ML20081H014
| ML20081H014 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/21/1995 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20081H013 | List: |
| References | |
| NUDOCS 9503240057 | |
| Download: ML20081H014 (78) | |
Text
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O NRC FORM 474 i i
4f 4._ w l
l REPORT
SUMMARY
I FOUR YEAR PERFORMANCE TESTING REPORT ;
(1991-1994) l l
O l PERFORMANCE TESTING PLAN (1995-1999) -
SIMULATOR TEST PROGRAM (STP-3) i 1
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- 333 uceMagE DATE l New York Power Authority 3/21/95 f
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James A. FitzPatrick Nuclear Power Plant P.O. Box 41 Lycoming, New York 13093 ,
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Attachment Tab 3: Four Year Performance Testing Report j i
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Attachment Tab 4: Simulator Test Program (STP-3) l l
PERFOstd4MCE TESTDeG PLAN OtANGE. Per ear mammusam a e seemuseus meng sam amaned ese e assens omshedsQ l
OEsapupnaps oF PEppoptdAsstE TESTDs3 PLApe OtAssBE $namen sedumespgms e amosesy sus assey su em 40matsam emy esensa) l Attachment Tab 2: Report Summary - Performance Testing Plan Change !
Attachment Tab 4: Simulator Test Program (STP-3) !
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NEW YORK POWER AltfilORITY JAMES A. IT17fATRICK NUCLEAR POWER PIJNT PLANT REFERENCED SIMULA110N FACILI1T
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REPORT
SUMMARY
i Facility: James A. FitzPatrick Nuclear Power Plant - Docket Number 50-333 i
I Licensee: New York Power Authority !
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Location: New York Power Authority James A. FitzPatrick Nuclear Power Plant P.O. Box 41 Lycoming, New York 13093 Performance Testine Comoleted '
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The testing program described in the " Simulator Certification Abstract" submitted to the i commission on March 21,1991 has been completed. Performance testing has been conducted in accordance with the requirements of ANSI /ANS 3.51985. Pursuant to 10CFR55.45(bX5Xii), all test performance failures during this report period have been corrected. !
Pursuant to 10CFR55.45(bX5Xvi), a report is attached (Tab 3), describing the testing completed [
during this report period. The report lists each test that has been performed, grouped by test type, and includes the test number, test title, and the last date the test was performed. Deviations from the originally submitted testing plan are itemized and explained in the notes below:
- 1) The following operator conducted surveillance tests were added to the performance
~
testing program as a result of new procedure additions to the referenced plant's index of Operations Surveillance Test Procedures; 03ST-lY,03ST-ST,03ST-5U,03ST-20N, and 03ST-23E. These tests were performed and are included in the report.
- 2) The following operator conducted surveillance tests were removed from the initial performance testing program due to their deletion from the referenced plant's index of Operations Surveillance Test Procedures: 03ST-25,03ST-16J,03ST-23A. These tests .
were deleted prior to their scheduled performance dates and do not appear on the report.
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NEW YORK POWER AU1110RITY JAMLS A. ITrZPATRICK NUCLEAR POWER PLANT PLANT REFERENCED SIMULATION FACILfrY j
^'\
(U i REPORT
SUMMARY
- 3) The following new malfunctions have been added since the initial certification submittal: AN01, FP01, FP02, FW26, FW27, FW28, FW29, RD21. RR27, and RR28. !
These malfunction tests were developed and performed during this report period and are ,
included in the report.
- 4) Simulator changes incorporating completed plant modifications have required the
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deletion of several malfunctions that were included in the testing plan submitted with the !
initial certification. The malfunction tests listed below were deleted prior to their !
scheduled performance dates and do not appear in the report:
06NM16 TIP(X) Detector Stuck; Deleted I l-16-92 due to completed Modification 88-253 !
DR# 5475 !
06NM18 Leak in TIP(XX-YY) Dry Tube; Deleted 11-16-92 due to i completed Modification 88-253; DR# 5475 06NM19 TIP Ball Valve Fails To Close; Deleted Il-16-92 due to completed .
O Modification 88-253; DR# 5475 06RH02:A-D Torus Level Increase; Deleted 1-21-94 due to completed Modification 75-253; DR# 5461 06RH15 RHR Head Spray Flange Failure; Deleted 2-16-93 due to ,
completed Modification 92-091; ;
DR# 6637 ,
06RWO2 RSCS Failure; Deleted 12-8-94 due to completed Modification 88-086; DR# 5473 Discrepancies identified during performance testing have been documented and controlled in accordance with the Simulator Configuration Management Control Procedure (STP-1). Testing ;
related discrepancy reports and all performance test results are on file and available for review in i the Simulator. l O l l
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~ NEW YORK POWER AtTINORrTY JAMES A. FITZPATRICK NUCLEAR POWER PLAfff PIAhri REFERENCED SIMULATION FACIllTY REPORT
SUMMARY
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Performance Testine Plan Chanee:
- Simulator performance testing for the next four years will continue to be conducted in accordance with the requirements of ANSI /ANS 3.51985. The program to implement the testing for the next four years is a revision of the program used for the last four years. The changes in the program are minor and summarized below
}
- 1) The initial simulator certification and performance testing was described and i implemented by two Simulator Training Procedures, STP-3 and STP-6. The simulator performance testing requirements of STP-6 have since been moved into STP-3, and STP-6 I has been withdrawn. All ANSI /ANS 3.51985 simulator testing requirements are now implemented by one procedure, Simulator Training Procedure-3 (STP-3), entitled ,
" Simulator Test Program". l
- 2) Appendix B of STP-3 lists the Normal Operations and Operator Conducted Surveillance Tests to be performed over the next four years. The listing has been revised :
-O to reflect changes to referenced plant procedures and to eliminate unnecessary
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performances of functionally redundant Operator Conducted Surveillance Tests. ;
- 3) Appendix E of STP-3 lists the Malfunction Tests to be performed over the next four ,
years. This list has been revised, adding planned new malfunctions (annotated in the j
appendix) and removing malfunctions that have been deleted due to modifications completed during the past four years.
i !
Pursuant to 10CFR55.45(b)(5)vi, a description of the tests to be performed and a testing schedule for the next four year period is attached (STP-3; tab 4).
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NEW YORK FOWER AUT110RITY JAMES A. f1TZPATRICK NUCLEAR FO47.R PLANT PLANT REERENCED SIMULATION FACILITY FOUR YEAR PERFORMANCE TESTING REPORT O (PERFORMANCE TESIS) n-NORMAL d%; MgM,jdL.e __ f . .-adLN E ggga Q.s'Mj.Qgj 03ST 0ll! DRAIN ISOIAT10N VALVE TEST (IST)* 20-Dec.94 OPERATIONS 03ST-01C OMANN IM.AN W,W MERC5E (ISD IRA ONS 17 h 92 03ST-ole NORMAL INSTRUMENT FUNCTIONAL TEST 05-Mar-94 OPERAT10NS 03ST01O NORMAL MAIN SITAM RAD MONrrOR (17RM-25 l A,B, CAD) FUNCTIONAL EST 11-Oct-91 OPERAT10NS 03ST Olli NORMAL OPERATIONS 31-JanM 03ST-Oli .A H N 27-Jan-95 L ONS 03ST-olK , SA A A 01-Fe W I ONS ,
03ST-01L ""
ONS !
03ST-01R MORNAL REACTOR BUILDING CIDSED LOOP COOLING COrTTAINMENT ISOLATION 14-Feb-95 OPERATIONS AOV EXERCISE (IST)*
03ST 0IS C)I'l (AT10NS
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ONS 03ST-02B & OP & Emm, SMH NNE ET 2N M ONS I
03ST-021 ' ""
IIRA ONS 03ST 02N f FRA ONS LPCI MODE INOPERABLE TEST 27-Jan-95 I 03ST-02R RIIR SERVICE WATER PUMP & MOV OPERABILITY TEST 20-Dec-94 ONS 03ST-02T I ONS '""
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03ST-02Y I 10NS
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- 03ST-03A CORE SPRAY PUMP & VALVE OPERAllIIIFY 1EST 20-Dec-94
()l'I ItAT10NS NORMAL.
03ST-03K CORE SPRAY SYSTEM INOPERABLE 1EST 27-Jan-95 OPERATIONS O 03ST-03M NORM ^i.
OPERATIONS CORE SPRAY TESTAllLE CIIECK VALVE TESTING (IST) 16-Apr-92 PageI
NEW YORK POWER ALTrilORITY JAMES A. FTTZPATRICK NUCLEAR FOWER PLANT Pl. ANT REFERENCED SIMULAT10N FACILITY FOUR YEAR PERFORMANCE TESTING REPORT J
(PERFORMANCE 11?STS)
- I .
NORMAL 03ST43P CORE SPRAY FIDW RATE AND VALVE INSERVICE T1?ST (ISTJ* 20-Jan-95 OPERAT10NS NORMAL 03ST-04fl IIPCI PUMP & MOV OPERABIIJTY TEST 20-Dec-94 OPERAI ONS NORMAL 03ST-04G IIPCs SYSTEM INOPERABLE 11?ST 27-Jan-95 OPERATf0NS NOIUAAL 03ST-411 IIPCl/RClc TESTABLE CIIECK VALVE TEST 1NG (IST)* 15-Feh95 OPERAT10NS NORMAL 03ST-04M IIPCI TORUS SUC110N OPERABILITY TEST (IST) 27-Jan-94 OPEMONS NORMAL 03ST-04N OPERA 110NS I ^ ^" ' "
03ST 05C
['r ONS IRM-APRM INSHUMENT RANGE OVERLAP CIIECK 08-Mar-94 NORMAL 03ST-05N #
OPERA 110NS NORMAL 03ST-050 OPERA 110NS NORMAL O 03ST-05P OPERAllONS AN E m m N W 25A p NORMAL' 03ST-05Q gpg .nONS APRM FIDW BIAS FUND 110NAL TEST (RUN MODE) 09-Dec-94 NORMAL 03ST-05R "
OPERAI ONS NORMAL 03ST-05T RPS CilANNEL A APRM DOWNSCALE FUNC110NAL1EST(RUN MODE) 20-Dec-94 gppy.nONS 03ST-05U N'O # " I ) ~
ONS N BGT ME BMSS TERAMN, mm CMACM, EM T' 03ST-07A 09-Feh95 OPERATIONS AND DOWNSTREAM PIPING LEAK 1TISTS
- NORMAL 03ST-07C OPERA 110NS U ^ ""~
NORMAL' 03ST 07D STANDBY GAS REA11 DINT FAN AND VALVE EXERCISING (IST)* 25-Apr-94 ggygg3 NORMAL 03ST-08C ESW MOTOR OPERATED VALVES OPERABIllTY TEST 300ct-91 OPERATIONS NORMAL 03ST 08D OPERA 110NS RAE MW) MM2 l 03ST 08N NORMAL ESW PUMP INSERVICE 11?ST(IST)* 09-Fe495 OPERA 110NS NORMA 1' 03ST-0911 EDG iTJLL LOAD IT.ST AND EDW PUMP OPERAllILTTY TEST 11-May-92 NORMAL 03ST-09C EMER AC ID SFQ & 4KV EMER PWR VOLT RELAYS INSTRU FUNC110NAL I4-Feh95 OPERAllONS Page 2
NEW YORK POWER AUlllORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT PLANT REERENCED SIMULATION FACILITY FOUR YEAR PERFORMANCE TESTING REPORT n(./ (PEPJORMANCE TESTS)
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NORMAL 03ST-09D EDG,115Y,V RESERVE PWR, STAT BATT, ESW PMP INOPERABLE TEST 20-Dec-94 OPERATIONS NORMAL I 03ST-10A OPERAllONS AS E M.AEN WC SYSW MCMM.MT* WeW 03ST-10Il NORMAL OFF4AS SYSTEM AUTO ISOLA 110N AND CLOSURE TEST 31-Jan-95 OPERATIONS 03ST-1I NORMAL gpggg.nONS OFFGAS RAD MON INSTRUMENT CIIANNEL FUNCRONAL TI!ST 10-Mar-94 03ST-1211 NORMAL OPERADONS REACTOR BUILDING EXilAUST RAD MON INSTRUMENT RESPONSE TEST 15-Feb95 03ST-12F RON \M.AMN RAD WNSENU MMSE OPERAllONS ll?ST 03-Fe495 03ST-12!
NORMAL LIGUID RADWASTE EFFLUENT MONTFOR INSTRUMENT AND ISOLA 110N OPERATIONS 09-Feb95 IDGIC SYSTEM FUNCTIONAL TEST' l NORMAL 03ST-12K OPERAlf0NS ^ " '"
NORMAL 03ST-13 OPERATIONS
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NORMAL STACK GAS RADIAT10N MONflDR INSTRUMENT CllANNEL FUNCRONAl' O 03ST-13A OPERATIONS IT3T' 14-Feb95 03ST-14A NORMAL OPERAllONS N A RAD WN MCMM WT 304an-95 03ST 15G NORMAL PRESSURE SUPPRESSION CilAMBER-RX BLIXl VACUUM BRKR OPERATIONS 09-Fe495 OPERABILTTY AND SET POINT TEST (IST)'
NORMAL 03ST-1511 OPERAlf0NS ^ ~
03ST-16Il NORMAL I' "A -*
OPERATIONS NORMAL 03ST-18 OPERATIONS
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l NORMAL 03ST-20A OPERATIONS ORm N.R MNM ET OWM2 l NORMAL CONTROL ROD OPERABILITY AND llCU COOLING WAllIR SUPPLY 03ST-20C 09-Feb95 OPERATIONS CIIECK VALVE REVERSE FLOW ClIECK (IST)*
03ST-20F NORMAL OPERADONS I ""
NORMAL 03ST-203 " ' ""'
OPERA 150NS NORMAL 03ST-20K PRE-CON!ROL ROD WTn IDRAWAL CilECKLIST 19-Mar-92 OPERAl ONS 03ST-20M SCM WSCH MWE N & M US M.I. SHM & NG 31-Jan-95 OPERADONS TEST 03ST-20N NORMAL OPERAllONS CONTROL ROD EXERCISE /!IMING/STAl.L FLOW TEST 06-Mar-94 l
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NEW YORK POWER AUTilORITY JAMES A. TTF2.PA1 RICK NUCLEAR POWER PLANT PLANT REFERENCED SIMULATION FACILITY FOUR YEAR PERFORMANCE TESTING REPORT (PERFORMANCE TESTS)
EENE 03ST-22F NORMAL OPERAT10NS EEd@lMEM E M MlllG EE b MORE T11AN ONE VALVE OF ADS INOPERABLE TEST M 30-Jan-95 03ST-23B NORMAL 01, ROD COWWG MRW MT O h 94 OPERATIONS 03ST-23C NORMAL OPERATIONS TWO LOOP OPERATION (EPIC AVAIIABLE) 14-Feb94 03ST-23D JET PUMP OPERABILITY EST FOR SINGLE LOOP OPERATION
- I5-Feb95 ONS NORMAL 03ST-23E TWO IDOP OPERATION (EPIC NOT AVAILABLE) 20-Dec-94 OPFRATIONS 03ST-24A NORMAL RCIC PUMP AND MOV OPERABIIJFY TEST 30-Jan-95 OPERATIONS 03ST-24F Omu MT 3 Nan-M ERA ONS 03ST-24J El ONS
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03ST-26K L T10NS ' ' '
03ST-26M RA OR WARR G.EAN-W SYSE MW MMG (IST) 30-AM3 ERA ONS 03ST-27A NORMAL RECIRC LOOP VALVE OPERABILITY TEST (IST) 31 Jan-95 OPERA 110NS 03ST-29A MANUAL SCRAM FUNCTIONAL EST 29-Aug-94 03ST-29B MODE SWITCII IN SIIUTDOWN FUNCTIONAL EST" 25-Apr-94 ONS 03ST 29C ' ""
Ol'ERATIONS 03ST-40D DAILY SURVEILIANCE AND INSTRUMENT CIIECK' 14-Feb95
NORMAL OP-65(D) STARTUP PROCEDURE (INCLUDING APPLICABLE OPS AND RAPS) 25-Apr-94 OI DONS NORMAL OP-65(F)
OPERATIONS PRWEDM(NG WWG MCABE Om m m) 07-FeW 06AIMI MAIEUNCTION ADS TIMER FAILS TO START 12-Jan-95 06 AIM 2 MAIEUNCTION ADS INADVERTENT TIMER AND IDGIC START 16-Jan-95 Page 4
NEW YORK TOWER ALTrliORITY JAMES A. f1T71ATRICK NUCLEAR POWER PLANT PLANT REFERENCED SIMULATION FACILITY FOUR YEAR PERFORMANCE TESTING REPORT (PERFORMANCE TESTS) 06AD43 MALFUNCTION ADS VALVE FAILS TO INITIATE AtHOMAT1CALLY I 1-Jan-95 06AD-04 MAIEUNC110N RX SAFETY R11IEF VALVE SOLENOID FAILURE I l-Jan-95 06AD45 MAllTJNC110N RX PRESS RELIEF VALVE LEAK 12-Jan-95 06AD46 MALFUNCTION RX SAFETY RELIEF VALVE INADVERTENTLY OPENS 17-Jan-95 06AD47 MALFUNCTION RX SAFETY RELIEF VALVE FAILS TO OPEN 24-Jan-95
%AD48 MAIJ11NCTION RX SAFETY RELIEF VALVE STUCK OPEN 02-Feb-95 06AD49 MAIEUNCTION RX SRV VACUUM BREAKER STUCK OPEN 16-Jan-95 06AN-01 MAIEUNCT10N CONTROL ROOM ANNUNCIATOR POWER FAILURE I 1-Jan-95 06CS41 MAIEUNCTION CORE SPRAY PUMP TRIP (A/B) 23-Aug-91 06CS-02 MAIEUNC110N 21-Aug-91 CS INJEC110N VALVE (S) FAILS TO AUTO OPEN 14MOV-12A(B) 06CS-03 MAIJUNCT10N CS SUPPRESSION POOL SUCT10N 14MOV-7A(B) FAILS CIDSED 23-Aug-91 06CS44 MAIEUNC110N CORE SPRAY (A/B) INJECTION LINE BREAK 22-Aug-91 06CS-05 MAIEUNCTION CORE SPRAY TORUS SUCTION PIPE FAILURE 22-Aug-91 06CU-01 MAIEUNC110N RWCU BIDWDOWN FLOW CONTROL VALVE (12FCV-55) FAILURE 20-Dec-91 06CU-02 MAIEUNC110N REACTOR WATER CIEANUP PUMP (A/B) TRIP 27-Aug-91 06CU-03 MAIEUNCT10N 111BE LEAK IN RWCU IIEAT EXCIIANGER (NON-REGEN, REGEN) 30-Sep-91 06CU44 MAIEUNCTION RWCU RESIN INTRUSION DRO T1IE REACTOR VESSEL 18-Mar-92 06CU-05 MAIEUNCTION RWCU RESIN DEPLETION 06-Sep-91 06CU-06 MAIEUNC110N RWCU INADVERTANT ISOIATION 06-Sep-91 06CU 07 MAIEUNCTION RWCU PIPE BREAK OUTSIDE PRIMARY CONTAINMENT 06-Sep-91 06CU48 MAIEUNC110N RWCU RETURN TEMPERA 11TRE TRANSMTFIER FAILURE 02-Feb-95 06CU-09 MAIEUNC110N RWCU INLET PIPE FAILURE 06-Sep.91 P.. ,
NEW YORK POWER AtHilORTTY 1AMES A. F1T7.PATRJCK NUCLEAR FOWER PLAtn PLAPG REFERENCED SIMULAT10N FACILITY
, FOUR YEAR PERFORMANCE TESTING REPORT (PERFORMANCE TESTS) g y . ,, p ; m sgy y~n .>-- m uuanamww. apgy,y.3 y n ..: -+ n l$ t h lhhh _
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I 06DG-01 MAIJUNC110N EDO FAILS TO START 02-Feb95 06DG42 MAIJUNC110N DIESEL GENERATOR MANUAL TRIP FAILURE 16-Mar-92 06DG43 MAlfUNC110N ElXI OLTIT'UT BREAKER FAILS TO AUTO CLOSE 02-Feb95 06DG44 MALF11NCTION DIESEL GENERATOR TRIP 28-Apr-93 06DG45 MALFUNCTION DIESEL GENERTOR VOLTAGE RFEULATOR OSCILLATIONS (A,B,C) 18-Jan-93 06DG-06 MAlfUNC110N DIESEL GENERATOR SIDW TO START (>10SEC) 21-Oct-91 06LX1-07 MAIJUNCTION DIESEL GENERATOR GOVERNOR FAILS IllGli 10-Mar-92 06fx148 MAIEUNCTION EDG GOVERNOR FAILS LOW 02-Feb95 06EIMI MALFUNCTION 1RANSFORMER TI Affl B FAILURE (345/24KV) 15-Aug-91 06ED42 MALFUNC110N l l 5/4 KV 1RANSFORMER (T2,T3) FAILURE 23-Mar-93 06ED-03 MAlfUNC110N 4 KV/600V 1RANSFORMER (T13,T14,T15,T16) FAILURE 17-Jan-95 06EDel MAIEUNC110N INVERITR (7IINV-3A/I3) FAILURE 16-Jan-95 06EIM5 MALFUNC110N 4KV/600V TRANSFORMER (TS,T6,T7,T8,T9,T10,TI 1,T12) FAILURE 24-Feb92 06ED46A MAIJUNCllON 120 VAC IlUS FAILURE (R11ACAS) 21-Oct-91 06EIM613 MAIJUNCTION 120 VAC IlUS FAILURE (TBACA6) 21-Oct-91 j 0613M6C MAIJUNCT10N 120 VAC BUS FAILURE (SWACA7) 21-Oct-91 06ED-06D MAIEUNCTION 120 VAC IlUS FA! LURE (IUlACIIS) 21 Oct-91 06EIM6E MAlfUNC110N 120 VAC 110S FAILURE (T11ACll6) 21-Oct-91 06EIM6F MAIEUNCTION 120 VAC BUS FAILURE (RWACil7) 21-Oct 91 06EIM711 MAIEUNCTION 120 VAC IJUS FAILURE (RRACB8) 21-Oct-91 06ED47C MALFUNCllON 120 VAC BUS FAILURE (RBACC5/RBACG5) 21-Oct-91 06ED47D MAIEUNCTION 120VAC BUS (TBACC6) FAILURE 16-Jan-95 1
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NEW YORK POWER AtJI110RITY JAMES A. FITZPATRICK NUCLEAR POWER PI/MT PLANT REFERENCED SIMULAT10N FACILII'Y FOUR YEAR PERFORMANCE IT. STING REPORT O (PERFORMANCE 1ES13) i l
06ED47E MAIJUNC110N 120 VAC BUS FAILURE (SWACC7) 21-Oct-91
%IHM7F MAIEUNC110N 120VAC BUS (RBACDS) FAILURE 16-Jan-95 06ED0711 MAIEUNC110N 120VAC BUS (RWACD7) FAILURE 16-Jan-95 06ED071 MAIEUNC110N 120 VAC BUS FAILURE (RBACE5) 25 & -91 MEIM71 MAIEL NC110N 120VAC BUS (71 ABACl) FAILURE 16-Jan-95 1
0613M7K MAIEUNC110N 120VAC BUS (71ACNMS) FAILURE 16-Jan-95 06flM7L MAIEUNCTION 120VAC BUS (71ACNMS-A) FAILURE 16-Jan-95 06ED47M MAIJTJNC110N 120VAC BUS (71ACNMS-B) FAILURE 16-Jan-95 06EIM7N MAIJTJNC110N 120VAC BUS (71EBAC1) FAILURE 16-Jan-95 06EIMRA MAIEUNC110N 120/240 VAC BUS FAILURE (71AC9) 25-Oct-91 06ED-08B MAIJUNC110N 250ct-91 120/240 VAC BUS FAILURE (71 AC10) 06ED-09 MALFUNCTION UNINTERRUITABLE POWER SUPPLY (UPS) MG DIU VE FAILURE 18-Jan-92 06ED-10 MAIJUNC110N 120 BAC BUS FA~ LURE (71ACUPS) 21-Feb92 06ED-l1 A MAIEUNC110N 125 VDC BUS A(BCB-2A) FAILURE 19-Dec-91 06ED 11B MAIEUNP110N 125 VDC BUS B(BCD-2B) FAILURE 20-Dec-91 06ED-12 MAIEUNC110N 125VDC BATTERY CHARGER (A/B) FAILURE 06-Sep-91 06ED-13A MAIJUNC110N 24 VDC BUS A(RR24DCA) FAILURE 17-Dec-91 06ED-138 MA11UNC110N 24 VDC BUS B (RR24DCB) FAILURE 17-Dec-91 06ED-14 MAIEUNC110N 24VDC BATTERY CHARGER FAILURE 08-Feb-95 i 061'D-15 MAIEUNCTION 24KV/4KV1RANSFORMER T4 FAILURE 08-Feh95 06ED-16A MAIEUNCTION POWER GRID TRANSIENT %TITI IDAD INCREASING 21-Mar-92 06ED-16B MAIEUNCTION POWER GRID TRANSIENT WITil IDAD DECREASING 08-Mar-92 Page 7
I NEW YORK POWER AlfrilORITY JAMES A. I1TZPATRICK NUC11AR POWER PIANT PLANT REFERENCED SIMUIATION FACILITY
,OeR YEAR PER,ORMANCE TESTING REPORT O (PERFORMANCE 111sl3) 5777^ SEVNGIT' Q l
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NEW YORK POWER AtTIllORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT PLANT REFERENCED SIMULATION FACILITY O FOUR YEAR PERFORMANCE TESTING REPORT (PERFORMANCE TESTS) l j
06ED-3611 MAIJTINCT10N 120VAC IlUS (71ACA3) FAILURE 24-Jan-95 06ED-36C 1 MAIJUNCDON I20VAC BUS (71 ACA4) FAILURE 24-Jan-95 06ED-36D MAIJUNCT10N 120 VAC IlUS (71 ACB2) FAILURE Il-Dec-91 l
06ED-36E MAIJUNCDON 120 VAC BUS (71 ACD3) FAILURE Il-Dec-91 06ED-36F MAIEUNCT10N 120VAC IJUS (71 ACB4) FAILURE 24-Jan-95 06ED-38 MAIEUNCT10N 125VDC BUS 71BMCC FAILURE 23-Jun-94 06ED-39 MAIEUNCDON 125VDC CON lROL POWER FAILURE TO 4160V BUSSES 24-Jun-94 06EG-01 MAIJUNCTlON MAIN GNERATOR TRIP 30-Apr-93
%EG-02A MAIJUNCT10N MAIN GENLRATOR FIELD BREAKER FAILS TO CLOSE 06-Jan-93 06EG-0211 MAIEUNC110N MAIN GENERATOR FIELD IIREAKER FAILS TO OPEN 08-Feb-95 06EG43 MALITJNCTION LOSS OF ISOLATED PilASE IlUS COOLING FAN 08-Feb-95 06EG-04 MAIEUNC110N MAIN GENERATOR FIELD BRUSIIES GROUND 12-May-93 06EG45 MAIEUNCTION MAIN GENERATOR STATOR TEMP 10G1I 08-Feb 95 06EG-06 MALFUNCDON GENERATOR IIYDROGEN COOLING SYSTEM LEAKAGE 25-Jun-92 06EG-07 MAIEUNC110N IIYDROGEN SEAL OIL SYSTEM FAILURE 25-Jun-92 06EG-08A MAIEUNCTION MAIN GENERATOR AUID VOLTAGE REGUIATOR FAILS INCREASING 18-Mar-92 06EG-08B MAIEUNCT10N MAIN GENERATOR ALTfD VOLTAGE REGUIATOR FAIlli DECFEASING 18-Mar-92 06EG49 MAIEUNCDON MAIN GENERATOR AITIO VOLTAGE REGUIATOR OUTPlTT FAILURE 25-Jun-92 06EG-10 MAIEUNCDON TOTAL LOSS OFSTATOR COOLING 05-Mar-92 06FP-01 MAIEUNCT10N EDG ROOM FIRE 23-Aug-94 06FP-02 MAIEUNCTION IIRE ZONE SMOKE AIARM l 31-Jan-94 O 06FW 01 MAlJUNC110N REACTOR FEEDWATER PUMP TRIP 04-Jan-93 Pace 9
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Page 10 I i
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NEW YORK PO%T:R AUrliORITY JAMES A. ITTlfATRICK NtK'IFAR POWER PLANT PLANT RUT:RENCED ** t ' TION FACILITY i
FOUR YEAR PERFORMAi.CE TESTING REPORT O (PERFORMANCE TES13)
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NEW YORK POWER ALTFIIORITY JAMES A ITTZPATRICK NUCLEAR POWER PLANT !
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06MC-08 MAIJUNC110N CIRCULA11NG WATER PUMP DISCilARGE VALVE FAILS TO OPEN 30-Sep-92 06MC-09 MAIEUNCTION LDSS OF CONDENSER WATER BOX VACUUM PRIMING I I-Sep-92 06MC-10 MAIJUNCTION INTAKE ICING Il-Sep-92 06MS 01 MAIEUNCT10N MAIN STFAM IIEADER PRESSURE TPANSMITIER FAILURE 12-Nov-92 06MS-02 MAIEUNC110N S1FAM LEAKAGE INSIDE PRIMARY CONTAINMENT 28-May-93 06MS43 MAIEUNCTION MAIN STFAM LINE RUFIURE INSIDE T1E PRIMARY CONTAINMENT 08-Apr-94 06MS 04 i AIEUNCT10N MAIN SITAM llNE RUPTURE OUTEIDE TIE PRIMARY CONTAINMENT 24-Mar-93 06MS-05 MAIEUNCTION STEAM LEAK OUISIDE PRIMARY CONTAINMENT 24-Mar-93 06MS46A MAIEUNCT10N STEAM SEAL PRESSURE REGUIATOR FAILS OPEN 30-Dec-92 06MS-06B MAIEUNCDON STFAM SEAL PRESSURE REGUIATOR FAIIE CIDSED 4
30-Dec-92 06MS47 MAIEUNC110N MAIN SITAM ISOIA110N VALVE DISC SEPARATES FROM SUIM 21 Oct-92 1
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NEW YORK PO%T:R AtTrilORITY JAMES A. IlTEPATRICK NUCLEAR POWER PLANT PLANT RFJERDJCED SIMULATION FACILITY FOUR YEAR PERFORMANCE TESTING REPORT O (PERFORMANCE 1ESTS) l l l .
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06NM 15 MAIEUNC110N APRM CllANNEL INOPERA11VE 22-Sep-92 06NM-17 MAIEUNCBON LPRM DRY 1UBE (XX-YY)l.EAK 06-Nov-92 Page 13
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NEW YORK POWER ALTrilORITY JAMES A. I1TZPATRICK NUCLEAR POWER PIANT PLANT REIT.RENCED SIMULAT10N FACl!JTY FOUR YEAR PERFORMANCE TESTING REPORT O (PERFORMANCE TESTS) l
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%RD-16 MALFUNC110N ROD POSITION INFO SYSTEM TOTAL FAILURE 15-Dec-93 Page 15
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06RR-04 MALFUNCT10N RWR PUMP #1 SEAL FAILURE 20-Jun-94 06RR-05 MAIEUNCT10N RWR PUMP #2 SEAL FAILURE 20-Jun-94 06RR46 MAIEUNCTION RWR PUMP DUAL SEAL FAILURE 21-Sep-94 l
l Page 17 l
NEW YORK POWER AtJIllORITY JAMES A. ITTZPATRICK NUCLEAR PORT.R PLARI PLANT REFERENCED SIMULATION FACILITY FOUR YEAR PERFORMANCE TESTING REPORT O (PERFORMANCE TESTS) la i r 06RR-07 MALFlJNCTION RWR IDOP FLOW TRANSMTFIER FAILS 10-Nov-94 06RR4)8 MAIE11NC110N JET PUMP FAILURE 28-Nov-94 06RR-09 MAIEUNCTION RWR MASTER FLOW CONTROLLER FAILURE 12-Apr-94 06RR-10 MAIJUNCT10N RWR SYSTEM MG FIDW CONTROLLER FAILURE 21-Sep-94 06RR-11 MALFUNCTION RWR PUMP SHAFT BINDING 22-Feb-94 06RR-12 MAIEUNCT10N RWR PUMP DRIVE MOTOR BRFAKER TRIP 07-Mar-94 06RR-13 MAIEUNC110N ATWS SYSTEM FAILS TO INITIATE RWR PUMP TRIP 05-Jul-94 06RR-14 MALFUNCTION RWR LOOP RUFIURE(DBA) 28-Sep-94 06RR-15 MAIEUNCTION RWR COOIANT LEAKAGE INSIDE PRIMARY CONTAINMENT 21-Jul-94 06RR-16 MAIEUNCT10N REACTOR VESSEL WIDE RANGE LEVEL TRANSMTTIER FAILS 27-Jan-94 06RR-17 MAIEUNCTION REACTOR VESSEL FUEL ZONE LEVEL FAILURE 20-Jul-94 l
06RR-18 MAIEUNC110N REFUEL WATER LEVEL INDICATOR FAILS 27-Jan-94 06RR-19 MAIEUNCT10N RX VESSEL LVL TRANSMTI'IER TO FW LVL CONTROL SYSTEM FAILURE 21 Jul-94 06RR-20 MAIEUNCDON LOSS PRESSURE COMPENSATION TO FEEDWATER CONTROL SYSTEM 22-Feb-94 06RR-2i MALFUNCDON IDSS OF PRESSURE COMPENSAT10N TO FEEDWATER CONTROL SYSTEM 18-Jul-94 l l
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- 1 ll ll 06RW.01 MALFUNCTION ROD WORT 11 MINIMIZER FAILURE 12-Dec-94 06RW-02 MALFUNCT10N RSCS FAILURE 20-Sep-94 06RX41 MAIEUNCT10N FUEL CIADDING FAILURE 12-Jan-95 06RX-02 MAIEUNCTION INCREASED ROD WORTII(XX-YY) 30-Nov-94 06RX-03 MAIEUNCTION CORE TIIERMAL IIYDRAULIC INSTABILITY 20-Sep-94 06SL-01 MAIEUNCTION STANDBY LIQUID CON 1ROL PUMP BREAKER TRIP 20-Sep-94 06SIA2 MAIEUNCTION STANDBY LIQUID CONTROL SQUID VALVE FAILS TO OPEN 28-Jun-94 '
06SI,03 MAIEUNCT10N Sir PUMP RELIEF VALVE IlfTS 28-Jun-94 06SW-01 MAIEUNCT10N LOSS OF RBCLC FIDW TO RWR 23-Aug-94 06SW-02 MALFUNCTION TBCIf IlX COOLING WATER BLOCKAGE 22-Sep-94 06SW-03 MALFUNC110N RBCLC IIX COOLING WATER BIDCKAGE 27-Oct-94 I 06SW44 MALFUNC110N RIIR SERVICE WATER PUMP TRIP 04Det-94 i
06SW-05 MAIEUNCTION SERVICE WATER PUMP TRIP 26-Sep-94 06SW46 MAIEUNC110N RIIR IIX COOllNG WATER BIDCKASE 25-Oct-94 06SW-07 MAIEUNCTION T13Cif PUMP TRIP 26-Sep-94 06SW 08 MAIEUNC110N TBCLC IIX TUBE IIAK 2 W 94 06SW49 MAIEUNC110N RBC1f PUMPTRIP 23-Aug-94 06SW 10 MALFUNC110N RBCLC IIX TUBE LEAK 20-Sep-94 06SW-11 MAIEUNCT10N RBCLC IEAKAGE IN DRYWELL 07-Oct-94 06SW-12 MAIEUNCT10N [ DSS OF DRYWELL COOLING ASSEMB!lES 07-Oct-94 06SW-13 MAIEUNCTION IDSS OF COOLING TO RWCU NRIIX 26-Sep.94 06SW-14 MAIEUNCT10N EMERGENCY SERVICE WATER PUMP 1 RIP 26-Sep-94 I
Page 19
NEW YORK POWER AtJriiORITY JAMES A. FITZPATRICK NUCLE /Jt FO%IR PLANT PLANT RFJTRENCED $1MULATION FACILITY FOUR YEAR PERFORMANCE TESTING REPORT (PERFORMANCE 1ESTS) s.
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. . .J!h w & RIE l miBR ' ore mura M* MM P -2 n- S m.J 06TC-01 MALIUNCT10N MAIN TURBINE ACCELERA110N 17-Nov-94 06TC-02 MALFUNCDON EllC PUMP TRIP 10-Nov-94 06TC-03 MALFUNC110N EllC PUMP PRESS REG FAILS 10-Nov-94 06TC-04 MALEUNC110N BYPASS VALVE FAILURE 12-Dec-94 06TC45 MALIUNCTION MAIN 1URBINE LDAD SELECT FAILURE 17-Nov-94 06TC-06A MAIEUNC110N ElIC SYSUN REGULATOR FAILS IDGli 07-Apr-94 ,
06TC-06B MAIEUNCTION EllC SYSTEM REGULATOR FAILS LOW 17-Nov 94 06TC-07 MALFUNC110N ElIC SYSTEM REGULATOR OSCILLA110N 10-Nov-94 06TC-08 MAIEUNC110N 1URUINE CONTROL VALVE FAILURE 13-Dec-94 06TC-09 MAIEUNC110N TURBINE STOP VALVE FAILURE 29-Nov-94 06TC-10 MAIEUNCTION IURBINE LOAD RFJECT 17-Nov-94 061U-01 MAIEUNCTION INADVERTENTIURBINE TRIP 28-SeP-94 06TU-02 MAIEUNCTION MAIN TURBINE BEARING 1UGIraMP 260ct-94 i
061U-03 MAIEUNC110N MAIN 1URBINE BEARING OIL PRESSURE LOW 25-Oct-94 061U-04 MALFUNC110N MAIN 1URBINE BEARING IDGH VIBRATION 17-Nov-94 06TU45 MAIEUNCTION MAIN TURBINE SilAFT DRIVEN OIL PUMP FAILURE 07-Oct-94 l
061U-06 MAIEUNC110N TURBINE MOTOR SUCTION PUMP TRIP 074ct-94 06TU-07 MAIEUNCTION MAIN IURBINE EMERGENCY BEARING OIL PUMP TRIP 070ct-94 061 U 48 MAIEUNCTION EX11AUST llOOD SPRAY VALVE FAILURE 07-Oct-94 06YC-Ol MAIEUNC110N EPIC FAILS 28-Jun-94 CPU REAL11ME N/A CPU UTILIZAT10N AND SPARE TIME DETERMINATION 13-Jan-95 EST 04SS41 STEADY STATE 25% STEADY STATE 13-Dec-94 Page 20
NEW YORK POWER AtJTilORITY JAMES A. ITTZPATRICK NUCLEAR POWER P! ANT l PIANT REFERENCED SIMULATION FACILITY I FOUR YEAR PERFORMANCE TESTING REPORT (PERFORMANCE 11?STS) g-. . . _ .. .
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04SS43 S11%DY STATE 100% STEADY STATE 09-Dec-94 07IT-01 1RANSIElR MANUAL RIMCTOR SCRAM 044kt-94 07IT-02 TRANSIENT 1 RIP AIL FFEDWATER PUMPS 044kt-94 077T-03 TRANSIINT CLOSURE OF ALL MSIVS 04 Oct-94 07IT-04 TRANSIENT 1 RIP OF DOT 11 RECIRC PUMPS 04-Oct-94 07IT-05 1RANSIENT SINGLE RECIRC PUMP 1 RIP 054)ct-94 071T-06 IRANSIENT MAIN lllRBINE TRIP (NO SCRAM) 05-Oct-94 071T47 IRANSIENT MAX RATE POWER RAMP 054)ct-94 07IT-08 O 1RANSIE?R DBA LOCA %Till LOSS OF OFF-STTE POWER 05-Oct-94 071T-09 IRANSIEtU MAIN STEAM IJNE RUPTURL 05-Oct-94 07TT-10 TRANSIENT CLOSURE OF ALL MSIVS Willi SITJCK OPEN RELIEF VALVE 05-Od-94 O
Page 21
NEW YORK POWER AtRilORITY JAMES A. ITI7. PATRICK NUCLEAR POWER PIJJ4T PLANT REFERENCED S!MULATION FACILITY FOUR YEAR PERFORMANCE TESTING REPORT O-(MODIFICA110NS 1ESTED) 7 EM98FNG10k jfdQTfW ZE Essa #Tarsummili%f@@if4hddhin@$flMMNEA I?R det?d#6 4666 MODIFICAllON MOD 82-021-F05: UPGRADES AND MODIFIES TEMP MONITORING FOR RIIR 19-Mar-92 100S. PROVISION FOR MORE STABLE RIIR SW OLTITIT TEMP AND SIGNAL INPITT TO EPIC. EXISTING INPlJIS TO 10-1RS-131 ARE DISCONNECTED.
4667 MODIFICATION MOD 82-021-F15: PROVIDES MN S1M TUNNEL VENT EXHAUST FIDW RATE 28-Feb-92 INDICATION, VIA EPIC, ON DEMAND 4668 MODIFICATION MOD 82-022: DISCREPANCES EXIST BETWEEN PLANT AND SIMULA1DR - I l-Jul-91 EPIC RESPONSE.
4669 MOD &lCAllON MOD 84-005: PROVIDE I 15,1 16 AND A & B LPCIINVERTERS ENCLOSURES 10-Oct-91 Will! AIR CONDmONING FOR IIARSH D4VIRONMENT DURING IDGH ENERGY LINE IIRFAK.
4670 MODIFICADON MOD 84-038: REPLACES NUMAC IDG RADIAT10N MONITORS WTDI 29-Jan-92 NUMAC MONTTORS FOR 17RM-25 i A, B, C, & D (MAIN STEAM) AND 17RM-150A & B (OFFGAS).
4676 MODIFICA110N MOD 84-084:PROVIDES A REPLACEMENT INSERT TYPE ClECK VALVE 9-Mar-92 FOR USE IN SWS. REPLACEMDir VALVE IIAS A IIIGIER PRESSURE DROP 11IAN T1E ORIGINAL.
4678 MODIFICA110N MOD 94-099: RELOCATED VARIOUS COMMUNICATION EQUIPMDir 8-Apr-92 WTTIIIN TlIE CONTROL ROOM DUE TO REMOVAL OF SAS PANEL.
4679 MODIFICAllON MOD 85-007: PROVIDES ALTERNATE BORON INJECTION VIA CRD SYSTEM. 27-Feb-92 4683 MOD &1 CATION MOD 85-057; CllANGES POWER SUPPIlES TO 2711-10! A & B AND 76-CP-136 9-Mar-92 FROM 71 ACUPS-2 AND 71 ACA2 TO 71 ACA2 AND 71 ACB4 RESPEC11VELY.
4690 MODIFICATION MOD 85-102: PROVIDES IlYDROGEN ADDITION TO TIE CONDENSATE 4-Oct-91 l SYSTEM TO REDUCE IGSCC.
4699 MODIFICA110N MOD 87-014: CIIANGES TlE REFLRENCE IEG SENSING LINES FOR WIDE 8-Apr-92 RANGE AND FUEL ZONE IIVEL INSTRUMENIS AND CIIANGES IUEL l ZONE RANGE. l 4700 MOD &lCAllON MOD 87-018: PROVIDES T1E ABilIIY TO BACKFFID NSS TRANSFORMER T 22-Jul-91 4 FROM 345KV SYSTEM.
4702 MODIFICA110N MOD 87-043: CllANGES RWR MG OLTTER SPEED CONTROL LOOPS FROM 26-Sep-91 l CIDSED TO OPEN LOOPS. TlE MOD WILL PROVIDE FINER CONTROL AND i REDUCE POTEN11AL FOR POWER SPIKES. '
4703 MODIFICA110N MOD 87-044:PROVIDES FOR ESW TOTAL FLOW INDICATION VIA EPIC. 23-Oct-91 4705 MOD &1 CATION MOD 87-046: PROVIDES FLOW RATE IN TIE STACK VIA EPIC. 29-Oct-91 4714 MODIFICAllON MOD 87-141: REPLACES FOUR llGRAPil 100 RECORDERS WrDI FOUR 9-Mar-92 llGRAPH 200 RECORDERS (EMRP PANF1).
4725 MODIFICAllON MOD 85-032 ADDED RDdOTE TERMINAIS FOR MMRAS COMPUTER 8-Apr-92 CAPABIllTY IN CONTROL ROOM.
Page 22
NEW YORK POWER AIRIlORITY JAMES A. ITTZPATRICK NUCLEAP, POWER PLANT PLANT REFTRENCED SIMULATION FACILITY
% FOUR YEAR PERFORMANCE TESTING REPORT (MODIFICATIONS TESTED) 4727 MODIFICATION MOD 86-115:IS USED TO UPGRADE \'ARIOUS COmROL ROOM AND RELAY 10-Feb92 ROOM RECORDERS.
4729 MOD &lCATION MOD 87-061: INCORPORATES VARIOUS CONTROL ROOM DESIGN REVEW 16-Fe494 ClIANGES AS A RESULT OF IIUMAN FACTORS EVALUATION.
4730 MODIFICAllON MOD 87-134: REPLACES IIPCI CIIECK VALVES. 17-Jun-91 4906 MODIFICATION MOD 86-115: REPLACES VARIOUS EXISTING RECORDERS IN ComROL 3-Oct-91 AND REIAY ROOM Wmi TRACOR-WESlRONIC DDRIO MODELS.
DUPLICATE OF DRf 4727 4915 MODIFICATION MOD 87-134: REPLACES IIPCI VALVES 23fiPI-I1,12,65 Wmi A NEW TYPE. 17-Jun-91 4919 MOD &lCATION MOD 88448: INSTALLS 11E ZlNC INSERllON (GEZIP) SYSTEM. I3-Apr-92 4928 MODIFICATION MOD 88-136: Cl!ANGES POWER SUPPLY FOR EMERGENCY DAMPER 28-Fe492 POSmON INDICATORS 66PNS-100A,B.
4929 MODIFICATION MOD 88-161: CilANGES 11E ALARM SETPONT FOR TIE BATTERY ROOM 5-May-92 VENTILATION 72TS-122A,B FROM 45 TO 60 DEGREES F.
4933 MODIFICAllON MOD 88-194: REPLACES EXIS11NG PRESSURE SWITCII 93PS-10B Wm1 A 18-Nov-91 NEW TYPE.
5087 MOD &lCAllON MOD 88-050: SUPPORTS llE ACTl\TITES REQUIRED FOR REMOVAL OF 8-Feb93 GEPAC 5226 MOD &lCATION MOD 85-036:(SUPERCEDES MOD F1-78442). REMOVES 11IE SCR 14-Apr-92 CONTROLLER FOR T1E SBGTIIEATERS AND ALTERS T1IE CONTROL CIRCUIT.
5227 MODIFICAllON MOD 86-003B: INCREASES T1E FIRE PROTECTION SYSTEM CAPABILITY 23-Jun-92 l
FOR NEW JAF FACILMES 5228 l MODIFICATION MOD 86494: PROVIDES A CROSS CONNECTION FOR INJECTING WATER 4-Sep-92 NIO 11E RPV USING TIE DESEL FIRE PUMP (76P-1),111RU RIIRSW l REMOVABLE CONNECTION. !
5229 MOD &lCAllON MOD 87450; ALTERS 11E 11ERMOCOUPLE PENETRAllONS FOR T1E RX 14-Apr-92 LEAD TO ALLOW EASIER (DIS) ASSEMBLY FOR FLOOD UP DURING REFUEllNG.
5230 MODIFICAllON MOD 87-105: REPIACES 02-3LIS-101B & D Wml A NARROW RANGE PJC 5-May-92 WATER LEVEL INSTRUMENT.
5233 MODIFICAllON MOD 88-196: CllANGI3 TlIE AUTO CONTROL SETPONTS ON T1E EDG DAY 19-Sep-91 TANK LEVEL SWITCilES.
5282 MODIFICATION MOD 86 001: ANNUN 09-4(2-15) CLNUP PMP 12P-1 A OR IB FLOW LOW IS IN 12-Jul-91 AIARM DURING NORMAL OPERAllON.
Page 23 I
NEW YORK M)WER ALTrilORITY JAMES A. FITZPATRICK NUCLEAR FOWER PI/J4T PLANT REFERD4CED SIMULATION FACILITY (N FOUR YEAR PERFORMANCE TESTING REPORT d (MOD &lCAT10NS TESTED)
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5464 MOD &7 CATION MOD 83-058: INSTALLS T1E MMRAS COMPUTER SYS11M i 1-Oct-91 5465 MODIFICA110N MOD 85-011: REPIACES T1E PLANT 24VDC INSTRUMDir BATTERY. 16-Mar-92 5466 MOD &lCAT10N MOD 85-054:INSTAILS TIE ARI UPGRADE AND RECIRC PUMP TRIP ATWS 5-May-92 LOGIC.
5467 MODIFICA110N MOD 85459: CIIANGES 11E RECOMBINER ISOLAT10N LOGIC. 8-Apr-92 5468 MODIFICA110N MOD 86-011: REPLACES 11IE DRYWELL VENT 11AT10N FAN MOTORS. 16-Apr-92 5469 MODIFICATION MOD 86-094:PROVIDES FOR A FIRE PROTEC110N TO RIIRSW CROSS-TIE 3-Oct-91 !
CONNEC110N. DUPLICATE OF DR8 5228 5470 MODIFICA110N MOD 87-002: REPIACES T1E MAIN TURBINE Tr LP ROTOR WTI11 A NEW 29-Oct-91 DESIGN.
5471 MODIFICATION MOD 87-164: INSTAILS NEW SENSING LOCATION AND ALARM POIN13 FOR 23-Jun-92 l DW INSTRUMENT NI1ROGEN SUPPLY.
5472 MOD &lCAT10N MOD 88-080: REPLACES 11E MAIN TURBINE 'N LP ROTOR WTDI A NEW 29 Oct-91 DESIGN.
5473 MOD &lCA' HON MOD 88-086: DISABLES 11E RSCS ROD BLOCK. 22 Jul-91 5475 MOD &lCAT10N MOD 88-253: UPGRADES 11IE 1RAVERSING INCORE PROBE SYSTEM (11P) 20-Nov-91 TO A NEW DESIGN.
5476 MODIFICA110N MOD 89-029: ClIANGES 11E EDG OVERSPEED TRIP SETTOINT 30Sep-91 5477 MOD &lCA110N MOD 89-036: CliANGES 11E CONTROL CIRCUIT FOR T1E EDG GOVERNOR 26-Feh92 SIIUTDOWN SOLENOID. !
O 5478 MOD &1 CATION MOD 89 094: REMOVES Tim RCIC AND lilX'l LEAK DETEC110N TIMERS 21-Feb92 l
AND RE-ARRANGES TIE INDICATING I AMIS ;
I Page 24
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NEW YORK FOWER AlfrilORITY JAMES A. FIT 73'ATRICK NtX' LEAR POWER PLANT PLANT REFERENCED SIMULATION FACILTrY FOUR YEAR PERFORMANCE TESTING REPORT p)
( (MODIFICAllONS TESTED) l 5479 MODIFICAllON MOD 89-096: CIIANGES TIE LMERGENCY BUS SECOND LEVEL 14-Nov-91 UNDERVOLTAGE RFLAY SEllOINT3.
5480 MODMCAT10N MOD 89-129: CIIANGES DE OPERATING SYSTEM SUPPLY FOR DE RBC 5-May-92 ISOLADON VALVES FROM INST. AIR TO NITROGEN.
5481 MOD &lCAllON MOD 89-170. CilANGES U E SEllOINT FOR 23DI'T-76 AND 77. 18-May-92 l
l i
5937 MOD &lCAT10N MOD 87-084: ADDS ADDIllONAL LOAD TO 600VAC SYSTEM - TURB BLDG 7-Apr-92 MACIIINE SIIOP.
5939 MOD &lCATION MOD 86-084- REPLACES TlE MSR DRAIN TANK VLVS WITII A NEW TYPE. 13-Apr-92 5940 MODIFICAllON MOD 88422: REMOVES IlE MN STM LINE LOW PRESS BYPASS SWTTCIES 5-May-92 02-3PS-51 A-->D(RX PRESS <1005 PSIG).
6004 MODIFICATION MOD 87-040. REMOVES IlE SEAL-IN FUNCTION OF 34MOV-102NB 10-Jun-91 O 6005 MODIFICAllON MOD 87-087: CllANGES TIE SEDOINT OF 70TS-109ND AND 70T3-110A/B FROM 104 TO 98 DEGREES F.
14-Apr-92 6006 MODIFICADON MOD 88-044: REDUCES 11E ROW CAPACITY OF 33FCV-133 BY REPLACING 18-May-92 UIE VALVE TRIM. (VALVE WAS ORIGINALLY 34FCV-136 6007 MODIFICADON MOD 89-157: CllANGES T1E RGSC IDLE VOLTAGE FROM -1.0 VDC TO 5-May-92 BE1TVEEN -4.010 -5.0 VDC AND ADDS IIYDRAUIJC BYPASS 6008 MODIFICAllON MOD 89-122: CilANGES TIE SETlOINT ON T1E SLC TANK LEVEL 18-May-92 TRANSMIT 1ER, ilLT-45 6009 MODIFICADON MOD 90437: CilANGES TTE 27PT-117 LOW PRESSURE SETPOINT 5-May-92 6077 MODIFICAllON MOD 90-026: FULL ARC 10 PARTIAL ARC CONVERSION OF T1E MAIN 22-Dec-92 TURBINE 6339 MODIFICATION MOD 91-156: REP 1 ACES UE CONIROL SWTTCll FOR 10MOV-12A & B WTili 29-Jun-92 A NEW TYPE.
6415 MODIFICATION MOD 91-067: REPIACEMENT OF TlIE FEEDWATER CORIROL FLOW 23-Jun-92 INTEGRATOR AND DE DRYWELL EQUIPMENT FLOW INTEGRATORS.
6416 MODE 1CADON MOD 90-227: ALTER A1 ARM 9-7(l-27) TO BE *OFF" INSTEAD OF 4-Sep.92 CORIINUOUSLY *ON".
6538 MODIllCATION MOD 89-141: TO REPLACE VARIOUS CONTROL ROOM RECORDERS 29-Sep-93 Page 25
NEW YORK POWER ALTrilORITY JAMES A. FITZPATRICK NUCLEAR POWER PIANT PIANT REl'ERENCED SIMULATION FACILITY FOUR YEAR PERFORMANCE TESTING REPORT O (MODIFICA110NS TESTED)
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SETI'OINT CIlANGE l
4 6613 MOD &lCAllON MOD 89-140: REPLACE MENSOR INSTRUMENT- AFTECTS 16DPR-200 AND 6-Aug-93 i EPlc POINIE 6614 MOD &lCABON MOD 90-002: OFFGAS DRYING TOWERS & CUT AND CAP IT RECOMBINER. 22-Jun O 6615 MOD &lCADON MOD 90-010: REPIACES IIPCI EGR ACRJATOR MODEL 9903-026 WITli MODEL 9903-099 21-Dec-92 '
6616 MODIFICADON MOD 90-138: FEEDWATER DISCilARGE VALVE 34MOV-100A/B REPLACED 7-May-93 WITII KEYLOCK SWITCIIES 6617 MODIFICADON MOD 90-195: CIIANGE 02SOV-39/40 TO 02AOV-39/40 8-Feb93 6618 MODIF1 CAT 10N MOD 90-197: REPLACE 13MOV-16 7-Jun-93 l
6619 MODIFICAllON MOD 90-212: REPLACE DEC VAX 6430 (EPIC UIURADE) 27-Jul-94 6620 MODIFICADON MOD 90-232: CIRC WATER TRAVELING SCREENS SETPOINT CHANGE 7-Jun-93 l l
l 6621 MODIFICADON MOD 90-234: STROKE TIME CIIANGE FOR VALVE 10MOV-57 7-Jun-93 6622 MOD &7 CATION MOD 90-237: 36P-1 A/B/C CIRC WATER PUMPS - FLOW TEST PERFORMED TO 7-Jun-93 GENERATE PUMP CURVES. USE CURVES TO VALIDATE SIMUIATOR MODEL.
6623 MODIFICADON MOD 90-238: 3-D MONICORE INSTALIADON 18-Jan-94 6624 MODIllCATION MOD 91-081: TORUS TEMPERATURE 16-11R-131 A/B SE110lNT ClIANGE 30-Apr-93 Page 26
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/ 6632 MODIFICAllON MOD 91-269: 76-E-7 REPLACEMENT CO2 VAPORIZER FOR TIIE MAIN 30-Apr-93 GENERATOR ,
6633 MODIFICAllON MOD 91-305: LPCI UPS MAINTENANCE KEYLOCK SWIICII 18-Jan-94 6634 MODalCAllON MOD 340. SWAP FROM INSTRUMINF AIR TO INSTRUMENT N2 FOR 14-Jul-93 27AOV-101A/B !
6635 MOD &1 CATION MOD 068: REROUTE EDG JACKET COOLER RElVRN LINE 3-Aug-93 6636 MODIFICAllON MOD 069: UPGRADE CST LEVEL INSTRUMENT POWER SUPPLY 16-Mar-93 6637 MODIFICAllON MOD-92 091:IIEAD SPRAY REMOVAL 26-Mar-93 6638 MODIFICA110N MOD-92-109. INSTALL FIRE SUPPRESSION SYSTEM FOR EAST AND WEST Il-May-94 !
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6639 MODIFICAllON MOD 92-111: ISOLATE RIIR VALVES FOR RX BLIX)(APPENDIX R) 16-Jun-93 6640 MODR'ICAllON MOD 92-120. INSTALL NEW SDIV IEST SWrfCIIES 7-Jun-93 O _ 664i MODIFICA110N MOD 92-132: INTAKE STRUCTURE IIEATER 16-Mar-93 Page 27
NEW YORK POWER AIRif0RITY JAMES A. ITIZPATRICK NUCLFAR POWTR PLAfR PLAtG REFERENCED SIMULATION FACILITY FOUR YE 4R PERFORMANCE TESTING REPORT (MOD &lCAllONS TESTED)
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$1 6642 MOD &lCAllON MOD 92-149: VER&lCATION OF STROKE TIMES FOR 10MOV-26ND 30-Apr-93 6643 31-Mar-93 MODIFICAllON MOD 92-166: ISOLATE !!PCI VALVES FOR RX BLDG (APPENDIX R) 6644 MOD &lCATION MOD 92-173: RCIC CONTROL CIRCUTIRY FB WPO (APPENDDC R) 31-Mar-93 6645 MOD &lCAllON MOD 92-184: 02R111121 Sim'OINT CIIANGE 30-Apr-93 6646 MOD &lCATION MOD 92-207: Sir ACC111ATOR II ACC-7NB REMOVAL 7-Jun-93 i
l 6647 2-Jul-93 MODIFICA110N MOD 92-214:IIPCI/RCIC TORUS SUC110N VALVES (APPENDIX R) 6648 MODIFICAllON MOD 92-257: INSURE AVAILABILITY OF 71MCC-261 FOR A FIRE WmIIN 30-Apr-93 111E RX BLDO 6649 MOD &lCATION MOD 92-273: REMOVAL OF ENCLOSURES FOR 71-INV-3A/B FOR LPCI 6-Aug-93 J INVERTORS L15 AND Ll6 6650 MODIFICAllON MOD 92-282: REWIRING OF AIARM RELAY FOR ANNUNCIATORS 30-Apr-93 6659 MODalCADON MOD 904)06: REMOVAL OF 12MOV-80 8-Feb-93 6707 MODIFICATION MOD 90-242: CilANGE TIE SOV DESIGN FOR VARIOUS CAD SYSTEM 30-Nov-93 VALVES.
6709 MODIFICATION MOD 92-194: CilANGE T1E EDO GOVERNOR CONTROL POWER SUPPLY. 20-Sep-93 6710 MODIFICATION MOD 91-138: PROVIDES A HOT WATER IEATING BOILER REPLACEMENT 18Jan-94 FOR T1TE OLD STEAM BOILER.
-6 71I MODIFICATION MOD 92-271: REMOVES ANN 9-7(3-45)
4 6712 MODIFICAllON MOD 92-334: DISABLES OPERAllON OF VALVES: 10MOV-36B,70A,708, 9-Nov-93 15MOV-101,102,103 BY PERMITTING OPERAllON WIT 11 T11E MOV BREAKERS OPEN. '
6713 MODIFICADON MOD 92-331: ClIANGES TIE IIVAC SYSTEM OPERATION FOR 11IE NSW, 30-Nov-93
[3W, RIIRSW, W.DFP ROOMS 6714 MOD &lCAllON MOD 92-379. CilANGE I1E ACTUATOR FOR 10MOV-39A 8-Dec-93 Page 28
l NEW YORK IOWER AUTllORITY JAMES A, FTIZPATRICK NUCLEAR IO%T.R PIANT PLANT RFIERENCED SIMULATION FACILIIT FOUR YEAR PERFORMANCE TESTING REPORT ,
(MODIFICA110NS TESTED) I g g 6715 MODIFICATION MOD 92-294: ADDS A IIEADPIIONE JACK TO 11E CONIROL ROOM TO i
I8-Jan-94 SUPPORT SIIU1DOWN COMMUNICAllONS.
6716 MOD &lCA110N MOD 92-370: CilANGES TiiE ESW FILTER DP SWITCil & ALARM SETTOINT. 30-Nov-93 6804 MODIFICATION MOD 90-190: MCC CUBICLE BUCKET AND BRFAKER RI1OCAllON OF 2-Dec-93 71MCC-253-0B4, OB5. REQUIRES CIIANGE IN PROCEDURE TO SWAP BKR OB4 & OBS LOADS. TEST PROCEDURE CIIANGE ONLY.
6805 6-Aug-93 MODIFICAllON MOD 91-11: REGEARING OF 10MOV-38A & B 1D REDUCE VALVE 11ME.
STROKE l 6806 MODIFICATION MOD 92-306: RX BLDO IN/OUT DIFF PRESS TRANSIETR REPLACEMENT 3-Aug-93 NEW1RANSMTTIER IS SMALIIR.
6807 MODIFICATION MOD 92-323: COOLING WATER PUMP PRESS SWITCil SETPOINT Cl!ANGE 24-May-94 FOR PRFSSURE SWTTCIES 94PS-60 A/B (LOW COOUNO WATER PUMP DISCIIARGE PRESSURE PUMP START) 6808 3-Aug-93 MODIFICAllON MOD 92-387: 3-IIR FIRE BARRIER @ 76FDR-A-272-K I
p 6809 MODIFICADON MOD 92-390: WR# 098980 FIRE PROTECTION CONTROL UNTT COMPONENT 3-Aug-93 v REPLACEMENT. 24V BATTERY SUPPLY TO SYSTEM TROLT1LE/ BATTERY 1ROUBIE CIIANGED FROM 6 amp-hr TO 7 amp-hr RATING.
6810 MODIFICAllON MOD 88-244:EDO FUEL OIL SUPPLY SIIUTOFF. REVISE ASSOCIATED 13-Jan-94 l
ANUNCIATORS AND EPIC POINTS.
6811 MODIFICAllON MOD 90-158: REPLACEMENT OF PRESSURE SWITCIES 76PS-100 & 102. 6-Aug-93 VERIFY SETTOIN13.
6812 MODIFICAllON MOD 92-246: INCREASE SETTOINT OF 01 107FS-10811 FLOW SWilril TO 50 3-Aug-93 SCFM (RECOMBINER IUGH FLOW).
I 6813 MODIFICAllON MOD 92-292: CALIBRATE SET IOINT CilANGE FOR OFF-GAS III & LO FIDW 6-Aug-93 l STEAM FIDW INSTRUMD(T T1IIS Cl!ANGES T1E FIDW SWITCil ALARM
& TRIP SETPOINI3 6814 MODIFICATION MOD 93-009: REPLACE 31MOV-RSSV2, NEW VALVE STROKE IS 9.375" 6-Aug-93 COMPARED TO 10.75', VALVE WILL CLOSE AGAINST A 1250 psid.
POSSIBLE STROKE TIME CIIANGES.
6815 MODIFICATION MOD 934120: PRIMARY CONTAIN N2 SOV REPLACEMD(T 1111S ISOLATES 3' Aug-93 I N2 SUPPLY TO EACH OF T1E *A' DW COOLING ASSEMBLY INLET DAMPERS I
& OPENS T1E DAMPERS.
6916 MODIFICATION MOD 87-099: REPLACED RWR LOOP FIDW TRANSMrrlERS AND REDUCED 8-Aug-94 SPAN OF INST.
l 6917 I MODIFICATION MOD 93-141: CllANGES 11IE CONTROL ROOM VENI1LABON OPERA 110N. 28-Mar-94 6918 MODIFICATION MOD-93-075: ADDS A BACKFILL SYS11N TO T1E INSTALLED REACTOR 6-Apr-94 WATER IEVEL REFERENCE LEGS Page 29
MEW YORK POWER ALTTI1ORITY JAMES A. ITrZPATRICK NUCLEAR POWER PLANT PLANT REFERENCED SIMULATION FACILTTY FOUR YEAR PERFORMANCE TESTING REPORT (MOD &lCATIONS TESTED)
! e $7piw a ,, y f' R(
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3 69!9 MODIFICA110N MOD-92-187: ADDS SCREENWELL LEVELINDICA110N TO EPIC WII11 28-Mar-94 AIARM 7
7090 MOD &lCA110N MOD-89-159; CilANGE POWER TO RCIC EXIIAUST FAN. 8-Nov-94 7092 MOD &lCA110N MOD-94470: INSTALLATION OF PADIDCK DEVICE FOR 34MOV-100A & B 25-Aug-94 SWITCIIF3.
7093 MOD &lCAT10N MOD-94460; ISOLATE REDOILER STM SUPILY 31E-l TO WASTE 8-Dec-94 CONCENTRATOR 20EV-64BA.
7095 MOD &lCA110N MOD-93-129. INIt.KIDCK 12PS-108 ANN. SIGNAL %TITI 12MOV-56 & 57 31-Oct-94 POSITION.
7096 MODIFICAT10N MOD-92-405: CONIROL ROOM IIVAC AIR SUCTION REALIGNMINT 31-Oct-94 7098 MOD &lCA110N MOD-91-217; CALIBRA110N TOLERANCE INCREASE FOR SDIV LEVEL 31-Oct-94 TRANSMrl'113tS. ,
7099 O MODIFICATION MOD-94426: 12FE-126A & B ORi1CE PLATE SUBSITIVFION. 15-Sep-94 i
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Page 30
. f 3) NEW YORK POWER AUTHORITY ,
JAMES A. FITZPATRICK NUCLEAR POWER PLANT i SIMULATOR PROCEDURES SIMULATOR TEST PROGRAM i STP-3 REVISION 3 !
SUBMITTED: A d -
DATE: E!zJ F Siqulat ato( Specialist ' ,
REVIEWED:
Simulat$r Supervisor DATE: 2/23/ff APPROVED:
M DATE: M aining Manager
O EFFECTIVE DATE: February 28, 1995 f r
FIRST ISSUE D FULL REVISION B LIMITED REVISION O i
- CONTINUOUS USE *
- NTSR *
- I TECHNICAL *
- i a
E I
l PERIODIC REVIEW DUE DATE 1996
b
, i SIMULATOR TEST PROGRAM STP-3 l- ("T
'() !
REVISION SUBOULRY SHEET f
EgV. NO. REASON FOR CHANGE 3 1. Incorporate latest review of Operations Surveillance Test Procedures Index for '
applicability to the Simulator: Appendix B 3 2. Incorporate latest review of Malfunctions: '
Appendix E 3 3. Revised responsibilities and wording on Step 8.1.1 and 8.1.2 2 1. Biennial Review Incorporating AP-02.01 Requirements 2 2. Combine the requirements of STP-3 " Simulator Test Program" and STP-6 " Performance Test Plan". STP-6 was written to support the initial certification effort and is no longer necessary.
STP-6 will be deleted following approval of this procedure.
- 2 3. Revised titles on various Normal Operations tests (Appendix B), various Transient tests (Appendix D and Figure 1), and various Malfunction tests 3 (Appendix E).
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SIMULATOR TEST PROGRAM STP-3
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1.0 PURPOSE ................................................. 4 i 2.0 SCOPE ................................................... 4 l 3.0 DEFINITIONS ............................................. 4 4.0 DISCUSSION .............................................. 6 5.0 RESPONSIBILITY .......................................... 6 5.1 Training Manager ................................... 6 5.2 Simulator Supervisor................................ 7 5.3 Simulator Test Opcrator ............................ 7 -
5.4 Operations and Training Staff ...................... 7 5.5 Simulator Modification Review Committee ............ 7
6.0 REFERENCES
.............................................. 8 6.1 ANSI /ANS 3.5, 1985 ................................. 8 6.2 Regulatory Guide 1.149, Revision 1, April 1987...... 8 6.3 STP-1, Simulator Configuration Management
() 6.4 Procedure ..........................................
AP02.01, Control of Plant Procedures ...............
8 8
7.0 PROCEDURE ............................................... 8 [
7.1 General ............................................ 8 7.2 Types of Tests ................................ 9 7.3 Procedure ..................................... .... .... 10 8.0 EVALUATION .............................................. 11 8.1 Method ............................................. 11 8.2 Criteria ........................................... 12 FIGURE 1 - Transient Test Determination..................... 16 APPENDIX A - Computer Real Time Testing ...................... 17 APPENDIX B - Normal Operations Testing ....................... 18 APPENDIX C - Steady State Operations Testin .................
APPENDIX D - Transient Testing ............g...................
23 24 APPENDIX E - Malfunctions Testing ............................ 25 Rev. No. 3 Page 3 of 43
t SINULATOR TEST-PROGRAM STP-3 l
1.0 PURPOSE '
1.1 To describe the administrative requirements regarding performance testing. '
1.2 To describe the testing to be conducted to ensure the ;
JAFNPP plant referenced simulator meets the NRC ;
certification criteria.
1.3 To describe the method for documentation, evaluation, and !
validation of the performance testing. '
1.4 To establish a test program that evaluates simulator model completeness and' integration, as well as, steady state and transient performance.
j 1.5 To ensure that testing will address any simulator design change.which results in significant configuration or performance variations. -
t 2.0 SCOPE The New York Power Authority owns and operates the plant
'(]) specific simulator referenced to the James A. FitzPatrick i Nuclear Power Plant. This simulator Test Program is formatted to. satisfy the requirements of ANSI ANS 3.5, 1985 and endorsed i' by the NRC Regulatory Guide 1.149.
3.0 DEFINITIONS 3.1 Annual Testing '
r Includes, but is not limited to, ANSI /ANS-3.5-1985, Appendix B. '
3.2 Backtrack !
Restoration of the simulator to a previous set of l conditions that have been automatically recorded at designated time intervals. .
l 3.3 Best Estimate The value or significance of a parameter determined to be acceptable for the purpose of this performance testing.
This determination to be made by the Simulator Review- l Committee, based upon engineering evaluation or operational assessment.
Rev. No. _ 3 Page 4 of 43 l
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.. SIMUIATOR TEST PROGRAM- STP-3 !
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3.4 Critical Parameters t i
- 1) Those parameters that require direct and continuous-observation to operate the power plant under manual control.
- 2) Input parameters to plant'safoty systems. ,
3.5 Preeze A condition whereby the dynamic simulation is interrupted {
and remains static until the simulator is taken out of-the +
" freeze" mode, at which time dynamic simulation resumes. '
3.6 Initialization Condition I,
A set of data that represents the status of the referenced plant from which real time simulation can begin.
3.7 Malfont. tion Testing i b
Includes, but is not limited to, all ANSI /ANS-3.5, 1985 !
malfunctions performed at 25 per cent per year. j i
O 38 aodiria tioa
- tias Test performan=e for verification following modification ))
(see Simulation Configuration Management Procedure No. t STP-1).
] :
3.9 Performance Test i
Used to demonstrate compliance with'the documentation !
requirements of ANSI /ANS 3.5, 1985, Section 4.0 Performance !
Criteria.
3.10 Real Time Simulation of dynamic performance in the same time base relationships, sequences, durations, rates and !
accelerations as the dynamic performance of the reference l plant. t i
3.11 Reference Plant i
The specific. nuclear power plant from which the siJRulator control room configuration, system control arrangement and simulator design data is derived.
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- SIMULATOR TEST PROGRAM- t STP-3 3.12 Shall, Should and May i
\
The word "shall" is used to denote a requirement; the word j "should" to denote a recommendation; and the word "may" to denote a permission, neither a requirement nor a i i
recommendation. >
3.13 Snapshot n i
1 The instantaneous storage of existing conditions at any !
selected point in time. The stored condition then becomes a temporary initialization point-and may be called up :
repeatedly. i 3.14 Testing Cycle i Malfunction testing has been split'up into a 4 year cycle. !
This allows for, but not limited to, the testing of i approximately % of the malfunctions each year. !
I 4.0 DISCUSSION b t
r The purpose of simulator certification is to ensure that the. i
() simulator possesses a sufficient degree of accuracy and completeness to train safe and efficient-operators. In I
addition, simulator certification supports initial and requalification operator examinations. 10CFR Paragraph 55.45(b) requires that candidates for operator or senior operator !
licenses be examined, in part, on a certified simulator. i Replatory Guide 1.149 endorses ANS-3.5 - 1985 as a means by- ;
which a simulator may be certified. Based on these documents, i this procedure specifies the requirements by which the JAFNPP !
simulator certification is maintained. t I
t 5.0 RESPONSIBILITIES t
5.1 Trainino Man =aer !
i The Training Manager or designated alternate is responsible !
for insuringsthat the Simulator configuration Management is I implemented and maintained in accordance with this f procedure and references.
Rev. No. 3 Page 6 of 43 f
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' SIMULATOR TEST PROGRAM STP-3 5.2 Simulator Supervisor The Simulator Supervisor or designated alternate will be !
responsible for the coordination and integration of the i overall configuration management for the JAFNPP plant simulator. Responsibilities relative to the Simulator Test i Program include the following:
scheduling of simulator usage for testing authorizing and determining the validity of testing l selection of testing to verify a completed plant r modification on the simulator '
provide Quality Control of all simulator testing i through a review of all simulator test results j presenting the applicable test results to the !
Simulator approval Modification Review Committee (SMRC) for !
5.3 Simulator Operation Specialist f
5.3.1 Maintains and updates the simulator Initial Condition's (IC's) L 5.3.2 Prepares and performs the simulator testing i O vroer - i 5.3.3 Conducts the annual ANSI /ANS 3.5 - 1985 testing [
5.3.4 Maintains and updates the simulator CMS database 5.3.5 Provides a monthly suunnary report of the !
simulator test program to the simulator Supervisor 1
5.4 Operations and Trainino Staff 5.4.1 Provide assistance in conduct of the simulator !
test program when authorized to do so, by the '
Simulator Supervisor and/or Training Manager. i 5.4.2 Provide subject matter expert review for validation of completed simulator tests as ;
assigned by Training / Operation supervision.
5.5 Simulator Modification Review Connaittee (SMRC) 5.5.1 The SMRC membership and requirements are specified in Reference 6.3.
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5.5.2 The SMRC reviews all simulator performance test f procedures prior to their use in the simulator. l 5.5.3 The SMRC determines the acceptability and validity of the simulator Steady State and Transient Testing.
L i
6.0 REFERENCES
6.1 ANSI /ANS 3.5, 1985 '
6.2 Regulatory Guide 1.149, Revision 1, April 1987 6.3 Simulator Configuration Management Procedure, STP-1 '
6.4 AP02.01, Control of plant procedures 7.0 PROCEDURE
[
7.1 General '
7.1.1 Testing will be conducted in accordance with procedures as described in Section 7.3.
7.1.2 Testing shall be conducted using only the current O revision of an approved test and/or plant procedure. ,
4 7.1.3 The simulator performance shall be evaluated as described in Section 8.0.
7.1.4 Differences between the simulator test procedure '
used and the equivalent plant procedure shall be noted, if applicable.
7.1.5 Exceptions - Any problems encountered during the performance of testing shall be identified sequentially and added to the exceptions page for that test. (i.e., the first error would be exception #1, the next, #2, etc.) Types of exceptions may be test procedure errors, plant procedure non-compliance, functional fidelity, '
physical fidelity, etc. Any exception that requires a Deficiency Report (DR) shall have the ,
applicable DR number listed with the exception.
7.1.6 Discrepancies noted as a result of testing shall be documented on a Discrepancy Report (DR) form and corrective action taken as per Simulator Configuration Management Procedure No. STP-1.
7.1.7 Data collected and documented results shall be maintained for the life of the simulator.
Rev. No. 3 Page 8 of 43
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SIMUIATOR TEST PROGRAM STP-3 LO 7.2 Types of Tests '
7.2.1 Computer Real Time Testing The purpose of this testing is to. ensure that the simulator is running in real time.
The tests to be performed are listed in Appendix A.
7.2.2 Normal Operations Testing The purpose of this testing is to determine.the ability to operate the simulator in accordance with approved JAFNPP procedures under normal conditions.
The tests to be performed are given in Appendix l B.
7.2.3 Steady-State Operations Testing The purpose of this testing.is to demonstrate simulator Steady State Performance and stability
() by establishing steady-state conditions and monitoring parameter variations with respect to time.
s The tests to be performed are given in Appendix C and shall be completed annually, on a date 125%,
based on the date of last completion.
l 7.2.4 Transient Testing !
The purpose of this testing is to ensure that simulator performance is consistent with,the reference plant, in areas where: 1) actual plant response is documented and available 2) compare simulator response to "best estimate" results for transients where design data or plant response data is unavailable.
Transients included in this testing are those given in Appendix Bl.2 to ANSI /ANS 3.5-1985.
The tests to be performed are given in Appendix D and shall be completed annually, on a date 125%,
based on the date of last completion.
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JSINULATOR TEST PROGRAM STP-3
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7.2.5 Malfunctions Testing !
l The purpose _of this test is to ensure that the ,
simulator is capable of performing the j
?
malfunctions listed in ANSI /ANS 3.5, 1985, Appendix A, as well as others. i N
Malfunction testing as outlined by Appendix E of i this procedure, shall be completed once every i four years as a minijuum. Those items designated for completion during a specific year in the four year cycle, shall be performed on a date 1254, ;
based on the date of last completion. ,
7.2.6 Modification Testing l This testing is used to ensure the simulator will accurately model the physical and functional !
fidelity of the reference plant following the .
installation of applicable plant modifications. i The tests to be performed are to be selected by {
the Simulator Supervisor, in accordance with the !
Simulation Configuration Management' Procedure,
() STP-1. The intent of the testing is to verify overall simulator model completeness and i
{
integration. !
7.3 Procedure !
L 7.3.1 Simulator performance test (s) shall be written 5 using reference 6.4 as'a guide, l 7.3.2 Upon completion of a test, the following will be )
assembled for submittal to the Simulator i Supervisor: (
- a. Completed test procedure. l
- b. Completed plant procedures, if applicable (e.g.
Surveillance Tests).
- c. All data sets required as part of the test performance.
- d. A copy of any DR(s) written as a result of test performance. l 7.3.3 Testing will be scheduled by the Simulator Supervisor, including any re-tests required as a result of the simulator performance evaluation.
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7.3.4 In addition to the above requirements, where ~I r applicable, each test will contain the following: '
.. . 1
- a. Type of test- ;
- b. A cause for.a malfunction, transient,'etc.,. !
if applicable. '
- c. Instructor Station requirements.
- d. ' EPIC requirements !
- e. Initial Condition required i f.. Simulation of any' required auxiliary ,
operation functions-(remote functions) ;
'g. Insertion of malfunctions including rates, ,,
delays, etc. j
- h. Data collection-points, duration,.etc. l
- 1. Annunciators expected ;
- j. Automatic actions expected .
- k. Responses to any required control' functions i
- 1. Operator actions required.
i 8.0 EVALUATION l l
This section specifies the method and criteria to be used for- l
(]j evaluation of the simulator Performance Test results. l 8.1 Method 8.1.1 The simulator Supervisor or designee will j evaluate all completed simulator performance ,
tests. l !
8.1.2 The simulator Supervisor will review and approve !
all completed Simulator performance tests. l 1
8.1.3 Any tests that are evaluated as UNSAT will be i rescheduled and Discrepancy Report (s) initiated l for resolution. ji 8.1.4 The Simulator Supervisor or designee shall I present completed steady state and transient tests and all supporting data to the Simulator Modification Review Committee (SMRC) for approval.
8.1.5 The Committee (SMRC) shall evaluate the test data against the criteria given in Section 8.2 of._this procedure.
8.1.6 Performance tests deemed satisfactory by the Committee shall be approved for inclusion in appropriate report.
Rev. No. 3~ Page 11 _ of 43-l
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'STP-3 -j
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8.1.7 Performance tests found unsatisfactory by the Committee (SMRC) shall be returned-to the i !
Simulator Supervisor for resolution of the !
unsatisfactory determination.. The Simulator l Supervisor _will ensure that corrective action is l taken and resuhait the performance test for -
review by the Cossaittee.
8.2 Criteria The following criteria will be used in evaluation of'the i simulator performance test results:
8.2.1 Computer Real Time Test (7.2.1)
- a. CPU utilization will not exceed 90%. I 8.2.2 Normal Operation Tests (7.2.2)
- a. Plant Operating Procedure and Surveillance Test Procedure acceptance criteria shall-be i used where applicable.
- b. The observable change in the parameters
() shall correspond in direction to those expected from a best estimate for the simulated transient and do not violate the :
physical laws of nature. ~
- c. The. simulator shall not fail to cause an '
alarm or automatic action if the reference l plant would have caused an alarm or automatic action. i
- d. The simulator shall not cause an alarm or automatic action if the reference plant would not have caused an alarm or automatic ;
action. ';
8.2.3 Steady-State Operations Testing (7.2.3) 1 8.2.3.1 Simulator steady state performance shall be demonstrated at 25%, 75% and 100% of rated i thermal power.
Simulator stability shall be demonstrated 8.2.3.2 I over a 60-minute period at 100% of rated thermal power. !
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SIMULATOR TEST PROGRAM STP-3 O
8.2.3.3 During the stability test the following parameters shall be recorded at one second intervals for at least one (1) hour for the 100% test and 20 minutes for the 25% and 75%
tests
- a. Neutron flux (%)
- b. Core thermal power (4)
- c. Individual Recirculation Loop Flows
- d. Total Core Flow
- e. Reactor Dome Pressure
- f. Reactor Water Level
- g. Total Steam Flow
- h. Total Feedwater Flow
- i. Feedwater Temperature (After Last Stage of Feedwater Heaters)
- j. Control Rod Drive Hydraulic System Flow and Temperature
- k. Reactor Water Cleanup System Inlet and Return Flows
- 1. Reactor Water Cleanup Return Temperature
- m. Secondary Heat Balance Data
() 8.2.3.4 The simulator computed values for stesdy-state, full power operation, with the reference plant control system configuration, shall be stable and not vary more than 12% of the initial values over the testing period.
8.2.3.5 The simulator computed values of critical parameters shall agree within 12% of the l reference plant parameters and any {
deviations shall not detract from training. )
8.2.3.6 The simulator computed values of non-critical parameters pertinent to plant operation, that are included on the simulator control room panels, shall agree within 110% of the reference plant parameters and any deviations shall not detract from training.
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/- i 8.2.4 Transient Testing (7.2.4) !
8.2.4.1 The transient tests will be run from an f initial condition of approximately'1004 l power, steady state xenon and decay heat, '
with no operator follow-up action (unless otherwise noted). i 8.2.4.2 The following parameters will be recorded +
simultaneously versus time at 0.5 second intervals for a period of fifteen (15) '
minutes:
a.
b.
Reactor Power (% Neutron Flux) -
Total Steam Flow
- c. Total Feedwater Flow -
- d. Wide Range Reactor Pressure
- e. Wide Range Reactor. Water Level i
- f. Narrow Range Reactor Water Level ;
(Feedwater Control)
- g. Generator Gross Electrical Power !
- h. Turbine Steam Flow
- 1. Total Core Flow !
- j. Recirculation Loop A Flow O k. Recirculation Loop B Flow '
- l. Calibrated Jet Pump Flow
- m. Fuel Zone Reactor Water Level
- n. Suppression Pool Air Temperature i
- o. Suppression Pool Water Temperature I
- p. Suppression Pool Pressure ;
- q. Drywell Temperature ;
- r. Drywell Pressure i
- s. LPCI Flow i
- t. Core Spray Flow
- u. Total HPCI Flow {
i
- v. Total RCIC Flow ,
8.2.4.3 Transient test responses will be compared to actual' plant response, Analytical or Design data, or results from other similar plants.
Where this data is unavailable, then a best-estimate approach will be utilized.
8.2.4.4 The observable change in the parameters shall correspond in direction to those expected from a best estimate for.the simulated transient and do not violate the physical laws of nature.
O Rev. No. 3 Page 14 of 43 lJ
SIMUIATOR TEST PROGRAM ,
STP-3 OL 8.2.4.5 The simulator shall not fail to cause an alarm or automatic action if the reference plant would have caused an alarm or automatic action.
8.2.4.6' The simulator shall not cause an alarm or automatic action if the reference-plant-would not have caused an alarm or automatic.
action.
8.2.4.7 .The transient test validation data is determined by the matrix given in Figure 1.
8.2.5 Malfunctions Testing (7.2.5)
- a. Plant startup test procedure acceptance criteria shall be used where applicable.
- b. The observable change in the parameters shall correspond in direction to those expected from a best estimate for the simulated transient and do not violate the physical laws of nature.
O-c.
The simulator shall not fail to cause an alarm or automatic action if the reference plant would have caused an alarm or automatic action.
d.. The simulator shall not cause an alarm or automatic action if the reference plant would not have caused an alarm or automatic action.
O Rev. No. 3 Page 15 of 43
SIMULATOR TEST PROGRAM STP-3 TRANSIENT TEST DETERMINATION (FIGURE 1)
ANSI PLANT TEST SECTION FSAR LER S/U TESTING (APP. B) 81-30
- 2) TRIP ALL FEEDWATER Bl.2(2) 14.5.5 84-10
'. UMPS 84-23
- 3) CLOSURE OF ALL MSIV's Bl.2(3) 14.5.2.3 85-17 STR f 25-5
- 4) TRIP OF BOTH RECIRC STR f 30-1.2.1 PUMPS Bl.2(4) 14.5.6.3 STR f 30-1.2.2 STR f 30-6.2.2 77-12 SINGLE RECIRC PUMP TRIP Bl.2(5) 14.5.6.2 77-51 STR f 30-1.2.3 78-45 STR f 30-6.2.1
- 6) MAIN TURBINE TRIP (NO OR SCRAM) Bl.2(6) 14.5.2.2 83-05 83-43 STR f 27-1
- 7) MAX RATE POWER RAMP 77-16 Bl.2(7) 14.5.6.1 77-19 STR f 32-3 14.5.7.1 85-18 STR i 32-4 87-18
- 9) MAIN STEAM LINE RUPTURE Bl.2(9) 14.6.1.5
- 10) CLOSURE OF ALL MSIV's WITH STUCK Bl.2(10)
OPEN RELIEF VALVE l
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Rev. No. 3 Page 16 of 43
SIMULATOR TEST PROGRAM STP-3 k- APPENDIX A .;
COMPUTER REAL TIME TESTING ,
i The following test will be evaluated by criteria in Section 8.2 1: '
A.1 A calculation of CPU cycle time statistics.
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SIMULATOR. TEST PROGRAM STP-3 APPENDIX B NORMAL OPERATIONS TESTING The following tests will be evaluated by the criteria in Section
.8.2.2:
B.1 Plant Startup -
from cold shutdown to hot standby.
B.2 Plant Startup -
from hot standby to minimum generator load including turbine startup and generator synchronization.
B.3 Plant Power Increase -
frost minimum load to rated plant power.
B.4 Plant Power Decrease -
from rated power to minimum generator load.
B.5 Plant Shutdown -
from minbaum load to hot standby.
B.6 Plant Shutdown -
from hot standby to cold shutdown.
B.7 Plant Startup, power operations and shutdown with less than full reactor coolant flow. ,
i Q B.8 Core Performance Tests B.8.1 Heat Balance B.8.2 Shutdown Margin Demonstration l
)
B.8.3 Measurement of Reactivity Coefficients B.8.4 Control Rod Worth B.9 Operator Conducted Surveillance Tests B.9.1 ST-01B MSIV Fast Closure and Main Steam Line Drain Isolation Valve Test (IST)
B.9.2 ST-01E Main Turbine Stop Valves Limit Switch Instrument Functional Test B.9.3 ST-01G Main Steam Radiation Monitor (17RM-251A, B, C and D) Punctional Test B.9.4 ST-O1I Main Steam Isolation Valves Limit Switch Instrument Functional Test B.9.5 ST-01K Main Steam Line Isolation Valves, Main Steam Drain Valves and Reactor Water Sample Valves Simulated Automatic Isolation Test B.9.6 ST-01L
() Main Turbine Control Valve Instrument Channel and Valve Operability Check I
Rev. No. 3 Page 18 of 43 l
e uh-
SIMULATOR TEST PROGRAM l STP-3
-APPENDIX B (Coetinued)
NORMAL OPERATIONS TESTING B.9.7 ST-01S Shutdown Cooling Containment Isolation Valve Testing (IST) l j
B. 9. 8 - ST-01Y MSIV Partial closure Exercise Test !
B.9.9 ST-02AN RER Loop A Pump and MOV Operability and LPCI Keep-Full Level Switch Functional Test f' B.9.10 ST-02AO RER Loop B Pump and MOV Operability and LPCI ,
Keep-Full Level Switch Functional Test !
B.9.11 ST-02J One RER Service Water Pump or One Containment Cooling Subsystem Inoperable Test ,
i t
B.9.12 ST-02N LPCI Mode Inoperable Test :
B.9.13 ST-02R RER Service Water Pump and NOV Operability Test f
i B.9.14 ST-02T LPCI Cross Connect Position Functional Test !
ST-02Y RER Heat h ehanger Performance Test 4
B.9.15 l I
B.9.16 ST-03A Core Spray Pump and Valve Operability Test B 9.17 ST-03M Core Spray Testable Check Valve Testing (IST)
B.9.18 ST-04B HPCI Pump and MOV Operability Test B.9.19 ST-04L HPCI Class 2 Piping Functional Test-(ISI) l B.9.20 ST-04M HPCI Torus Suction Operability Test (IST)
B.9.21 ST-04N HPCI Flow Rate and Inservice Test (IST)
B.9.22 ST-05B APRM Instrument Functional Test (Run Mode) !
B.9.23 ST-05C IRM-APRM Instrument Range Overlap Check 4 B.9.24 ST-05N APRM Instrument Functional Test (Refuel, Startup, or Shutdown Mode) '
B.9.25 ST-050 SRM Functional Test )
B.9.26 ST-05P Source Range Channel checks 1
B.9.27 ST-05Q APRM Flow Bias Functional Test (Run Mode)
B.9.28 ST-05R RBM Upscale and Downscale Instrument Functional O Test l
Rev. No. 3 Page 19 of 43
t SIMULATOR TEST PROGRAM STP-3 O
k/ APPENDIX B (Continued)
NORMAL OPERATIONS TESTING B.9.29 ST-OST RPS Channel A APRM Downscale Functional Test '
(Run Mode)
B.9.30 ST-05U RPS Channel B APRM Downscale Functional Test (Run Mode)
B.9.31 ST-08C ESW Motor Operated Valves Operability Test '
i B.9.32 ST-09B EDG Full Load Test and ESW Pump Operability Test B.9.33 ST-09C Emergency AC Power Load Sequencing Test and 4 KV Emergency Power System Voltage Relays Instrument Functional Test ,
B.9.34 ST-09D EDG, 115KV Reserve Power, Station Battery, or ESW Pump Inoperable Test B.9.35 ST-10B Off-Gas System Automatic Isolation and Closure Test B.9.36 ST-11 Off-Gas Process Rad Monitor Instrument Functional Test B.9.37 ST-12B Reactor Building Exhaust RAD Monitor Instrument Response Test B.9.38 ST-12F Main CR ventilation Rad Monitor Instrument ,
Response Test B.9.39 ST-12K Main CR ventilation Rad Monitor Instrument channel Functional Test B.9.40 ST-13 Main Stack Rad Monitor Response Test B.9.41 ST-14A Normal Service Water Radiation Monitor Functional Test B.9.42 ST-20A Rod Worth Minimizer Functional Test ,
B.9.43 ST-20C Control Rod Operability and HCU Cooling Water Supply check Valve Reverse Flow Check (IST)
B.9.44 ST-20J Verification of Scram Discharge Volume Vents and Drains B.9.45 ST-20K Pre-Control Rod Withdrawal Checklist B.9.46 ST-20M Scram Discharge Volume Vent and Drain Valves O' Full Stroke and Timing Test (IST)
Rev. No. 3 Page 20 of 43
l t
SIMULATOR TEST. PROGRAM-STP-3 !
/~
'(s) APPENDII B (Continued)
NORMAL OPERATIONS TESTING B.9.47 ST-20N Control Rod Exercise / Timing / Stall Flow Test '
B.9.48 ST-21A Main Turbine Overspeed Trip Test (Actual Overspeed Trip Test - Valves Remain Open)
B.9.49 ST-21C Main Turbine Combined Intermediate Valve Test !
B.9.50 ST-21E Main Turbine Backup Overspeed Trip System Test i (Actual Overspeed)
B.9.51 ST-21F Main Turbine Overspeed Trip Device and Mechanical Trip valve Test B.9.52 ST-21I Main Turbine Thrust Bearing Wear Detector Test
- i B.9.53 ST-21K Main Turbine Overspeed Trip System Test (Actual Overspeed)
B.9.54 ST-23B Control Rod Coupling Integrity Test B.9.55 ST-23C Jet Pump Operability Test for Two Loop Operation (EPIC Available)
B.9.56 ST-23D Jet Pump Operability Test for Single Loop Operation B.9.57 ST-23E Jet Pump Operability Test for Two Loop Operation (EPIC Not Available) .
B.9.58 ST-24A RCIC Pump and MOV Operability Test B.9.59 ST-24F RCIC System Inoperable Test '
B.9.60 ST-24J RCIC Flow Rate and Inservice Test (IST) I B.9.61 ST-26J Heatup and Cooldown Temperature Checks B.9.62 ST-26K Recirculation Pump Start-up Differential Temperature Check B.9.63 ST-26L Main Turbine Mechanical Trip Valve and Master Trip Solenoid A and B Test B.9.64 ST-27A Recirc Loop Valve Operability Test (IST)
B.9.65 ST-29A Manual Scram Functional Test B.9.66 ST-29B Mode Switch in Shutdown Functional Test B.9.67 ST-29C RPS Channel Test Switch Functional Test Rev. No. 3 Page 21 of 43
SIMULATOR TEST PROGRAM STP-3 i
APPENDIZ B (Continued)
NORMAL OPERATIONS TESTING .
B.9.68 ST-40C Computer Out of Service Surveillance -
B.9.69 ST-40D Daily Surveillance and Instrument Check
.B.9.70 ST-40K Periodic Pump, Valve, and Component Test B.9.71 ST-40X Daily Shutdown Surveillance and Instrument Check B.9.72 ST-41B Valve Testing - Reactor Building Closed Loop Cooling Water (IST)
O t
i i
O Rev. No. 3 Page 22 of 43
SIMULATOR' TEST PROGRAM- STP-3 APPENDIX C STEADY-STATE OPERATIONS TESTING The following tests will.be evaluated by criteria in Section 8.2.3:
.C.1.0 Steady State 25% Rated Thermal Power C.2.0 Steady State 75% Rated Thermal Power C.3.0 Steady State 1004 Rated Thermal Power Stability Test O
O Rev. No. 3 Page 23 of 43
SIMULATOR TEST PROGRAM STP-3 l
APPENDIE D TRANSIENT TESTING t
The following met of transients will be evaluated by criteria in Section 8.2.4: i D.1 07TT01 -
Manual RX Scram .
D.2 07TT02 -
Trip All Feedwater Pumps I D.3 07TT03 -
Closure of All MSIVs k
D.4 07TT04 -
Trip of Both Recirc Pumps i D.5 07TT05 -
Single Recirc Pump Trip D.6 07TT06 -
Main Turbine Trip (No Scram)
D.7 07TT07 -
Max Rate Power Ramp t
D.8 07TT08 -
DBA LOCA With Loss of Off-site Power '
D.9 07TT09 -
Main Steam Line Rupture !
O D.10 07TT10 -
Closure of All MSIVs With Stuck Open Relief Valve t
1 i
I O
.Rev. No. 3 Page 24 of 43 l r
- SIMULATOR TEST PROGRAM STP-3 APPENDIE E MALFUNCTIONS TESTING YEAR 1 Tha following tests will be evaluated by the criteria in Section 8.2.5:
MALFUNCTION NUMBER DESCRIPTION ' TYPE AD01 ADS Timer Fails to Start Boolean
.AD02 ADS Inadvertent Timer and Logic Start Boolean
'AD03:A-B ADS Valve (s} Fall to Initiate Automatically Boolean AD04 A-K RX Press Relief Valve Solenoid Failure Boolean AD05 A-K RX Press Relief Valve Leak Variable l AD06 A-K RX Press Relief Valve Inadvertently Opens Boolean AD07:A-K RX Press Relief Valve Fails to Open Boolean AD08:A-K RX Press Relief Valve Stuck Open Boolean AD09:A-K RX SRV Vacuum Breaker Stuck Open Boolean AN01:A,B Control Room Annunciator Power Failuro Boolean i
CS01 A,B Core Spray Pump Trip Boolean i CS02 A,B Core Spray Injection Valve Fails to Auto Open Boolean CS032A,B Core Spray Torus Suction Fails Closed Boolean CSO4 A,B Core Spray Injection Line Break (non-recovereble) Variable CS05:A,B Core Spray Torus Suction Line Pipe Failure Variable CUO1 RWCU Flow Control Failure Variable CUO2:A,B RWCU Pump Trip Boolean CUO3:A,B Tube Leak in RWCU HX (non-recoverable) Variable OCUO4 A,B RWCU Resin Intrusion Variable
. i l
Rev. No. 3 Page 25 of 43 ;
l SIMULATOR TEST PROGRAM STP-3 APPENDIE E (Continued)
MALFUNCTIONS TESTING {
YEAR 1 !
MALFUNCTION NUMBER DESCRIPTION TYPE CUO5 A,B RNCU Rosin Depletion in Filt/Demin Variable i CUO6 RWCU Inadvertent Isolation Boolean CUO7 RWCU Pipe Break Between 12MOV-15'and 12MOV_18 Variable (non-recoverable) i CUO8 RWCU Return Temperature Transmitter Failure Variable CUO9 RNCU Inlet Pipe Failure (non-recoverable) Variable !
t
_________________________________________________________________________ j DG01 A-D EDG Fails to Start Boolean DG02:A-D EDG Fails to Trip Boolean DG03 A-D EDG Output Breaker Fails to Auto Close Boolean DG04:A-D EDG Trip Boolean -j DG05:A-D EDG Voltage Regulator Oscillations Boolean DG06 A-D EDG Slow to Start Boolean DG07:A-D EDG Governor Fails High Boolean .I DG08:A-D EDG Governor Fails Low Boolean f l
ED01 A,B \
345/24KV Transformer (T1A, TIB) Failure Boolean -
ED02 A,B 115/4KV Transformer (T2, T3) Failure Boolean ED03 A-D 4KV/600V Transformer (T13, Tid, T15, T16) Failure Boolean ED04 A,B Inverter (71INV-3A/B) Failure Boolean ED05:A-B 4KV/600V Transformer (TS, T6, T7, T8, T9, T10, Boolean Til, T12) Failure ED06A 120VAC Bus (RBACAS) Failure Boolean Rev. No. 3 Page 26 of 43
CIMULATOR TEST PROGRAM STP-3 A
(_) APPENDIX E (Continued)
MALFUNCTIONS TESTING YEAR 1 MALFUNCTION NUMBER DESCRIPTION TYPE ED06B 120VAC Bus (TBACA6) Failure Boolean ED06C 120VAC Bus (SWACA7) Failure Boolean ED06D 120VAC Bus (RBACBS) Failure Boolean ED06E 120VAC Bus (TBACB6) Failure Boolean ED06F 120VAC Bus (RWACB7) Failure Boolean ED07A 120VAC Bus (RRACAB) Failure Boolean ED07B 120VAC Bus (RRACB8) Failure Boolean ED07C 220VAC Bus (RBACCS) Failure Boolean ED07D 120VAC Bus (TBACC6) Failure Boolean ED07E 120VAC Bus (SWACC7) Failure Boolean ED07F 120VAC Bus (RBACDS) Failure Boolean ED07G 120VAC Bus (TBACD6) Failure Boolean ED07H 120VAC Bus (RWACD7) Failure Boolean ED07I 120VAC Bus (RBACE5) Failure Boolean ED07J 120VAC Bus (71ABAC1) Failure Boolean l
ED07K 120VAC Bus (71ACNMS) Failure Boolean i
ED07L 120VAC Bus (71ACNMS-A) Failure Boolean ED07M '
120VAC Bus (71ACNMS-B) Failure Boolean ED07N 120VAC Bus (71EBAC1) Failure Boolean !
ED08A 120V/240VAC Bus (71AC9) Failure Boolean ED08B 120V/240VAC Bus (71AC10) Failure Boolean ED09:A,B UPS MG Drive Failure (AC/DC) Boolean s/
ED10 120VAC UPS Bus (71ACUPS) Failure Boolean Rev.-No. 3 Page 27 of 43 l
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i SINULATOR TEST PROGRAM STP-3 I
~ - \/
>Q APPENDIX E (Continued) '
MALFUNCTIONS TESTING YEAR 1 !
MALFUNCTION !
NUMBER DESCRIPTION TYPE '
ED11A !
125VDC Bus A (71BCB-2A) Failure Boolean i i
ED11B 125VDC Bus B (71BCB-2B) Failure Boolean !
ED12 A,B 125VDC Bus Battery Charger Failure Boolean ,
ED13 A,B 24VDC Bus System Failure Boolean !
ED14 A,B 24VDC Battery Charger Failure Boolean ED15 24KV/4KV Transformer T4 Failure Boolean !
ED16A Power Grid Transient With Load Increasing Boolean ED16B Power Grid Transient With Load Decreasing Boolean ED 17 Station Blackout Boolean l O .ED18:A,B 4.16KV' Emergency Bus (10500, 10600) Failure Boolean !
ED19 A-E U' 4.16KV Normal Bus (10100, 10200, 10300, 10400, 10700) Failure Boolean '
ED20:A-H 600VAC Bus (11300, 11400, 12300, 12400, 13300, I 13400, 14300, 14400) Failure Boolean i ED21 A-D 600VAC Emergency Bus (11500, 12500, 11600, 12600) !
Failure Boolean
{
ED22:A-C 600VAC Normal Bus (113100, 113200, 113300) Failure Boolean i ED23:A-C 600VAC Normal Bus (114100, 114200, 114300) Failure Boolean l ED24 A-D 600VAC Emergency Bus (115100, 115200, 115300, 115600)
Failure !
Boolean i ED25 A-F 600VAC Bus (116100, 116200, 116300, 116400, 116500, 116600) Failure Boolean i
ED26:A,B 600VAC Bus (123100, 123200) Failure Boolean I i
ED27:A,B 600VAC Bus (124100, 124200) Failure Boolean
(
Rev. No. 3 Page 28 i
of 43
-i SIMUIATOR TEST, PROGRAM STP-3 APPENDIX E (Continued) '
MALFUNCTIONS TESTING i YEAR 1 ,
i MALFUNCTION NUMBER DESCRIPTION TYPE f
ED28 A-D 600VAC Bus (125100, 125200, 125300, 125400) Failure Boolean' i ED29:A-D 600VAC Emergency Bus (126100, 126200, 126300, 126400)
Failure Boolean !
ED30:A-D 600VAC Bus (133100, 133200, 133300, 133400) Failure Boolean i
ED31 A-D 600VAC Bus (134100, 134200, 134300, 134400) Failure Boolean [
ED32:A-E 600VAC Bus (143100, 143200, 143300, 143400, 143500) Boolean Failure {
ED33 A-E 600VAC Bus (144100, 144200, 144300, 144400, 144500) Boolean Failure '
ED34A 120VAC Bus RPS-A Failure Boolean ED34B 120VAC Bus RPS-B Failure Boolean i ED35A 120VAC Bus (71 ESSA 1) Failure Boolean i ED35B 120VAC Bus (71ESSB1) Failure Boolean i ED36A 120VAC Bus (71ACA2) Failure Boolean ED36B :
120VAC Bus (71ACA3) Failure Boolean l ED36C 120VAC Bus (71ACA4) Failure Boolean ED36D 120VAC Bus (71ACB2) Failure Boolean ED36E 120VAC Bus (71ACB3) Failure Boolean :
ED36F 120VAC Bus (71ACB4) Failure Boolean ED37A 1-5 125VDC Bus (71DC-A) Failure Boolean :
ED378:1-5 125VDC Bus (71DC-B) Failure Boolean l ED3'4:A-E 125VDC Bus (71BMCC) Failure Boolean !
ED39 A-G 125VDC Control Power Failure To 4160V Busses Boolean j OeD40=A-t 125vDC Centre 1 Fe er Fei1ure Te 600v Busses Bee 1ean
[
Rev. No. 3 Page 29 of 43
'-m -.- . - - .
I SIMULATOR TEST PROGRAM
.STP-3 I APPENDIX E (Continued)
MALFUNCTIONS TESTING i
YEAR 1 i MALFUNCTION NUMBER DESCRIPTION TYPE EG01 Main Generator Trip Boolean EG02A Main Generator Field Breaker Fails to Close Boolean !
EG02B Main Generator Field Breaker Fails to Open Boolean EG03:A,B Loss of Isolated Phase Bus Cooling Fan Boolean f EG04 Main Generator Field Brushes Ground Boolean l EGOS Main Generator Stator Temp High Variable '
EG06 Generator Hydrogen Cooling System Leakage (non-recoverable) Variable EG07 Hydrogen Seal Oil System Failure Boolean l
{}EG08A Main Generator Auto V/R Fails Increasing Boolean !
EG08B Main Generator Auto V/R Fails Decreasing Boolean -
EG09 Main Generator Auto V/R Failure Complete Boolean ;
EGIO Loss of Stator Cooling Water Flow Boolean !
i l
Rev. No. 3 Page 30 1
of 43 ,
L SIMULATOR TEST PROGRAM. i STP-3 1 AFFENDIX'E (Continued)'.
MALFUNCTIONS TESTING ;
YEAR 2-MALFUNCTION NUNRRR DESCRIPTION TYFE ,
FP01 A-D EDG Rm Fire Boolean ,
FP02 Smoke - Ione 01 through Eone 82 Boolean ,
_________________________________________________________________________ l FW012A,B' RX Feedwater Pump Trip Boolean PWO2A A,B RX Feedwater Pump Recirc Valve Fails Open Boolean FWO2B:A,B RX Feedwater Pump Recirc Valve Fails Closed Boolean [
FWO3:A,B RX Feedwater Pump Auto Controller Failure Variable l FWO4 A,B RX Feedwater Pump Manual Controller Failure Variable FWO5:A,B RX Feedwater Pump High Vibration Boolean FWO6 A,B RX Feedwater Pump Coupling Failure Boolean FWO7:A,B RX Feedwater Pump Discharge Valve Seat Failure Variable f FWO8 Master Feedwater Flow Control Auto Failure #
Variable .
FWO9 Master Feedwater Flow Control Manual Failure Variable i
FW10 Master Feedwater Flow Control Oscillates Variable FWil:A-D Loss of Steam Flow Signal To Fdwtr Level i Control System Boolean >
FW12 A,B Loss of Feed Flow Signal To Fdwtr Level Control System Boolean l FW13 A,B Feedwater System 6th Point Beater Tube Leak :
(non-recoverable) Variable ;
PW14 A,B Feedwater System 5th Point Beater Tube Leak (non-recoverable) Variable FW15:A,B Feedwater System 4th Point Heater Tube Leak (non-recoverable) Variable OFW16:A,B Feedwater System ard Point Beater Tube teak (non-recoverable). Variable !
.?
Rev. No. 3 Page 31 of 43
L : SIMULATOR TEST PROGRAM STP-3 j APPENDIZ E (Continued) l MALPUNCTIONS TBSTING l YEAR 2 MALFUNCTION .
MUMBER DESCRIPTION TYPE
'PN17:A,B Feedwater System 2nd Point Heater Tube Leak i (non-recoverable) Variable ,
FW18 A,B Feedwater System Drain Cooler Tube Leak (non-recoverable) Variable :>
FW19:A-E Condensate Pump Trip Boolean ;
PW20 Normal Botwell Level Controller Failure Variable FW21:A-H Condensate (DEMIN) Conductivity Increases Variable FW22:A,B CST Leak Manway Flange Failure Variable FW23:A-D High Pressure Heater Level Control Failure Variable
.FW24:A,B RX Feedwater Pump Loss of Oil Pressure Variable '
C:) FW25:A-C ' Condensate Booster Pump Trip Boolean PW26:A,B Condensate Transfer Pump Trip Boolean i FW27 A,B Feedwater Line Break Inside Primary Containment Variable (non-recoverable)
FW28 A,B Feedwater Line Break Outside Primary Containment Variable !
(non-recoverable)
FW29 A,B Feedwater Line Inboard Containment Check Valve Failure Boolean
't FW30 A-D Rx Feedwater Pump Discharge Check Valve Fails Open Boolean (UNDER DEVELOPMENT)
_________________________________________________________________________ l l
HP01 BPCI Failure to Auto Start Boolean HP02 HPCI Turbine Trip Boolean HP03 HPCI Discharge Line Break (non-recoverable) :
Boolean I i
HPO4 HPCI Flow Controller Auto Output Failure Variable '
HP05 HPCI Inadvertent Initiation Boolean HP06 HPCI Steam Line Break (non-recoverable) Variable l Rev.-No. 3 Page 32 of 43 )
o -
' SIMULATOR TEST PROGRAM STP-3
(^)s
( APPENDIE E (Continued)
MALFUNCTIONS TESTING YEAR 2 MALFUNCTION i NUMBER DESCRIPTION *IFE HP07 HPCI Valve 23MOV-19 Fails to Auto Open Boolean HP08 HPCI Turbine Exhaust Piping Failure (non-recoverable) Variable HP09 HPCI Torus Suction Pipe Failure (non-recoverable) Variable f
HV01:A-C Rx Bldg Supply Fan Trip Boolean HV02:A,B Rx Bldg Exhaust Fan Trip Boolean HV03 Secondary Containment Leakage Variable ,
IA01 Loss of Air Pressure to Scram Air Header Variable IA02 Loss of Instrument Air Variable IA03:A-C Air Comprescor Trip Boolean MC01 Main Condenser Air In-Leakage Variable ,
MCO2:A-D Main Condenser Tube Leak Variable MCO3:A-D Main Condenser Water Box Flow Block Variable MC04A SJAE Steam Supply Valve Fails Open Boolean '
MC04B SJAE Steam Supply Valve Fails Closed Boolean MC05:A-C 1
Circulating Water Pump Trip Boolean MC06 Air Ejector Condenser High Level Variablo MC07:A-C Circ Water Pump Discharge Valve Fails to Close Boolean MCOB:A-C Circ Water Pump Discharge Valve Fails to Open Boolean
()MC09:A-D Loss of Condenser Water Box Vacuum Priming Boolean MC10 Water Icing in Intake Structure Variable .
Rev. No. 3 Page 33 of 43
SIMULATOR TEST PROGRAM.
STP-3 APPENDIX E (Continued)
MALFUNCTIONS TESTING YEAR 2 MALFUNCTION NUMBER DESCRIPTION TYPE MS01 A,B Main Steam Header Press Xmtr Failure Variable MS02 A-D Steam Leakage Inside Primary Containment (non-recoverable) Variable MS03 A-D Main Steam Line Rupture Inside Primary Containment (non-recoverable) Boolean MSO4 A-D Main Steam Line Rupture Outside Primary Containment Boolean (non-recoverable)
MS05 Steam Leak Outside Primary Containment (non-recoverable) Variable MS06A Steam Seal Pressure Regulator Fails Open Boolean
[}MS06B Steam Seal Pressure Regulator Fails Closed Boolean MS07:A-H MSIV Disc Separates from Stem (non-recoverable) Boolean MS08AIA-H MSIV Fails Closed Boolean MS08B:A-H MSIV Fails Open Boolean MSO9:A,B First Stage Reheat Steam Supply to MSR Fails Closed Boolean MS10 A-H MSIV Slow Test Closure Time Variable MSil:A,B Second Stage Reheat Steam Supply to MSR Fails closed Boolean MS12 A-D Moisture Separator Drain Tank Level Control Failure Variable MS13:A-D First Stage Reheat Drain Tank Level Control Failure Variable MS14:A-D Second Stage Reheat Drain Tank Level control.
Failure Variable MS15:A-J Loss of Feedwater Extraction Steam Boolean MS16:A-L SRV Discharge Line Break Above Torus Water Level Variable (non-recoverable) .
Rev. No. 3 Page 34 of 43
~
.. SIMULATOR TEST PROGRAM STP-3 i i
APPENDIE E (Continued)
MALFUNCTIONS TESTING l YEAR 2 -
1 MALFUNCTION 5 NUynWR DESCRIPTION TxPE r
NM01 A-D SRM Channel Failure Variable NM02 A,B SRM Channel Recorder Failure Boolean l NM03 A-D SRM Channel Inoperative Boolean 5
i NM04 A-D SRM Channel Detector Stuck Boolean ~
NM05:A-D SRM Channel Retract Permit Failure Boolean ;
NM06 A-B IRM Channel Failure Variable NM07:A-H 'IRM/APRM-RBM Channel Recorder Failure' Boolean !
,NM08:A-H IRM Channel Inoperative Boolean ;
NM09:A-B IRM Channel Detector Stuck Boolean ;
O NM10:A-H IRM Channel Retract Permit Failure Boolean ;
NM11 XXYYZZ LPRM (XX-YY-ZZ) Failure Variable i
NM12:A,B RBM Channel Failure Variable !
NM13 A,B RBM Channel Inoperative Boolean !
h NM14:A-F APRM Channel Failure Variable NM15 A-F APRM Channel Inoperative Boolean NM17 XX YY Leak in LPRM Dry Tube (non-recoverable) Boolean .
I i
i i
i
)
l O
Rev. No. 3 Page 35 of 43
i SIMULATOR TEST PROGRAM STP-3 i APPENDIE E (Continued)
MALFUNCTIONS TESTING YEAR 3 i l
MALFUNCTION NtDfRRR - DESCRIPTION 11rE
- OG01 Off Gas Condenser High Level Boolean !
OG02 Off Gas Drain Pot High Level Boolean-OG03 Explosion in Air Ejector Discharge !
(non-recoverable) Boolean i OG04 Fire in Air Ejector Boolean OG05 Recombiner Trip Boolean .
OG06 Stack Isolation Valve Fails Closed Boolean !
5 PC01 Containment Vent Purge Fan Trip Boolean !
PCO2 Loss of Instrument Nitrogen Variable PCO3 A-H Drywell Cooling Fan Trip Boolean :
i PC04:A,B SBGT Fan Trip Boolean PC05 A-Q Containment Pressure Transmitter Failure Variable !
-PC06 Torus Drywell Vacuum Breaker 27VB-1 Fails to Close Boolean i PC07 -Primary Containment Leakage (non-recoverable) Variable PCO8 Primary Containment Hydrogen High Variable PC09 . Primary Containment Oxygen High' Variable PC10 Torus Level Decreases (non-recoverable) Variable RC01:A,B RCIC Turbine Loss of Oil Pressure Boolean RCO2 i RCIC System Fails to Auto Start Boolean !
RC03 RCIC System Turbine Trip :
Boolean j ORC 04 RCIC Turstne Fai1ere to auto Trie Beelean RCOS RCIC System Isolation Boolean Rev. No. 3 Page 36 I
of 43 ,
-- . _ _ ~ . . . _ __ - ___ _ _ _ -- . _ . _ . ._ _ . . _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
. SIMULATOR _ TEST PROGRAM STP-3
. APPENDIX E (Continued)
MALFUNCTIONS TESTING YEAR 3 MALFUNCTION NUMBER DESCRIPTION irrB RC06 RCIC Inadvertent Initiation Boolean RC07 A,B RCIC Governor Fails High/ Low (BSS/LSS) Boolean RC08sA,B RCIC-RBR Suction Valve (10NOV-36A/B) Fails Closed Boolean RC09 RCIC Steam Line Break (non-recoverable) Variable RC10 RCIC Discharge Line Break (non-recoverable) Variable RC11 RCIC Turbine Exhaust Pipe Failure (non-recoverable) Variable RC12 RCIC Isolation Relay, 13A-K15, Failure Boolean (UNDER DEVELOPMENT)
{}RD01A:A-BSDVVentorDrainValveFailsOpen Boolean RD01B A-H SDV Vent or Drain Valves Fail Closed Boolean RD02:A,B Scram Discharge Instrument Volume High Level Variable RD03:A,B CRD Flow Control Valve Failure Variable RD04 A,B CRD Drive Water Filter Clogging Variable RD05 A,B CRD Stabilizing Valves Fail Closed Boolean RD06:A,B CRD Hydraulic Pump Trip Boolean RD07:***** Control Rod (XX-YY) Drift-In Boolean RD08:***** Control Rod (XX-YY) Drift-Out Boolean RD09:***** Control Rod (XX-YY) Accumulator Trouble Boolean RD10 **z**
Control Rod (XX-YY) Blade Stuck- Boolean RD11:**:** Control Rod (XX-YY) Uncoupled Boolean RD12:***** Control Rod (XX-YY) Scrammed Boolean
()RD13:**:**ControlRod(XX-YY)FailtoScram Boolean RD14:***** Control Rod (XX-YY) RPIS Failure Boolean ,
Rev. No. 3 Page 37 of 43
g l J
SIMULATOR TEST PROGRAM STP-3 :
0:- APPENDIX E (Continued) l MALFUNCTIONS TESTING t
YEAR 3 MALFUNCTION t NUMBER DESCRIPTION TYPE RD15 Rod Drive Control System Timer Fall Boolean '
i RD16 Rod Position Info System Total Failure Boolean RD17 ***** Control Rod (XX-YY) High Temperature Boolean RD18 A,B Scram Discharge Volume Rupture (non-recoverable) Variable RD19:A,B -CRD Suction Filter Hi Delta-Pressure Boolean I RD20 ***** Line Break CRD HCU (XX-YY) (non-recoverable) Boolean RD21:***** Leaking Control Rod Withdraw SOV Boolean RD22 Scram Discharge Volume Hydraulic Lock Variable i (UNDER DEVELOPMENT) g______________________________________________________________________ l RH01:A-D RHR Pump Trip Boolean !
RH03:A,B RER Heat Exchange Tube Leak (non-recoverable) Variable RH04A A,B LPCI Injection Valve Fails Closed Boolean RH04B:A,B LPCI Injection Valve Fails Open Boolean RH05 A-D RBR-Pump Discharge Leak (non-recoverable) Variable
{
RH06 RER/SDC Valve 10MOV-18 Fails Boolean !
RH07 RBR/SDC Valve 10MOV-17 Fails Boolean !
RH08:A-D RER Pump SDC Suction Valve Fails Closed Boolean RH09:A,B LPCI - Injection Line Failure (non-recoverable) Variable RH10*A,B RER Loop Suction Line Piping Failure (non-recoverable) Variable >
RHil:A,B RER Ex Level Controller Auto Mode Failure Variable !
RH12 A,B RER Ex Steam Supply Valve Fails Closed !
Boolean j RH13 A,B RBR Ex Press Reducing Valve Fails Closed i Boolean i RH14' LPCI Failure to Auto Initiate Boolean Rev. No. 3 Page 38 of 43 ;
SIMULATOR TEST PROGRAM STP-3
'. APPENDIX E (Continued)
MALFUNCTIONS TESTING YEAR 3 MALFUNCTION
. NUMBER DESCRIPTION TYPE RM01A 1-5 Process Rad Mon Failure Variable RM01B:1-4 Process Rad Mon Failure Variable RM01C21-7 Process Rad Mon Failure Variable RM01D:1-8 Process Rad Mon Failure Variable RM01E 1-7 Process Rad Mon Fallure Variable RM02A:1-10 ARM Failure Variable RM02B 11-20 ARM Failure Variable RM02C:21-30 ARM Failure Variable RPOIA RPS Auto Scram Failure Boolean RP01B RPS Manual Scram Failure Boolean RP02 Inadvertent Reactor Scram Boolean RP03 Inadvertent Group I Isolation Boolean RPO4 Inadvertent Group II Isolation Boolean RP05:A,B RPS M-G Set Trip Boolean RP06:A,B RPS Electrical-Protection Assembly Trip Boolean RP07 A-D Control Rod Group Fail to Scram Boolean RP08:A-D Control Rod Group (1,2,3,4) Scram Boolean RP09 ARI Fails to Actuate Boolean O .
Rev. No. 3 Page 39 of 43
CIMULATOR TEST PROGRAM STP-3 APPENDIX E (Continued)
MALFUNCTIONS TESTING !
YEAR 4 MALFUNCTION MUunRR DESCRIPTION TxPE
..RR01 A,B RWR Pump / Gen Field Breaker Trip i Boolean RR02 A,B RWR Pump Control Signal Failure Scoop Tube Lock Boolean RR03 A,B RWR Pump Incomplete Start Sequence Boolean !
RR04 A,B RWR Pump fl Seal Failure (non-recoverable) Variable l RR05:A,B RWR Pump $2 Seal Failure (non-recoverable) I Variable RR06 A,B RWR Pump Dual Seal Failure-(non-recoverable) Variable !
RR07 A-B RWR Loop Flow Transmitter Fails Variable RR08 A-T Jet Pump Failure (non-recoverable) I Variable !
RR09 RWR Master Flow Controller Failure Variable ,
RRIO A,B RWR System MG Flow Controller Failure Variable RR11:A,B RWR Pump Shaft Binding Variable !
RR12 A,B RWR Pump Drive Motor Breaker Trip Boolean j RR13 A-C ATWS System Fails to Initiate RWR Pump Trip Boolean i RR14 A,B RWR Loop Rupture (DBA) (non-recoverable) Boolean RR15 A,B RWR Coolant Leakage Inside Primary Containment Variable !
(non-recoverable) i RR16 A,B Reactor Vessel Wide Range Level Transmitter Fails RR16:C,D,E,F Boolean -
(UNDER DEVELOPMENT) Variable I RR17 A,B Reactor Vessel Fuel Zone Level-Failure Boolean RR18 Refuel Water Level Indicator Fails Boolean ;
RR19 A-D Rx Vessel Lvl Transmitter To FW Lvl Control System Failure !
Variable !
t RR20 A,B Loss Pressure Compensation to Feedwater Control !
System Boolean 4
RR21 A-D Loss of Pressure Compensation to Feedwater Control System ;
Boolean .
i Rev. No. 3 Page 40 of 43
l SIMULATOR TEST PROGRAM !
STP-3
- i r i 7-N-d ;
APPENDIX E (Continued) <
MALFUNCTIONS TESTING t YEAR 4 MALFUNCTION.
NUNRRR DESCRIPTION !
TYPE !
RR22 A-D Reactor Vessel Scram Level Transmitter Failure Variable i RR23 A-D RWR Flow Unit Failure :
Variable- (
RR24 A-D Jet Pump Summer Failure Variable RR25 A,B Core Spray Pipe Break Inside Downconer (non-recoverable) Variable RR26 Unexplained Reactivity Change (non-recoverable) Variable RR27:A,B. Rx Level Marrow Range Reference Leg De-Gassing Variable
-RR28 Rx Level Narrow Range Reference Legs Severe De-Gassing Boolean RR29 Reactor Vessel NR Lvl Transmitter Falls Variable (UNDER DEVELOPMENT)
RWOI Rod Worth Minimizer Failure Boolean RX01 Fuel Cladding Failure Variable RXO2:XX YY Increased Rod Worth (XX-YY) Variable RX03 Core Thermal Hydraulic Instability Variable SLO 1 A,B Standby Liquid Control Pump Breaker 'frip Boolean SLO 2 A,B Standby Liquid Control Squib Valve Fails to Open Boolean SLO 3:A,B 'SLC Pump Relief Valve Lifts Boolean SWO1 A,B Loss of RBCLC Flow to RWR Boolean
()SWO2:A-C TBCLC Ex Cooling Water Blockage Variable SWO3 A-C RBCLC Ex Cooling Water Blockage Variable ,
Rev. No. 3 Page 41 of 43
SIMUIATOR TEST PROGRAM STP-3 APPENDIZ E (Continued)
MALFUNCTIONS TESTIEfa YEAR 4 MALFUNCTION NUMBER DESCRIPTION i
iXPE SWO4 A-D RER Service Water Pump Trip Boolean
'Tr705 A-C Service Water Pump Trip Boolean SWO6 A,B RER Ex Cooling Water Blockage Variable l
SWO7:A-C TBCLC Pump Trip Boolean SWO8 A-C TBCLC Ex Tube Leak (non-recoverable) Variable SWO9:A-C RBCLC Pump Trip Boolean SW10 A-C RBCLC Ex Tube Leak (non-recoverable) Variable SW11 RBCLC Leakage in Drywell (non-recoverable) Variable SW12:A,B Loss of Drywell Cooling Assemblies Boolean SW13 Loss of Cooling to RWCU NRHX Boolean SW14 A,B Emergency Service Water Pump Trip Boolean TC01 Main Turbine Acceleration Boolean TCO2 A,B EBC Pump Trip Boolean TC03A A,B EBC Pump Press Reg Fails High Boolean TC03B A,B EBC Pug Press Reg Fails Low Boolean TC04 A-D Bypass Valve Failure Variable TC05A Main Turbine Load Select Fails High Boolean TC05B Main Turbine Load Select Fails Low Boolean TC06A A,B EHC System Regulator Fails High Boolean TC06B A,B EBC System Regulator Fails Low Boolean TC07:A,B EHC System Regulator Oscillation Boolean Rev. No. 3 Page 42 of 43
SIMULATOR TEST PROGRAM '
STP-3
'( ) APPENDIX E (Continued) f MALFUNCTIONS TESTING i
\
YEAR 4 MALFUNCTION.
NLwann. DESCRIPTION TIPR 1 TC08A A-D Turbine Control Valve Fails Open Boolean .l TC08B A-D Turbine Control Valve Fails Closed. Boolean ,
TC09A A-D Turbine Stop Valve Fails Open Boolean ,
TC09B A-D Turbine Stop Valve Fails Closed Boolean l
)
TC10 Turbine Load Reject Boolean i
l TUO1 Inadvertent Turbine Trip Boolean t
}
TUO2 A-J Main Turbine Bearing High Temp Variable h
TUO3 Main Turbine Bearing Oil Pressure Low '
(non-recoverable) Variable ]
TUO4 A-J Main Turbine Bearing High Vibration Variable !
?
TUO5 Main Turbine Shaft Driven Oil Pump Failure i l
(non-recoverable) Boolean '
TUO6 Turbine Motor Suction Pump Trip Boolean TUO7 Turbine Emergency Bearing Oil Pump Trip Boolean !
t TUO8A Exhaust Bood Spray Valve Fails Open Boolean !
),
TUO8B Exhaust Bood Spray Valve-Fails Closed Boolean i I
YC01 EPIC Fails Boolean i
i i
f i
()
l-Rev. No. 3 Page 43 of 43