH FAILS TO DE-ENERGIZE YES 3.1.2(21) NIO7 l
, NTI-624.01' LOSS OF PMC PRI CMPTR CMPLX YES 3.1.2(22) PC01 NTI-625.06' RAIL CEAC CHANNEL (S) LOSS OF YES 3.1.2(11) PWO6 CPO2 CRT CH. . 1,2 4
- NTI-626.05 RCP LOS3 OF LUBE OIL YES. 3.1.2(4) RC05 NTI-626.12' CODE SAFETY RELIEF VLV LEAKS- YES 3.1.2(1) RC12:
NTI-626.17:. SI SYS PRESS INTLK FAILURE' YES' 3.1.2(17).RC17 NTI-626.21 RCS HOT LEG CNTRL1 TT FAILS YES 3.1.2(22) RC21: i NTI-626.25 RCS LEAK'INTO CNTMT YES 3.1.2(1)- RC25
.NTI-627.04 ~ CEAS FAIL To MOVE IN MAN IDc YES 3.1.2(13) RD04
- NTI'-627.09- CEA-REG GRP UNCNTRLD WITHDRW YES 3.-l.2(12) RD09
\
NTI-627.13 CEA-DRIFT YES 3.1.2(12) RD13 l (() F - 11 1 e
- ass' a 1stes, - - - g w.y-dy--earn'A=y-w'-MyW m *'es 9-w+-vW-y. 3r%' w-y-wrw esi'- 7-e v + 3rw' w 1 - -
*.tv - - -+ fa
I ? k , APPENDIX F { PERFORMANCE PERFORMANCE TEST CERT. ANS-3.5 MALF TEST NUMBER DESCRIPTION REQ'D REF. USED NTI-629.05 ESFAS CH FAILS TO TRIP YES 3.1.2(23) RP05 NTI-630.07 PZR PRESS CNTRLR FAILS OFF YES 3.1.2(10) RXO7 NTI-630.11 PZR PROP HTRS FAIL ON/OFF YES 3.1.2(18) RX11 NTI-632.11 SDC HX TUBE LEAK YES 3.1.2(7) Sill NTI-634.06 LOSS OF TCCW CLG TO IA/SA YES 3.1.2(6) TP06 COMPRESSORS NTI-635.06 TURBINE TRIP YES 3.1.2(15) TUO6 O
~
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