ML20028H644
| ML20028H644 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/17/1991 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20028H643 | List: |
| References | |
| NUDOCS 9101220177 | |
| Download: ML20028H644 (610) | |
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O OneStep*
GENERAL INFORMATION j SIMULATOR DESIGN DATA 2 CONTROL ROOM 3 INSTRUCTOR INTERFACE 4 SIMULATOR TEST AllSTRACTS 5 SIMULATOR DISCREPANCY RESOLUTION AND UPGRADES 6 OPERAllILITY TEST 7 L
APPENDIX $
'W* 91o122o177 91o117
',DR ADOCKc500g3
SIMCERT,1/SIMDOCS/SIM1 December 3, 1990
'O ARKANSAS NUCLEAR ONE UNIT 1 SIMULATOR CERTII'ICATION SUBMITTAL O
O
___-___._____.___..__-_-_--_.____-_-___.__._____--___-____.______-a _- -e a
SIHCERT.1/SIMDOCS/SIH1 D:ccab r 3, 1990 p_~ TABLE OF CONTENTS
's
~, TAB I . bENERAL INFORMATION
. SIMULATOR AND PLANT INFORMATION
. OPERATING PROCEDURES
. SUBJECT HATTER EXPERTS ,
TAB 2 . SIHULATOR DESICN DATA TAB 3 . CONTROL ROOH TAB 4 . INSTRUCTOR INTERFACE i
TAB 5 . SIMULATOR TEST ABSTRACTS A. REAL TIME COMPUTER TEST B. NORMAL OPERATION TEST C. STEADY STATE TEST D. SURVEILLANCE TEST E. TRANSIENT TEST F. HALFUNCTION TEST TAB 6 . SIMULATOR DISCREPANCY RESOLUTION AND UPGRADING TAB 7 . OPERABILITY TEST TAB 8 . APPENDIX-
- r-~ A-I
- ANO-] SIMULATOR HALFUNCTION LIST
(' A-2: ANO-1 PLANT EQUIPMENT LIST A-3: SIHULATOR REQUIREMENTS A-4 'GIMULATOR FIDELITY TESTING' TRAINING ADMINISTRATIVE PROCEDURE, 1064.092.
l 1
-p V
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m.
SIMCERT.1/SIMDOCS/SIM, J nuary 14, 1991 6 s-4c- _ SIMULATOR INFORMATION ;
OWNER ARKANSAS POWER & LIGHT CO.
LITTLE ROCK,.AR ,
OPERATOR ENTER 0Y OPERATIONS INC. .
ARKANSAS NUCLEAR ONE :
RT 3 BOX 132 :
RUSSELLVILLE, AR 72801 MANUFACTURER ELECTRONIC ASSOCIATES, INC. I 195 MONHOUNTH PARKWAY I WEST LONG BRANCH, NJ 07764 p
REFERENCE PLANT ARKANSAS NUCLEAR ONE-UNIT 1 BABDCK & WILCOX PWR ,
WESTINGHOUSE TURBINE-GENERATOR :t 860 MW.-
. i([]) t 1
0
'DATE AVAILABLE FOR TRAINING JANUARY 6, 1986
-t TYPE OF REPORT' INITIAL' j 1
P
([])
1-1
SIMCERT.1/SIMDOCS/SIM January 14, 1991
- Operating Procedures for Reference Plant I
-U: The operating procedures utilized at the Arkansas Nuclear One-Unit
-1 simulator are a controlled copy of the operating prodedures t utilized at the referenced plant. To assure the operating procedures are identical, the same document control procedure governing the issuance of the operating procedures is used.
The procedures are maintained current by the plants document control staff on a semi-weekly basis.
Due to model simplifications and the lack of training significance, some.eteps in the plant procedures cannot be performed on the simulator. Rather than write specific simulator procedures, the .
reference plant procedures are simply marked "NS". l The steps marked "NS" are recorded in the performance test. The general items that caused the steps to be marked "NS" are listed below. Some items have a DR numbar beside them indicating there will be modifications made to include them in the simulation. The Unit One Simulator Training Supervisor has reviewed this list and a3rees. . llis memo follows.
DR NUMBER ITEM 90-213 RR8060 REACTOR BUILDING RADIATION CHART RECORDER
' gg PPAS COMPUTER e 1 TURBINE GENERATOR VIBRATION MONITORING SYSTEM 88-277 QUINDAR_ PANEL 4 FIRE PANEL C463 RPS BISTABLES r ESAS BISTABLES i 90-214. ARTS TRIP & RESET LAMPS l MSSV MONITORING CABINET
.SPING MONITORS ICCMDS CABINET-ALTERNATE Sil0TDOWN CABINETS90-215 LOCAL TRIP OF P7A DRAIN &' VENT' VALVES PilYSICAL PIPING, PUMPS, MOTOR, BREAKERS, !!ANDWilEELS H 0:~ ANALYZER CABINETS i CHEMISTRY-SAMPLES90-027 CV6864-6 CV6865 MNSTM TO MSR MORPHOLINE Cl!EMISTRY POWER SUPPLY FOR SOURCE RANGE ~ DETECTORS 90 ,'57 BREAKERS B51111 &-B6193 NA0H TO RB SPRAY 90-218 CV1410,'CV1050.ESAS CABINET TRIP / RESET SWITCHS/ STATUS LOGIC: TEST MATRIX FOR ESAS 1
'90-219 hFW TURBINE CAN'T BE RELATCHED LOCAL 90-220 HN TURBINE CAN'T BE RELATCHED LOCAL LOCAL' BREAKERS FOR MINOR LOADS.-
b U
1-2
SINCERT.1/SIMDOCS/SIME-January 14, 1991-ARKANSAS NUOLEAR ONE r']
MEMORANDUM Date: November 28, 1990 l Number: RER-90-04583 Office: Training and Emergency Planning To i - Bryan'Heikes s
From: Dan Smith ll
' Subject Unit 1 Simulator Performance i Test-Steps Not Completed -
i I have reviewed _-the list of. procedural steps not completed during the. _
1,erformance-test and-agree that other than'the identified steps, there is - 1 no adverst craining-effects as a result of these steps _not being performed.
-/N:
'I concur that the following items should' be addressed as deficiencies and V' should be implemented to provided adequate training.
- - RR 8060,- Reactor _ Building Radiation Chart Recorder
- - Quindar; Panel: Alarm / Acknowledge .;
e' ARTS Trip:and Roset Lamps for RPS
- Local trip of P7A ~
- .CV6864 and CV6865, Main Steam to MSR's-e :-B51111 and B6193, Breakers for.NA0H: Valves to RB Spray -i
- - _.ESAS cabinet trip / reset switches / status for CV1410 and CV1050 ,
.. Local Latch function for both MFW Pump Turbines-
- ~ Local Latch function for Main Turbine-DES /sjf cc: E. A. Force ;
Fred Uptagrafft )
ANO-DCC 1-3
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.SINCERT.1/SIMDOCS/SIMJ Janunty 14,.1991
. SUBJECT MATTER EXPERTS N./ .
For the: malfunction end transient portions of the performance test,
-baseline data for use to evaluate the results of these tests were
.largely based on the opinion of ' Subject Matter. Experts'.
The' expected outcome was derived, as a starting point, from eny and all data sources (i.e. FSAR, Plant Transient Report from.ANO and like plants, ete'.) 'This information was compiled and presented to the
' Subject Matter Experts'.. These individuals made independent reviews and presented-their comments._- The comments were compiled and differing opinions resolved on a case by case basis.
Thisdocumentationisonfileand_mayberevieweduponreguest. A table-
-has been provided to identify.the ' Subject Matter = Experts and their
. qualifications.
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N January 14, 1991 ' -
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-ATTACHMENT R-7 SUBJECT MATTER EXPERT EXPERIENCE
SUMMARY
SUBJECT MATIER EDUCATION /- YEARS JN YEARS'IN YEARS l-IN YEARS OTHER.' ' NRC. OPERATOR
' EXPERT DEGREE (S) THE PLANT OPS'TRNG NUC NAVY . NUCLEAR LICENSE TITLE ,
F. Uptagrafft BS 5 4 8 0' SRO Technical' Specialist IV l D. E. Smith HS '8- 7- 6 0 SRO Supv. Simulator Trna R. E. Stancliff HS 8' 10 0 0 SRO Operations Trainer II D. G. Slusher HS 6 3- 10 0 SRO Operations Trainer II E. D. Wentz HS 2.5 '11.5 0- 9* SRO Supt. Ops Training' E. Jacks HS 9 0 6 0 SRO Tech Specialist-III.
K. W. Canitz AA- 3.5 7 6 0 SRO Supv. Unit 1 Ops Trng
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- U.S. Army Engineers Reactor. Group, 1-5
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..m-_ . ~ .a. ._ __ . _. _ __._. _ . , -
SINCERT.1/SIMDOCS/SIM January 14, 1991 i
SIMULATOR DESIGN DATA The Arkansas Nuclear One-Unit I simulator was built several years after the plant was operational. Actual plant information was utilized in the design and development of the simulator. The plant information requested by Electrical Associates Inc. is available for review.
Updates to the simulator since delivery have also been based on actual plant information whenever available. The training department is on distribution for cuntrolled copies of design change packages. These packages are reviewed for impact on the simulator. This is proceduralized in Training Department Administrative Procedure 1064.011.
A listing of design data base items is contained in the following pages.
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G %J . V UNIT 1 DESIGN DATABASE DDB NO. DESCRIPTION ID NO./ DOC PM NO MOD DATE 000.00.000. DESIGN DATA ANNUNCIATOR' SYSTEM
-000.00.000.- DESIGN DATA AUX STEAM 000.00.000;_ DESIGN DATA CHILLED.WTR,PENE ROOM. VENT 000.00.000 DESIGN DATA. CONDENSATE,FEEDWATER, CONDENSER.
000.00.000 DESIGN DATA CONTAINMENT SYSTEM
-000.00.000 DESIGN DATA CONTROL ROD DRIVE SYSTEM 000.00.000 DESIGN DATA CVCS & HPI 000.00.000 DESIGN DATA DHR,LPSI,RX BLDG. SPRAY-000.00.000 . DESIGN DATA ELECTRICAL' DISTRIBUTION 000.00.000 DESIGN DATA ELECTRICAL GENERATION SYSTEM 000.00.000 DESIGN DATA ELECTRO-HYDRAULIC CONTROL 000.00.000 DESIGN DATA EMERGENCY FEEDWATER SYSTEM 000.00.000 DESIGN DATA EXCORE DETECTORS-000.00.000 DESIGN, DATA INCORE DETECTOES;,
., 000.00.000 . DESIGN DATA INSTRUMENT &. SERVICE AIR 000.00.000 DESIGN DATA INTERMEDIATE COOLING 000.00.000 DESIGN DATA MISC SYSTEM (SPENT FUEL, QUENCH Trj 000.00.000 DESIGN DATA NSS CONTROLS (ICS,NNI) 000.00.000- DESIGN DATA NUC. INSTR. SYSTEM 000.00.000 DESIGN DATA PROCESS COMPUTER 000.00.000 -DESIGN DATA PROTECTIVE ~ LOGIC (RPS&ESAS) 000.00.000 DESIGN DATA RADIATION MONITORING SYSTEM 000.00.000 DESIGN DATA REACTOR COOLANT &PZR SYSTEM 000.00.000 DESIGN DATA SERVICE WATER SYSTEM 000.00.000 ' DESIGN DATA STEAM GENERATOR <
000.00.000 . DESIGN. DATA STEAM SUPPLY (NEW ORK & ENERGY) 000.r~.000 DESIGN DATA TURBINE (LUBRICATION & COOLING) 000.0o.000 DESIGN DATA TURBINE (POWER & SUPERVISORY) 000.00.000 DESIGN' DATA WASTE DISPOSAL SYSTEM 000.00.000. PLANT DATA-OPERATIONS 000.00.000 PLANT DATA-TRANSIENTS 000.00.000- SIMULATOR TESTING DOCUMENTATION 000.00.001 - SIMULATOR PERFORMANCE TEST 85 000.00.002 ' SIMULATOR PHYSICS TEST 85 000.85.000 ALL NON DCP RELATED DR'S_IMPL.lIN 1985 000.85.001 SYS UNDERVOLTAGE PROTECTION (MILLSTONE DCP663) DCP 00-0663 01/01/86 000.85.002 ESAS DIVERSE. SIGNALS DCP 79-1059, 01/01/86 000.85.003 AUTO VITAL POWER EFW P7B DCP 79-1024 01/01/86 000.85.004 ' RX TRIP 'ON W OR TRB TRIP- DCP 79-1032 .01/01/86 2-2
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. 'o ' UNIT:1: DESIGN DATABASE; DDB NO.-- DESCRIPTION ~ ID NO./ DOC- PM NO- MOD DATE 000.85.005 EFW PUMP SUCTION PS- ,
DCP 79-1033. 01/01/86 000.85.006 . BLOCK UV PROT ON RCP. START :DCP 79-1041:-01/01/86 1000.85.007: EFW' CONTROL SYSTEM DCP 79-1049' 01/01/86 000.85.008 RCS RELIEF VLV POS'IND. DCP 79-1050 '01/01/86L 000.85.009 TSAT PONITOR DCP 79-1051~ 01/01/86.-
-000.85.010 'IN CORE RAD MONITOR- DCP 79-1061 01/01/86 ;
000.85.011 CONTAINMENT PRESSURE INDICATION 1 DCP 79-1063 01/01/86' ,
'000.85.012 CONTAINMENT WATER LEVEL INDICATION DCP.79-1065 01/01/86-000.85.013 EW INDICATION DCP 79-1069 01/01/86 000.85.014 :RUSS SWITCH TIE' PTS.NN TURB & FWP, DCP 80-1010: 01/01/86 -
'000.85.015 MAIN. STEAM RAD MONITORS 1 DCP 80-1022.~01/01/86' 000.85.016'- PZR' PILOT VALVE. DCP 80-1030. 01/01/86' 000.85.017 . UNIT 2,USE OF;S/U #2 TRANS ~DCP 81-1039 01/01/86 000.85.018- RX ' TRP LOSS' 0F W &/OR TURBINE - DCP 80-1032 01/01/86 000.85.019 DELETION OF NUISANCE ALARMS DCP 80-10351 01/01/86' i 000.85.020 RAD MONITORING . . DCP 80-1065 01/01/86: !
000.85.021- INSTALL'TSAT MODULES- DCP 80-1051 01/01/86:
000.85.022 ~ SILENCE TROUBLE ~ HORN..FOR CORE FLOOD TANKS DCP 80-1054 01/01/86 t 000.85.023 : STEAM DUMP SELECT SWITCH' DCP 80-1060 ~ 01/01/86;'
000.85.024 SG WET LA10P LVL- DCP'80-1061. 01/01/86i 000.85.025 EFW FLOW INDICATION INST DCP 80-1084 01/01/86 000.85.026 1PZR LEVEL INIDICATION~ DCP 80-1086, 01/01/86 ];
000.85.027 CS9 BYPASS- DCP 80-1069 01/01/86 000.85.028 STM DUMP. MOD- DCP 81-1060 01/01/86 000.85.029 .COND PMP LO HOTWELL'LVL TRIP DCP 82-1079 01/01/86 000.85.030-. MN'STM CV6670~ DCP 79-1011 01/01/86 000.85.031-- GEN SYNC. DCP 79-1014 01/01/86 000.85.032 " EW SUCTION .DCP'79-1022 01/01/86 000.85.033 EFW FLOW: DCP 79-1025 01/01/86 -}
000.85.034 ~PZR HTR INDICATION DCP 79-1078 01/01/86 000.85.035- RX BLDG VENT HDR DCP 80-1002 01/01/86i L
~000.85.036 - NNI" POWER DC1. 80-1027.' 01/01/86 -[
000.85.037 : DECAY HEAT ISOLATION VALVE RESET CONTROLS DCP 80-1057 01/01/86 000.85.038- ' LL BLOCK VALVES ' & MW STOP VALVES - POWER 'SPLY . DCP 80-1113 01/01/86:
000.85.040 ' MOD. OF PENETRATION RM ISO VALVE- DCP 80-1041 01/01/86- 1 000.85.041 - MSR LEVEL CONTROLS' DCP 79-1060 01/01/86 000.85.042 K07-A4 ALARM MODIFICATION DCP 83-1048 12/31/85
.000.85.043 SOLENOID VALVE REPLACEMENT (79-01B). DCP 83-0134 12/31/85 2-3'
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' UNIT 1 DESIGN DATABASE
-DDB NO. DESCRIPTION ID N3./ DOC PM NO MOD DATE 000.85.044'. REMOVAL OF RZHEAT STEAM DISTILLER DRAIN FLOW ~DCP.82-1017 12/31/85 000.86.000 ALL NON DCP RELATED DR'S'IMPL. IN 1986 000.86.001 PROVIDE MANUAL' TRIP A501/B631 CRD FEED BRKRS DCP 83-1045~ 01/07/86 000.86.003' LPI/HPI FLOW ~ INDICATION DCP 83-1170 04/08/86 l-000.86.006' ICS & NNI POWER; INDICATORS DCP 82-1009 04/30/86
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l 000.86.007 HI LVL ALARMS 0TSG A/B DCP.82-1013 05/19/86-l 000.86.0081- HPI-LPI-CS. DCP 83-1170A 04/08/86 000.86.009 SPDS DCP 80-2123 06/23/86' 000.86.011 SERVICE WATER-PUMP DISCONNECT (P4B) DCP 83-1007 10/01/86 000.86.012 HPI VALVE POSITION. INDICATION. DCP 82-1102 10/01/86' 000.86.015 DISCONNECT SW PRIMARY MU PUMP "B" DCP 83-1008 10/02/86
, 000.86.016 HANDSWITCH RELOCATION DCP 81-1049 10/02/86 i
000.86.017 PANEL C10 C NTROL O MOD DCP 85-1080 12/19/86-000.86.023 MFW BLOCK VLV & LOW LOAD SLOCK .DCP 81-1065 10/09/86 000.86.024 NEUTRON FLUX MEASUREMEhT DCP 84-1004 10/26/86 000.86.025 BREAKER CHANGE IN MCC #61 DCP 79-1062- 10/26/86 000.86.026 HI PRESS AUX SPRAY TO PRESSURIZER DCP 83-1106 '10/27/86 000.86.027 ERV POSITION INDICATION LIGHTS DCP 86-1016 10/27/86-000.86.028 LS-1000-SETPOINT CHANGES DCP 83-1111 11/03/86 000.86.029 MU LETDOWN SYS PRESS INDICATION DCP 81-1072 11/05/86 000.86.030 1R6 RCS PRESSURE INDICATION DCP 84-1003 11/05/86 000.86.031 CNTRL ROOM LIGHTING REPLACEMENT DCP 85-1070 11/07/86 000.86.032 RCP EMG OIL LIFT PUMP LOGIC MOD DCP 83-1098 11/09/86 000.86.033 VALVE POSITION IND FOR CV1428/1429 DCP 83-1129 11/09/86 000.86.034 CONTROL REMOVAL FOR CV2809 DCP 81-1038 11/11/86 000.86.035 D.G. BREAKER ANNUNCIATION DCP 61-1077 11/17/86 000.86.036 RCS PRESSURE INDICATION DCP 84-1003A 11/07/86 000.86.037 . DEMIN. CONDUCTIVITY AIARM MODS DCP 82-1097 .11/19/86
~000.86.038 CORE' FLOOD MOV'S POWER FROM EMERG DIESEL DCP 80-1056 11/23/86 '
000.86.039 PROVIDE' POWER FOR BACKDRAFT DMPR VLV DCP 83-1116A'11/23/86 000.86.040 MONITOR SYS FOR-MS. SAFETY RELF VALVES -
DCP 83-1157 12/02/86 t 000.86.042 HOT LEG LEVEL INDICATION DCP 84-1041B 12/04/86 000.86.042 . PRIMARY RTD REPLACEMENT DCP 84-1041A 12/04/86 000.86.042 - RTD REPLACEMENT DCP 84-1041 12/04/86 000.86.043 CLEAN & DIRTY LIQ RADWASTE ALARM MODS DCP 82-1112 12/05/86 000.87.000 - ALL NON-DCP RELATED DR'S IhPL. IN 1987 000.87.001 QUENCH TANK TEMP INDICATOR DCP 85-1059 03/04/87 000.87.002 EFIC UPGRADE DCP 80-1083A 02/05/87 000.87.003 LOW FLOW TRIP SEAL INJ VALVE DCP 85-1079 02/16/87 2-4
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! DDB'NO. ' DESCRIPTION ID NO./ DOC PM N0' MOD DATE j 000.87.004 PANELS C04/C14. CONTROL MODS 'DCP 86-1035 02/16/87 000.87.005 - COMPUTER' POINTS P437-P440, P499, P500 DBCR 1.070-7.12/02/87
! 000.87.006~- COMPUTER POINT P2940 DBCR 1.082-8 12/02/87 000.87.007 COMPUTER POINTS P1505,.P1544 DBCR 1.079-8 12/02/87 000.87.008 COMPUTER POINTS P589,.P688, P3435 DBCR 1.075-8 12/02/87 000.87.009 AUTO DISPATCH CONTROL SYSTEM DISCONNECTION DCP.82-1051- 02/27/87 000.87.010 ADD CONTACT TO CONTRL CIRCUIT FOR PRS SPR VLV- DCP 80-1031 02/27/87
'000.87.011 MFWP SETBACK CIRCUIT ~ DCP 85-1089 .10/30/87 000.87.012.' ALTERNATE SHUTDOWN 120V AC INST POWER DCP 84-1015- 03/04/87 000.87.013' RCP SEAL WATER RETURN VALVES DCP 82-1098 03/08/87 000.87.014 - MOD OF CV-2214/CV6203 ISO VALVES DCP 80-1042 03/10/87 000.87.015 IR7 EFW MODIFICATIONS DCP 85-1012 03/10/87:
000.87.016 CONTAINMENT PURGE CONTROL SYSTEM MOD DCP 80-1136 03/11/87 000.87.017 RCP SEAL MODIFICATION' DCP 81-1051 03/18/87-000.87.018 RCP CONT BLEED OFF BYPASS TO Q.T.- DCP 81-1066 03/30/87 l 000.87.019 PREVENT DH VLVS CV-1050/1410 FROM AUTO-CLOSE DCP 83-1060' 03/14/87 000.87.020 CHANGE PWR SUPPLY TO BORIC ACID PUMPS- DCP 82-1057 03/14/87 000.87.021 COMPUTER POINTS P499, 500, 503, 504, 545, 546- DBCR 1.068-7 12/02/87 000.87.022 COMPUTER POINT P3162 DBCR 1.073-7 11/23/87 000.87.023 FWP TURBINE CONTROL UPGRADE DCP 86-1002. 03/18/87 000.87.024 REPLACE CV-3812/3813 I;CP 80-1135 03/18/87 000.87.025' ' CORE FLOOD TANK POINTS / DELETE INCORES DBCR 1.078-8 11/25/87 000.87.026 GENERATOR DIFFERENTIAL RELAY FOR DG1/DG2 DCP 81-1086 03/18/87 000.87.027' DC POWER SYSTEM MODIFICATIONS DCP 83-1119 03/24/87 000.87.028. MAIN CHILLER DELAY DCP 82-1095 03/11/87 000.87.029 ADDITIONAL CLASS 1E POWER IN ANO-1 DCP 82-1111 04/01/87 000.87.030 CV-1000 ISOLATION DCP 83-1012 04/01/87 000.87.031 DH BYPASS-0UTLET VLV/ AIR. BLOCK VLVS DCP 82-1074 04/03/87 000.87.032 COMPUTER POINTS P417, P418, P419 DBCR 1.065-7 11/23/87 000.87.033 VSF2, RX BLDG PURGE DCP 80-1178 05/08/87 000.87.034- REMOVE VIBRATION MONITOR FROM C12 DCP 85-1063 05/10/87 000.87.035 ' COMPUTER POINT: P378 DBCR 1.063-6 11/23/87 000.87.036 REPLACE:LT-1000 PRESS LVL INDICATION DCP 83-1075A 05/11/87 000.87.036 .-REPLACE LT-1000' PRESS LVL INDICATION DCP 83-1075B 05/11/87 .
000.87.037 REPLACE LT-1000 PRESS LVL. INDICATION DCP 83-1075 07/27/87 I 000.87.038- REMOVE TR6613 DCP 83-1063 05/12/87 000.87.039 COMPUTER POINT P 3307 DBCR 1.062-6 11/23/87 000.87.040 COMPUTER POINTS P1559, P1560 DBCR 1.060-6 11/23/87 000.87.041- COMPUTER POINTS P2757-P2762 DBCR 1.064-6 11/23/87 6
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- UNIT 1 DESIGN DATABASE-O-
DDB NO.- DESCRIPTION.: ID NO./ DOC PM NO- MOD DATE-000.87.042 COMPUTER. POINT P1653' DBCR 1.061-6 11/23/87 000.87.043 ANNUNCIATOR K06.U" GRADE- :DCP 82-1030 11/16/87 000.87 044 ANNUNCIATOR K15/K16 MODIFICATION.
DCP 82-1004. 11/16/87.
000.87.045 - ' ANNUNCIATOR PANEL K12 UPG2ADE DCP 82-1056 11/16/87 000.87.046 : ANNUNCIATOR' UPGRADE DCP.82-1041 11/16/87i 000.87.047 ANNUNCIATOR UPGRADE-FOR PANEL K11 DCP 82-1027 11/16/87-000.87.048 PHASE 1. MODIFICATION'0F ANNUNCIATOR K12 DCP 82-1008 11/16/87 000.87.049 ANNUNCIATOR UPGRADE FOR K12, K15 & K16 DCP 82-1028 11/16/87.
000.87.050 ANNUNCIATOR K04/K05 UPGRADE- DCP 82-1029 11/16/87 000.87.051 ANNUNCIATOR K10 UPGRADE DCP 82-1031 11/16/87-000.87.052- ANNUNCIATOR UPGRADE ~ DCP 82-1025 11/16/87 000.87.053 ANNUNCIATOR UPGRADE DCP 82-1024 11/16/87^
000.87.054 ANNUNCIATOR K01/K02 UPGRADE DCP 82-1020 11/16/87 000.87.055 ANNUNCIATOR UPGRADE DCP 82-1026 '11/16/87' 000.87.056 H2 ANALYZER POWER INDICATION ON C26 DCP 82-1072 11/17/87-000.87.057 ANNUNCIATOR K04/K05 UPGRADE DCP 82-1029 11/04/87 000.87.058 SPARE OUT INCORES DBCR 1.059-6.11/23/87' 000.87.059 COMPUTER POINTS P735-P738 DBCR 1.058-6 11/23/87-000.87.060 - COMPUTER POINT P436 DBCR 1.057-6 11/23/87 000.87.061- COMPUTER POINTS P3087 DBCR 1.056-6 11/23/87 000.87.062 SILENCE MEANS.TO TRBL HORN FOR CORE FLOOD TK DCP'80-1054 11/23/87 000.87.063- COMPUTER' POINTS P417-P419- DBCR 1.054-6 11/23/87 000.87.064 PASS HANDSWITCH ON C26 DCP 82-1071 11/17/87 000.87.065- POST-ACCIDENT SAMPLING SYSTEM DCP.80-2043 11/18/87.
000.87.066 - LTOP & PRESSURIZER HTR INTERLOCK SETPT CHGS .DCP 87-1115 12/15/87 000.87.067 MODIFY PMS DATABASE DBCR 1.066-7 12/02/87 000.87.068' MODIFY PMS DATABASE DBCR 1.069-7 11/23/87 000.87.069 . MODIFY NSSS BOP LOGS SEL.145-8 11/16/87 000.87.070 -MODIFY'NSS HOURLY LOGS SEL.146-8 11/16/87 000.87.071 MODIFY PMS PER DBCR' DBCR 1.086-8 12/14/87 000.87.072 IMPLEMENT PLANT CHANGE SEL1.144-8 12/21/87' 000.87.073 MODIFY PMS DATABASE. DBCR'1.078-8 12/01/87 000.87.074 TURB THROTTLE Pi! ESSURE LIMITER DCP 81-1012 ~05/12/87 000.87.075 COMPUTER POINT 3161- DBCR 1.072-1 11/23/87
.000.87.076 REPLACE RCP SEAL RECORDER DCP 84-1027 05/29/87 000.87.077 ALARM DELETIONS ON K11 C-7, D-7 DCP 82-1093 11/16/87'
-000.87.078- DELETE CITY WATER SYSTEM ALARMS ON K15- DCP 83-1001 11/16/87 000.87.079' EFW CHECK VALVE' INSTALLATION DCP 86-1005. 02/05/87 000.87.080 CONDENSATE STORAGE TANK INSTRUMENT ANALYSIS DCP 84-1029A 02/05/87
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LDDB NO. DESCRIPTION- ' ID NO./ DOC' PM NO4 LMOD DATE l 000.87.081 CONDENSATE' STORAGE TANK' TIE-INS: DCP 84-1029.7 02/05/87?
000.87.082?1R6 PROIECT' EFW SOLENOID VALVES DCP~83-1134; 02/05/87; ;;
000.87.083 TRANS M.S. ATMOS. DUMP-VLVS TO DIESEL GEN.
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000.87.085,lEFW UPGRADE. TURBINE-REPLACEMENT .DCP.82-1050L02/05/87"=
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000.87.086. REPLACE ACTUATORS FOR CV-2618.AND CV-2668; DCP,81-1043a02/05/87?
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000.87.087- ' CONTROL ROOM ANNUNCIATOR' DEFICIENCIES.- ;DCP 81-1083 11/04/87: ;
, '000.87.088- C09iMODIFICATION.
~DCP 82-1003 402/05/87., '
000.87.089 COMPUTER. POINTS P1565-P1569_ DBCR 1.053-6 :11/23/871 '
000.88.000~ ALL-NON DCP RELATED DR'S IMPL. IN 1988' l 00C.88.001. CHANGE LIGHTS BETWEEN TERMINALS 517 & 507 .DCR 519A . 04/18/88l [
000.88.002 : UPGRADE LVL-CONTROL SYS FOR VAC.. DEGAS T14:- DCP.80-1016 03/22/88( ;
000.88.003 MODIFY'"A":SG STARTUPLBUFF POWER TO NNI "Y"' DCP 80-1048 03/15/88. i 000.88.004 iTEMPLINDICATIONS.TO. PLANT" COMPUTER DCP 80-1096 .06/28/88: !
000.88.005- REPLACE.SERVICErWATER SLUICE: GATES DCP 80-1109 05/06/88 l
, 000.88.006 MONITORING CAPABILITY FOR ADDITION STATR WIND DCP.80-1162 05/06/88. ]
000.88.007 - MODIFY' DIESEL GEN LUBE OIL SYSTEM K4A/K4B' 'DCP 80-1172 08/04/88' ?
000.88.008 TURBINE.. THROTTLE; PRESSURE LIMITER DCP 81-1012 05/26/88 o 000.88.009 - AUTO PROHIBIT CIRCUIT FOR S/U TRANSFORMER #2 DCP 81-1021 05/05/88 j 000.88.010 MODIFY DECAY: HEAT UNIT / COOLERS DCP 81-1023' 05/19/88 1 000.88.011.- RELOCATE RECORDING PNT RI-2400 TO C25 RECORDR
.DCP 81-1067 05/06/88-000.88.012 'CHNGE DG'BKR' ANN FROM AUTO CLOSE TO FAILLCLSE DCP 81-1077' 05/06/88 9 000.88.013 ' ADD OPEN SEAL-IN TO CV'S ON SCHEME E-235 DCP.82-1023 04/25/88 1 000.88.014 H2 PURGE HTR SETPOINT MODS DCP 82-1065 '04/18/88 j 000.88.015 01B REPLACE H2 PURGE TEMP SENSORS. DCP 83-1158 04/18/88-000.88.017 79-01B: PRESSURE TRANSMITTER UPGRADE DCP 83-1049 05/23/88 ,
000.88.018 SET' POINT ANALYSIS.RPS:& ESAS DCP 83-1049A 05/23/88 000.88.019- SG PRESSURE INDICATION TO SPDS- .DCP 83-1057 05/17/88 000.88.020.: CHANGE L&N SPEEDOMAX "W" TYPE' RECORDERS DCP 83-1064 07/31/88 i 000.88.022 ETURBINE BEARING LIFT OIL SYSTEM MOD DCP 83-1068 .07/26/88 l 000.88.023 MODIFICATION OF U/V-RELAYS- DCP 83-1070 04/25/88
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000.88.024' H2/02--WASTE GAS' ANALYZER C119A DCP 83-1077 06/09/88 000.88.025 FW HTRLOVER; PRESSURIZATION. PROTECTION DCP 83-1101 05/11/88 000.88.026; INSTALL.UNITJ1-'KEYLOCK SWITCH' DCP 83-1117 .04/14/88 -
000.P8.027' BWST LEVEL INDICATION. DCP 83-1153 ^ 05/11/88 l 000.88.028: RG 1.97 CORE ~ FLOOD TANK LEVEL' DCP 83-1154 -04/25/88 :i 000.88.029- MSR. UPGRADE. , DCP 83-1179 05/11/88- 1 4 000.88.030 . FLOATING' LID'FOR CONDENSATE STORAGE-TANK DCP 83-1182 05/31/88 ;
000.88.031 ' REG. GUIDE 1.97' ELECTRICAL SYSTEM MODS- DCP 83-1163 07/31/88 ,
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_ . . a a= n _4- __ __.___ _____ ___ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ __
O O UNIT 1 DESIGN DATABASE d
DDB NO. DESCRIPTION DCP 84-1046 06/09/88 t 000.88.032 ROTORK OPERATOR REPLACEMENT DCP 85-1014 05/19/88 000.88.033 -ANO-1R7 ICW BYPASS LOOP TEMP CNL DCP 85-1032 05/23/88 000.88.034 EMERGENCY DIESEL GEN ALARM UPGRADE DCP 85-1033 06/09/88 000.88.035 RG197 REPLACEMENT OF LIMIT SWITCHES DCP 85-1057 04/18/88 000.88.036 HYDROGEN ANALYZER MODIFICATION DCP 86-1044 04/29/88 000.88.037 MODIFY CONTROL SCHEME FOR CV-4642 DCP B6-1087 04/29/8J 000.88.038 MAIN TURBINE VIBRATION TRIP JUMPERS l DCP 86-1088 08/22/88 l 000.88.039 PRESSURIZER HTR CABLE REPLACEMENT DCP 86-1098 05/26/88 000.88.040 MOVATS - VALVE OPERATOR MODS DCP 86-1117 05/26/88 000.88.041 ACTUATOR REPLACEMENTS FOR CV2620/2627/2870 DCP 86-1118 05/26/88 000.88.042 REPLACEMENT OF VALVES CV1300/CV1301 DCP 86-1121 04/18/88 000.88.043 MFW TURBINE TRIP MODIFICATIONS DCP 86-1131 05/26/88 000.88.044 MOVATS - VALVE AND ACTUATOR MODS DCP 86-1138 05/26/88 000.88.045 MOVATS - MODS TO VALVES CV1270/1271/1272 DCP 87-1095 04/28/88 000.88.046 CONT ATMOSPHERE & LOCAL COMPONENT TEMP MONITR DCP 80-1041 05/'2 M8 000.88.047 MOD OF PENETRATION RM ISO VLV AUX C,RL RELAY DCP 79-1060 05/19/88 000.88.048 MSR LEVEL CONTROLS DCP 86-1107 05/26/88 000.88.049 MOVATS - MODIFICATIONS 1N) VALVE CV-1273 DCP 86-1108 04/28/88 000.88.050 REMOVAL OF VALVE CV-3903 DCP 87-1108 10/12/88 000.88.052 BORIC ACID BATCH ONTROLLER REPLACEMENT DCP 79-1001 09/29/88 000.88.053 HIGH PRESSURE INJECTION DCP 82-1101 01/25/88 000.88.057 MFW FLOW TRANSMITTERS DCP 87-1119 01/31/88 000.88.058 PENETRATION RM VENTILATION SYSTEM MOD DCP 84-1069 02/19/88 000.88.059 HYDROGEN RECOMBINERS RE: OP1104.31
~
DCP 80-1083 05/06/88 000.88.061- INTERFACING BETWEEN EFIC CAB W/ PLANT COMPUTER DCP 80-1004 06/14/88 000.88.062 REMOTE OPERATED RCS HIGH POINT VENTS DCP 83-1084 07/26/88 000.88.063 SECONDARY SYSTEM SAMPLE PC 87-2873 02/19/88 000.88.064 REPLAC"O SCALE ON QI-7457 DCP 84-1014C 09/26/88 000.88.065 ICC MDS CABINETS 000.89.000 ALL NON DCP RELATED DR'S IMPL IN 1989 DCP 83-1144 03/10/89 000.89.001 DIESEL GENERATOR CLOSING CIRCUIT MOD DCP 86-1006 04/26/89 000.89.002 SAFETY SYSTEMS DIAGNOSTIC INSTRUMENTATION DCP 86-1126 05/05/89 000.89.003 REVERSE POWER RELAY ADDITION DCP 86-1103 02/01/89 000.89.004 ANO-1 ALARM SYS UPGRADE, PHASE 1 DCP 83-1128 12/14/89 000.89.005 TURB BLDG DRAIN LINE RADIATION MONITOR DCP 83-1136 02/01/89 000.89.006 RX COOLANT PUMP SEAL CART. REPLACE DCP 84-1014E 04/25/89 000.89.007 INSTALL 8 ADDITIONAL QUAL CORE EXIT THERMCPL DCP 85-1022 03/06/89 000.89.008 ANO-1 CONT SUMP DRN VLV & OPERATOR REPLACE DCP 85-1085 03/17/89 000.89.009 FIRE PROTECTION DETECTION 2-8 i
A O O O('s V UNIT 1 DESIGN DATABASE ID NO./ DOC PM NO MOD DATE DDB NO. DESCRIPTION DCP 85-1105 12/27/89 000.89.010 CONTROL RM INSTRUMENT FAILURE INDICATION DCP 86-1070 04/27/89 000.89.011 RCP CONTROLLED BLEED 0FF CHECK VLV ADDITION DCP 86-1101 06/29/89 000.89.012 EFW INITIATION ON FALSE LOW LVL SIGNAL DCP 86-1106 01/18/89 000.89.013 CV-1009 MOVATS MODIFICATION DCP 87-1013 01/31/89 000.89.014 SERVICE WATER SYSTEM PIPING & VALVE REPLACE DCP 87-1048 06/30/89 000.89.015 MAIN FEEDWATER TRIr REDUCTION DCP 87-1070 11/28/89 000.89.016 ICS SIMPLIFICATION DCP 87-1098 01/30/89 000.89.017 DECAY HEAT SYS MOV MODS CV1414,1415,2415,2419 000.89,018 CV-1221 LETDOWN ISOLATION VALVE REPLACEMENT DCP 87-1101 03/06/89 000.89.019 FIRE PROTECTION SYS MOV MODS, CV-5611 DCP 87-1103 03/06/89 DCP 88-1015 05/12/89 000.89.020 RB TEMP MONITOR INSTRUMENTATION DCP 88-1075 05/05/89 000.89.021 TSAT/ES MODIFICATIONS DCP 88-1078 01/18/89 000.89.022 GEAR MODS TO CV3811,3820,3821,3822 000.89.023 GEAR MODS TO CV2416,2418,2420 DCP 88-1080 01/18/89 000.89.024 GEAR MODS TO CV3823,3824 DCP 88-1082 01/17/89 000.89.025 GEAR REPLACEMENT FOR CV1300,CV1301 DCP 88-1084 01/18/89 DCP 88-1103 01/18/89 000.89.026 CV1820 VALVE REPLACE AND ACTUATOR MOD DCP 87-1114 03/21/89 000.89.027 DOSE ASSESSMENT SYSTEM UPGRADE 04/25/89 DECR 5.091 000.89.028 REMOVE ENGINEERING RANGE CK FOR DBASE POINTS 04/25/89 DBCR 5.088 000.89.029 RESET ALARM VALUES (HIGH ONLY) SPDS.044 04/24/89 000.89.030 DBAS: EXPANSION, SOURCE CODE UPDATE, SYSTEM DOC DBCR 5.069 04/25/89 000.89.031 ADD 18 LEVEL STATUS POINTS DBCR 5.097 04/25/89 000.89.032 ADD 8 ICC CET POINTS SPDS.059 04/25/89 000.89.033 ADD NEW CET'S TO GRAPHICS DISPLAYS D3CR 5.099 04/26/89 000.89.034 MODIFY RANGE OF REACTOR BLDG COOLER FLOWS 04/24/89 DBCR 5.098 000.89.035 DELETE 4 RCP SEAL TEMP POINTS DBCR 5.094 04/24/89 l
000.89.036 ADD 4 ANALOG POINTS SPDS.055 04/24/89 1
000.89.037 MODIFY RCSI DISPLAY SPDS.061 04/24/89 000.89.038 ADD NEW LOW PRES TRIP SET PT DATA IN ATOG DIS PC 88-2401 04/25/89 000.89.039 CHANGE PS3000 SETPOINTS DCP 86-2132 04/25/89 000.89.040 MODIFY PLANT PAGING SYSTEM PC 88-3511 04/25/89 000.89.041 CORRECT LOGIC FOR K10-A6 PC 85-1831 04/25/89 000.89.043 ICW BOOSTER PMPS PRESS SWITCHES PS2286,2296
( DBCR 5.092 05/11/89 l 000.89.046 ADD DIAGNOSTIC INSTRUMENTATION POINTS DBCR 1.089-9 05/12/89 000.89.047 MODIFY PMS DATABASE DCP 88-1012 06/18/89 000.89.049 CHILLED WATER PUMP REPLACEMENT DCF 88-1108 12/14/89 000.89.050 DELETE MU45A-D DEFINITION FROM CCDB 000.90.000 ALL NON DCP RELATED DR'S IMPL. IN 1990 SPDS.073 03/28/90 000.90.002 PSHT CORRECTION 2-9
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O O O UNIT 1 DESIGN DATABASE ID NO./ DOC PM NO MOD DATE DDB NO. DESCRIPTION E-202.SH2 REV1 102.49.016 PZR-HTR E-203 REV6 102.49.019 PZR HTR E-205 REV6 102.49.021 PZR SPR MOV E-206 REV1 102.49.022 QT COND MU E-207 REV3 102.49.023 QT XFR PMP E-208 REV6 102.49.024 QT ISOL MOV E-246 REV8 102.49.025 QT&RX BLDG VENT E-247 REV8 102.49.026 QT&RX BLDG VENT 102.49.027 RC,MU,DH RCDR E-324 SH1 REV3 102.49.028- RC,MU,DH RCDR E-324 SH2 REV5 E-331 SH8 REV5 102.49.029 MISC INSTR E-196 SH1 REV14 102.49.031 RCP'S E-204 REV16 102.49.033 PZR RELIEF VLV M-230 REV20 102.55.002 RCS M-238 REVIS 102.55.003- CRD P&ID M-416 SHI REV6 102.57.001' RCS M-416 SH2 REV8
'102.57.002 RCS 102.57.005 PZR LVL W/ TEMP COMP M-3700-1 102.66.002 VOL OF RCS M-3700-2 102.66.003 RCS DATA M-3750-1 102.66.004 QT OVERALL SIZE M-3770-5
.102.66.005 PZR ELECT RELIEF VLV LEAKAGE M-3740-1 102.66.006 GAS VOL PZR H-3750-2 102.66.009 QT SIZE M-3750-5 102.66.010 QT LEAK CAP M-3750-6 102.66.011 QT RUPTURE DISK-M-3770-3 102.66.013 PZR RELIEF VLV PIP M-3770-4 102.66.014 PZR ERV-PILOT VLV 102.74.001 RCP SEAL FAILURE 102.75.001 RCP DCR-206B l
102.75.002 RCS DCP 79-1051 102.75.003 ANN IDCR-1-79-29 102.75.004 RCS DCP80-1086 102.75.005 RCS DCP 80-1030 102.75.006 RCS DCP 80-1031 103.12.001 CAL SHEET HIC-1428 103.12.002 CAL SHEET HIC-1429 103.14.001 P34A,B PMP PERF CURVE M-1H-43-1 l
2-11
O O O
. UNIT 1 DESIGN DATABASE ID NO./ DOC PM NO MOD DATE DDB NO. DESCRIPTION 103.14.002 P34 PMP PERF CURVE M-1H-45-2 I
103.49.001 DHR CONT VLV E-182 SH2 REV7' 103.49.002 DHR MOV'S E-182 SHI REV13 103.49.004 DHR RETURN ISOL VLV E-182 SH3 REV5 103.49.005 DHR RETURN ISOL VLV E-182 SH4 REV1 103.49.006 DHR ISOL MOV'S E-183 SH1 REV9 E-183 SH2 REV1 103.49.007 DHR ISOL MOV 103.49.008 DHR-BRG CLR E-186 REV4 103.49.009 DHR-ANN AUX RELAY E-187 REV4 103.49.012 SCHEM-PLT AUX CONT DHR E-265 SHI REV6 103.49.013 SCHEM-PLT AUX CONT DHR E-265 SH2 REV8 103.4 1.014 SCHEM-AUX BLDG DHR CLR MOV E-284 REV6 103.49.015 DH REMOVAL PMP E-181 REV12 103.49.017 LPSI-SYS AUX DIAG EDS-0111-011-107 103.55.002 DHR M-232 REVI5 103.57.001 DHR M-418 SHI REV7 103.57.002 DHR M-418 SH2 REV7 103.57.005 DH PMP INLET HRD TEMP 103.57.006 DH LOGIC DHR 103.66.007 NPSH SUMP TO PMP M-3820-7 103.66.008 DH PHP P34A CHAR M-3820-8 103.66.010 DH PMP P34B CHAR M-3820-10 103.66.014 EMERG CLG SYS FOR REACTOR M-3820-4 104.14.001 P36A,B PMP PERF CURVE M-1J-49-2 104.14.002 MU-PIB,P36B PMP PERF CURVE M-1J-48-2 104.49.001 PLT AUX CONT SYS E-264 SH1 REV8 104.49.002 PLT AUX CONT SYS E-264 SH2 REV8 104.49.003 ' PLT AUX CONT E-264 SH3 REV3 104.49.004 PLT AUX CONT E-264 SH4 REV5 104.49.005 COND TO MU&PURIF SYS MOV E-194 REV4 104.49.006 PRI MU PMP A,C E-211 REV8 104.49.007 PRI MU PMP B E-212.REV8 104.49.008 PRI HU PMP A,C LO PHP E-213 REV5 104.49.009 PRI MU PMP B LO PMP E-214 REV8 104.49.011 L/D CLR INLET MOV E-215 REV8 104.49.012 L/D CLR DISCH MOV E-216 REV7 E-218 REV9 104.49.013 L/D BLEED / FEED MOV 104.49.014 PRI MU & RX BLDG SPR ISOL VLV E-219 REV9 l 104.49.015 PRI MU ISOL VLV E-220 REV2 2-12 l
UNIT 1 DESIGN DATABASE-DDB NO. ' DESCRIPTION: ID NO./ DOC PM NO MOD DATE-104.49.016 CH ISOL MOV'S . E-221 REV10 104.49.017.- PRI MU SYS SV'S E-222 REV7 104.49.018- PRI MU ISOL SOV'S' E-223 REV2 104.49.019 PRI MU FILTER COND WTR INL VLV E-224 REV8 104.49.0f PRI MU TK H2 SV' E-225 REV5 104.49.02.. ISOL-SV'S E-235 REV8 104.49.022 PRI:MU TEMP RCDR E-321 REV3 104.49.023 MISC INSTR E-331 SH15 REV3 104.49.024 MISC INSTR E-331 SH17 REV4 104.55.001 MAKEUP & PURIFICATION SYS P&ID M-231 REV17 104.57.001 MU6PURIF/HPI M-417 SH1 REV4 104.57.002 MU&PURIF/HPI M-417 SH2 REV5 [
104.57.003 MU&PURIF/HPI M-417 SH3 REV5 '
104.57.004 MU&PURIF/HPI M-417 SH4 REV1
'104.57.005 MU&PURIF/HPI M-417 SHS REV1 104.57.011- L/D FLO CONT 104.57.012 MU PMP DISCH HDR PRESS 104.57.013 LOGIC L/D FLOW 104.66.002 - PRESS DROP-T4 TO P36B M-3800-2 104.66.004 N16 DECAY IN L/D LINE M-3800-4 104.66.015 L/D LINE ACTIVITIES IN AUX BLDG M-3800-15 104.66.019 MU TK GAS EXP M-3800-19' 105.30.001 OTSG INSTR MAN (M-1-22-06) 105.49.001 OTSG MN FDWTR STOP VLV- E-316 REV14 105.49.002 -0TSG LOW LOAD MOV'S E-317 SH1 REV12 105.49.003 OTSG LOW LOAD MOV'S E-317 SH2 REV3 105.49.004-' OTSG LOW LOAD MOV'S- E-317 SH3 REV4
- 105.66.001 OTSG SKIRT TEMP M-3600-3 105.66.002' OTSG LEAKAGE M-3720-1 105.66.003 -MN STM RELIEF VLV CAPACITY M-3720-2 105.66.004 MN STM RELIEF VLV, M-3720-3 105.66.005 MSL&WL BREAK OUTSIDE CONT M-3720-4 106.30.001 CRD. INST. MAN. VOL 2.(M-1-37) 106.30.002 CRD INST MAN VOL 1 106.30.004 CRD INST MAN VOL 3 106.49.001 CRD CW PMPS-SCHEM DIAG
~
E-237 SH1 REV6 106.49.002 CRD CW PMPS- PREFILTER-SCHEM DIAG E-237 SH2 REV3 106.49.003 WIR BLK DIAG-RX CONT ROD PWR SUPPLY- E-256 SH1 REV7 106.49.004 WIR BLK DIAG-RX CONT ROD PWR SUPPLY: E-256 SH2 REV9 2-13
~
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-UNIT 1 DESIGN DATABASE
~
t- DDB NO. DESCRIPTION' ID NO./ DOC PM NO MOD DATE.
106.49.005 ;WIR'BLK DIAG-RX CONT ROD PWR SUPPLY E-256 SH3 REV4 106.49.006:;RX CRD E-257 SH1 REV4 106.49.007 RX CRD. E-257 SH2 REV3
!' 106.49.008 :RX CRD E-257 SH3 REV2-l 106.49.009 'RX CRD -E-257 SH4 REV3 106.49.010 RX CRD E-257.SHS REV5 106.49.011 RX~CRD E-257 SH6 REV7-
-106.49.012 -MISC INSTRUMENTATION E-331 SH10 REV5 106.49.013'~ WIR DIAG-SYS LOGIC. CAB M-1C SH383 REV3 106.66.001 CRD COOLING M-3600-4 108.14.001 P35B PERF CURVE M-1H-53-2 108.14.002' P35B PERF CURVE- M-1H-52-2 108.14.003 RX BLDG PMP PERF. CURVE -
M-1H-44-2 108.49.001 ' RX BLDG SPR PMP-SCHEM- _- E-241'REV8 108.49.002 RX BLDG SPR MCV E-242 REV7 108.49.003 -RX BLDG SPR E-267 REV5 108.49.005 'RX BLDG SPR-AUX DIAG EDS-0111-011-104 108.55.001 RB SPR & CORE FLOOD- M-236 REV16 108.57J001 RX BLDG SPR &' CORE FLOOD M-422 REV7 108.57.003 CORE FLOOD TANK PRESS-108.57.004 ' RX BLDG SPR FLOW 108.66.025 'NPSH .. 'M-2880-22 109.49.001. CLN' LIQ.RADWASTE MISC VLV E-395 REV11 109.49.002 CLN LIQ RADWASTE INST- -E-405 SH1 REV4 109.49.003 CLN LIQ RADWASTE INST E-405 SH2 REV10 109.49.004 CLN LIQ RADWASTEl INST: E-405 SH3 REV5 109.49.005 CLN LIQ RADWASTE-INST E-405 SH4 REV7
.109.49.006 CLN LIQ RADWASTE INST E-405 SH5 REV8
.109.49.007 CLN LIQ RADWASTE INST E-405 SH6 REV5 i
109.49.008 CLN' LIQ RADWASTE' INST E-405 SH7 REV5 109.49.009 DIRTY RADWASTE INST- E-406 SH1 REV3 I
109.49.010 DIRTY RADWASTE INST E-406 SH2 REV4 109.49.011 DIRTY RADWASTE INST E-406 SH3 REV5 109.49.012 DIRTY RADWAGTE INST E-406 SH4 REV3-109.49.013 - VAC DEGAS =DR PMP .E-390 SH1 REV6
'109.49.014 DEGAS VAC PMP E-391 SH1 REV7 109.49.015 VAC DEGAS CIRC PMP- E-397 SH1 REV5 109.55.001 .DRTY RADWASTE M-213 REV18 109.55.005 CLN LIQ RADWASTE M-214 REV17 2-14
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%) v UNIT 1 DESIGN DATABASE ID NO./ DOC PM NO MOD DATE DDB NO. DESCRIPTION 109.57.001 DIRTY RADWASTE M-408 SH1 REV4 109.57.002 DIRTY RADWASTE M-408 SH2 REVO 109.57.006 CLN LIQ RW M-409 SH1 REV6 110.02.001 FSAR ACC' ANAL M-4135-3 j 110.02.002 FSAR ACC ANAL M-4135-10 110.49.001 WASTE GAS COMPRESSOR E-402 REV8 110.49.002 RW CONT HISC SV'S E-404 SH1 REV6 110.49.003 RW CONT MISC SV'S E-404 SH2 REV7 110.49.005 GS RW INST E-407 SH2 REV6 110.49.006 GS RW INST E-407 SH3 REV8 110.49.007 GS RW INST E-407 SH4 REV3 110.49.009 GS RW INST E-407 SH6 REV3 110.57.001 GASEOUS M-215 REVIS 110.57.002 GS RW SYS M-410 REV5 113.02.001 FSAR RX BLDG DBA PRESS M-4135-22 113.49.001 MISC INFO E-331 SH11 REV3 113.49.003 RX BLDG ISOL SYS-AUX EDS-0111-011-112 113.49.004 H2 PURGE SYS E-396 SH1 REV3 113.49.005 H2 PURSE SYS E-396 SH2 REV7 113.49.006 H2 PURGE SYS E-396 SH3 REV4 113.49.007 H2 PURGE SYS E-396 SH4 REV5 113.49.008 H2 PURGE SYS E-396 SHS REV8 113.66.001 CONT ALLOW-LEAK RATE M-4330-1 113.66.006 CONT PRESS ANAL M-3860-4 113.66.007 CONT PRESS ANAL M-3860-5 113.66.008
SUMMARY
CONT VOL M-3860-6 113.66.011 POST LOCA H2 PURG DOSE M-3890-4 113.66.019 MHA CALC-CONT ROOM DOSE M-4110-12 113.66.020 ACTIV IN CONT ROOM M-4110-13 113.66.021 CONT LEAKAGE M-4110-14 113.66.022 N16 ACTIV M-4110-17 113.66.023 RX FP-11 FAIL FUEL M-4110-18 113.66.030 CS-137-1% FAIL FUEL M-4110-25 113.66.048 CONC AT PLT BIDS M-4110-43 118.49.001 TRT WST MON PMP E-392 REV5 118.49.002 CLN WST RCVR RECIRC PMP E-393 REV2 118.49.003 CLN WST RCVR TK XFR CI' E-394 REV3 201.06.001 - FDWTR FTR INSTR. MAN.
201.12.001 COND&FV HTR INSTRUMENTATION DATA 2-15
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UNIT 1 DESIGN DATABASE ID NO./ DOC PM NO MOD DATE DDB NO. DESCRIPTION-
, 201.14.001 COND PHP TECH MAN 201.17.001 CONDENSER
-201.30.001 INSTR. BOOK-NUC FEED PUMP DRIVE TJR. (M-19-20
'201.37.001 FDWTR HTR DATA SHEETS 201.49.001 W HTR BLDR TRIP VLV CONTROL E-167 REV4 E-168 REV4 201.49.002 W HTR BLDR TRIP VLV POS IND 201.49.003 COND PMP E-306 SH1 REV8 201.49.004 COND PMP- E-306 SH2 REV4 201.49.005 COND PMP E-306 SH3 REV4 201.49.006 COND PMP E-306 SH4 REV3 201.49.0' COND MISC SV E-308 SHI REV11 E-308 SH2 REV4 201.49.008 COND MISC SV 201.49.009 AFW PHP E-309 8H1 REV9 201.49.010 AW PMP E-309 SH2 REV3 l E-314 REV6 l
201.49.011 COND XFR PHP 201.49.012 MW PMP TURB TRIP & RESET E-285 REV7 l
201.49.013 MW PHP TURB AUX CONTROLS E-286 SH1 REV6 E-286 SH2 REV3 201.49.014 MFW PMP TURB AUX CONTROLS E-287 REV11 201.49.015 MW PMP TRIP AUX CONTROLS 201.49.016 MFW PMP TURNING GEAR E-288 REV10 201.49.017 MFW PMP AC LO PMP E-289 REV8 201.49.018 MW PHP TURB EMERG LO E-290 REV7 E-291 REV5 201.49.019 MFW PHP LO VAPOR EXTRACTOR 201.49.020 MFW PMP X0VR VLV E-292 REV5 E-328 REV4 201.49.021 MW PHP TURB VIBRATION E-329 REV8 201.49.022 MW PMP TURB TEMP & THRUST E-331 SH2 REV9 201.49.023 MISC INSTRUMENTATION E-331 SH4 REV3 201.49.024 MISC INSTRUMENTATION E-331 SH5 REV8 201.49.025 MISC INSTRUMENTATION E-331 SH6 REV7 201.49.026 MISC INSTRUMENTATION E-331 SH18 REV3 201.49.027 MISC INSTRUMENTATION
-M-19 SH2 REV8 201.49.031 TURB TRIP & RESET M-204 SH1 REV28 201.55.001 P&ID COND&FW l
201.55.006 P&ID COND FW .M-204 SH2 REV5 M-402 SH1 REV6 201.57.001 COND&FW M-402 SH2 REV6 201.57.002 COND&FW 201.57.004 COND&FW M-402 SH4 REV6 201.57.011 COND&FW M-402 SH3 REV10 201.60.001 -FW HTR EIA/B 2-16
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-UNIT 1-DESIGN DATABASE:
! ;DDB NO.- DESCRIPTION ID NO./ DOC- PM NO MOD DATE l 202.75.004 EFW IDCR 1-79-30 ,
i 203.49.001 MS LINE ENCL EXH FANS- E-348 REV3 203.49.003 TURB MS PRESS E MP RCDR E-180 REV7 t
- 203.49.004 COND STM DUMP VLV ;E-307 REV3 203.55.002 MAIN STM M-202 REV18 203.57.002- TURB~DHR PRESSURE 203.66.001 STM LINE CRITICAL CRACK- M-4135-19 203.66.002 STM LINE INVENTORIES. M-4135-17 '
l 203.66.003 MS-LSR ASSY OPER @ GUAR PT. M-4510-8 203.66.004 ARRGT PIPING STM"FLO- M-4510-9 ,
203.66.005 MS WALL THICKNESS M-4510 '
203.66.006 MS LINE PRESS DROP' M-4510 203.66.007 MS; PIPING DELTA P M-4510-4.
203.66.008 MS.LINE PRESS DROP' M-4510-6 203.66.009 MS SAFETY VLV' M-3770-1 203.66.026 MS RELIEF.VLV VENTS M-4290 203.66.028 ATMOS VENT,VLV M-4540-4 204.55.001 EXT STM HDR VENT DRN M-205 SH1 REV20 204.55.002 EXT _STM HDR VENT DRN M-205 SH2 REV12 205.49.0C1 SU; BOILER FW PUMPS E-311 SH1 REV6 205.49.002 SU BOILER FW PUMPS E-311 S32 REV3 205.49.003 SU BOILER FW PUMPS E-311 SH3 REV2 205.49.004- SU BOILER FORCED DRAFT FANS E-312 REV4 205.66.004 AUX BOILER-BIU REQUIREMENTS 'M-4550-1 205.66.006 SU BOILER STM SYS M-4550-8 206.05.001 COMP TURB SU FLOW CHARTS M-506 SHI REV1 206.05.002 ' COMP TURB SU FLOW CHARTS M-506 SH2 REV1 206.05.003 COMP TURB SU' FLOW CHARTS M-506 SH3 REV1 206.05.004- COMP TURB SU FLOW CHARTS .M-506 SH4 REV1 206.05.006 COMP TURB SU FLOW CHARTS M-506 SH6 REV1 206.05.009 COMP "IURB SU FLOW CHARTS M-506 SH9 REV1 206.05.010 COMP TURB SU FLOW CHARTS M-506 SH10 REV1 206.05.011 COMP TURB SU FLOW CHARTS M-506 SH11 REV1 206.06.001 INSTR TYPE Y SYNCHR0' ACCEPTOR 206.06.002 XASV AUTO GEN SYNC SYS.
206.08.001- GOV VLV POS VS FULL LOAD CURVES 206.08.002- GOV VLV POS VS'% FULL LOAD 206.12.001 . THERMOMETER & THERMOCOUPLE' LIST M-4 SH50 REV3 206.30.001 INSTR.-BOOK STM TURBINE (M-4-147) 2-18
u O O 6 UNIT 1 DESIGN DATABASE ID NO./ DOC PM NO MOD DATE DDB NO. DESCRIPTION 206.30.002 STM TURB VOL 2 DESCRIPTIVE MATERIAL (M-4-147) 206.49.001 BRG LIFT OIL PUMP E-153 REV14 E-155 REV12 206.49.002 TURNING GEAR MOTOR 206.49.003 TURBINE TRIP ALARMS E-162 REV11 206.49.005 TURB B/P SYS AUX DIAG EDS-0111-011-114 205.57.001 TG SYS M-428 SHI REV4 j 206.57.004 -TG SYS H-428 S42.REV3 206.65.003 MN TURB TEMP 206.66.002 STM INLET TO TURB M-4210-2 206.66.003 SYNC MN TURB USING AUX BRE M-4210-3 206.74.001 GOVERNOR VLV OSCILLATION 206.74.002 IMPROPER OPC TEST OPER 206.74.003 TURBINE TRIP 206.74.004 TURBINE TRIP 757, 206.74.005 TURBINE TRIP 6-3-81 206.74.006 TURBINE TRANSIENT 207.12.001 GEN. STARTUP DATA 207.23.001 MAIN GEN CALC. CAP. CURVE-RATED VOLTAGE 207.30.002 EXCITATION ' SWITCHGEAR-INST. M ANUAL (M-4-137-1 E-136 SH1 REV7 207.49.001 GEN PROT &L.O. RELAYS-GEN E-136 SH2 REV1 207.49.002 GEN. PROT &L.O. RELAYS-GE'I 207.49.003 ISO-PHASE BUS CLR FANS E-114 SHI REV4 E-114 SH2 REV5 207.49.004 ISO-PHASE BUS CLR FANS E-137 REV6 207.49.005 GEN PROT &L.O. RELAYS-XTRMS E-138 REV10 207.49.006 GEN PROT SLO REITY-TURB& REACTOR E-139 REV7 207.49.007 TG EXC FLD ACB 207.49.008 MTR OPERATED VOLT BASE ADJUSTER E-140 REV3 E-141 REV4 207.49.009 MTR OPERATED VOLT ADJUSTER E-142 REV4 207.49.010 EXCITATION SYS E-143 REV5 207.49.011 VOLT REG CONTROL E-144 REV4 207.49.012 AUTO FLD GND DETECTOR E-145 REV8 207.49.013 HYDROGEN SYS ALARMS M-4 SH52 REV4 207.52.001 WTA VR EQPT-PROT DRAWER M-4 SH67 REV3 207.52.007 WESTINGHOUSE SCHEM 588C335 M-4 SH71 REV3 207.52.010 WTA VR EQPT-LOGIC DRAWER E-37 SH1 REV2 207.57.001 ELECT SYS-GEN L.O. RELAYS 207.67.001 MN GEN NO LOAD SATURATION CURVE M-4 SH86 REV6 208.42.001 GS COND-OUTLINE E-156 REV4 208.49.001 L.O. VAP EXTR & GS COND 2.-19 I
p .-R.
' %,I O j' i UNIT l' DESIGN DATABASE DDB NO. DESCRIPTION ID NO./ DOC PM NO ' MOD DATE ,
208.49.002 GS-TURB SHUT 0FF MOV- E-158 REV8
.208.49.003 - GS B/P.MOV. E-159.REV9 208.49.005' VAP EXT &GS COND MOTOR-SCHEM M-4-40-7 SH4 208.49.006 B/P& SHUTOFF VLV-SCHEM .
M-4-40-7:SH10 l 209.46.002 AIR'. SIDE SEAL OIL BACKUP PUMP- E-14/ REV7 l 209.49.001 H2. SEAL OIL PUMPS. E-146 REV4 209.55.001 AC'TG SEAL OIL DIAG' M-4-35-5' l
-210.49.001 ; TURNING GEAR OIL, SEAL OIL BU PMP E-151 REV6 l 210.49.002 EMERG BRG OIL PMP E-152 REV9 210.49.003 LO XFR, FILTER PMP. E-157 REV5 210.49.004 VLV PIT AUX E-384 SH2 REV1 210.49.005 VLV PIT AUX E-384 SH3 REV1 210.49.009 TURNING GEAR OILPMP. SEAL OIL' PMP M-4-40-7 SH2 210.49.010 BRG LIFT PMP _. M-4-40-7'SH9 210.49.011 EMERG OIL PHP M-4-40-7 SH3-210.55.001 P&ID LO CONDITION & STO SYS M-216 REVI5 210.55.002 ' P&ID LO MN TURB & FW PMP BRG SYS M-226 REV6 211.42.001 EDG FLT INTidE PLENUM M-265 REV2- ,
211.49.001 SCHEM-DG AUX CONTROL E-108 SH1 REV10 -;
211.49.002 SCHEM-DG AUX CONTROL- E-108 SH2 REV7 211.49.003 ' DIESEL F.O. XFER. PUMPS E-115 REV12 211.49.004 .DG~ LOAD DISC CONTROL E-116 REV2.
211.49.005 AUTO SYNC SYS E-117 REV4 211.55.006 P&ID EDG & F.O. SYSTEM M-217 SH2 REV4 211.57.001 EDG'& F.O.1SYS- M-412 REV5 211.66.013 DSL OIL STORAGE CAPACITY M-3160-16 213.55.004 OTSG SEC SYS M-206 REV25
.214.55.001 P&ID COND. DEMIN M-207 REV11 {
215.49.001 INST & SERV. AIR COMPRESSOR- ~ E-380 SH1 REV14 215.49.002 INST & SERV AIR-COMP. E-380 SH2 REV11 215.49.003 INST & SERV AIR COMP E-380 SH3 REV4 215.49.004 AIR. PALLET A/C 2C26. E-477 REV2-215.55.003 P&ID IA,SA M-218 SH4'REV3 215.55.004 P&ID IA SA M-218 SH3 REV3 215.55.005 P&ID.IA SA M-218 SH1 REV16 215.55.006 P&ID IA SA M-218 SH2 REV5' 215.57.001 COMP AIR SYS. M-413 REV6 215.66.001 IA,SA M-4810-1 215.66.002 - SA RQMT' M-4820-1 2-20
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/
l UNIT-1 DESIGN DATABASE
! DDB NO. DESCRIPTION ID NO./ DOC PM NO MOD DATE-
! 219.55.001 P&ID GAS SUPPLY SYS M-225 REV5 j 221.06.001 REHTR TEMP CONT STS(3.PAGES) l 221.42.002 MSR-0UTLINE M-4 SH85 REV6 l 221.49.001 TG MS HTG STM TO.COND MOV'S. E-160 REV4 l 221.49.002 REHT& INTER VLV TEST &POS-IND- E-164 REV5 l 221.49.003 REHT& INTER.VLV TESTSPOS IND E-165 REV4 l 221.49.004 LP W HTR CONDENSER E-170'REV12 221.49.005 REHT VLV CONTROL E-171 SH1 REV4 221.49.006 REHT VLV-CONTROL" E-171 SH2 REV2 221.55.001 P&ID MN REHEAT STM- M-203 REV25
, 221.60.001 FOUR-DISTILLERS (A,B,C,D) l 221.60.002 MOIST. SEPAR TK T-76 221.60.003 MOIST. SEPAR&REHT E12A,B,C,D'
.221.60.004 MOIST. SEPAR TK T40A,B'.
! 222.55.001 MISC PIPING P&ID- M-228 REV6
! 224.12.001 RMS-TEST DATA SHEETS l 224.30.001 RAD MON'SYS OPER& MAIN MAN (M-217-41) l 224.30.002 MOD RP-1A OP& MAIN MAN (AVO) 224.49.003 -AREA RM SYS E-408 REV3 224.49.004 PROCESS-RMS E-409 SH1 REV8 -
224.49.005 PROCESS RMS E-409 SH2 REV9
- 224.49.006 PROCESS RMS E-409 SH3 REV5 224.49.007 PROCESS RMS E-409 SH4 REV3 224.49.008 PROCESS RMS E-409 SHS REV3 224.49.010 RM SAMPLING PUMPS E-411 SHI REV10 224.49.011 RM SAMPLING PUMP E-411 SH2 REV7 224.49.012 RM SAMPLING PUMP E-411 SH3 REV9 224.49.013 RM SAMPLING PUMP. E-411 SH4 REV6' 224.49.014 RM SAMPLING-PUMP E-411 SHS REV5 224.49.015 AIR PARTICULATE MONITOR SYS:ISOL. VLVS E-412 SH1 REV7 ,
224.49.016 AIR PARTICULATE MONITOR SYS ISOL VLV E-412 SH2 REV3 224.49.019 RAD MONITORING M-430 REV1-230.49.002- MS ATMOS DUMP ISOL VLV. E-442 REV4 301.49.001 SW PMP A&C E-275 REV14 301.49.002 'SW PMP B E-276 REV14 301.49.003 SW PMP A,C'DISCH MOV'S- E-277 REV3 301.49.004 SW PMP B DISCH MOV E-278-REV3-301.49.005 SW PHP X0VER MOV E-270 SH1 REV9 301.49.006 SW PMP X0VER MOV E-279 SH2.REV2 2-21
-(
[: -
.W
'- ( i.
(mG) .Q %f UNIT 1 DESIGN DATABASE'
.DDB NO. DESCRIPTION 'ID NO./ DOC PM NO MOD DATE-
'301.49.007 SW SYS ISOL SV'S E-280 REV16
-301.49.009- SW SYS ISOL MOV- E-282 REV3-301.49.010 SW SYS MOV.- ; E-283 SHI REV8 301.49.011: SW SYS MOV. ..E-283 SH2 REV2 301.55.002 SW P&ID M-210'REV1B 301.57.001-.EW AUX CLG, FIR WTR SYS M-406 SH1'REV5 301.57.002 . SW AUX CIE& FIR WTR SYS. M-406 SH2.REV6 301.57.003 SW AUX CLG & FIR WTR'SYS M-406 SH3 REV4 301.66.001 SW FLO RQMT 5-4720 301.66.002 PLT WTR RQMT- M-4720 301.66.003 SW SYS PMP SIZING' M-4720-3 301.66.004 RX BLDG SW CLG M-4720-6 301.66.005 SW PMP DBA- M-4720-7 ,
301.66.006- SW SYS ANAL M-4720-9 301.66.007 SW SYS-LINE DATA SHEETS M-4720-11 303.49.001 ICW PMP A&C E-223 REV3 303.49.002 ICW PMP B E-229 REV4 303.49.003 ICW.PMP AUX CONT E-230 SH1 REV5 303.49.004 ICW PMP AUX CONT E-230 SH2 REV4 303.49.005 ICW'PMP AUX CONT E-230 SH3 REV3 303.49.006 ICW PMP SV E-231 REV4 303.49.007 ICW ISOL MOV E-232 REV7 303.49.008' ICW' SURGE TK SV >- E-236 REV5 303.49.009 L/D CLR ICW E-240 REV6 303.49.010 : ICW OUTLET ISOL VLV E-233 REV8 303.55.003 ICW ~M-234 SH1 REV17 303.55.004 .ICW M-234 SH2 REV12 303.57.001 ICW M-420 SHI REV5 303.57.002 ICW .M-420 SH2 REV6 303.66.001 ICW FLO RQMT M-3840-2 303.66.002 ICW M-3840-3 -t 303.66.003 ICW M-3840-4 303.66.004 HT RML CAPACITY M-3840-6 303.66.005 .ICW 4X E28A/B/C M-3840-28 303.66.006 ICW RQMT COND FLO M-3840-29 303.66.007 ICW HT XFR-AREA- M-3840-33
.303.66.005 ICW HX SIZING M-3840-36 i 303.66.009' ICW MEAT LOADS M-3840-38 304.49.001 SFP CLG PMP E-244'SH1 REV10 2-22 ,
> l ,
UNIT 1 DESIGN DATABASE.,
DDB N_0. DESCRIPTION ID NO./ DOC PM NO MOD DATE .
304.49.002, SFP CLG PMP- E-244 SH2 REV3: d 304.55.001 . SF CLG SYS M-235 REV17 304.57.001 SFP CLG M-421 REV3 304.66.002. FP BOILOFF M-3850-2' 304.66.003'.FP B01LOFF M-3350-3 _
305.49.001 .CW IMP E-271 SH1 REV12 305.49.002 CW PHP E-271 SR2 REV12 305.49.003 CW PHP DISCH MOV E-272 REV8 305.49.004 CW7SW TEMP RCDR- E-322 REV5 305.49.005 CCR WSH PMP 'E-341 REV5 305.49.006 SCR WSH SYS MOV E-342 REV7-305.49.010 COND CW VAC BER MOV E-274 REV9 305.49.011 WTR BOX VAC PMP E-301 REV2 305.49.012 MN COND CV INLT , OUTLET TEMP RCDR E-327 REV8 305.49.014 MISC INSTR E-331 SH13 REV1 305.49.017 TRVL~SCRN WASH SYS CONTROL E-344 REV6 305.49.018 SLUICE GATES E-416 SH1 REV5 305.49.019 SLUICE GATES E-416 SH2 REV5 355.49.020' SLUICE GATES E-416 SH3 REV6 305.49.021 SLUICE GA*ES -E-416 SH4 REV5 305.49.022- SLUICE GATES- E-416 SHS REV5-305.49.023 SLUICE GATES- E-416 SH6 REV6 305.55.001 COND VAC CW INTAKE M-209 REV18 305.57.001 CW COND VAC SCN WASH- M-405 REV6 305.66.005 -
SUMMARY
OF CW LOSSES M-4330-4 305.66.007 PMP FOR COOLING SERVICBS M-4330-8 305.66.009 ' PLT OUTPUT VS CIRC WTR TMP M-4310-7 305.66.010 - BACK PRESS.VS CW TEMP 'M-4310-8 305.66.011 BACK PRESS VS CW TEMP M-4310-9 305.67.001 AIR VLV CLOSING TIMES M-4330- 5 306,55.005 CST M-212 SH1 REV22 306.55.007 P&ID PLT M/U- M-212 SH2 REV6 307.49,001 CW PMP E-374 REV7 307.55.003 AUX CW M-221 SH1 REV11 307.55.004 P&ID CW M-221 SH1 REV11 307.55.006 P&ID CW M-222 REV13 307.57.001 CW CLG SYS M-415 REV5' 400.00.002 NOTES, SYMBOLS,ELEC DIAG E-50 REV13 400.00.006 BUS VOLTAGE. LEVEL STUDY-VOL 1 i
L l 2 t .
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UNIT 1 DESIGN DATABASE ID NO./ DOC PM NO MOD DATE DDB NO. DESCRIPTION ._
400.00.007 BUS VOLTAGE LEVEL STUDY-VOL 2 400.29.001- LOAD
SUMMARY
SU#2 400.29.004- NNI-X,NNI-Y PWR SUPPLIES (UPC.iTE) 400.49.001 SYS PHASING, SYNC DIAG E-31 REV9 400.49.003 LOAD CENTER XFMR FDR PROTECTION E-79 REV7 j
400.72.001 ELECT CALC-BOOK 1 400.72.002 ELEC CALC-BOOK 2 1
400.74.001 PARTIAL LOSS OF OFF-SITE l 400.74.002 LOS3 0F OFF-SITE POWER 401.49.001 riN TRANS AUX SYS-SCHEM E-111 SH2 REV1 401.49.002 MN TRANS AUX SYS-SCHEM E-111 SH1 REV6 402.49.001 SU& UNIT AUX.TRANS AUX SYS E-112 SHI REV6 403.49.001 SU&TRANS 1&2 L.O. RELAY E-94 REV7 403.57.001 SU TRANS L.O.6UV RELAY E-37 SH2 REV1 404.01.001 SNG LINE MTR& RELAY DIAG (6900V) E-3 REV7 404.49.001 METER RELAY DIAG (6900) E-33 REV14 404.49.003 TYRICAL CIRCUIT BRK 6900&4160V SVGR E-76 SHI REV8 4.04.49.005 6900V MOTOR PROTECTION E-77 SHI REV6 404.49.006 6900V MTR PWR MONITOR CONT CNT E-82 REV5 404.49.007 UNIT AUX TRANS 6900V ACB-SCHEM E-87 REV7 404.49.008 SU TRANS 1 6900V ACB E-88 REV14 404.41.009 SU TRANS 2 6900V ACB E-89 REV17 404.49.010 SWGR BUS LO UV RELAY E-93 SHI REV7 404.49.011 TRANS UV RELAYS E-95 REV8 l
404.75.001 TYPICAL CIRCUIT BRK 6900&4160V SWGR a-76 SH2 REVf l E-4 REV12 I 405.01.001 SGL LINE MTR& RELAY DIAG-4160 405.49.001 SCHEM MTR, RELAY DIAG-4160 E-34 REV6 405.49.003 SCHEM-MTR, RELAY DIAG E-35 REV13 405.49.006 A.16KV ENG SFG BUS FEEDER ACB E-97 REV14 405.49.007 4160V ENG SH; BUS TIE ACB'S E-98 REV8 405.49.009 -SCHEM-UNIT AUX TRANS-4160 E-90 REV6 405.49.010 SCHEM-SU TRANS 1-4160V ACB E-91 REV16 405.49.011 SCHEM-SU TRANS 2 4160V ACB E-92 REV16 405.49.012 SWGR BUS LO, RELAY E-93 SH2 REV8 405.49.013 LOAD CENTER TRANS PRI ACB'S E-104 REV7 405.57.001 6900,4160 BUSES LO, RELAY E-38 SHI REV2 405.57.002 6900,4160 BUSES LO, RELAY E-38 SH2 REV1 1
405.57.005 6900,4160V TRANS FDR ACB'S E-39 REV2 405.57.007 ELEC SYS-ENG SFG BUS ACB'S E-41 REV2 2-24
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UNIT 1 DESIGN DATABASE ID NO./ DOC eM NO MOD DATE DDB NO. DESCRIPTION E-4 la,V12 405.75.001 SGL LINE MTR& RELAY DIAG-4160V MN SUPPLY E-5 KEV 9 405.75.002 SGL LINE MTR& RELAY DIAG-4160 ENG SM 405.75.003 4160 MTR PROTECTION E-78 RE77 405.75.004 4160V ENG SFG BUS L.O. E-99 SH1 REV10 406.01.001 480V MTR CONT CNTR B71,24,72,44 E-9 REV17 406.01.002 4COV MTR CONT CNTR B55-56 E-16 "ZV19 406.01.004 480V LOAD CNTR, MAIN SUPPLY E-7 REV12 406.01.006 480V LOAD CNTR;ENG SFG75UPPLY E-8 REV10 406.01.008 480V MTR CONT CENT-B11,12,13 E-10 REV18 406.01.010 480V MTR CONT CNTR-BIS,16,21 E-11 REV20 406.01.012 480V MTR CONT CNTR-B22,23,25 E-12 REV16 406.01.014 480V MTR CONT CELT-B31,32 E-13 REV22 406.01.018 480V MTR CONT CEhr-T51,52 E-15 REV19 406.01.022 480V MTR CENT-B61,62 E-18 REV22 406.01.024 480V MTR CONT CENT-333,63 E-19 REV13 l
406.49.001 SCHEM-MTR, RELAY-480V STS LOAD CNTR E-36 7EV6 406.49.003 TYP 483V LC BRK E-81 REV2 406.49.005 480V MCC B56 MAN IFR SW E-107 REV7 406.49.006 TYP 480V MTR CNT NONREV STARTER E-83 REV4 406.49.007 480V MISC WR FEEDERS E-431 SHI REV6 406.49.008 480V MISC WR FEEDERS E-431 SR2 REV8 406.49.009 480V MISC PWR FDR E-431 SH3 REV2 406.49.010 480V MIEC PWR FDR E-431 SH4 REV2 406.49.011 480V MISC PWR FDR E-431 SH5 REV2 406.49.012 480V MISC PWR FDR E-431 SH6 REV3 406.49.013 480V MISC PWR FDR E-431 SH7 REV6 406.49.014 480V MISC PWR FDR E-431 SHS REV3 406.49.015 480V MISC PWR FDR E-431 SH9 REV3 E-431 SH10 REV8 406.49.016 480V MISC WR FDR 406.49.018 480V MISC PWR FDR E-431 SH12 REV2 E-431 SH13 REVO 406.49.019 480V MISC PWR FDR 406.49.020 480V MISC PWR FDR E-431 SH11 REV12 406.49.027 480V MTR CONT CNTR FVR STR E-84 SHS REV1 406.49.028 LOAD CONT TRANSFR SEC MN&ENG SFG E-105 REV6 406.49.029 FULL VOLT REVERSING STARTER E-84 SHI REV9 406.49.030 IJLL VOLT REVERSING STARTER E-84 GH2 REV10 406.49.031 FULL VOLT REVERSING STARTER E-84 SH3 REV3 E-106 REV7 406.49.033 LOAD CTR BUS TIE MN&ENG SFG ACB'S 406.57.001 ELEC SYS-LOAD CNTR IFMR ACB E-42 REV2 2-25
._ . . _ _ _ _ _ _ _ _ _ . _ . - _ _. _ ~
b Q ~Q Q l I -
- UNIT.1 DESIGN DATABASE i
- - DDB NO.' DESCRIPTION ID NO./ DOC 'FM NO MOD DATE SGL LINE MTR& RELAY-125VDC SYS= E-17 REVIS SH1 !
F .407.01.001:
407.01.003 ENG SFG&l25VDC PWR DIST PNL' L 22 REV22 I
[ 407.49.001 .125VDC MAN TRANS SUITCHES E-104-REV3 408.24.001~ DG CURVE-CALC EXCIT CHAR .f!
[ 408.24.002 DG CURVE-CALC DECREMENT CURVE-AC i
408.30.001 - INSTR & PARTS MAN-2750KW .'IEN (M-12) 408.49.002 DG PROTECTIVE SYS E-101 REV10 408.49.003 - DG ENGINE CONTROL E-102 REV13 '[
.. 408.49.004.- DG EXCITATION' CONTROL E-103 REV6 i b 408.57.001- ELEC STS-Df- 4CB'S E-40 REV2
{ 409.01.001 STA SGL LIV DIA E-1 REV9 !
409.01.003' SGL LINE MTR& RELAY DIA-GEN. .E-2 REYS 409.01.006 SGL LINE STA ELEC COMPOSITE. E-6 REV4 409.49.001 SCHEM MTR& RELAY DIAG-GEN SYS ._. E-32 REV13' '[
409.49.003 AUTO SYNC STA 500KV GEN BKR E-123 REV2 !
) 409.49.004 ' AUTO SYNC SYS E-121 REV6 !
- 409.49.005 161,22 KV SU TRANS BKR E-124 REV5 2
409.49.010 SWYD BKRS IND E-125 SH1 REV5 1 409.49.011 SWYD DISCONN IND E-125 SH2 REV2 !
- 409.49.018 500KV BREAKER AN-500-002 SH2 & 3 i 409.49.019 500KV 3REAKER AN-500-002 SH 4 & 5 !
411.01.001' SGL LINE-LIGHT DIST SYS- E-20 REV16 !
411.01.003 120/20SV INST AC PNL E-23 REV26 -
411.49.001 120/208V MISC PWR FDR E-430 SH1 REV4 !
, 411.49.002 120/208V 7 MISC PWR.FDR. E-430 SH2 REV7 [
l 411.49.003 120/208V MISC PWR FDR- E-430 SH3 REV3 .!
[ 411.49.004 120/208V E-430 SH4 REV7 [
411.49.005 120/208V MISC PWR BKR E-430 SH5 REV6 1
411.49.006 120/208V HISC PWR FDR E-430 SH6 REV7 412.49.002 MISC INST PWR SUPPLIES E-330 SHI REY 3 !
412.49.003 MISC INST PWR SUPPLIES E-330 SH2 REV5 )
4 412.49.004' MISC INST PWE. SUPPLIES E-330 SH3 REV9 I
! 412.74.001 LOSS OF.24VDC POWER j 504.49.001 REAC NI PROT SYS E-260 SHIlREV5 504.49.002- REAC MI PROT SYS E-260 SH2 REV7 504.49.003 REAC NI PROT SYS E-260 SH3 REV11 '
504.49.004 - REAC NI PROT SYS E-260 SH4 REV7 ;
l 504.49.0051 NI&RPS-REACTOR TRIP E-268 FEV7' 8
504.74.001 TRANS ASSESS-RX TRIP 5-13-81 l i
i i
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UNIT:1 DESIGN DATABASE DDB NO'. DESCRIPTION ID NO./ DOC PM NO MOD DATE 504.74.002 - TRANS ASSESS-RX TRIP 9-1-81 504.74.003 TRANS ' ASSESS-RX TRIP ON HIGH PIE 5duxt.
504.74.004 TRANS ASSESS-RX TRIP 7-8-81" 504.74.005 TRANS ASSESS-RX TRIP 4-8-81 504.74.006 RX TRIP
- 504.74.007 RX' TRIP 757.
504.74.008 RX TRIP 3-18-81 504.74.009 RX TRIP 4-8-81 504.74.010 - RX TRIP 12-14,16-19, SC4.74.011 RX TRIP 20-34~
( 504.75.002. RPS DCP 79-1032 4 505.30.001 ICS,NNI. MAN VOL 1A (M-1-16) 505.30.002 ICS,NNI Mali VOLIB (M-1-17) 505.30.006 ICS,NNI MAN VOL IC-(M-1-18)
, 505.30.007 ICS,NNI MAN VOL 2 (M-1-19) 505.49.001- WIR BLK DIAG-ICS' E-261 SHI REV9
, 50'. 49.002 WIR BLK DIAG ICS E-261 SR2 REV9 505.49.00s WIR BLK DIAG ICS 'E-261 SH3 REV9 505.49.005 WlR BLK DIAG ICS .E-261 SHS REV7
) 505.49.008 WIR B1K DIAG ICS E-261 SH4 REVIS 505.75.001 RPS DCR 1-79-15 505.75.002 ICS DCP 81-1050 506.12.001 INCORE THERMOCOUPLE' REPORT
~
, 506.30.001 INSTR. BOOK-INCORE MONITUR SYS (M-1-13) d 506.42.001 INCORE MONITOR SYS PIPING STS M-77 REV5 506.49.001 PEAC INCORE MONITOR SYS E-259 SHI REV4
- 506.49.002 '.AC INCORE MONITOR SYS E-259 SH2 REV4
, 506.49.003 REAC INCORE MONITOR SYS E-259 SH3 REV3 506.49.004 REAC INCORE MONITOR STS E-259 SH4 REV1 509.30.001 INST. MAN.-NI,RPS,ESAS VOL 1 (M-1-20) 509.30.002 - INST. MAN.-NI&RPS VOL 2 510.30.001 ENG SAF SYS MAN VOL 3 (M-1-29)
, 511.30.001 EH CONT SYS BOOK 1 (M-4-147) 511.30.002 EH CONT STS BOOK 2 (M-4-147) 511.49.001 WIR BLK DIAG-EH STS INTERCONN E-173 REV1 511.49.002 TURBINE TRIP & RESET E-161 SH1 REV13 511.49.003 TURBINE TRIP & RESET E-161 SH2 REV2 511.49.004 TURBINE TRIP.& RESET E-161 SH3 REV2 2-27
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Q O UNIT 1 DESIGN DATABASE C
ID NO./ DOC FM NO MOD DATE DDB NO. DESCRIPTION 602.49.035 ANN K06 E-456 REV21 602.49.036 AWN K07 E-457 REV20 602.49.037 ANN K08 E-458 REVIS 602.49.038 ANN K09 E-459 REV27 602.49.039 ANN K10 E-460 REV22 602.49.040 ANN K11 E-461 REV26 602.49.041 ANN K12 E-462 REV32 6C2.49.042 ANN K112 E-463 REV7 602.49.043 Ah% K113 E-464 REV16 602.49.044 ANN K115 E-465 REV8 602.75.004 ANNUNCIATOR DCR-519A 706.49.002 CONT ROOM RELAY ROOM EM CONT AIR &ISOL VLV E-359 SE1 REV11 706.4S.002 CONT ROOM RELAY ROOM EM CONT AIR &ISCL VLV E-359 SH2 REV4 706.49.002 CONT ROOM RELAY ROOM EM CONT AIR &ISOL VLV E-359 SH3 PIV5 707.49.001 RX BLDG PENE RM VENT E-253 SH1 REV7 707.49.002 RX BLDG PE ;r, EM VD.'T E-253 SH2 REV7 707.49.003 RX BLDG PENE RM VENT E-253 SH3 REV7 707.49.004 RX BLDG PENE EM VENT E-253 SH4 REV6 707.49.005 RX BLDG EENE EM VENT E-253 SH3 REV10 701.49.006 PENE RM VENT SYS-SCHEM E-253 SH6 REV8 707.49.007 PENE RM VFNT STS-SCHEM E-253 SH7 REV9 707.49.008 AUX STS MISC IN'7F E-254 SH4 REV1 707.49.009 AUX STS MISC INSTR E-254 SR2 REV2 707.55.001 CONT PENE RM VENT STS AIR FLO M-264 REV7 707.51.001 PENE RM VENT H-432 REV6 707.15.001 CONTAINMENT DCP 80-1041 2-29
SINCERT.1/SIMDOCS/SIH1 January 14, 1991 Control Room s 1 V The physical arrangement of the simulator main control room area is basically a duplicate of the reference plant control room. Design changes have been incorporated updating the main control boards to September 1, 1990.
Comparison to Reference Plant Equipment not in Simulator Control Rooms
- a. Complete control room emergency air conditioning equipment.
All CR normal & Emergency air conditioning equipment controls end indications are available on C19 and the INSTRUCTOR CONSOLE.
- b. Complete RPS channels. All RPS channels are simulated in software and selected hardware features are incorporated on the " Super Panel".
- c. Complete ESAS channels. All ESAS channels are simulated in software and selected hardware features are incorporated on the " Super Panol".
- d. Complete EFIC channels. All EFIC channels are simulated in software. Complete hardware for channel A is incorporated and ir -selected hardware features for channels B, C, and D are
( incorporated.
- e. Main Steam Safety Valve Monitoring System. Cabinsts are not simulated, but the output is simulated,
- f. Quindar panel will be simulated (1991) only to include the audible alarm and alarm resets,
- g. Hoteorological data panel.
- h. Emergency radio equipment. A functional intercom was substituted for this item. Radio to be purchased for simulator in 1991.
- i. Fire Protection System alarm Panel in the rear portion of the control room.
- j. Super Particulate, Iodine, Noble Gas System (SPINGS).
- k. Main turbine metering and relay equipment in the rear portion of the control room. Digital meters instead of watt-hour meters are provided in cabinet C20/21 for the main generator megawatt hours, diesel generators 1 6-2 kilowatt hours, aux, transformer kilowatt hours, startup transformer 1 megawatt
, hours and startup transformer 2 megawatt hours.
(v) 1. Loose Parts Monitoring System.
3-1
S1HCERT.1/SIMDOCS/SIH1 January 14, 1991 cs Major differences in simulator and reference plant main control rooms.
(v)
- a. Back panels in the simulator are arranged differently than those in the reference control room,
- b. Panel C-20 in the simulator does not duplicate C-20 in the reference control room. Simulator utilizes Ifghts for protective relay' status where the reference control room C-20 uses " drop flag relays. Lockout relay reset switches are also different. Watt meters on the simulator are digital rendout vice analog on reference control room.
- c. There is audio-visual equipment in the simulator and does not exist in the reference control room,
- d. There are viewing windows in the simulator and not in refer-nea control room,
- e. The control room furniture is similar.
- f. The telephone system is similar but all phone numbers are different than the plant phone numbers. All communication equipment is in the correct location.
Features that are identical in simulr'.ar and reference plant main p control rooms.
- a. All main control board controls and indications. h
- b. Wall and floor finishes including red tilo indicating the restricted area.
- c. Book cases and file cabinets.
- d. Procedures and forms are maintained current by the Document Control Department. Procedures not used for training are not maintained in the simulator, h.
U 3-2
- j SIMCERT.1/SIMDOCS/SIH1 January 14, 1991 D l I
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SIMCERT.1/SIMDOCS/SIM, l January 14, 1991 l s Instructor Interface
! )
\- ' Location of the Instructor Controls The instructor controls are centralized in the Instructor Console located in the room used as the Shift Supervisor's office in the plant. Included in this operator console is the controls fo- the audio-visual equipment. A hand-held remote control devict .y be operated anywhere within the simulator area. A self-conta..:ed telephone and paging system is located in the Instructor Console and the simulator control room area.
Simulator Initial Condition List 10-1 100% POWER EQUIL XE BOL IC-2 100% POWER EQUIL XE MOL IC-3 100% POWER EQUIL XE EOL IC-5 80% POWER EQUIL XE 10-4 74% 3 RCP'S EQUIL XE 10-6 50% 2 MFW PUMPS EQUIL XE IC-7 35% 1 MFW PUMP TRANS XE
'IC-8 25% 1 MFW PUMP TRANS XE 10-18 15% FROM STARTUP MN TURBINE ON 10-17 7% FROM STARTUP MN TURBINE OFF IC-16 26 FROM STARTUP AFW ON IC-15 REACTOR CRITICAL 1E-8 AMPS
'~N g 10-14 534*F SAFETIE RODS OUT y\ _,! IC-13 534'F GROUP ONE RODS OUT IC-19 HOT SHUTDOWN 1 il0VR POST TRIP 10-20 110T SHUTDOWN 6 HURS POST TRIP IC-12 HEATUP IN PROG 435'F 1650#
IC-9 C00LDOWN IN PROG 290*F IC-11 COLD SHUTDOWN 225# STM IN PZR IC-10 COLD SHUTDOWN NO BUBBLE IN PZR Simulator Unprotected Snapshots (SN-21 to SN-41)
SN-21 to SN-39 are used by Trainers to store specialty prepared IC's for training sessions.
SN-40 and SN-41 are used for instant storage of snapshots.
These are not protected and are only used for quick reference, q
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_ _ . . _ _ . _ _ _ _ _ _ _ _ _ . _ . . _ . . _ __.____.-..______..__m.__.._. _m_
SIMCERT.1/SIMDOCS/SIM J Jcnusry 14, 1991 1 Lists of Malfunctions
()
V Appendix A-1 is a list of malfunctions that the simulator is capable of performing Plant Equipment (operated outside the contrcl room) t Appendix A-2 lists the equipment that.is operated through the instructor's station to allow performance of plant evolutions.
Additional special instructor / training features available l The following is a list of available features:
a.= Sixty backtrack initial conditions are available. The backtrack feature is normally set up to default to one-minute snapshots. The time variable is adjustable over the range of
.5 to 10 minutes.
- b. Fast time is available to change a limited number of parameters, specifically core xenon concentration,. turbine heatup, primary heatup (pump heat only), decay heat storage -
and condenser vacuum.
- c. Overrides are available to change the state of any panel ,
. Indication or input.
- d. Fallable component overrides are available for motors, pumps, fans, and valves,
- e. The abilityto develop a. scenario with the manipulations of
. plant functions, etc., and take a snapshot for repeatability of training.
' f. ; The capability to develop computer-aided exercise (CAE) flies off-line to contain a series of drills or' operational ,
. procedures.
- g. Conditional trigger mechani'.as for malfunctions.
- h. The manipulation of plan ( equipment or parameters via the Instructor Consolo, i=
i- i.- Daily readiness testing provides several options to test lights, recorders,. meter indications, and alarms.
t
- j. Delay and ramp features allow malfunction insertion without giving pre-warning to operating crew.
- k. Limited remote control features allow run, freeze, starting and stoping of malfunction timer and~ single step from a *
.j hand-held remote transmitter.
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$1MCERT.1/SIMDOCS/SIM, l January 14, 1991 l
-( '). Initial conditions for 27 plant conditions without requiring maneuvering'the simulator.
- m. Automatic static check after initialization of simulator.
- n. Nine hundred ciscrete panel presentations are available in the replay " hands-off" mode. Replay records are stored as one second snapshots. The time variable to replay is adjustable over the range of 1 to 15 minutes.-
[
- o. Manipulation or monitoring of global variables via Instructor Console,
- p. The ability to record reactivity manipulations through records ,
management.
- q. Illstorical data Sogging provides the ability to log up to 95 -
variables in each of 25 flies. Each file can be. recorded on a range of-intervals from one second to several minutes. Each j file can be sent to a line printer for hard copy, a tape save for later use or converted to LOTUS 1 2 3 (Spreadsheet) format. The LOTUS format allows the creation of graphs of simulator performance. !
- r. Simulator operating limit light to alert the instructor of potential loss of realism of simulatton.
- 2. Reactor Building Pressure >59 PSIG
- 3. Fuel Temperature > 700'T,
- 4. RCS subcooled margin <0'F Steam generator pressure >1100 pSIG
'5.
- 6. Reactor power.>2876 MW
- 7. 09teexitthermocouple$800'F ,
- 8. Reactor. Building Temperature >280'T
{
- s. Simulator models operating status is constantly displayed-by'a light that flashes each time the executive completes a cycle. .;
There are six executive operating lights to keep the L
instructor informed.
4-3 l
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. . . - . . - - . - - - - . . - - - - . - . . . - . . . . . . - ~ - -. - - - . . -. - - -
l SIMCERT.1/SIMDOCS/SIM
' January 14, 1991 i .
i 4
REAL TIME COMPUTER TEST i
ABSTRACTS L
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i SIMCERT.1/81MDOCS/81h January 15, 1991 t
NAME AND DESCRIPTION OF TEST: Real time operation test. Computer clock
( ) frequency will be measured to ensure operations at 120 HZ.
1 ANSI /ANS-3.5, 1985 RELATIONSHIP:
Appendix A, A3.1 DATE TEST CONDUCTED: October 8, 1990 TESTED OPTION: Using a timer / counter measure computer clock time (Back ;
plane pins P1A-31 for each system).
INITIAL CONDITIONS: 100% Full Power, MOL '
FINAL CONDITIONS / DURATION OF TEST: All simulator computer clocks will be 120 t .05 HZ or 8.333 i .0034 Msec.
System 1 8.3332 MS >
System 2 8.3334 MS System 3 8.3333 MS-BASELINE DATAs- Sel Specifications.
DEFICIENCIES: None EXCEPTIONS TO ANSI /ANS-3.5, 1985: 'None e
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. . _ . _ . - _ . . _ _ . . ~ _ . . _ . _ _ . _ . . . . _ . _ _ - - .- . . . - - ,-
SINCERT.1/SIMDOCS/SIM.
Jcnuary 15, 1991 ,
NAME AND DESCRIPTION OF TEST: Real time operation Test. (Normal Ops)
O CPU /IPU Spare Cycle time Statistics will be computer calculated using a routine called ' IDLE' ANSI /ANS-3.5, 1985 RELATIONSHIP: Appendix A, A3.1
'DATE TE N W SUCTED: October 8, 1990 TEDTED OPTION: Run ' IDLE' program on all 3 systems. 4 s
INITIAL CONDIT10NSt= 100% Full power, HOL FINAL CONDITIONS / DURATION OF TEST: Test completed when all CPU /IPU Spare times are calculated for each of the 3 systems.
System 1 IPU 27.39 CPU 31.67 System 2 IPU 24.23 CPU & 30 System 3 IPU 29.82 CPU 64.27 BASELINE DATA: Spare cycle. time greater than 0%.- .
O :
t DEFICIENCIES:
None EXCEPTIONS TO ANSI /ANS-3.5, 1985:
None l
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SIHCERT.1/SIMDOCS/SIM.
January 15, 1991 NAME AND DESCRIPTION OF TEST: Real time operation test (Abnormal Ops)
(~ CPU /IPU Spare cycle time Statistics will be computer calculated using a routine called ' IDLE'.
ANSI /ANS-3.5, 1985 RELATIONSHIP: Appendix A, A3.1 DATE TEST CONDUCTED: October 8, 1990 TESTED OPTION: Trip reactor and run ' IDLE' program on all 3 systems.
INITIAL CONDITIONS: 100% Full Power, HOL FINAL CONDITIONS / DURATION OF TEST: Test Completed when all CPU /IPU spare times are calculated for each of the 3 systems.
System 1 IPU 27.03 CPU 29.07 System 2 IPU 25.2_2 CPU $9.75 System 3 IPU 24.70 CPU 42.43 ,
BASELINE DATA: Spare cycle time greater than 0%.
DEFICIENCIES:
None EXCEPTIONS to ANSI /ANS-3.5, 1985:
None O
5-4
SIHCERT.1/SIMDOCS/SIH4 Janusry 15, 1991
- NAME AND DESCRIPTION OF TEST: Real time operation test. (Emergency Ops)
CPU /IPU Spare cycle time statistics will be computer calculated using a routine called ' IDLE'.
ANSI /ANS-3.5, 1985 RELATION 8 HIP: Appendix A, A3.1 DATE TEST CONDUCTED: ' October 8, 1990 TESTED OPTION: Activate malfunction for main stram s .ine rupture (100%)
and run ' IDLE' program on all 3 systems.
INITIAL CONDITIONS: 100% Full power, MOL.
FINAL CONDITION 8/ DURATION OF TEST: Test completed when all CPU /IPU spare times are calculated for each of the 3 systems.
.SystemL1 IPU _26.90 CPU 21.75
' System'2 IPU 25.91 CPU 71.16 '
System 3 IPU 20.54 CPU 73.26 BASELINE DATA: Spare cycle time greater than 0%. ,
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\,_./ DEFICIENCIES:
None EXCEPTIONS TO ANSI /ANS-3.5, 1985: ,
None.
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S1HCERT.1/SIMDOCS/SIM January 14, 1991 Y
NORMAL OPERATIONS TEST-ABSTRACTS-t i- .
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SIMCERT.1/SIMDOCS/SIM Jcnuary 15, 1991 NAME-AND DESCRIPTION OF TEST: Reactor trip recovery from 100% power.
f) Manually trip the simulator from 100% power. Establishing a stable V hot shutdown and a xenon concentration for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> post-trip.
start up and continue to 100% power using plant procedures.
ANSI /ANS-3.5, 1985 RELATIONSHIP: Section 3,1,1m (2), (3), (4), (5), (6)
P DATE TEST CONDUCTED: October 8, 1990
. TESTED OPTION: The parameters monitored and graphed at 30 second intervals are as follows:
PARAMETER NI-5 REliCTOR POWER (%)
CORE THERMAL MEGAWATTS-ELECTRICAL WATTS PRODUCED (WATTS)
'TAVE'('F) '
A OTSG OPERATER RANGE LEVEL (%)
PRESSURIZER LEVEL (INCHES)
=
B OTSG STEAM' TEMPERATURE ('F)-
B OTSG OPERATE RANGE LEVEL (%)
PRESSURIZER WATER TEMPERATURE ('F)
~RCS PRESSURE (PSIA).
A OTSG STEAM-TEMPERATURE ('F)
A MFW TEMPERATURE'('F)
A HFW FLOW (LBM/HR)
-LOOP A'TCOLD'('F)
LOOP A THOT ('F)
GROUP 7 CONTROL ROD POS (INCHES) -
B MFW TEMPERATURE ('F)
B MFW FLOW (LBM/HR)-
LOOP B TCOLD.-('F)
LOOP B THOT ('F)
INITIAL CONDITIONS: 100% Full power, MOL=
FINAL CONDITIONS / DURATION OF TEST: Fimulator returned to 100% power.
All procedures are signed, logs are completed and discrepancies noted.
f 5-7
SIMCERT.1/SIMDOCS/SIM January 15, 1991 i BASELINE DATA: E0P 1202.01 Reactor Trip Tab
\ OP1102.06 Reactor Trip / Outage Recovery OP1102.02 Start up to 20% Power OP1102.04 20% to 100% Power DEFICIENCIES: DR 90-098 RPS Manual Trip DR 90-099 E-1 VS E-2 Temps DR 90-100 D3 Function on LP wrong
- DR 90-110 8023/24 change to SU105/108 EXCEPTIONS TO ANSI /ANS-3.5, 1985:
None O
O 5-8
SIMCERT.1/SIMDOCS/SIM January 15, 1991 NAME AND DESCRIPTION OF TEST: 3 Pump Power Operations. Establish a 70%
'j steady state power level with 3 reactor coolant pumps and maneuver N simulator to hot shutdown and return to 70% steady state power.
ANSI /ANS-3.5, 1985 RELATIONSHIP: Section 3.1.1, (3), (5), (6), (7)
DATE TEST CONDUCTED: October 9, 1990 TESTED OPTION: The parameters monitored and graphed at 30 second intervals are as follows:
EARAH1:TER NI-5 EEACTOR POWER (%)
CORE THERMAL MEGAWATTS ELECTRICAL WA1TS PRODUCED (WATTS)
TAVE ('F)
A OTSO OPERATER RANGE LEVEL (%)
PRESSURIZER LEVEL (INCHES)
B OTSG STEAM TEMPERATURE ('F)
B OTSG PRESSURE (PSIG) r's 'B OTSG OPERATE RANGE LEVEL (%)
('~') PRESSURIZER WATER TEMPERATURE ('F)
RCS PRESSURE (PSIA)
A OTSO STEAM TEMPERATURE ('F)
A MFW TEMPERATURE ('F)
A MFW FLOW (LBM/HR)
LOOP A TCOLD ('F)
LOOP A THOT ('F)
GROUP 7 CONTROL ROD POS (INCHES)
B HFW TEMPERATURE ('F)
B MFW .u0W (LBM/HR)
LOOP B TCOLD ('F)
LOOP B THOT ('F)
INITIAL CONDITIONS: 100% Full Power, MOL to less than 60% Power. Remove 1 RCP from operation and retura to 70% steady state power.
FINAL CONDITIONS / DURATION OF TEST: Simulat or returned to 70% Power.
All procedures are signed, logs are completed and discrepancies noted.
O 5-9
i SIMCERT.1/SIMDOCS/S1H. ;
January 15, 1991 l l
, , , BASELINE DATA: OP1102.04 Power Ops '
/ ) OP1103.06 Removal of RCP
'\ - OP1102.10 Reduced Power to Hot Shutdown DEFICIENCIES DR 90-116 B OTSG BTU Ifmit alarm in 3 RCP Ops
- DR 90-117 Q tank enthalpy wrong
> max diff.
DR 90-122 RE 7400 purge cautta 1silure alarm DR 90-123 Rad monitors out of spec on logs DR 90-125 EFIC low range level wrong EXCEPTIONS TO ANSI /ANS-3.5, 1985:
None
.m v
v 5-10
l SIMCERT.1/SIMDOCS/SIM l Janitary 15, 1991 l J'" NAME AND DESCRIPTION OF TEST: 100% Power to Cold Shutdown and back to
' 100% Power.
ANSI /ANS-3.5, 1985 RELATIONSHIP: Section 3.1.1, (1), (2), (3), (5), (6),
(8), (9)
DATE TEST CONDUCTED: October 11, 1990 TESTED OPTION: The parameters monitored and graphed at 30 second intervals are as follows:
PARAMETER
-NI-5 REACTOR POWER (%)
CORE TilERMAL MEGAWATTS ELECTRICAL WATTS PRODUCED (WATTS)
TAVE ('F)
A 0TSG PRESSURE (PSIG)
A OTSG OPERATER RANGE LEVEL (%) r PRESSURIZER LEVEL (INCHES)
B 0TSG STEAM TEMPERATURE ('F)
RSC BORON CONCENTRATION (PPM) ,
( b.OTSG OPERATE RANGE LEVEL (%) _
PRESSURIZER WATER TEMPERATURE ('F)
A OTSG-STEAM TEMPERATURE ('F)
A.MFW TEMPERATURE ('F) r A MFW FLOW (LBM/HR)
LOOP A TCOLD ('F) 4 LOOP A THOT ('F) '
GROUP 7 CONT.0L ROD POS (INCHES)-
B MFW TEMPER,sTURE ('F)
B MFW. FLOW (LBM/HR)
LOOP B TCOLD ('F)
LOOP B THOT ('F)
- INITIAL CONDITIONS: 100% Full Power, MOL.
1 FINAL CONDITIONS / DURATION OF TEST: Simulator returned to 100% Power.
LAll procedures are signed, logs are completed and discrepancies- --'
noted, f
O 5-11
- . . . - . . -- -- - - - - - . . . . . . - . .. - . , . - . . - . . ,_._.w., . . - .
SIMCERT.1/SIMDOCS/SIM.
January 15, 1991
,-ss BASELINE DATA: OP1102 04 Power ops
( ) OP1102.10 Plant Shutdown OP1102.02 Startup DEFICIENCIES:** DR 90-127 DH3A doesn't isolate flow
- DR 90-137 FW10 & FW20 too large
- DR 90-138 CET > MAX difference DR 90-139 ADD N2 to T hot leg 6 N2 press control DR 90-151 CV1000 LTOP test DR 90-152 Margin to saturation monitor TR1011 had DR 90-153 CV2674/CV2624 overrides from ICS DR 90-154 PMS alarm screen shows pumps tripped DR 90-155 RCP air inlet temp alarm DR 90-158 K11B8 Alarm retpoint error DR 90-159 2nd RCP seal stage temp
(~N ** DR 90-160 PZR heatup rate uncontrollable
( ** DR 90-161 PZR spray response uncontrollable
None 5-12
l SIMCERT.1/SIMDOCS/SIM Jrnut.ry 14, 1991 STEADY-STATE OPERATIONS TEST ABSTRACTS O
(
O 5-13
_ - . - - - . ~ . . . . - - . ~ . - - . . - .
SIMCERT.1/SIMDOCS/SIH4 ,
January 15, 1991 ,
q NAME AND DESCRIPTION OF TEST: Steady State Operations (50% Power).
Q Establish a steady state 50% Power Level. Record data via plant logs and computer recording for 20 minutes.
AN81/ANS-3.5, 1985 RELATIONSHIP: Section 4.1, Appendix A.3.2 .
DATE TE87 CONDUCTED: October 21, 1990 s
TE8TED OPTION As stated in description above.
INITIAL CONDITIONS . The parameters monitored'and graphed at one second intervals are as follows:
PARAMETER HIN VAL , MAX VAL NI-5 REACTOR POWER (%). -0 125%-
CORE TliERMAL MEGAWATTS 0 2568 MW
- ELECTRICAL WATTS PRODUCED (WATTS) 0 1000 MW 4
TAVE ('F) $20 620'F
-A OTSG PRESSURE (PSIO) 0 1100 PSIG A OTSO OPERATE RANGE LEVEL (%) 0 .100%'
PRESSURIZER LEVEL (INCHES) 0 320 INCilES B OTSG STEAM TEMPERATURE ('F) 0 650'T RCS BORON CONCENTRATION (PPM) 0 2050 PPM
'/ B OTSG PRESSURE (PSIG) 0 1100 PSIG
( B OTSG OPERATE RANGE LEVEL (%) 0- 100%
PRESSURIZER WATER' TEMPERATURE ('F) 0 700'T ;
RCS FRESSURE (PSIA). O. 3000 PSIG A OTSO STEAM TEMPERATURE (,'F) 0 650'F a- A HFW (EMPERATURE ('F) 0 500*F 3 A MFl' FLOW (LBM/HR) 0- 6E6 LBM/HR LOOP A TCOLD ('F) 50 700'F LOOP A Tii0T ('F) 50 700'F GROUP 7' CONTROL ROD POS'(INCHES) -0 144 INCilES B MFW TEMPERATURE ('F) 0 500'F.
B HFW FLOW (LBM/IIR) 0 6E6 LBM/HR LOOP B TCOLD.('F) 50 700'F.
LOOP B THOT ('F) 50 700*F
?
FINAL CONDITIONS / DURATION OF TEST: Test is terminated af ter 20 minutes.
4 Plant logs and computer data la. compared to actual plant data.
Discrepancies noted. -
BASELINE DATA: Computer Plant Loga Dated 5-12-89
~ Control Room Logs Dated 5-12-89 DEFICIENCIES: . DR 90-157 Generated megawatts too low
. EXCEPTIONS TO ANSI /ANS-3.5, 1985:
None !
5-14
SIMCERT.1/SIMDOCS/SIM.
January 15, 1993 NAME AND DESCRIPTION OF TEST: Steady State Operations (80% Power).
O Eatablish a steady state 80% Power Level. Record data via plant logs and computer reentding for 20 minutes.
ANSI /ANS-3.5, 1985 RELATIONSHIP: Section 4.1, Appendix A.3.?
DATE TEST CONDUCTED: October 19, 1990 TESTED OPTION: As stated in description above.
INITIAL CONDITIONS: The parameters monitored and graphed at or.o second ,
intervals are as follova:
PARAMETER MIN VAL MAX _ VAL NI-5 REACTOR POWER (%) 0 125%
CORE THERMAL MEGAWATTS 0 2368 MW ELECTRICAL WATTS PRODUCED (WATTS) 0 1000 MW TAVE ('F) 520 620*F A OTSG PRESSURE (PSIG) 0 1100 PSIG A OTSG OPERATE RANGE LEVEL (%) 0 100%
PRESSURIZER LEVEL (INCHES) 0 320 INCHES B OTSG STEAM TEMPERATURE ('F) 0 650'F r% RCS BORON CONCENTRATION (PPM) 0 2050 PPM
- (J B OTSG PRESEURE (PSIG) 0 1100 PSIG B OTSG OPERATE RANGE LEVEL (%) 0 100%
PRESSURIZER WATER-TEMPERATURE ('F) 0 700'F RCS PRESSURE (PSIA) 0 3000 PSIG A OTSG STEAM TEMPERATURE ('F) 0 650'F A MFW TEMPERATURE ('F) 0 500'F A' FW FLOW (LBM/HP) 0 6E6 LBM/HR
' LOOP A TCOLD ( F) 50 700*F LOOP A TH0T-('F) 50 700'F GROUP 7 CONTROL ROD POS (INCHES) 0 144 INCHES B MfW TEMPERATURE ('F) 0 500'F ,
B MFW FLON (LBM/IIR) 0 6E6 LBM/im LOOP B TCOLD ('F) 50 700 F ~
LOOP B T110T ('F) 50 700'F FINAL'r0NDITIONS/ DURATION OF TEST: Test is terminated after 20 minutes.
Plant logs and computer data is compared to actual plant data.
Discrepancios noted.
BASELINE DATA: Plant Computer Logs Dated 3-28-89 '
Control Room Logs Dated 3-28-89 5-15
SINCERT.1/SIMDOCS/SIM January 15. 1991 i DEFICIENCIES:
None EXCEPTIONS TO ANSI /ANS-3.5, 1985:
None O
I f:
i i
{
l '..
O ,
1 5-16
.n , . .- - ..~ -
p~g- - . .- - - . . - . - . _ . . - . . . - . ~.
t $
l'#
SINCER* T.!MDOCS/SIM January '15 4 1991
< , , -l W lNAME:AND DEBCRIPTION OF TEST: Steady State 3perations (100% Power).-
Establish;als'teady state'100% Power Level. Record data via_ plant:-
' f(
^ "
clog's. and computer recording for 70 minutes. =l i
- ANSI /AN8-3.5, 1985 RELATIONSHIP: -Section 4.1, Appendix A.3.2:
a
. -t DATE TEST CONDUCTED:' October- 19, 1990 1
TESTED OPTION: As stated:in description:above. "
o ,
W-- -INITIAL CONDITIONS: The. parameters monitored and_ graphed at on's-second- I Intervals are as:follows'i=
1 a PARAMETER = -MIN VAL- . MAX VAL i
- NI-5 REACTORiPOWER,(%)
0- .125%
9 CORE TilERMAli HEGAWATTS 0- <2568-MW.
KELECTRICAL WATTS PRODUCED (WATTS) 0 -~ 10 0 0 -- MW ---
TAVE ('F) .
520- :: 620'F -
A.0TS0iPRESSURE (PSIG)' _
O' i1100 PSIG A'078010PERATE RANGE' LEVEL.(%) 0 .100%:
W, PRESSURIZER LEVEL -(INGi!ES) '
0 -320: INCHES 1
) -B'OTSO STEAM MPERATURE ('F) 'O 65 0 'F. -
=RCS/ BORON-CONCENTRATIONL(PPM)-- '0 : 2050: PPM B'OTSG PRESSURE'(PSIG)- _.
'0; -1100.PSIGi JB OTSO-OPERATE _ RANGE. LEVEL l(%) 0- 100% a 2 PRESSURIZER WATERiTEMPERATURE ('F)~ 0 .. 3700'F-iRCS' PRESSURE!(PSIA)(. -
.. . _ ' :Oi <
3000 PSIG
'. ?:'A10TSG STEAM:TEMPERATUREL('F) '
'O : .650'F, y._ LAlMFW! TEMPERATURE!('F) s.0 : :500'FJ 4 m .: ,
,A MFW FLOWl(LE1/HR)! 9 .'0~ 6E6LDM/HR
'700'Fi S 4 LOOP A TCOLD c'F)L :-509 a
. ~ LOOP A:Til0T f,'F) . .
TSO 700 F D
, GROUP.7.CONTx0L ROD.POS (INCHES) 0 E144 INCHES 1 B.MFW: TEMPERATURE ~('F) 0- :500*F- . ,
?B:MFW FLOW (LBM/IIR).
O- 6E6ELBM/HR
~. ... LOOP BLTCOLD ('F). :50i .
1700'F
, , LOOPj B; Til0T' ( 'F) (50n . 700'F ,
-(
- - 1 : FINAL CONDITIONS / DURATION.0F TEST: ' Test is terminatedLafter 70. minutes;:
>!p " .
. : Planttlogs and l computer data is compared t6" actual! plant data;-
(', : Discrepancies -noted.-
s
, 'l i
>9 ;
5-17
.1 lw .
1
SIMCERT.1/SIMDOCS/SIM.
January 15, 1991 O)
( LASELINE DATA: Plant Computer I,ogs Dated 1-6-89 Control Room Logs Dated 1-6-89 DEFICIENCIES:
None EXCEPTIONS TO ANSI /ANS-3.5,1985:
None
.1N 4
v O
5-18
SIMCERT.1/SIMDOCS/SIM January 14, 1991 6
SURVEILLANCE TEST ABSTRACTS O
4
~
5-19 1
m 4
- d.
+
$1MCERT.1/SIMDOCS/SIMi i < -
January 15, 1991
-w NAME AND DESi:RIPTION OF TEST: Surve11' lance Test REQUIRED PLANT _ DATE SURVEILLANCE DESCRIPTION -CONDITION TESTED 1015.02 ATT.A VLRIFICATION OF Dil REMOVAL AND CSD 13-90 "LTOP" WHEN'RCS IS 2 280' F 1015.02 ATT-F- ~ VERIFICATION OF DH SYS ALIGNMENT CSD 10-13 1102.01 SUPP-~1 RCS HIGH POINT VENT OPERATOR CK NOTE 1- 31-90
^-:1102.01180PP 2. DH SUCT!ISOL VLYS CV-1050 &- NOTE 2 11-12-90 !
CV-1410 LEAK TEST 1
- 1102.01 SUPP-3 MAIN: STEAM & MFW ISOL VALVE TEST NOTE.3 11-12-90 4
1102.01-SUPP 5 LRCS LEAK TEST : POWER OPS 11-01-90 1102.10 SUPP 1 ' LOW TEMP ~0VERPRESSURE PROTECTION CSD 10-18490
' ALARM TEST 1103.05:SUPP 1- EXERCISING OF PZR ELECTROHATIC- CSD' 10-13-90' l m RELIEF VLV (PSV-30t'0) 11103.05'SUPP 2 ERV BLOCK VALVE-(CV-1000) LEAK. HSD- 10-10-90 LTEST) 1103.13 SUPP 2 RCS LEAK RATE'DETERMIN WHEN.RCS POWER:-OPS 11-14-90
- w. LEAKAGE IS BEINO RETURNED T0-RCS
- 1104'.01 SUPP'11JCORE FLOOD CHECK VLV TEST-- NOTE-4 o10-12 :(CF-1A,CF-1B.DH-14A.DH-14B)
' 1104.02 SUPP 1'.RCS LOOP A ilPI'MOV, QUARTERLY TEST i POWERiOPS: 10-09-90: ::
-i
~1104.02 SUPP 2- RCS LOOP;B HPI M0V QUARTERLY TEST- : POWER OPS10-08-90. ;
i
- 1104.02 SUPP 3 'HPI PUMP P-36A TEST POWER-OPS 08-90 1 q
- 1104.02 SUPP 4 HPI PUMP P-36B TEST POWER-OPS '102 08 !!
1104.02 SUDP.5 HPI PUMP P-36C TEST POWER OPS 10-09-90
- 1104.02 SI'PP 6 ; RCP SEAL . BLEEP 0FF CV TEST 1 GCSD 10-13-90'- .7
- 1104.02 SUPP 7 .HPI FLOW PATH VERIFICATION- .CSD 10-17-90 a
y ,
L 5-20 s
i 5
t ;j
, ,,- , ,,r,. , . . _ . . . . - . . , , _ , _ _ . - . ~ _ -. . _ . . - . - - _ _ ~_.
SIMCERT.1/SIMDOCS/SIH; January 15, 1991 7 REQUIRED PLANT DATE b-- ~ - SURVEILLANCE DESCRIPTION CONDITION TESTED 1104.02 SUPP-8 MU & P SYSTEM CHECK VALVE AND LSD 10-13-90 CV SYROKE TEST 1104.04 SUPP 1 LO-PRESS INJ-(DH) PUMP P-34A POWER OPS 10-12-90
& COMPONENTS QUARTERLY TEST 1104.04 SUPP . ?4 PRESS INJ (DH) PUMP P-34B POWER OPS 10-12-90 b J0MPONENTS QUARTERLY TEST 1104.04 SUPP 3 DH SUCT HOV & INJECTION CHECK CSD 10-12-90 o VALVE STROKE TEST 1104.05-SUPP 2 RB SPRAY NA0H ADDITION VALVES POWER OPS 10-09-90
-QUARTERLY TEST
- 1104.05 RUPP 3 RB SPRAY PUMP P-35A QUARTERLY POWER OPS 10-08-90
. TEST 1104.05:SUPP 4 :RB APRAY BLOCK (CV-2400 & CV-2401) POWER OPS 10-09-90
-STROKE TEST' I
'1104.05 SUPP)5 LRBLSPRAY. PUMP P-J5B QUARTERLY POWER OFS 10-09-90 r
t y : TEST.
lJ '
f1104.29 SUPP;1 SERVICE WATER-PUMP P-4A TEST POWER OPS 10-09-90 1104.29~SUPP 2 SERVICE WATER PUMP P-4B TEST POWER OPS 10-09-90 l1104.29 SUPP 3 SERVICE WATER PUMP P-40. TEST POWER OPS 10-09-90~
- 1104.31 SUPP 1= HYDROGEN < SAMPLER C178 TEST ANY- 10-11 1104.31 SUPP 2 HYDROGENJSAMPLER C179 TEST ANY. 10-11-90 1104.31:SUPP-3 HYDROGEN RECOMBINER MSSA' ANY 10-12-90 FUNCTION IIST 1104.'31 SUPP 4 . HYDROGEN RECOMBINER M55B ANY 10-12-90
' FUNCTION TEST
~1104.31~SUPP 5 MSSA HEATUP TEST' POWER OPS 10-12-90 1104.31 SUPP 6 M55B HEATUP TEST POWER OPS 10-12-90 10-10-90 11104.33 SUPP 3 MONTHLY RB-COOLING UNIT .441 ANY 1104.33 SUPP 4 RB PURGE SYSTEM TES1 CSD 10-31-90 1104.36.SUPP 1 DG1'MONTRLY TFC ANY 10- 10-!JO 5-21 <
i
-l- , v
b i SIHCERT.1/SIMDOCS/SIM.
January 15, 1991
, ,m REQUIRED (N- )~ PLANT DATE SURVEILLANCE DESCRIPTION CONDITION TESTED 1104.33 SUPP 5 RB COOLING UNITS VCC-20 & VCC-2D POWER OPS 10-10-90 FLOW TEST 1104.33 SUPP 6 RB COOLING UNITS 33 VCC-2A POWER OPS 10-10-90
& VCC-2B FLOW TEST 1104.36 SUPP 2 D02 MONTHLY TEST ANY 10-11-90 1104.36 SUPP 9 DG1 ENDURANCE & LOAD ANY 10-31-90 REJECT TEST 1104.36 SUPP 10 DG2 ENDURANCE & LOAD ANY 10-30-90 REJECT TEST 1104.43 SUPP I PENETRATION ROOM VENTILATION ANY 10-09-90 LEAD SYSTEM MONTHLY TEST 1104.43 SUPP II PENETRATION ROOM VENTILATION ANY 10-09-90 STANDBY MONTHLY TEST
.1104.43 SUP III PENETRATION ROOM VENTILATION ANY 10-11-90
- SYS 18 MONTH SURVEILLANCE TEST
(_,) 1105.05 SUPP 2 EFIC FUNCTION TEST CSD 10-11-90 1105.09 SUPP 1 ABSOLUTE & RELATIVE POSITION POWER OPS 10-11-90 INDICATION COMPARISON 1106.06 SUPP 1 ELECTRIC EMERGENCY FWP (P-7B) POWER OPS 10-11-90 TEST (MONTHLY) 1106.06 SUPP 2 STEAM DRIVEN EMERGENCY FWP POWER OPS 10-11-90 (P-7A) TEST (MONTHLY) 1106.06 SUPP 3 EMERGENCY FW' VALVE STROKE TEST POWER OPS 10-11-90 1106.06 SUPP 4 EFW FLOW PATH & AUTOMATIC CSD 10-10-90 ACTUATION VERIFICATION 1106.09 SUPP 1 TURBINE OVERSPEED TRIP TEST 20% POWER 10-09-90 1305.01 APP A PROCESS MONITOR TEST CHECK POWEA OPS tv-09-90 1305.06 TNTEGRATED ES SYSTEM CHECL CSD 40-15-90 fy
? $
V 5-22
SIHCERT.1/SIMDOCS/SIM.
January 15, 1991- 1 1
g 2); REQUIRED' i
( f PLANT- DATE l SURVEILLANCE DESCRIPTION CONDITION TESTED 1
1305.07 SUPP 1 NORMAL OPERATION VALVE SROKE POWER OPS 10-09-90 .
TIMES 1305.07 SUPP 2 COLD SHUTDOWN VALVE STROKE CSD 10-13 90 TIMES ,
1305.07 SUPP.3 HONTHLY HIGC SAFETY SYSTEMS POWER OPS 10-11-90 STATUS' VERIFICATION. ;
1
- 1305.16 SUPP 2 HONTHLY SAFE SHUTDOWN Ih3T POWER OPS 10-11-90 [
CHANNEL CHECKS 1307.45 REFUELING OFF-SITE PONER CSD 10-16-90
-SURVEILLANCE-i 1 NOTE: .
1
- 1. PLAN 7 ^- ' 7LD SHUTDCi
- E J PYESc0E6 200 TO 235 PSIG
.P34A AND B ARE, STOPPED '
4' )
-3.. :HEATUP FROM CSD, RCS TEMPERATURE 2270 <280'F
- 4. ;RCS C00L'.r0WN,- RCS PRESSURE >900 PSIG ANSI /AN3-3.5,1985?K6LATIONSHIP: .Section 3.l.1, (10) Lt DATE TEST CONDUCTED:- As shown above. -!
' TESTED OPTIONi As shown above.-
'!WitTAL CONDITIONS: As shown above.
TInAL CONDITIONS / DURATION OF IISTi : Surveillance has been performed,_
! steps have been' initiated, and discrepancies noted,
- a. BASELINE DATA: Acceptance criteria _as stated in surveillance procedure. -
5-23
- - ~ n , ,m -
t SIMCERT.1/SIMDOCS/SIM.
Jsnuary 15, 1991 ge y - DEFICIENCIES: DR 90-101 "B" makeup pump. pressure d DR 90-111 -VEF38B> flow excessive-N'e}f.- **- DR.90-112 EDG Voltage > GRID Voltage
- DR 90-113 Stroke time CV2663/2613
-DR 90-114 VSF 7A & 7B VEF 8A 6.8B Don't trip on ESAS 5 DR 90-115 VEF 38 B won't start correct
- DR 90-126 Stroke time wrong CV3814/15
-DR- 90-130: EFW flow thru' idle EFW pump
- DR 90-131- CV2214 stroke time _too high DR 90-132_ _MU pump suction: press from DH Iow DR- 90-141 ESAS test /CV2233/6202/2234 failure DR 90-142- CV7403 fails 1to respond to. manual-following ES .
DR 90-143 CV1428 response following ESAS-resat DR 90-144 CV1065/1667/5612 fail to shut on ES-cha:)nel 5 DR- 90-145 CV1065/1667/5661/SV7510/7512/ failed to shut on ES DR 90-146 P36C fails to< start on ES signal' DR 90-147 CV1429 response.following ESAS reset-DR- 90-148 'CV2214/CV6203 fall ES test f(T:
DN ,T-
.- DR -
DR 90-149'90-156 CV2233/2234/6202 fail ES: test 1 VEF 38 B fails to start on ES#6;
/
EXCEPTIONS.TO ANSI'AN8-3.5, 1985 -
Nonei
(
i W
}
[ 5-24
SIMCERT.1/SIMDOCS/SIM January 14, 1991 l
-v t ~)
TRANSIENT TEST ABSTRACTS I. -
F v ,
se k
h 7 ,,
5-25 l
=--_____-____________-_-________
SIMCERT.1/SIMDOCS/SIM Jcnuary 15, 1991
- ;,.s --
NAME AND DESCRIPTION'0F TEST: Manual Reacter trip. Manual reactor Trip
.( was initiated, letdown and reheat- steam were isolated and
\ --
pressurizer level setpoint to 100". Simulator was stab 111 rad at hot. shutdown.-
ANSI /ANS-3.5, 1985 RELATIONSHIP: Section 4.2.1, 4.3; Appendix A A3.3; Appendix B, B2.2 (1)
DATE TEST CONDUCTED: November 3, 1990 TESTED OPTION: The parameters monitored and graphed at;one second
-intervals-are as follows:
PARAMETER NI-5 REACTOR POWER (%)-
TAVEL('F)
PRESSURIZER PRESSURE (PSIA)
RCS PRESSURE (PSIA)
PRESSURIZER LEVER (INCHES)
PRESSURIZER WATER TEMPERATURE ('F) s A OTSG STEAM FLOW ~(LBM/HR)
A OTSG STEAM FLOW (LBM/HR)
A MFW FLOW (LBM/HR)
B MFV FLOW (LBM/HR) -!
LOOP B TH0T ('F) v LOOP 1B TCOLD ('F)
_(,^ .
B OTSG OPERATE RANGE LEVEL-(%)
B OTSG~ STARTUP RANGE LEVEL (INCHES)
INITIAL CONDITIONS: _ 100%'Fu11 power, MOL 1
FINAL _ Col:DITIONS/ DURATION OF TEST: -Simulator was stabilized at n'ot t
' shutdown.-. Data =was collected to be compared _to baseline l.ata and.
. deficiencies were noted.
BASELINE DATA: ' Reactor Trip at ANO-1 5-01-89 !
Reactor _ Trip;at_ANO-1-_1-20-89 Panel of_ Subject Matter Experts t
DEFICIENCIES:
None-s
. ~ EXCEPTIONS TO ANSI /ANS-3.5, 1985:
I
'N None T
5-26 j l
l
. .~ _ _ _ _ . . _ ._ _ _
SIMCERT.1/SIMDOCS/SIM January 15, 1991 NAME AND DESORIPTION OF TEST: Simultaneous trip of all feedwater pumps.
.)
(
v1 Both main feedwater pumps were tripped. Emergency feedwater
. actuation was blocked, letdown and reheat steam were-isolated and pressurizer level setpoint was set 100". The simulator was stabilized at hot shutdown.
ANSI /jNS-3.5,_1985. RELATIONSHIP: Sections 4.2.1, 4.3; Appendix A, A3.3;--
i.ppendix B, B2,2 (2)
.DATE TEST CONDUCTED: November 3, 1990 TESTED OPTION: The parameters monitored and graphed at one second intervals are as follows:
PARAMETER NI-5 REACTOR-POWER (%)
TAVE ('F)
PRESSURIZER PRESSURE (PSIA)
RCS PRESSURE (PSIA)
PRESSURIZER LEVER (INC.9ES)
PRESSURIZER WATER TEMPERATURE ('F)
A OTSG STEAM FLOW (LBM/HR)
-A OTSG STEAM _ FLOW (LBM/HR)-
A MFW FLOW (LBM/HR)
D MFW FLOW (LBM/HR) f LOOP B TH0T ('F)
()- LOOP B TCOLD ('F)
B OTSG OPERATE' RANGE LEVEL (%)
B OTSG STARTUP RANGE LEVEL (INCHES)
-INITIAL CONDITIONS: 100% Full Power,-MOL FINAL CONDITIONS / DURATION OF TEST: Simulator was stabilized'at hot 1 shutdown. Data was' collected to 'be compared to baseline data- and deficiencies were noted.
! BASELINE-DATA: : Reactor Trip at ANO-1 5-01-89 l Reactor Trip at ANO-1 1-20-89 L B & W ATOG Book Panel of Subject Matter Experts DEFICIENCIES:
!' =None-EXCEPTIONS TO ANSI /ANS-3.5, 1985:
'd- None l
5-27 L
L~ __ _ - . _ ..
3IMCERT.1/SIMDOCS/SIM
,lenuary 15. 1991
/ NAME AND DESCRIPTION OF TEST: Simultaneous closure of all rt.tn steam isolation valves. Both main steam isolation valyce were shut, b Letdown and reheat steam were isolated and pressurizer level setpoint was set at 100". -The simulator was stabilized at hot shutdown.
ANSI /ANS-3.5, 1985 RELATIONSHIP: Section 4.2.1, 4.3; Appendix A, A3.3;
- Appendix B, B2.2 (3)
DATE TEST CONDUCTED: November 3, 1990 TESTED OPTION: The parameters monitored and graphed at one second 4 intervals are as follows:
PARAMETER NI-5 REACTOR POWER (%)
TAVE ('F): '
PRESSURIZER PRESSURE (PSIA)-
RCS PRESSURE-(PSIA)
PRESSURIZER LEVER (INCHES) 1
-PRESSURIZER WATER. TEMPERATURE ('F)
A OTSG. STEAM FLOW (LBM/ilR) ,
A OTSG STEAM-FLOW (LBM/f!R)
A MFW: FLOW (LBM/IIR)
._ B-MFW FLOW-(LBM/ilR) ',
. F .- LOOP B Til0T ('F)
\'
LOOP B TCOLD ('F)
B OTSO OPERATE RANGE LEVEL (%)
B OTSG STARTUP RANGE LEVEL (INCilES)
INITIAL' CONDITIONE: -100% full power, MOL-
-FINAL CONDITIONS /DURATIvN OF TEST: The simulator was stabilized at hot !
-shutdown. Data was collected to be: compared to' baseline data and. i
' deficiencies noted. ,
BASELINE DATA:~ Reactor Trip on'MSIV closure at Crystal Rive,r Site E 6-16-89 Reactor Trip at ANO-1 1-20-89 Reactor Trip at ANO-1 5-01-89 B.6 W ATOG Book Paael c,f Subject Matter Experts ,
DEFICIENCIES: DR 90-182 RCS Pressure <2355 with both MSIV I shut.
- p. . EXCEPTIONS TO ANSI /ANS-!.5, 1985: ,
\~" -
None 5-28 ,
SIMCERT.1/SIMDOCS/SIM.
January 15, 1991 7s NAME AND DESCRIPTION OF TEST: Simultaneous trip of all reactor coolant
! ) pumps. All reactor coolant pumps were manually tripped. Letdown
\' and reheat steam were isolated and the pressurizer level setpoint was set to 200". The simulator was stabilized at hot shutdowa.
ANSI /ANS-3.5, 1985 RELATIONSHIP: Sections 4.2.1, 4.3; Appendix A, A3.3; Appendix B, B2.2 (4)
DATE TEST CONDUCTED: November 3, 1990 TESTED OPTION: The parameters monitored and graphed at one second intervals are as follows:
PARAMETER NI-5 REACTOR POWER (%)
TAVE ('F)
PRESSURIZER PRESSURE (PSIA)
RCS PRESS'JRE (PSIA)
PRESSURIZi',R LEVER (INCHES)
PRESSURIZE 9 WATER TEMPERATURE ('F)
A OTSG STEid FLOW (LBM/HR)
A OTSG STEAD FLOW (LBM/HR)
B MFW FLOW-(LBM/HR)
B MFW FLOW (LBM/HR)
' ~'N LOOP B TH0T ('F)
(_,) LOOP B TCOLD ('F)
B OTSG OPERATE RANGE LEVEL (%)
B OTSG STARTUP RANGE LEVEL (INCHES)
EFW FLOW FROM P?A-TO A OTSG (LBM/HR)
EFW FLOW FROM P7A TO B O'fSG (LBM/HR)
EFW FLOW FROM P7B TO A OTSG (LBM/HR)
EFW FLOW FROM P7B TO B OTSO (LBM/HR)
INITIAL CONDITIONS: 100% Full power, MOL FINAL CONDITIONS / DURATION OF TEST: The simulatt was stabilized at hot shutdown. Data was collected to be compared to baseline data and deficiencies noted.
BASELINE DATA: Reactor Trip at Crystal River Site Due to Loss of Offsite i' Power
! Reactor Trip at ANO-1 01-20-89 Reactor Trip at ANO-1 05-01-89 h Reactor Trip at ANO-1 12-28-89 f-~3 Panel of Subject Matter Experts L (s-l 5-29
SIMCERT.1/SIMDOCS/SIM. <
January ',5, 1991 i i
DEFICIENCIES:
None EXCEPTIONS TO ANSI /ANS-3.5, 1985:
None
./
O 5-30
SIMCERT.1/SIMDOCS/SIM January 15, 1991
- 1 NAME AND DESCRIPTION OF TEST
- Trip of a single reactor coolant pump, f( The "C" reactor coolant pump was' tripped. Letdown and reheat steam i u were isolated and the pressurizer level setpoint was set to 100".
The simulator was stabilized at hot shutdown.
ANSI /ANS-3.5, 1985 RELATIONSHIP: Sections 4.2.1, '4.3; Appendix A, A3.3; Appendix B, B2.2 (5)
DATE TEST CONDUCTED: November 3, 1990 TESTED OPTIOF The parameters monitored and graphed at one second intervals are as follows:
PARAMETER NI-5 REACTOR' POWER (%) (
LOOP A THOT ('F)
LOOP B THOT ('F)
LOOP A TCOLD-('F)
' LOOP B TCOLD ('F)
A.0TSG OPERATE RANGE' LEVEL (%)
B'OTSG OPERATE RANGE LEVEL (%)
p A OTSG STARTUP RANGE LEVEL-(INCHES)
Q B'OTSG STARTUP-RANGE LEVEL (INCHES)
A OTSG STEAM FLOW (LBM/HR)
B OTSG STEAM FLOW-(LBM/HR)
A'MFW FLOW (LBM/HR)-
B HFW FLOW'(LBM/HR)
INITIAL CONDITIONS: 100% Full Power, MOL
~ FINAL CONDITIONS / DURATION OF TEST: The simulator was stabilized at hot shu tdown.~. Data was collected to be compared to baseline data and deficiencies noted.-
BASELINE DATA: Reactor trip at ANO-1 11-10-89 Reactor trip t ANO-1 01-20-89 ,
Reactor trip at ANO-1 05-01-89
' Rear.toritrip a'c ANO-1 12-28-89 Pane 1~ of Subject Matter- Experts DEFICIENCIES:
None i f EXCEPTIONS TO ANSI /ANS-3.5, 1985: !
None 5-31
SIMCERT.1/SIMDOCS/SIM.
Jenuary 15, 1991 NAME AND DESCRIPTION OF TEST: Main turbine trip (from maximum power
. 'j (q that does not cause and immediate reactor trip). From 40% power trip the main turbine. The ERV and Pressurizer spray was used to control RCS pressure while ICS runs reactor power back. The simulator was stabilized at less than 15%.
ANSI /ANS-3.5, 1985 RELATIONSHIP: Sections 4.2.1, 4.3; Appendix A, A3.3;
-Appendix B, B2.2 (6)
DATE TEST CONDUCTED:
TESTED OPTION: The parameters monitored and graphed at one second intervals are as follows:
PARAMETER NI-5 REACTOR POWER (%)
TAVE ('F)
PRESSURIZER PRESSURE (PSIA)
RCS PRESSURE (PSIA)
PRESSURIZER LEVEL (INCHES)
PRESSURIZER WATER TEMPERATURE ('F)
A OTSG STEAM FLOW (LBM/HR)
B OTSG STEAM FLOW (LBM/HR)
A MFW FLOW (LBM/HR)
. B MFW FLOW (LBM/HR)
/ LOOP B TH0T ('F)
\,__. LOOP B TCOLD ('F)
B OTSG OPERATE RANGE LEVEL (%)
B OTSG STARTUP Rt.NGE LEVEL (INCHES)
INITIAL CONDITIONS: 50% Full power, then maneuver to 40% Full power.
FINAL CONDITIONS / DURATION OF TEST: The simulator was stabilized at hot shutdown. Data was collected to be compared to baseline data and deficiencies noted.
BASELINE DATA: Plant Runback, trip of main turbinc, ANO-1 11-26-89 Panel of Subject Matter Experts DEFICIENCIES:
None
/s EXCEPTIONS TO ANSI /ANS-3.5, 1985:
YY y9 g I
l 5-32
.- .= . . . - - . . .- - .- -- .
- )
SIMCERT.1/SIMDOCS/SIM; I January 15, 1991
.r
'g p NAME AND'-, 5;C 710N OF TEST: Maximum rate power ramp (100% down to 75% !
-3 ) .- nnd . . r is to 100%).- Set _ unit load demand to approximate value V for M% and set ICS rate demand to 10%/ minute. Reduce power.to 75%. -Adjust unit load demand back for 100% power. Increase power to 100% and stabilize.-
ANSI /ANS-3.5, 1985 RELATIONSIIIP: Sections 4.2.1, 4'.3; Appendix A, A3.3; Appendix B, B2,2 (7)
DATE TEST CONDUCTED: November 3, 1990 !
TESTED OPTION: The parameters monitored and graphed at one second j intervals are as follows: !
A
_P_A_RAMETER NI-S REACTOR PDFER (%),
e TAVE ('F)
PRESSURIZER PRESSURE (PSIA) 1 RCS PRESSURE (PSIA)
PRESSURIZER LEVER (INCilES)-
-PRESSURIZER WATER TEMPERATURE ('F)-
'A-0TSO STEAM FLOW (LBM/ilR) !
B OTSO STEAM' FLOW-(LBM/HR)- 1 A MFW FLOW (LBM/IIR)
B MFW FLOW (LBM/i!R)-
.( g.
LOOP'B Til0T ('F)_
"U LOOP B TCOLD ('F)
-B OTSGLOPERATE RANGE LEVEL (%)
B OTSG STARTUP RANGE LEVEL (INCi!ES)
INITIAL' CONDITIONS: 100% Full power, MOL FINA's CONDITIONS / DURATION OF TEST: Simulator was stab'ilized at hot-shutdown. : Data was collected to be compared-to baseline data and
' deficiencies noted.-
, BASELINE DATA ' Panel of Subject Matter Experts -
DEFICIENCIES: _
-l Nono-EXCEPTIONS'To ANSI /ANS-3.5,-1985:
None_
f .
U 5 , .. -. .
SIMCERT.1/SIMDOCS/SIM 4 c Jcnuary_15, 1991
. NAME AND DESCRIPTION OF TEST: Maximum size RCS rupture combine with a 4
' vI,} loss of offsite power. Malfunctions for loss of offsite power and a 8.5 Ft8 RCS rupture were inserted. Lotdown and reheat steam 1 were isolated and'the pressurizer level setpoint was adjusted to 100".
ANSI /ANS-3.5, 1985 RELATIONSHIP: Sections 4.2.1, 4.3; Appendix A,A3.3; Appendix B, B2.2.(8)
- DATE TEST CONDUCTED: November 3, 1990 TESTED OPTION: The parameters monitored and graphed at one second l Intervals are as follows:
PARAMETER PRESSURIZER PRESSURE (PSIA)
RCS PRESSURE'(PSIA)
PRESSURIZER LEVEL (INCHES)
REACTOR BUILDING PRESSURE (PSIA)-
INITIAL CONDITIONS: 100% Full power, MOL
. FINAL CONDITIONS / DURATION OF TEST: Test terminated when RCS' leakage and -l
,r g the llPI/LPI are equal and the CET's are stable at approximately
('). 200'F. . Data was collected to be' compared to baseline-data and deficiencies noted.
4 BASELINE = DATA::B 6 W AT00 Book
- SAR hapter 14
. Pan ' of Subject Matter Experts DEFICIENCIES:
None .
'l EXCEPTIONS TO' ANSI /ANS-3.5, 1985:-
+
None 5-34 W
SIMCERT.1/SIMDOCS/SIM January 15, 1991
-i NAME AN, DESCRIPTION OF TEST: Maximum _ size unisolable main steam line j-sp; -rupture-insert malfunction forEsteam line rupture in reactor
~4
'- J building (MS0131) at 3.14 Ft 8. Isolate letdown and reheat steam :
ar.d adjust pressurizer level setpoint to 100". !
- ANSI /AltS-3.5, 1985 RELATIONSHIP: Sections 4.2.1, 4.3; Appendix A, A3.3; Appendix B, B2.2 (9).
DATE TEST CONDUCTED: November 3, 1990 TESTED 0PTIONs.The parameters. monitored and graphe' dant one second
- lc intervals are as follows:
'I PARAMETER PRESSURIZER PRESSURE (PSIA)
-RCS PRESSURE (PSIA)
PRESSURIZER LEVEL (INCHES)
REACTOR BUILDING PRESSURE (PSIA)
.. ?
INITIALLCONDITIONS:- 100% Ful1~ power, HOL FINAL' CONDITIONS / DURATION OF TEST . Stabilize the simulator at hot shutdown. Data:was collected to be compu.:ed to baseline data and M/S deficiencies noted. .i rk$
t
- -BASELINE-DAIA: B & W'AT00 Book ,
SAR Chapter 14- 'I a; Panel of Subject-Matter Experts-
-DEFICIENCIES:
o None t
1( 1 EXCEPTIONS TO ANSI /ANS-3.5, 1985:
-u: w J'
None
_,a L
n l:
t' p
kj -
5-35
SIMCERT.1/SIMDOCS/SIM.
l January 15, 1991 l
l NAME AND DESCRIPTION OF TEST: Slow primary prepressurization to
\(-s) j saturation condition using pressurizer relief or safety valve stuck open Open ERV block valve and ERV. After reactor trips isolate letdown and reheat steam and adjust pressurizer level setpoint to 100".
ANSI /ANS-3.5, 1985 RELATIONSHIP: Sections 4.2.1, 4.3; Appendix A, A3.3; Appendix B, B2.2 (10)
DATE TEST CONDUCTED: November 19, 1990 TESTED OPTION: The parameters moe. tored and graphed at one second intervals are as follows:
PARAMETER ERV FLOW TO EQUECH TANK (LBM/HR)
PRESSURIZER PRESSURE (PSIA)
RCS PRESSUPE (PSIA)
PRESSURIZER WATER TEMPERATURE ('F)
PRESSURIZER STEAM TEMPERATURE ('F)
PRESSURIZER SURGE LINE TEMPERATURE ('F)
LOOP A THOT ('F)
SOURCE RANGE COUNTS O REACTOR VESSEL LEVEL ABOVE FUEL (FEET)
RCS MARGIN TO SATURATION ('F)
P INITIAL CONDITIONS: '100% Full power, HOL FINAL CONDITIONS / DURATION OF TEST: Stabilize the simulator at hot shutdown. Data was collected to be compared to baselina data and deficiencies noted.
BASELINE DATA: B & W ATOG Book SAR Chapter 14
-Panel of Subject Matt : Experts DEFICIENCIES: DR 90-177 K12 CS Cleared wrong EXCEPTIONS TO ANSI /ANS-3.5, 1985:
None NJ 5-36 1
l SIMCERT.1/SIMDOCS/SIM January 15, 1991 NAME AND DESCRIPTION OF TEST: Time in life test.
() Determine Plant response to a fixed size steam leak at 4 EFPD, 200 V EPPD and 400 EFPD. Steam flow of approximately 2%.
Fail CV6688 and CV6690 (Turbine Bypass Valves) 1/2 Open.
ANSI /ANS-3.5,1985 RELATIONSHIP: Section 3.1.1.9 DATE TEST CONDUCTED: November 3, 1990 TESTED OPTION: The parameters monitored and graphed at on. second intervals are as follows:
PARAMETER N1-5 REACTOR POWER (%)
LOOP A THOT ('F)
LOOP B TH0T ('F)
LOOP A TCOLD ('F)
LOOP B TCOLD ('F)
A OTSG PRESSURE (PSIG) 1 B OTSG PRESSURE (PSIG)
A OTSG OPERATE RANGE LEVEL (%)
, B OTSG OPERATE RANGE LEVEL (%)
A OTSG STARTUP RANGE LEVEL (INCHES) n )
B OTSG STARTUP RANGE LEVEL (INCHES)
- f. A OTSG STEAM FLOW (LBM/HR)
B OTSG STEAM TLOW (LBM/HR)
A MFW FLOW (LBM/HR)
B MFW FLOW (LBM/lL.)
NI-3 POWER (AMPS)
INITIAL CONDITIONS: RX power approximately 1E-8 AMPS on intermediate range, below the point of adding heat.
FINAL CONDITIONS / DURATION OF TEST: Reactor power stable at new value or 15 minutes.
BASELINE DATA: Arkansas Nuclear One - Unit 1, Cycle 9 reload report.
Panel of Subject Matter Experts DEFICIENCIES:
None g
EXCEPTIONS TO ANSI /ANS-3.5, 1985:
None 5-37 l
SINCERT.1/SIMDOCS/SIMI January 14,-1991 O
MALFUNCTION TEST ABSTRACTS l
l 0
b 5 38-
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. l ,a ma .-A- a ,.e,,
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L 1 1
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1 i
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9 i
S1HCERT.1/SIMDOCS/SlH1 Janunty 15, 1991 O
MALFUNCTION TEST ABSTR/'""':
O O
5-38
SIMCERT.1/SIMDOCS/S1H1 January 15, 1991 DATE TESTED ................. 11/05/90 HALFUNCTION SYH110L . . . . . . . . . . HRC001 MALFUNCTION NAME ............ OTSG A TUBE LEAK ANSI 3.5 REFERENCE ......... 3.1.2.la SPECIFIC CAUSE .............. CORROSION ON TUDES SEVERITY . . . . . . . . . . . . . . . . . . . 0-40 TUBES (1 TUBE = 235 GPH)
SEVERITY RATE .............. 0-30 HINUTES IMMEDIATE ALARHS RECEIVED:
K05 C3 S/G N-16 TROUBLE BASELINE DATI. SOURCES:
PANEL OF EXPERTS REVIEW AOP 1203.12 SHALL OTSG TUDE LEAKS E0P 1202.01 TUBE RUPTURE TAB B & W AT00 GUIDELINES HALFUNCTION TEST CONDITIONS:
. IC NAME ................ 100% POWER SPECI AL CONDITIONS . . . . . . ICS IN AUTO OPERATOR ACTIONS ........ STOP RCP'S WHEN SCH <50'F ISOLATE LETDOWN AT RX TRIP HALF SEVEhlTY .......... 2.0 TUBES HALF RAMP ............... O SEC0tIDS TEST DURATION .......... 10 MINUTES Dr's written due to testing: 90-174 RCS PRESSURE RES?ONSE TO LEAK 5-39
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