ML20237G247
| ML20237G247 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/31/1986 |
| From: | Maine Yankee |
| To: | |
| Shared Package | |
| ML20237G181 | List: |
| References | |
| NUDOCS 8708130378 | |
| Download: ML20237G247 (240) | |
Text
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l MAINEYANKEE SIMULATOR -
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ANNUAL l
REPORT 1986 l
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8708130370 070810 PDR
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V ADOCK 05000309 ;
PDR ;
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INDEX ,
Page I. Introduction 1 n
II. Simulator Information 1 III. Control Room 1 IV. Instructor Interface 1 V. Simulator Procedures 1 VI. Changes Since Last Report 1 VII. Simulator Data Base 2 l- VIII. Simulator Operations 2 IX. Upgrade Plans 4 l.ISTOFAPPENDICES
' Appendix A MR Report 12/31/86 Appendix B DR Summary 12/31/86 Appendix C Proc 18-343-1, Simulator Operability Test Appendix D MY Simulator Core 9 Physics Test Comparison Appendix E Simulator Benchmark Analysis Evaluation
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I. INTRODUCTION The purpose of the Maine Yankee Simulator Annual Report is to document the performance of the Maine Yankee Simulator. The initial report laid the
' groundwork and set the format for this and subsequent reports. This report will deal with testing data and changes made during the reporting year.
II. SIMULATOR INFORMATION Owner / Operator Maine Yankee Atomic Power Company Manufacturer Singer-Link Date Available for Training 5/14/84 Type of Report Annual 1986 .
III. CONTROL ROOM There were two major changes made to the Simulator Control Room this reporting period;
- 1. New furniture was added to the Simulator to coincide with the new furniture added to the Control Room.
- 2. A simulated Alternate Shutdown Panel was added late in 1986. In the plant, it is located in the EFW Room; in the Simulator, we located it in the SW corner of the Simulator Room. It will be enclosed to facilitate the idea of a remote panel.
IV. INSTRUCTOR INTERFACE There were no changes made that affect this section.
V. SIMULATOR PROCEDURES There were no changes made that affect this section. ,
VI. CHANGES SINCE LAST REPORT From 1/1/86 through 12/31/86, a total of 34 Modification Requests (MRs) and 237 f Discrepancy Reports (DRs) were generated. The MRs are separated into three ,
I categories;
- 1. Design Changes - a modification that is made as a result of an Engineering Design Change Request (EDCR).
- 2. Set Point Change - a modification that is made as a result of a change to a setpoint that is used internal to.the simulator software.
- 3. Enhancement - an increase in scope of simulation, usually as a result '
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of a training need.
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Appendix.A is a. listing of the status of all MRs written since RFT. The following is a breakdown _for 1986:
Written Incorporated Open Design Change 2 18 1 Set Point Changes 2 3 O Enhancements 30 28 17
. Appendix'B is a listing of the. status of DR's written since the warranty period expired (5/14/85). The.following is a breakdown for 1986:
Written Incorporated Open.
Discrepancy Reports 237 262' 36 VII SIMULATOR' DATA BASE 1
As. discussed in the initial Annual Report, the data. base for the Simulator is a.
living document. Initially, we attempted to maintain the Final Design Specifications.(FDS) updated every time a change was made to the software. He
.have found this to be nonviable. Our policy now is to update the FDSs every.six
. months (January and July). The documentation we require for any change will serve as the data base.
VIII. SIMULATOR OPERATIONS Procedure 18-343-1, " Simulator Operability Test", was completed in November.of
-1986. The test is divided into six distinct sections:
- 1. Integrated Test
- 2. Malfunctions
- 3. Surveillance
- 4. Simulator Operation Testing
- 5. Bench Mark Analysis-
- 6. Simulator Base Line Transients Integrated Test The integrated test involves taking the Simulator from cold shutdown through RCS heatup.and reactor startup. . Low Power Physics testing is then performed, followed.by power escalation testing. This testing uses approved plant and RE procedures. Data is taken on the Simulator and compared to plant data. The data' sheets are attached to the procedure which is presented in this report as Appendix C. An analysis of the results of the core physics and power escalation
-tests are shown in Appendix D.
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The next portion of the integrated test is three fold:
- 1. Determine the~ ability of the Simulator to mal'tain n 100% steady state condition ( 2%) for one (1) hour, l
L .2. Compare the heat balance of the simulator to the plant. J B
'3. Compare the instrument readings of the Main Control Board in the plant l at 100% power to the Simulator.
All tests were satisfactory; the results are attached to Procedure 18-343-1. f The. final portion of the integrated test is the plant shutdown using approved plant procedures.
Malfunctions The next major portion of the annual test involves testing 1/4 of the available malfunctions. The original ATP was used as a guide. This year we tested the following systems (malfunctions):
Annunciator System Component Cooling System Chemical and Volume Control System Electrical Distribution System Electrical Generation System Surveillance The following surveillance procedures were performed on the Simulator; Procedure # Title 3.1.2 ECCS 3.1.4 Diesel Generator 3.1.5 Aux Feed Pump 3.1.8 CEA Exercises 3.1.18 Control Room Ventilation '
3.1.19 RCS Leakage 3.1.3 Turbine Valve Testing 3.1.15.4 SI Check Valve
-3.1.14-A/B EDG/ECCS Cold S/0-Testing 3.1.15.1-A/B CIS 3.1.15.2 RAS 3.1.20 Safeguard Valves 3.1.22 AFW Cold S/D Flow 1
The data from the most recent surveillance procedure run in the plant was !
compared with Simulator data in the Annual Test Procedure, where appropriate DRs were written.
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l Simulator Operation Testing The Simulator Operation Testing is divided into four (4) parts.' Annunciator Offsets, Time and Memory Usage, Operational Time test, and a Functional test of l all the emergency S/D buttons. All tests were satisfactory except the time usago. A discrepancy report was written and we are planning on upgrading our computer complex in 1987 for a dual processor computer.
Benchmark Analysis The original Benchmark Analysis was a joint effort between YAEC and Maine Yankee. The results of the original analysis are outlined in the 1985 Annual Report. The simulator portion of the analysis was performed again subsequent to implementation of Singer-Link warranty DRs. Appendix E discusses the analysis in detail. .
In subsequent Annual Reports, the previous year's transient analysis will be compared to the current year's to check for discrepancies.
Baseline Transients Appendix B to ANSI /ANS-3.5-1985, " Simulator Operability Tests" lists ten (10) transients applicable to PWR Simulators. We have chosen to implement nine (9) of those as applicable to Maine Yankee. Transient #7, " Maximum Rate Power Ramp (100% down to approximately 75% and back up to 100%)" was not implemented since all power changes are done manually and therefore the results have too many unknown factors associated with them. All other transients are performed with no operator action. The purpose of which is to check performance of the Simulator from year to year.
. Initial review of the data appears appropriate for the transients. In subsequent reports, there will be two (2) sets of data per graph to show last year's data versus this year's data.
Summary The results of the annual test is data which is either compared to actual plant data or the judgment of an SRO licensed person. A total of 40 Discrepancy Reports were written as a result of this test procedure.
IX UPGRADE PLANS Appendix A and Appendix B are lists of outstanding Modification Requests and Discrepancy Reports respectively.
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APPENDIXA MRREPORT 12/31/86
' l SIMULATOR MODIFICATIONS STATUS REPORT 1-
'BY MRf ,
EDCRf- . SYSTEM HDW SFW' DESCRIPTION OPEN INCORP
)E ENG ENG DATE DATE h E80-038 'FW --- ' JFM POWER SUPPLY CHANGE FOR RELAYS C4/24/84 11/05/84
. .IN SG TRIP SYSTEM
) .A *-083 FW ~~- JWW COMPUTER MONITORING OF 04/24/84 05/11/84 l FEEDWATER HEATER ,
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) P 4-083 'ED RDE .JWW EMERGENCY MCC FEEDER REMOTE 04/24/84 11/26/B4 ,
IND. LIGHTS h P16-081 MI RDE --- INSTALL SMOKE DETECTOR IN 05/10/84 10/26/84 CR CABINETS -
si A 9-083 RC --- --- PORV INTERMEDIATE SETPOINT 05/10/84 REJECTED REJECTED i 'E81-010 RC S/L S/L PRESSURE TAPS &. ROOT" VALVES 05/10/84 03/17/86
. FOR A PRIMARY TREND SYS (PITS)
F E81-026 RC S/L S/L PITS - DEFFERRED 05/10/84 03/17/86 L E85-018 RC S/L S/L' PRIMARY INVENTORY TREND SYSTEM 10/02/85 03/17/86
!- A25-083 TU --- JFM .RX TRIP / TURBINE TRIP 05/18/84 06/27/04 REDUNDANCY l' A31-083 CV --- CAM ADD.A RTD TO DISCHARGE LINE 05/20/84 11/05/84 OF EACH CHARGING PUMP b E83-513 FW RDE JWW MAIN TURBINE / P-2C TRIP 05/20/84 07/29/85 INTERLOCK BYPASS FEATURE
) EBO-050 ED --- JWW MODIFY ED MODEL IAW 05/24/84 05/24/85 A 8-083 FW S/L S/L RELOCATE P-2C CONTROLLER FROM 05/28/84 10/28/85 INSIDE MCB TO FRONT OF MCB.
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.A30-083 RP 'RDE JWW ALARM FOR TCB-9 05/28/84 02/12/85 f
l- E84-009 ED RDE JWW LOSS OF 115KV ALARM 05/25/84. 09/18/84'l E83-510 RC --- CAM COMPUTER READOUT OF REACTOR 05/25/84 11/05/84 HEAD TEMPERATURE i .XXX-015 EG RDE JWW WRONG MVAR METER ON MCB 05/25/84 09/21/84 SECTION 'A' i E84-002 CH RDE HGJ INSTALLATION OF GEMS SUMP 06/22/84 07/15/85 LEVEL TRANSMITTERS E84-011 CH S/L S/L CONTAINMENT PARAMETERS 06/22/84 10/28/85
. RELOCATION
SIMULATOR MODIFICATIONS STATUS REPORT 2 BY MR$
EDCRf SYSTEM HDW SFW DESCRIPTION OPEN INCORP ENG ENG DATE DATE E81-011 CV --- --- MITIGATION OF HARSH 06/22/84 REJECTED ENVIRONMENT ,
E85-006 CV --- ---
MOD PAB HELB TRIP CIRCUIT 06/22/84 REJECTED I
, E81-003 CV RDE --- HPSI HEADER RECIRC LINES 06/22/84 12/14/84 REMOVAL OF SIA-AI2,22,32 CONT E84-014 CV --- JWW CHARGING SYSTEM FLOW 06/22/84 03/06/85 RESTRICTOR FOR LTOP CONCERNS A22-083 ED RDE JWW STAFF BLDG. UNDERVOLTAGE TRIP 06/22/84 10/30/84 4 E83-524 ED --- --- FEMCO PWR SWAP ON INVERTER #5 06/22/84 REJECTED REJECTED 1
l E83-028 FW RDE HGJ NEW CONDENSER SURGE TANK AND 06/22/84 09/16/85 PIPING E83-029 FW RDE JWW AUX FEED WATER SYS. MOD. 06/22/84 07/15/85 E83-512 FW RDE -JWW P-2A AND B RECIRC. SYSTEM 06/22/84 08/20/85 E83-520 FW --- --- REMOVAL OF AFW-1 INTERNALS 06/22/84 REJECTED REJECTED
'E84-010 FW RDE S/L P-2C LOW SUCTION TRIP TIME 06/22/84 10/23/85 DELAY JE83-032 RC S/L S/L NEW SAT. MONITORS 06/22/84 10/23/85 E83-031 RC S/L S/L LOW TEMPERATURE OVERPRESSURE 06/22/84 10/23/85 VARIABLE SETPOINT <
E84-012 NI --- --- LOG RECORDER REPLACEMENT 06/22/84 REJECTED REJECTED P22-082 MS --- JWW MANUAL OPERATIONS OF MS-T-163 06/22/84 10/18/.85 ,
1 A28-083 CH --- --- NNS INSTRUMENTATION, SIGNAL 06/22/84 REJECTED MULTIPLEXER - REJECTED l
- E84-006 MS RDE HGJ REROUTE SCAVENGING VENT TO 06/22/84 09/16/85 FIRST POINT HEATERS l
' E83-009 MI RDE --- APPENDIX R ELECTRICAL MOD. 06/22/84 11/20/84 A27-082 MS NES NES AUX STEAM SUPPLY FROM CROSS- 06/22/84 06/03/86 UNDER PIPING-REJECTED 07/05/84 XXX-038 RM RDE JWW MOVE LETDOWN LOW RMS MODULE 06/25/84 11/26/84
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' SIMULATOR MODIFICATIONS STATUS REPORT 3 BY MRf EDCRi SYSTEM HDW SFW DESCRIPTION OPEN INCORP )
ENG- ENG DATE DATE XXX-039 CR --- --- VOID - CHANGE CORE 6 TO CORE 8 06/25/84 REJECTED
~
- REJECTED XXX-040 PC --- JWW UPDATE MODCOMP 06/25/84 05/24/85 ;
XXX-041 RC RDE --- NEW AMMETERS FOR RCP'S 06/25/84 11/20/84' XXX-042 FW- RDE ---- NEW SCALE FOR P-2C PRESSURE 07/09/84 11/27/84 3 CONTROLLER E84-016 FW RDE CAM FW & EFCV BYPASS ANNUNCIATOR 07/23/84 01/09/85 E83-508 SW RDE --- APPENDIX "R" BUILDING 12/10/85 01/21/86 PAN ALARM WINDOW IN SECTION S XXX-04h MI RDE --- CHANGE ANNUNCIATOR BUTTONS TO 02/21/85 11/06/85 NEW COLORS E84-070 FW RDE JWW AUTO BLOCK OF P-2C RECIRC 07/11/85 11/05/85 ,
ABOVE 80%
E80-050 ED ---
S/L ADD ABILI'TY TO VARY 115 KV 07/22/85 10/23/85 VOLTAGE - ENHANCE MR #10 XXX-048 FW ---
S/L ADD ABILITY TO FAIL OPEN P-2C 07/22/85 10/23/85 RECIRC VALVE-EXPAND MALF FWO7 XXX-049 MI RDE --- DISPATCHERS PHONE TO RING IN 07/24/85 INSTRUCTORS STATION s ,
XXX-050 ED RDE KLP ADD 86P AND 86BU RELAYS TO MCB 08/07/85 04/17/86 '
. AND REMOVE REMOTE FUNCTION.
E85-008 SG' RDE KLP REGULATORY GUIDE 1.97 09/18/85 08/27/86 SG LEVEL RECORDERS i E84-072 RC NES NES REGULATORY GUIDE 1.97 09/18/85 07/30/86 PZR PRESSURE RECORDER XXX-053 RC RDE --- RX VESSEL LEVEL SIGMA 09/20/85 02/04/86!
XXX-054 CR --- YNS CORE UPDATE 09/20/85 09/25/86!
IMPROVE SIAS " LOSS OF CONTROL" 09/20/85 10/25/85, E84-060 RP RDE JWW ANNUNCIATORS E84-063 CS --- JWW ELIMINATE SEAL CONTACTS FOR 09/20/85 10/25/85 CS-M-66 & CS-M-71 E84-069 CV NES NES RELOCATE CH-M-87 CONTROL 09/20/85 07/30/86 SWITCH AND LIGHTS
' SIMULATOR MODIFICATIONS ' STATUS : REPORT ' 4:
BY-MR#
IEDCR$_ -SYSTEM HDW SFW: DESCRIPTION OPEN- INCORP ENG ENG _DATE DATE E84-071- RC- NES .NES- RELOCATION OF REACTOR HEAD 09/20/85 07/30/86-)
VENT SELECTION SWITCHES-E84-074 CS -RDE JWW INTERCHANGE POSITIONS P61A & 09/20/85 11/05/85 P61S CONTROL SWITCEES E84-075 FW RDE JWW PROVIDE INDICATION STEAM DUMP 09/20/85 12/03/85 OVERRIDE AND PR-A-38, E85-001 CV NES NES REMOV5 RCP THROTTLE BUSHING 09/20/85 07/30/86 '
'DP INSTRUMENTATION FROM MCB E85-002 RC NES NES PRESSURIZER PANEL MODIFICATION 09/20/83 07/30/86-E84-003 RP --- JWW REPLACEMENT OF RWST LEVEL 09/30/85 10/25/85 '
SWITCHES WITH TRANSMITTERS E85-007 RC RDE JWW NEW PZR LEVEL INDICATION 09/20/85. 09/02/86 E85-009 RC NES NES RCS TEMPERATURE MODIFICATIONS 09/20/85 07/30/86' E85-011 MI NES NES MCB PLATES FOR HUMAN FACTORS 09/20/85 07/30/86 DESIGN CHANGES 1
E85-012 CV NES NES CVCS/ LOOP PANEL MOD'IFICATION 09/20/85- 07/30/86 E85-014 MI --- --- SEISMIC ANCHORAGE OF THE 09/20/85- REJECTED CEILING & LIGHT FIXTURES XXX-068 MS --- JWW ' ADD DECAY HEAT RELEASE 09/20/85 11/07/85 VALVE ISOLATION XXX-069 RC RDE --- NARROW RAhGE PZR. 09/20/85 09/02/86 PRESSURE RECORDER XXX-070 RH --- --- P-129 AMP METER 09/20/85 REJECTED E85-026 RH NES NES SI PANEL MODIFICATION 10/02/85 07/30/86 ;
E84-053 PC --- JWW ADDITION OF 20 AST AND 20 ET 10/02/85 11/05/85 TO MODCOMP COMPUTER LOG E85-023 FW .--- JWW P-2A & B TRIP ON HIGH SG LEVEL 10/07/85 10/25/85 E85-016 MS NES NES AUX STEAM SUPPLY 10/07/85 06/03/86 UPSTREAM THE NRV E84-051 CV --- JWW P-14 RETROFIT OF DIRECT 10/18/85 11/05/85*
DRIVE LUBE OIL PUMPS E85-025 RP NES 'NES UPGRADE ECCS VALVES 10/21/85 07/30/861 LIGHT BOXES u .. ..
' SIMULATOR MODIFICATIONS STATUS REPORT . 5 BY MR#
- EDCR4 SYSTEM HDW- SFWl DESCRIPTION OPEN INCORP ENG ENG DATE DATE
- E85-042 'TU --- ~ JWW- GENERATOR STATOR RTD 10/21/85 12/03/85-COMPUTER CONNECTION E82-014 RH, -- . ' JWW SI TANK & LPSI~ PURIFICATION 11/05/85 11/07/85 E84-068 MI NES NES ELIMINATION OF UNUSED 11/05/85 07/30/86 COMPONENTS FROM MCB XXX-080' FW --- JWW. P-2C FIRST OUT OVERRIDE 11/05/85 11/07/85 E85-019 RC RDE KLP APPENDIX J PRIMARY. SAMPLING 11/05/85 05/08/86 ;
SYSTEM MODIFICATIONS
'XXX-082 CV RDE KLP BORONOMETER SELECTOR SWITCH 11/05/85 05/08/86 XXX-083 YP ---
S/L ADDITIONAL REMOTE FUNCTIONS 11/05/85' 03/24/86 XXX-084 FW --- KLP AUX FEED PUMP STEAM 11/19/85 BINDING MALFUNCTION XXX-085 CW RDE KLP NEW FOREBAY LEVEL. ANNUNCIATORS 11/20/85 05/20/86 XXX-086 ED --- 'KLP DP/ PAC, DP/IAC MALFUNCTION 11/27/85 08/23/86 4
XXX-087 PC RDE --- MODCOMP CRT AND KEYBOARD 12/03/85 05/05/86; FOR THE SOS DESK XXX-088 PC RDE JWW 13" CRT FOR MCB SECTION "B" 12/03/85 03/17/86 12/06/85 05/20/86 XXX-085 FW --- KLP P-2A AMP CHANGE CAUSED BY MOTOR ROTOR REPLACEMENT 1 i
XXX-090 RP --- KLP RPS SET POINT CHANGES 12/10/85 03/27/86 FOR CORE 9 XXX-091 FW ---
KLP P-2C SET POINT CHANGES 12/16/85 09/02/86(
XXX-092 RM --- KLP LOCAL START OF THE 12/30/85 04/30/86l CONTAINMENT APD XXX-093 PC ---' JWW PDIL ALARM SETPOINT CHANGES 01/07/86 03/17/86l FOR CORE 9 ,
E83-009 MI RDE P&W AUXILLIARY SHUTDOWN PANEL 02/25/86 XXX-095 MS --- KLP AUX STEAM DUMMY LOAD 03/04/86 10/28/86 XXX-096 CW --- KLP ADD P-26 BREAKER 03/10/86 10/01/86 REMOTE FUNCTION XXX-097 FW RDE --- HEATER DRAIN TANK LEVEL SIGMA 03/17/86 03/25/86
! SIMULATOR MODIFICATIONS STATUS REPORT 6 BY MRf EDCRf SYSTEM HDW SFW DESCRIPTION OPEN INCORP
, ENG ENG DATE DATE XXX-098 MI --- KLP ' POWER SUPPLIES FOR MOVS 03/28/86 04/30/86
! XXX-099 YP RDE JWW RECORDER POWER OFF - 04/09/86 09/26/86 TRAINER IN FREEZE
) XXX-100 YP --- JWW SL-P-3 SWITCH CHECK 04/22/86 10/10/86
, XXX-101 MS --- KLP PROVIDE REMOTE FUNCTION FOR 04/24/86 08/23/86 MS-M-255 POWER SUPPLY l XXX-102 ED --- KLP 3T5/5R INTERLOCK ,06/05/86 REMOTE FUNCTIONS E83-505 RD --- KLP REG GROUP WITHDRAWAL PROHIBIT 06/05/86 08/05/86 XXX-104 RP ---
KLP RP-86 DEVICES MALFUNCTION 06/05/86 08/23/86 XXX-105 FW RDE --- P-2C SUCTION PRESS METER 06/05/86 XXX-106 MI --- JWW CHANGE INSTRUMENT COMPARISON 07/23/86 10/10/86 REPORT PROGRAM XXX-107 MI --- JWW DEVELOP THERMAL PERFORMANCE 07/23/86 10/10/86 PROGRAM XXX-108 MI --- JWW DEVELOP SIMULATOR 07/23/86 09/16/86 STABILITY PROGRAM E83-014 PC --- JWW SAFETY PARAMETER DISPLAY 01/10/84 03/01/86 SYSTEM INSTALLATION ,
E83-015 PC --- JWW SAFETY PARAMETER DISPLAY 06/30/86 03/01/06 SYSTEM INSTALLATION XXX-110 RP RDE ---
REPLACE NUC - DT METERS 08/28/86 XXX-111 CW --- KLP HIGH VACUUM PRIMING PUMP 08/28/86 10/01/86, '
ANNUNCIATOR XXX-2,12 FW ---
KLP LOSS OF FEED REG CABINET 09/08/86 11/04/86 XXX-113 YP --- JWW MODIFY MONITOR PARAMETERS 09/22/86 11/10/86 TABLEAUX XXX-114 MI RDE --- SIGMA METERS 09/26/86 XXX-115 YP --- JWW I/O AREA OF DATAPOOL 09/29/86 XXX-116 RX --- KLF TREF PROGRAM SETPOINT 10/06/86 11/04/86 XXX-117 YP RDE JWW OPERATING LIMIT LIGHT 10/08/86
[* -
SIMULATOR MODIFICATIONS STATUS REPORT 7 l-BY MRf
) EDCRf SYSTEM HDW SFW DESCRIPTION OPEN INCORP ENG ENG ,
DATE DATE
) XXX-118 ED RDE P&W DP/ PAC & DP/IAC 10/10/86 THROW.-OVER SWITCH
) XXX-119 ED RDE P&W VITAL BUS CROSS-CONNECT 10/10/86 I SWITCHES l
) XXX-120 FW RDE P&W HEATER D3AIN TANK 11/04/86 ELECTRONIC CONTROLIER ,
, XXX-121 TU --- P&W TC-01 L LOSS OF P-2C 11/17/86 FAILURE TO TRIP TURBINE
! XXX-122 TU --- P&W FAILURE OF ASO PRES 3URE SWITCH 11/17/86
) XXX-123 CV --- P&W LETDOWN LINE LEAK MALFUNCTION 11/19/86 i XXX-124 FW --- P&W P-2A & B AUTO START PS FAILURE 11/19/86 i XXX-125 MI --- P&W MOV MALFUNCTION 11/19/86 i XXX-126 MI --- P&W MOV PROBLEM - TORQUE 11/24/86 AND LIMIT SWITCH OPEN 18 CLOSED 106 TOTAL 124
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APPENDIXB l
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l DR
SUMMARY
12/31/86
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DO SIMULATOR DISCREPANCY REPORTS: 1 BY DR NUMBER' S# SYSTEM HDW SFW DESCRIPTION OPEN INCORP ENG ENG DATE DATE D001 SG RDE --- STEAM GENERATOR fl LEVEL -
05/14/85 05/21/85 RECORDEF NOT ADVANCING'. .
D002 SW RDE --- RAW WATER PRESSURE INDICATOR 05/14/85 05/21/85 ERRATIC AND INACCURATE. ,_
)003 CV RDE --- SECOND RANGE LIGHT FOR BORON 05/29/85 05/31/85 METER DOES NOT COME ON.
2004 RP RDE --- 86-DEVICE CSAS B CONT SPRAY 05/29/85 06/10/85 SIGNAL FAILS TO FIRE.
)005 RP --- JWW TCB-9 DOES NOT.HAVE A POWER 06/07/85 07/29/85 SUPPLY FOR THE AUDIBLE ANNUN
)006 RC RDE --- HIGH ALARM ON SIGMA PIC'101Y 06/07/85- 07/02/85 WILL NOT CLEAR.
)007 RM --- JWW PVS RMS (APD) READS TOO-HIGH. 06/10/85 08/12/85 (ESPECIALLY DURING LOW POWER)
)008 EG --- JWW MVAR METER DOES NOT DISPLAY 06/10/85 09/04/85 ACTUAL MVARS BUT EGVAM.
)009 YP --- JWW MODCOMP POWER SUPPLY SHOULD 06/10/85 08/23/85-BE POWERED FROM NNS BATTERY.
)010 RP --- JWW NEGATIVE FLOW LIGHTS ON THE 06/10/85 08/26/85 RPS SHOULD BE LIT.
s
)0'11 RC --- JWW PZR LEVEL DROPS TOO FAR ON A 06/10/85 08/19/85 TRIP - 22%,
)012 CR --- KLP CORE EXIT THERMOCOUPLE DRIFT 06/10/85 09/26/86 CAUSING ASSOCIATED ALARMS.
1013 YP RDE --- SEL COMPUTER CANNOT IPL 06/12/85 06/20/85 FROM DISK.
1014 YP --- JWW N68 LOAD AND SYSLOAD R CAUSE 06/17/85 07/09/85 A COMPUTER FAULT.
l015 RP RDE --- RPS CHANNEL C fl AND (2 06/17/85. 06/24/85 DROP-OUT LIGHTS ARE REVERSED.
)016 YP --- JWW #1 EFCV OPEN POSITION IS NOT 06/17/85 07/12/85 MAPPED IN SWITCH CHECK.
)017' .SW --- JWW C-A-14 AND C-A 15 BLINK ON 06/18/85 08/22/85 ANNUNCIATOR TEST.
l018 RP BCG --- OCCASIONAL INADVERTENT FIRING 06/19/S5 10/29/85, OF 86 CIS B3
DO SIMU.LATOR DISCREPANCY REPORT 3 2 i BY DR NUMEER M SYSTEM HDW SFW DESCRIPTION OPEN INCORP ENG ENG DATE DATE 0019' RD --- JWW MANUAL SEQUENTIAL ROD CONTROL 06/19/85 12/27/85 SHOULD NOT WORK W/O MODCOMP. l D020 YP ---- JWW PORV/ SAFETY ACCOUSTIC MONITORS 06/20/85 04/04/86 MAP SWITCH D031 RD --- JWW GROUP 5B CONTROL RODS ARE NOT 05/23/85 06/05/85 BEING SENT TO THE MODCOMP.
D022 RC RDE --- PS-A-2 WILL NOT OPEN. 06/22/85 06/25/85 POSSIBLE SWITCH PROBLEM 0023 RP RDE --- RPS CHANNELS AUCTIONEERING 06/27/85 07/02/85 INPUT TEST.
D024 ED --- JWW 27Y5 AND Y6 SHOULD NOT FIRE IF 07/01/85 07/10/85 ASSOCIATED BREAKER IS IN PTL.
D025 RC RDE ---
CONTROL SWITCH FOR THE "E" 07/08/85 07/10/85 BACK-UP PZR HEATERS IS BROKEN.
D026 EG RDE --- DG-1B CONTROL SWITCH IN THE 07/10/85 07/10/85 PTL POSITION D027 FW --- JWW FEED REG VALVE PREVIEW SIGNAL 07/10/85 08/26/85 D028 ED --- JWW CROSS-TIE 480V NON EMG BUSES 07/10/85 09/04/85 WITH DIESELS RUNNING D029 RP --- JWW SIAS ANNUNCIATOR LIGHT TEST 07/10/85 11/15/85 D030 EG --- JWW DIESEL GENERATOR SYNSCOPE 07/10/85 08/30/85 TURNS WITHOUT INCOMING VOLTAGE D031 CH RDE --- CONT SUMP LEVEL INDICATION 07/11/85 07/12/85 POWER SUPPLY METERS D032 ED --- JWW 86 BU SHOULD NOT FIRE IMMEDI- 07/11/85 08/30/85 ATELY UPON A TURBINE TRIP.
D033 SG RDE ---
- 2 STEAM GENERATOR LEVEL 07/19/85 08/09/85i RECORDER IS ERRATIC.
D034 FW --- JWW TOO MUCH LEAKAGE PAST MFRV. 07/22/85 08/19/85; SHOULD ONLY BE 5%
D035 CV --- JWW DRAIN COOLER INLET PRESSURE 07/25/85 10/29/85 READS HIGHER THAN RCS PRESSURE D036 CV --- JWW SEAL INJECTION TEMPERATURE '
07/25/85 09/16/85 RESPONSE DROPS OFF TOO FAST.
-- -_--__.____._.____________s
SIMULATOR DISCREPANCY REPORTS' 3
)0 BY DR NUMBER 29 SYSTEM' HDW SFW DESCRIPTION OPEN INCORP ENG ENG_ DATE DATE 2037 CW --- -KLP COULD NOT REPRODUCE UNUSUAL' 07/25 T5 10/01/86 OCCURENCE REPORT #012-85.
)038' TU --- JWW TURBINE GOVERNOR VALVES AT 80% 07/25/85 11/15/85 POWER HAVE TOO MUCH BITE.
)039 CH BCG JWW INCORRECT SCALE ON CONTAINMENT 07/26/85 10/30/85 '
PRESSURE SIGMA
)040 YP ---
JWW SW 07 DESCRIPTION ON TABLEAU 07/26/85 08/12/85 PAGE SW-1 IS INCORRECT.
)041 RC --- JWW ENGINEERING UNITS REQUIRING 07/30/85 08/13/85 CONVERSION SHOULD BE ON SEL
)042 RC --- JWW SI LEVELS ARE IN PERCENT ON 07/30/85 08/12/85 MODCOMP. CONVERT SEL VARIABLES
)043 CH --- JWW CONTAINMENT FDN SUMP 07/31/85 11/05/85 ANNUNCIATOR W-D-3 1044 RD BCG JWW ROD POSITION DVM POWER SUPPLY 07/.31/85 11/15/85
)D45 RH --- JWW LSI M 11, 21, 31 POWER SUPPLY 07/31/85 09/04/85
>046 RM .--- JWW CONTAINMENT APD PUMP POWER 07/31/85 09/18/85 SUPPLY RM-6102
)047 YP --- JWW SYSLOAD R WILL NOT WORK. 07/31/85 08/12/85
)048 SW --- JWW SMOKE DETECTOR PANEL 08/05/85 08/23/85 POWER SUPPLY
!@49 RM --- JWW CONTAINMENT LOW & MANIPULATOR 08/07/85 11/05/85 CRANE RMS (RI 6104 & 6105)
)050 YP --- JWW PDIL ALARMS 08/07/85 09/06/85 l051 YP --- JWW TDFP CONTROLLER SWITCH CHECK 08/07/85 10/29/85,
'@52 SG --- KLP SG LOW PRESSURE SIGNAL LOGIC 08/19/85 05/08/86
'@53 SW --- JWW AUTO START TIME DELAY FOR P-4 08/19/85 09/04/85 DURING LOSS OF OFF-SITE POWER l@54 CV ---
JWW DR-S-11 IS NOT MODELED 08/20/85 11/05/85 l055 in? BCG --- OCCASIONAL POWER INTERRUPT 09/20/85 11/05/85 OF SIMULATION
'056 YP --- JWW BACKTRACK SWITCH CHECK 08/20/85 04/07/86
SIMULATOR DISCREPANCY REPORTS- 4 20 : -
BY.DR NUMBER
' SYSTEM 'HDW SFW DESCRIPTION OPEN INCORP 16 ENG ENG DATE DATE 2057 CS --- JW CS-A-55 AND CS-A-56 08/20/85 08/22/85 WRONG POWER SUPPLY MODELED
)C58' CV BCG --- VCT PRESS SIGMA CALIBRATION 08/21/85 09/04/85
)059 CS --- JW CONT SUMPS RISE TOO FAST WHEN 08/21/85 08/22/85 !
CS-A-55 AND 56 OPEN 1060 IA --- 'JWW CONTAINMENT AIR PRESSURE 08/23/85 08/30/85 l' TRANSMITTER CHECK VALVES
)D61 CH --- JWW ' CONTROL ROOM VENTILATION -
08/26/85: 11/05/85 l' DAMPER D-7A AND D-7B
)062 YP --- JWW EXEC 1 EXCEEDED MEMORY '08/23/85 08/30/85 BOUNDARY
)063' EG ' --- JWW GENERATOR VOLTAGE REGULATOR 08/29/85 09/16/85 SENSITIVITY l064 CV --- JWW VCT PRESSURE MPX 09/04/85 09/16/85
>065 RC --- JWW RCP BREAKER STATUS MPX POINTS 09/13/85 01/06/86 1066 PC --- JWW SOE MPX POINTS NOT MODELED 09/13/85 09/16/85 1067 CW --- JW CW SOE POINT IS NOT DERIVED 09/16/85 01/06/86
>068 ED --- JWW ED SOE POINTS ARE NOT DERIVED 09/16/85 03/16/86 iO69 EG --- JWW EG SOE POINT IS NOT DERIVED 09/16/85 01/06/86-1070 RC --- JWW RC SOE POINTS ARE NOT DERIVED 09/16/85 01/06/86
'071' RH --- JWW RH SOE POINTS ARE NOT DERIVED 09/16/85 '01/06/86 1072 SW --- JWW SW SOE POINTS ARE NOT DERIVED 09/16/85 02/10/86.j
'@73 CV' BCG --- CONTROL SWITCHES FOR 09/25/85 10/29/85 CH-M-1 & CH-M-87 i
1074~ YP --- JWW SOE'S DEFINED 09/26/85 01/06/86 BUT NOT IN N68PPCI \
1075 ED --- JWW ED SOE POINTS 09/27/85 04/30/86
)@76 EG --- JWW EG SOE POINTS 09/27/85 05/06/86 l077 FW --- JWW FW SOE POINTS 09/27/85 04/17/86' t078 MS --- JWW MS SOE POINT 09/27/85 12/23/85
- a. _ _ _ ._ _ _ _ _ _ _ _ _ . - - . _ _ - _ _
SIMULATOR DISCREPANCY REPORTS 5 20 BY DR NUMBER 2# SYSTEM HDW SFW DESCRIPTION OPEN INCORP ENG ENG DATE . DATE D079 ED --- JWW ANNUNCIATORS UPON A LOSS 10/24/85 11/05/85 OF MCC-12 D080 CV --- JWW RCP SEAL RESPONSE ON OUTLET 10/28/85 11/05/85 VALVE CLOSURE I
)081 CC --- KLP PCC TEMPERATURE RESPONSE 10/29/85 03/27/86 UPON RCP TRIP 9082 YP --- JWW 86-SIAS-B2 SWITCH CHECK 10/29/85 11/15/85
)0$3 YP --- JWW NO ROOM IN EXEC #2 10/28/85 10/30/85 0064 SW ---
KLP SWO2A BACKWARDS 10/31/85 04/06/86 '
)085 RM ---
KLP MAIN STEAM RAD MONITORS 10/31/85 04/30/86 LOGIC RESPONSE
)086 RP --- JWW LOSS OF SIAS CONTROL 11/01/85 11/05/85 POWER ANNUNCIATOR
)087 MS --- JWW MS-T-163 OVERRIDE RF 11/04/85 11/05/85
)088 RC --- KLP RCP VIBE RECORDER DEVIATION 11/05/85 03/27/86 1089 PC --- JWW COMPUTER ' SOE' S BACKWARDS 11/05/85 02/10/86 l090 PC --- JWW COMPUTER POSTMORTEM 11/05/85
)091 PC --- JWW COMPUTER XE PLOT 11/05/85 1092 PC --- JWW COMPUTER MWTH CALCULATION 11/05/85 12/27/85 1093 MS --- JWW MWE POWER LOWER 11/12/85 12/27/85 1094 FW --- JWW AUX FEED REG VALVE RESPONSE 11/15/85 11/18/85 UPON A LOSS OF DP/ PAC
!095 RC --- JWW RV HEAD TEMPERATURE 11/15/85 11/15/85
'@96 CC --- KLP TURBINE GENERATOR COLD GAS 11/19/85 03/27/06 TEMPERATURE TOO HIGH
'@97 EG --- KLP SIMULTANEOUS INSERTION OF 11/19/85 05/20/86 MALFUNCTIONS ED08 & EG05
@98 PC --- JWW SWITCH CHECK FOR HV-9 11/19/85 04/04/86
@99 CV ---
KLP CV-17 MALFUNCTION 11/21/85 04/06/86 LOSS OF VAPOR SEAL' 100 FW ---
KLP P-2C TRIP UPON MF CD05D 11/21/85 03/27/86
SIMULATOR DISCREPANCY REPORTS 6,
)0 I BY DR NUMBE5 lf - SYSTEM HDW SFW DESCRIPTION OPEN- INCCRP ENG ENG DATE DATE
)101 RM --- KLP CR01 FAILED FUEL MALFUNCTION 11/21/85
)102 RP: --- KLP MANUAL PUSH BUTTON 11/21/85 03/27/86 FIRST OUT ANNUNCIATOR
)103 PC --- KLP MPX POINTS CALCULATED 11/21/85 04/17/86 '
INCORRECTLY
>1,0'4 ED --- KLP REMOTE FUNCTION ED110 11/27/85 12/05/86 '
3T5/5R BYPASS INTERLOCK -
i
)105 FW --- KLP P-2C FLOW INDUCED VIBRATIONS 11/27/85 05/20/86
)106 MS' --- KLP MS-A-162 WON'T STAY CLOSED 11/27/85 04/06[86,
)107 MS RDE --- TURBINE GLAND SEAL 11/27/85 12/23/85 PRESSURE METER 1108 CV ---
KLP VCT PRESSURE RESPONSE 12/02/85 04/06/86' TOO SEVERE ;
'109 PC --- JWW MONITOR PARAMETER FOR MWTH 12/02/05 12/09/85
)110 RM --- KLP MANIPULATOR CRANE & 12/02/85 05/06/86 CONTAINMENT LOW RMS RESPONSE
'111 CW RDE --- VACUUM PRIMING ALARM SET POINT 12/02/85 12/04/85l l112 RC RDE --- PZR PRESSURE SIGMA "Y" STICKS 12/02/85 12/20/85'
!113 SG RDE --- PIC 1013A SIGMA OSCILLATES 12/02/85 12/19/85
)114 RX RDE --- FRV BYPASS PRESET CONTROLLERS 12/03/85 12/18/85
)115 ED --- FLP DG BREAKER RESPONSE UPON 12/03/85 05/20/86' ED04 A & B i
116 PC RDE ihWW 'MODCOMP TREND PRINTER 12/03/85 05/14/86 117 PC --- JWW MODCOMP ALARM SCREEN RESET 12/03/85 01/20/86;
)118 PC --- JWW XENON MPX INOPERABLE 12/03/85 12/09/85;
)119 FW --- JWW HEATER DRAIN TANK 12/03/85 01/06/86, LEVEL CONTROL
>120 CW --- KLP 4KV AUTO TRIP ANNUNCIATOR 12/03/85 05/08/86 CAUSED BY P-26 1121 PC --- JWW INCA DATA 12/03/85 12/13/85^
122 RM --- KLP CONTAINMENT APD LOW FLOW 12/03/85 04/30/86
'7
)0l . SIMULATOR DISCREPANCY REPORTS .
BY DR NUMBER SYSTEM SFW- DESCRIPTION OPEN INCORP 1(f HDW. .
ENG ENG- DATE DATE
)123 ' MI - RDE --- DISPATCHERS PHONE WON'T RING 12/03/85 01/20/86 ,
)124 MI RDE -- OCCASIONAL PCMER INTERRUPT 12/03/85 08/05/86
)125 SW' ---
JWW TIDE LEVEL RECORDER OFF 12/04/85 01/06/86 BY A FACTOR OF 10
)126 RM ----
KLP RMS RECORDERS ON UNIT 8 12/06/85 04/30/86
)127 NI RDE --- OCCASIONAL NI SPIKING 12/06/85 12/23/85' ON ALL CHANNELS
)128 'FW --- JWW P-2C RECIRC-AUTO BLOCK 12/09/85- 01/06/86 SET POINT CHANGE 1129 CV ---
KLP CV03 INbORRECT RESPONSE 12/10/85 04/06/86
)130 YP --- JWW- CANNOT CLEAR MALFUNCTIONS 12/12/85 01/30/86 ON LINE 1
)131' FW ---
KLP P-2C FIRST OUT POWER" SUPPLY 12/09/85 03/27/86 REMOTE FUNCTION
)132 YP --- JWW' CH-M-1 POWER SUPPLY 12/16/85 12/24/85 REMOTE FUNCTION I r
)133 NI RDE --- NI' RECORDER BROKEN FACEGLASS 12/16/85 01/17/86
)134 PC ---
JWW MAIN CONTROL BOARD PDIL' ALARMS 12/17/85 01/06/86 11351 YP --- JWW TPR INOPERABLE 12/17/85 1136 YP RDE --- REMOTE DEVICE INOPERABLE 12/17/85 12/19/85
'137 ED ---
KLP ELECTRIC BOARD AMP READINGS 12/18/85 08/07/86 DIFFERENT FROM REAL PLANT -
)138 ED --- KLP UNIT POWER IS ZERO IF 12/26/85 12/12/86 KG-1 & KG-1/375 IS OPEN
)139 RC --- KLP PZR BACKUP HEATER AUTO SHUTOFF 12/26/85 04/30/86
)140 RD --- KLP RDOS - EJECT ROD 12/26/85 03/20/86 POSITION INDICATION l141- RM ---
KLP RMS RESPONSE UPON A 12/26/85 05/06/86 SMALL PREAK LOCA
)142 SW ---
KLP SMOKF DETECTOR UPON'RCO2 12/26/85 08/23/86
)143 RC RDE --- LOOP 1 TC RECORDER NOT DRIVING 12/26/85 01/03/86
20 SIMULATOR DISCREPANCY REPORTS 8 BY-DR NUMBER lf SYSTEM 'HDW SFW DESCRIPTION- OPEN INCORP ENG ENG DATE DATE
)144' SG RDE ---- SG LEVEL SIGMA OSCILLATES 12/26/85 01/17/86 2001 'CV ---
KLP' CHARGING HEADER OSCILLATIONS 01/03/86_ 04/17/86
)002 YP --- JWW CAN'T I/O OVERRIDE 01/07/86 05/09/86-j '
EFCVS OR NRVS
)003' YP --- JWW CAN'T I/O OVERRIDE 01/07/86 06/11/86 RESERVE BREAKER 3R
)004 PC --- JWW NQNE OF THE DEMAND LOG , ,
01/08/86 01/28/86 PROGRAMS WORK -
1005' FW --- KLP DWST HIGH LEVEL ALARM SETPOINT 01/20/86 04/17/86
)006 PC --- JWW ALARM SCREEN PAGE FORWARD 01/08/86 03/17/86 i BUTTON NOT WORKING
)007 PC --- JWW CHANGE REPORT HEADERS 01/09/86 TO INCLUDE " SIMULATOR"
)008 FW --- KLP CST HIGH LEVEL ALARM SETPOINT 01/20/86 04/17/86
)009. MS- --- KLP STEAM BYPASS 01/15/86 05/20/86 I QUICK OPEN OVERRIDE 1010 MI --- JWW LO'S NEED CLEARING-IN IC-1 01/20/86 04/29/86 l011 RD RDE KLP' ROD CONTROL PANEL 01/20/86 03/20/86 LAMP TEST INOPERABLE
)012 RM --- KLP SG BLOWDOWN RMS EFFECT 01/20/86 04/30/86f RELATIVE TO LETDOWN FLOW 1013 RM --- KLP PRtMARY VENT GAS & APD RMS 01/20/86 04/30/86 1014 RP --- KLP LEVEL 1 BI-STABLE SETPOINT IS 01/20/06 04/30/86--
EXACTLY 15% - NOT REALISTIC 1015 RP --- KLP EXCESSIVE SUR NOISE 01/20/86 WHILE PERFORMING
)016 RX --- KLP MFRV AUTO SIGNAL CALLS FOR A 01/20/86 03/27/86 l FULL OPEN SIGNAL l017 YP --- JWW FW110 DESCRIPTION ON YP PAGE 01/20/86 01/28/86 IS INCORRECT 1018 MI RDE --- . INTERLOCK KEYS MISSING 01/20/86 02/05/86
~
)019 RC RDE --- LOOP 3 CHANNEL A & C 01/20/86 01/23/86 D/P METERS STICX
)0- SIMULATOR' DISCREPANCY REPORTS. 9 BY DR NUMBER lf . SYSTEM' 'HDW- SFW- DESCRIPTION OPEN- 'INCORP
'ENG. ENG DATE DATE -]
)0 2 0' - 'RP RDE --- CHANNEL D LOW SG LEVEL TRIP. 01/20/86 01/20/86 BIN LAMP TEST- ,
1021 SG RDE ---- SG-LEVEL SIGMA OSCILLATES 01/20/86 04/12/86
)022 FC ---
JWW MWTH CALCULATION. 01/20/86 01/28/86.
NO LONGER WORKS
~ ~
)023- RC - - - -
.KLP- RCP.HEATUP RATE TOO FAST 01/23/86 1024 .CV- RDE --- CH-F-38 & SL-P-3 01/22/86 03/28/86..
REOPENING ON BLOCK l025 PC --- JWW MPX 226 & 227 SHOULD NOT 01/27/B6 03/17/86
. BE SPARES
)026 YP --- JWW PS-A-4 SWITCH CHECK MAPPED 01/29/86 04/04/86 TO WRONG LO
)027 CH RDE --- LOWER CONT PARAMETERS RECORDER 01/29/86 02/03/86l 1028 -CS --- JWW SPRAY HEADER TEMPS - BACKWARDS 01/29/86 03/17/86R 1029 EG RDE --- GEN SYNC MODE SEL SWITCH 01/30/86. 02/04/86 i
)030 'YP --- JWW I/O DOESN'T WORK ON MCB-A-REAR 01/30/86
)031 YP --- JWW ERRONEOUS LAMPS LIT AT THE 01/30/86 04/29/86 INSTRUCTORS STATION l
iO32 RC RDE --- PZR WIDE RANGE PRESS RECORDER 02/03/86 02/03/86
t@33 RP RDE --- PIA - 102 ALL OSCILLATES 02/03/86 02/04/86-
@34 TU --- KLP PROBLEMS WITH GV. MANUAL 02/03/86 WHILE IN SPEED CONTROL
@35 YP --- JWW IM.LOADR ABORTED - 02/03/86 02/03/86 TASK SIZE TOO SMALL
'@36 CH --- KLP H2 MONITOR INOPERABLE 02/04/86 03/27/86
<037 YP ---
S/L EXECUTIVE PROGRAM OVERLOADED 02/04/86 03/26/86
@38 MI RDE --- POWER SUPPLY BREAKER 02/05/86 03/03/86 OCCASIONALLY TRIPS -
)039 PC RDE --- BAD ELECTRICAL RECEPTICAL 02/05/86 04/04/86 FOR MODCOMP
)040 RP RDE --- CHANNEL "D" DEVIATION METER 02/05/86 03/03/86 O
SIMULATOR DZ9CREPANCY REPORTS 10 BY DR NUMBER SYSTEM HDW SFW DESCRIPTION OPEN INCORP 0 DATE ENG ENG DATE
@41 RC --- KLP HEAD TEFJERATURE DROPS 02/05/86 09/10/86 DURING LOCA
@42 TU RDE --- TURBINE CONTROL 02/10/86 02/18/86 COMMON VOLT SIGNAL
@43 RD --- KLP - GROUP SB POWER SUPPLY 02/13/86 05/06/86
@44 FW RDE --- ANNUNCIATOR SECTION F 02/13/86 02/14/86
-@45 CV --- KLP BORONOMETER CHANGING 02/13/86 05/06/86 DURING SIAS
'@46 RX --- JWW RX FAILED THERMOCOUPLE 02/13/86 03/17/86 047 PC --- JWW RX TRIP PPC POINT OUT OF SYNCH 02/18/86 04/04/86 l048 RM --- KLP LD RMS FAIL HIGH UPON AN -
02/27/86 04/23/86 INADVERTENT SIAS
)049 EG RDE ---
KG1/375 SWITCH 03/04/86 03/06/86
)050 MI RDE --- INDICATOR GLASS 03/06/86 04/11/86
)051 RC RDE ---
QUENCH TANK LEVEL INDICATOR 03/06/86 04/18/86
)052 TU RDE --- TURBINE GLAND SEAL INDICATOR 03/06/86 04/18/86
)053 CV --- KLP BORON ADDITION VIA VCT 03/17/86
)054 CW ---
KLP FOREBAY LEVEL 03/17/86 05/20/86
)055 TU ---
KLP TURBINE VALVE TESTING 03/17/86 04/30/86 D056 YP --- JWW I/O OVERRIDE DELAY TIME 03/17/86 04/07/86 D057 PC --- JHW MODEL TRANSFORMER ALARMS 03/17/86 D058 RC --- KLP PR-A-38 CONTROL 03/19/86 03/27/86 D059 RP --- KLP CONTAINMENT PRESSURE SWITCHES 03/19/86 05/08/86 D060 YP RDE --- INST STATION RECORDER POWER 03/19/86 03/20/86 D061 EG RDE --- GEN SYNC MODE SWITCH 03/19/86 03/20/86 3062 SG RDE --- NUMEROUS METERS OSCILLATING 03/26/86 04/30/86 3063 'YP ---
JWW ACTIVATION OF LOAD 03/27/86 04/03/86 3064 MI ---
S/L PROPRIETARY INFORMATION 03/28/86 05/30/86 DISCLAIMER
- - - - - - - ~ - - . - - _ _ _ - - _ _ - - - _ _ _ _ _ - - - - _ _ _ _ _ _ _
SIMULATOR DISCREPANCY-REPORTS 11 h~ BY DR NUMBER 19 SYSTEM HDW SFW DESCRIPTION OPEN INCORP ENG ENG DATE DATE
)065' RM RDE --, MAIN STEAM LINE il MONITOR 03/31/86 03/31/86
)066 EG RDE ---
GENERATOR SYNC MODE SWITCH 03/31/86 '04/01/86
)067 RH --- KLP RH-M-1 & 2 AUTO CLOSURE 03/31/86 04/30/86 ANNUNCIATOR
)068 RX --- KLP TAVE/ TREF ANNUNCIATOR 03/31/86 04/17/86
>@69 RX --- KLP TAVE DEVIATION ALARM .04/01/86 04/17/86
)070 RC --- KLP SG TUBE RUPTURE FLOW 04/01/86 04/17/86 1071 EG --- KLP GENERATOR GAS TEMPS ON EGOS 04/03/86 05/20/86',
)072 CV --- KLP RAMP PROBLEMS WITH CV03 MF 04/03/86 1073 RC --- KLP SG D/P METERS UPON LOSS OF PWR 04/03/86 05/08/86
)074 RH --- KLP PUMP DOWN OF SUMP WITH LPSI 04/03/86 G CS
'@75 RX --- KLP PREVIEW OF SPRAY CONTROL 04/03/86 05/20/86 DURING RXO2
'@76 YP --- JWW SWITCH CHECK PRINT DESCRIPTION 04/04/86 08/28/86
>@77 RC RDE --- PZR CHANNEL X LEVEL INDICATOR 04/07/86 04/17/86 >
!078 FW --- KLP HOTWELL LEVEL MPX 04/11/86 04/30/86
)079 CV --- KLP CHARGING PUMP AMP VARIATION 04/14/86 04/30/86 WITH VOLTAGE
'@80 PC --- JWW MODCOMP ALARM SCREEN UPDATE 04/17/86 081 ED --- KLP ROD IN/OUT LO 04/28/86 04/30/86 082 MS --- KLP P-25B NO STEAM DEMAND 04/28/86 09/02/86, l@83 ED RDE --- ACB 3T5 SWITCH HANDLE BROKEN 04/23/86 05/01/86' l@B4 YP --- JWW NEWTIME 05/09/86 06/17/86 085 FW --- KLP P-2C LOCAL START 05/09/86 05/20/86
)086 YP --- JWW SPRAY CONTROLLER-SWITCH CHECK 05/12/86 06/05/86
)087 PC .
--- JWW SMSG APPEARS ON MODCOMP OPCOM 05/12/86
)088 FW --- KLP P-25B PUMP CURVE 05/04/86 08/23/86
@ SIMULATOR DISCREPANCY REPORTS 12 BY DR NUMBER
!f SYSTEM HDW SFW DESCRIPTION OPEN INCORP ENG ENG DATE- DATE
!@89 MI --- KLP VARIOUS VALVE STROKE TIMES 06/04/86 10/01/86 )
@90 YP --- JWW TABLEAU OF MV REMOTE FUNCTIONS 06/04/86 06/11/86
'@91 MI RDE --- SPURIOUS TRIPPING OF BREAKERS 06/04/86
'@92 EG RDE --- DG-1A AMP METER 06/05/86 06/16/86 f@93 CS ---
KLP SIA-M-54 THROTTLE CAPABILITY 06/13/86 08/07/86
!@94 FW RDE --- P-2C SUCTION PRESSURE HI ALARM 06/19/86 06/19/86
@95 PC --- JWW MODCOMP PRINTER BUFFER 06/23/86
'@96 RP RDE --- CIS - 86 DEVICE WILL NOT FIRE 06/23/86 07/31/86 097 MI RDE --- INDICATOR LIGHTS 06/25/86 07/31/86
@98 RC --- KLP RCS - HEAT BALANCE 06/27/86 08/07/86
'@99 SG --- KLF S/G PRESSURES ARE TOO HIGH 06/27/86 08/07/86 AT FULL POWER
!100 MS --- KLP PRESSURE DROP ACROSS NRV 06/27/86 08/07/86
)101 MI --- JWW FIRST OUT ANNUNCIATOR 06/27/86 12/05/86
>102 FW --- KLP CONDENSER PERFORMANCE 06/27/86 10/01/86 1103 FW --- KLP FW FLOW CALORIMETER 06/27/86 08/07/86 1104 RD --- KLP MG OUTPUT BREAKERS 06/27/86 08/23/86 l
>105 RP --- KLP RPS T-COLD INDICATION 06/27/86 08/07/86
>10 6 TU --- KLP TURBINE MANUAL CONTROL 06/27/86 08/23/86!
)107 TU --- KLP MWE ADJUSTMENT 06/27/86 08/07/86
)108 MI RDE --- DISPATCHER'S PHONE 07/02/86 08/04/86
)109 MI RDE ---
ERRATIC I/O ON UNIT 1 07/14/86 07/15/86
>110 RP RDE --- ESF PANEL A LIGHTBOX 08/01/86 08/05/86 1111 YP --- JWW "B" PORV CONTROLLER 08/19/86 10/10/86l SWITCH CHECK l 1112 SW --- KLP HEAT TRACING ALARMS 08/19/86 06/26/86
)113 RP RDE ---
CHANNEL D LIGHTS 08/19/86 08/25/86
)0 SIMULATOR DISCREPANCY REPORTS 13-BY DR NUMBER 16 SYSTEM EDW SFW DESCRIPTION OPEN INCORP ENG ENG- DATE DATE
)114' PC --- -JWW CALORIMETRIC 08/20/86 1 1
I
)115 MS' --- KLP MS BYPASS CONTROLLER NOISE 08/20/86 08/26/86 l f
1116- RC RDE --- "A" PORV INDICATOR 08/21/86 09/03/86 I
)117' ED RDE --- 4U BREAKER 08/21/86 12/08/86.
GIS .TU --- KLP GV FAST NOT WORKING 08/22/86 09/05/86
)119 YP ---
JWW 115 KV VOLTAGE VARIATION IT 08/22/86 08/27/86
)120 YP --- JWW ERRONEOUS LIGHTS LIT ON 08/22/86 09/11/86 INSTRUCTOR'S STATION
)121 SW --- KLP CONTAINMENT SMOKE DETECTOR 08/25/86 09/02/86
)122 CV RDE --- BORIC ACID BATCH INTEGRATOR 08/25/86 08/27/86 1123 'RP' RDE ---
il FEED FLOW / STEAM FLOW 08/25/86 08/25/86 RECORDER 1124 YP --- JWW SIMULATOR REAL TIME 08/26/86 08/26/86 t125 YP ---
JWW I/O OVERRIDE DELAY TIME 08/26/86 1126 YP ~~- JWW ANNUNCIATOR MALFUNCTION ENTRY 08/26/86 08/27/86 ON INSTRUCTOR STATION d27 CR --- KLP EOL GROUP 5 ROD 100RTH 08/26/86
>12 8 RP RDE ---
- 1 STEAM GENERATOR 08/27/86 08/28/86, LEVEL RECORDER
'12@ RP RDE KLP POWER SUPPLY FOR 08/27/86 09/10/86 PI 1013A, PIl023A, PI 1033A
'130 MS --- KLP POWER SUPPLY FOR PIA 1001 08/27/86 09/05/86 131 FW RDE --- CONDUCTIVITY RECORDER 08/28/86 08/28/86
@32 YP --- JWW MALFUNCTION RAMP TIME 08/28/86 10/10/86 1133 MS RDE --- GLAND SEAL PRESSURE 08/28/86 09/06/86
'134 'FW --- KLP CONDENSATE PUMP AUTO START 08/29/86 09/16/86 UPON ELECTRICAL FAULT ll35 RP --- KLP RCP LOW FLOW TRIP 09/02/86 09/16/86 1136 RH RDE KLP LSI-F-59 FLOW INDICATION 09/02/86 10/16/86.
DO SIMULATOR DISCREPANCY REPORTS 14 BY DR NUMBER H- SYSTEM HDW SFW DESCRIPTION OPEN INCORP ENG ENG DATE DATE D137 RC RDE --- SG SMM FAULTY 09/02/86 WHEN LESS THAN 10 F D138 FW --- KLP PPC POINTS 09/02/86 10/28/86 D139 YP ---
JWW MONITORED PARAMETERS 09/02/86 11/10/86' SUBCOOLING D140 RP RDE ---
SIAS PZR PRESS INDICATOR 09/03/86 09/04/86 i CHANNEL "B" D141 RC RDE ---
PZR LEVEL RECORDER 09/04/86 10/01/86
)142 RP RDE KLP RWST LEVEL BI-STABLES & METERS 09/04/86 10/11/86 WRONG POWER SUPPLY .
)143 RC ---
KLP PZR PRESSURE RESPONSE 09/06/86 09/10/86
)144 FW RDE KLP FEED REG CABINET POWER SUPPLY 09/08/86 11/04/86
)145 TU ---
KLP TURBINE VALVE TESTING 09/08/86 09/10/86
)146 RD RDE --- REG GROUP 2 DVM 09/08/86 10/08/86 1147 RX RDE ---
PZR PRESS CONTROLLERS 09/08/86 11/24/86 l CALIBRATION
)148 RX RDE ---
PZR LEVEL CONTROLLERS 09/08/86 09/08/86 CALIBRATION 11'49 SW RDE ---
RW PUMP PRESSURE METER 09/08/86 09/18/86 il
' TU --- KLP IMP-IN LIGHT BLINKS 09/10/86 09/26/86
>151 TU ---
KLP TURBINE MANUAL TOO SLOW 09/10/86 09/10/86 1152 CS ---
KLP PPC POINT - RWST LEVEL 09/10/86 09/16/86
'153 TU ---
KLP TURBINE VALVE TEST LIGHTS 09/15/86 09/26/86
'154 TU --- KLP T-2-6 TURBINE STOP VALVE 09/15/86 09/25/86 ANNUNCIATOR 1155 MS ---
KLP MS-A-162 CLOSED LIMIT LIGHT 09/16/86 09/26/86
'156 TU RDE ---
TURBINE CONTROL DVM SWITCH 09/16/86 09/16/86
'157 MI --- JWW INCLUDE PENCHMARK TESTS IN 09/16/86 10/10/86 ANSI 3.5 TEST PROGRAM 858 CV --- P&W REMOVE MALFUNCTION CV10 09/17/86 09/26/86
)$ SIMULATOR-DI'SCREPANCY. REPORTS
- 15 BY DR NUMBER If . SYSTEM HDW SFW DESCRIPTION OPEN INCORP j ENG ENG DATE DATE
)159' ' IG ---- KLP LOW FLOW TRIP 09/17/86 09/26/86 1 1
)160 1 RX ---
KLP POST TRIP - SG LEVEL RESPONSE 09/17/86
)161 ' FW 'RDE ---
TDFP TEMPERATURE. RECORDER 09/18/86 - 11/03/86 )
)162 PC --- JWW SPECIAL MESSAGE FILE CONTAINS 09/23/86 I UNPRINTABLE CHARACTERS I
)
)163 EG RDE --- 86 P. DEVICE WON'T FIRE 09/24/86 09/25/86l 1164. RCH RDE --- "B"' CONTAINMENT 09/24/86 09/24/86 '
PARAMETER RECORDER. j
)165 CV RDE --- LETDOWN TEMPERATURE INDICATOR 09/24/86
)166' RC RDE --- UNIT 1 CORE SMM 09/26/86 10/01/86
)167 CW --- P&W AIR REMOVAL RFS - WRONG TYPE 09/29/86 . 10/28/86.
)168 CV RDE ---
CHARGING PUMP "B" SWITCH 10/02/86 10/08/86~
1169 ' CC --- KLP SCC-PUMP AMPS 10/07/86 11/18/86 ;
1170 CV --- KLP CHARGING PUMP AMPS 10/07/86 12/12/86
!171' CV~ ---
KLP CHARGING T'MPERATURE E - LOW 10/07/86 12/16/86 <
l17.2 CW --- KLP , CIRC WATER PUMP AMPS 10/07/86 11/25/86
'173 ED --- KLP AMP READINGS TOO HIGH 10/07/86. 12/12/86
'174 FW --- KLP P-2C SUCTION FLOW INDICATION 10/07/86 12/12/86
'175 RP --- KLP TOTAL LOOP FLOW FI-102 - HIGH 10/07/86 11/18/86 176 YP --- JWW COMPUTER REAL TIME 10/07/86 177 RC --- KLP PR-M-16 AND PR-M-17 10/08/86 11/04/86 BISTABLE POWER SUPPLY 4
S78 RC RDE --- NARROW RANGE TC POWER SUPPLY 10/10/86 11/06/86
$79- CH RDE KLP CONTAINMENT SUMP LEVEL 10/10/86 11/18/86 POWER SUPPLY
@80 CH --- KLP PI-2012 POWER SUPPLY 10/10/86 11/18/86;
'181 RP --- KLP TRIP BREAKER 10/10/86 11/18/86 UPON LOSS OF-VITAL BUS
!182 RX --- KLP POWER SUPPLY FOR HIC-101-1 10/10/86 11/04/86 A--- _..._ _ _ -_ _ - _ _ . _ _ . _ _ _ _ _ _
SIMULATOR DISCREPANCY REPORTS 16 BY DR NUMBER HDU SFW DESCRIPTION OPEN INCORP 0 SYSTEM ENG ENG DATE DATE 183 RX -L KLP TI-111X LOSS OF POWER 10/10/86 11/04/86 184 RX --- KLP BU-HTR CONTROL UPON LOSS 10/10/86 11/14/86 OF VITAL BUS 1 185 CC --- KLP SCCW ISOLATION TIME DELAY 10/24/86 11/18/86 186 RP --- KLP 86 TRIP DEVICE PATH 10/24/86 11/25/86 ANNUNCIATOR 387 ED --- KLP UNIT & RESERVE BREAKER 10/29/86 11/18/86 AUTO TRIP ANNUNCIATOR 188 PC --- JWW 1544 OR 1545 -
10/29/86 ACE TABLE ACCESS FAILURE
'189 MI RDE --- BLANK MISC HOLES 10/29/86
>19 0 PC --- JWW UPDATE RPSS 11/03/86 12/08/86
>191 PC --- JWW UPDATE NORMAL OPERATING 11/03/86 LOG DISPLAY 1192 RC --- KLP ACOUSTIC MONITOR POWER SUPPLY 11/03/86 11/18/86
)193 YP --- JWW DEVELOPMENT LOAD NOT WORKING 11/07/86 11/14/86
)194 PC --- JWW LOAD SCHEDULE - CORE 8 11/10/86
)195 PC --- JWW CORE SURN-UP POINT ID'S 11/10/86 D196 YP RDE --- DISPATCHER PHONE WON'T RING 11/10/86 11/21/86 D197 MI RDE --- PROTECTIVE COVER PLATES 11/10/86 12/11/86 D198 MI WWW --- MAIN CONTROL BOARD MIMIC 11/10/86 D199 CV --- KLP PAB ALARM UPON SHUTDOWN OF P14 11/10/86 12/12/86 D200 CV --- JWW COMPUTER POINT FOR BORONMETER 11/10/86 3301 EG --- KLP COMPUTER POINT ID'S FOR 11/10/86 12/22/86 345 KV DISTRIBUTION 3202 FW --- KLP COMPUTER POINTS FOR 11/10/86 12/12/86 CONDENSER AIR TEMPERATURE 9203 MS --- KLP COMPUTER POINT FOR MS 11/10/86 11/25/86 HEADER PRESSURE 9304 NI --- KLP COMPUTER POINT FOR DETECTORS 11/10/86 , 11/25/86 9& 10 NI POWER 9
)d SIMULATOR DISCREPANCY REPORTS 17 BY DR NUMBER 2f' SYSTEM HDW SFW DESCRIPTION OPEN INCORP ENG' ENG DATE DATE
)205 BC --- KLP COMPUTER POINTS FOR RCP 11/10/86 12/12/86 LUBE OIL RESERVOIR
)206 RC ---
KLP COMPUTER POINT FOR REACTOR 11/10/86 11/25/86 VESSEL HEAD TEMPERATURE
)207 RM --- KLP RMS COMPUTER POINTS 11/10/86 12/12/86
)208 RM --- KLP WASTE GAS RMS 11/10/86 11/25/86 1 i
?209 RM ---
KLP FUEL POOL RMS . 11/10/86 11/25/86 '
)210 RC- --- KLP RCP AMPS HIGH 11/12/86 11/25/86 '
)211 EG --- KLP MAIN GENERATOR VOLTAGE / FIELD 11/12/86
)212 RP ---
KLP MATRIX TEST POWER 11/12/86 11/25/86
)213 RP --- KLP CEDM OUTPUT BREAKERS 11/12/86 13/18/86l i
)214 RC --- KLP HIGH VIBE IRNUNCIATOR 11/17/86 UPON RCP START 1215 RP --- KLP FIRST OUT ANNUNCIATOR 11/17/86 12/12/86
)216 RP --- KLP FLOW DEPENDENT SELECTOR 11/18/86 12/12/86 l217 CC --- KLP REMOTE FUNCTION FOR 11/18/86 11/18/86 PCC & SCC FILL VALVES 1818 CC RDE --- P-9B PTL POSITION 11/18/86 11/18/86 1819 RP RDE ---
% POWER LIGHTS 11/18/86 820 RC RDE --- VPSR LIGHTS 11/18/86 12/16/86
'821- YP --- JWW MALF SEVERITY - DELAY TIME 11/18/86 11/18/86 i
'222 ED RDE --- PANALARM WINDOW 11/20/86 12/12/86 1823 RP --- KLP CWP ANNUNCIATOR 1 OUT OF 4 12/01/86 12/12/86
'224 TU ---
KLP LOSS OF EHC CONTROL POWER 12/01/86 12/22/86 ANNUNCIATOR (T-4-8)
'825 CH RDE KLP HV-9 INDICATING LIGHTS 12/02/86 12/16/86 226 FW ---
JWW SG LEVEL INDICATORS 12/03/86 12/15/86
!227- RP --- KLP MATRIX STATUS LIGHT - 12/03/86 12/12/86 POWER SUPPLY
p i.
DO -
SIMULATOR DISCREPANCY REPORTS 18 BY DR NUMBER B#. SYSTEM HDW. SFW DESCRIPTION OPEN INCORP ENG ENG DATE DATE D228- EG --- KLP LOSS OF LOAD ANTICIPATOR 12/04/86 l12/12/85 D229 EG RDE --- 86 BU WON'T TRIP 12/05/86 12/05/86 D230- EG --- KLP T-1H OPERATION 12/05/86 12/22/86 D231 MI --- KLP SEWERAGE TREATMENT ANNUNCIATOR 12/05/86 12/22/86.-
9232 TU --- KLP POWER SUPPLY - TUREINE 12/05/86 12/22/86 !
VALVE INDICATORS D233' YP. --- dWW ODD OCCURRENCE WHILE 12/05/86 12/15/86 USING BACKTRACK D234 FW- .- - KLP P-25B STEAM DEMAND 12/0B/86 12/12/86 4 D235 FW RDE ---
MAIN STEAM / FEED WATER 12/10/86 12/11/86 '
FLOW RECORDER D236 ED --- JWW STAFF BLDG TRIP ANNUNCIATOR 12/15/86 D237 RP RDE ---- RPS CHANNEL D 12/18/86 12/18/86 HIGH RATE TRIP UNIT OPEN 36 CLOSED 345 TOTAL 381 .
we e
9 4
' - ~ ~ ~ ~ - - ~ - - - ~ ---
f=
i i
i d
- APPENDIXC PROCEDURE 18-343-1 _
SINULATOROPERABILITYTEST
'I i
i
' mar g
Dept. Mgr. ' Proc..No. 18-343-1 i
Class. D' Log No. 05-118-85_ Rev No. 1 Issue Date
-Review Date-l L 18-343-1 SIMULATOR OPERABILITY TEST
' 1.0 DISCUSSION - - _ _ _ . .
The operability test procedure will check the. accuracy of plant simulation as
, compared with the referenco plant. Portiens of the testing will:be done each .
year, such.that all testing will be completed in four years. The data will bei evaluated to the criteria provided in ANS/ ANSI-3.5-1985.4 At the end of each annual test, a report will be-developed describing any discrepanciesLor modifications that require-attention and the time table for their resolution.
- For the purpose of this procedure annually will mean each calender year.
Evaluation of the data from this test will be outlined in the simulator ' annual report.
Whenever.possible, existing documentation or procedures will be used, such as operating procedures, when performing plant evolutions. As discrepancies are noted, pertinent information will be recorded for later.resolutt'on..
"To ensure the simulator response is properly verified, as compared to the reference plant, an individual holding a Senior Operator License for Maine Yankee and certified as a simulator operator shall perform or direct all phases of this test.
'2.0 OBJECTIVES 2.1 Ver'ify overall simulator model completeness and integration.
2.2 Verify simulator performance of steady state conditions by c'omparison to actual reference plant data.
-2.3 Verify simulator performance of transient conditions by comparison to a bench mark analysis.
2.4 Verify simulator performance of transient conditions by comparison to base line data.
2.5 Provide a basis document for the Simulator Annual Report.
3.0 REFERENCE.
3.1 Reg. Guide 1.149 R 3.2 ANSI /ANS 3.5, 1985 3.3 Maine Yankee Operating Procedures-3.4 Maine Yankee Operations Surveillance Procedures
-1195a-
Proc. No. 18-343-1 Rev. No. 1 ,
Page 2 of 29 l 3.5 Maine Yankee Simulator ATP 3.6 Maine Yankee Simulator Cause & Effect Document R
3.7 Maine Yankee Simulator Benchmark Analysis INITIALS 4.0 INITIAL CONDITIONS 4.1 Ensure simulator is utilizing the training load with the latest ,
up to date disc. cDS .
4.2 A qualified simulator operator with a Maine Yankee Senior Operator license shall perform or direct all testing. 4)3-R 4.3 All plant data sho0ld be obtained and entered on to data sheets prior to performing the test. Careful consideration should be given to achieve the most recent and dependable data. Whenever possible, data should be obtained from station logs, procedures, or actual plant instrumentation. N 5.0 INTEGRATED TEST.
R 5.1 RCS Heat-up Testing 5.1.1 Reset the simulator to.IC-1 (cold shutdown). CO-Record the following data and compare to actual reference plant R 5.1. 7.
data. M PLANT SIMULATOR PARAMETER DATA DATA COMMENT LOOP 1 Tc r / I'i #F LOOP 2 Tc V / 2/ #7 LOOP 3 Tc y /cc *E LOOP 1 LPSI FLOW 4 /. 65c 6hn 2e d M ,-/.56 LOOP 2 LPSI FLOW 7 - c-LOOP 3 LPSI FLOW 4 /,6 5c6F/n M /a d, RI-3902X (VENT PART) .V e .%
RI-3902Y (VENT GAS) Fc /: c-RI-1801 (AIR EJ) s'n 15 ,
RI-3401 (PCC) /so /cc RI-1701 (SCC) >
vc 9e .
) RI-2601 (#1 80) /50 /cc be 86 - o/ z RI-2602 (#2 80) /6e /Jo ad 96 - o/ 7_
RI-2603 (#3 BD) /90 Lee de 06 -o/ 2
- FLAfr DATi\ doAttAkiE' 1195e
~
Proc. No. 18-343-1 Rev. No. 1 Page 3 of 29 PLANT SIMULATOR PARAMETER DATA DATA COMMENT RI-6106 (SERV BD) 6C +N
/oc rg
__RI-1601 (SERV WT) ,
RI-3801 (LIO WASTE) 7cc ss 6 RI-3101 (LD LOW) e 690 RI-3102 (LD HIGH) 4 /Z/o #
RI-3901 (WASTE GAS) /ac /,57/03 RI-3701 (BN WASTE) /.5 t/cv 4 1 /o r 3e9 RI-610_2X(CONT. PART) vgr t em > " tr ': _hs RI-6102Y(CONT. GAS) % /, ? E,63 L r s' < m e e.-
RI-6104 (MAIN CR) /,62 /c-3 F,9 v o-f .
/ , 5 E./o - J RI-6105 (CONT. LOW) % 7 E/o t' RI-6106 (DECON RM) 4 <' ' c - "- A /f3 /ze RI-6107 (FUEL POOL) Sort' /yg2 !
RI-6108 (SAMPLE RM) /, 8 Es - J 2, / z /o-v RI-6109 (PAB) Jr/o - f / ,6 E/o-V RI-6110 (SPRAY RM) ,3 e /o 'J /, 8 r# d PZR PRESS /50 /5c' PZR LEVEL /cc /eo N/I POWER A a 56 Pee u,,
N/I POWER B .5 2- neftw
-N/I P0Fe.R C 4 35 Pren se&*F-
~
N/I POWER 0 y y
- 1 S/G PRESS o b
- 2 S/G PRESS o o
- 3 S/G PRESS o D
_ LOOP 1 TH < 5/5' 2M/5 LOOP 2 TH < 5/5' <5/5 >
LOOP 3 TH <$/5 <:f/d kPuhor .D4rA A.'c7 ChrAi/05b did.A/dd? Ct"~ RdL LCAM 5.1.3 Commence plant heatup to 200*F using procedure OP l-1 and record following data. N PLANT R ULATOR' ~
PARAMETER DATA DATA COMMENT LSI-F-59 FLOW
- 3 cco P-12A AMPS O 'o P-128 AMPS So. 5 4.N W RCS H/U RATE 4/Re i. 29/de ac- be M-e23
- ' DATA W AV i .L a t L E' 5.1.4 Continue RCS heatup using OP 1-1 and record the following data after drawing a PZR steam bubble. M R NOTE: Fast time may be used after the data in Step 5.1.3 has been obtained.
1195a
__ _______________D
Proc. No. 18-343-1 Rev. No. 1
. Page 4 of 29 PLANT SIMULATOR PARAMETER DATA DATA COMMENT )
PZR COLO LEVEL A B6 PZR MATER TEMP 4t3 ') 3 sb #6)
PZR VAPOR TEMP A38 :
.750 *m PZR PRESS S Mo, 5 /e/ 3 *O PZR HOT LEVEL -5 /co 7 wth AWttabtE INITIALS G prees re conetaics % Sarah 4emperah-e-5.1.5 Continue RCS heatup using OP 1-1 and record the following data after 1 RCP is running. LD @--
R NOTE: Ensure the simulator is not in fast time prior to obtaining the following data.
PLANT SIMULATOR PARAMETER DATA DATA COMMENT
- 1 RCP AMPS Sao 55o RCS H/U RATE /3, V 45Me DM %-o z a RCS CORE EXIT TEMP * / 7d LOOP # D/P + G8 e 2ATA WAcattabir R 5.1.6 Continue RCS heatup using OP 1-1 and verify proper simulator response during HPSI/LPSI Recircs, record the following data:
R PLANT SIMULATOR PARAMETER DATA DATA COMMENT HPSI Recirc Flow Am .e 2B 4 WW,0 Ecw 5.1.7 Continue RCS heatup using OP 1-1 and record the following data after 2 RCPS are running. CDk__
PLANT SIMULATOR PARAMETER DATA DATA COMMENT
- l RCP AMPS f5&o $3e
- 2 RCP AMPS 535 6M RCS H/U RATE 2.V He Go/ac re- R-oz3 LOOP # t D/P M3 # GB LOOP # 2 0/P .X -us 4 68 e un @AcattabLr R NOTE: Fast time may be used after the data in Step 5.1.7 has been obtained.
1195a
-- Proc. No. 18-343-1 l
- Rev. No. 1 l Page 5 of 29 INITIALS 5.1.8 Continue RCS heatup using OP 1-1 and record the following data after 3 RCPS are running. M R NOTE: Ensure the simulator is not in fast time prior to obtaining the following data.
PLANT SIMULATOR PARAMETER DATA DATA COMMENT
- 1 RCP AMPS S/5 6do
- 2 RCP AMPS #4o 63o
- 3 RCP AMPS 535 53o RCS H/U RATE 2Wef e 59/r/E TE 5.1.9 Stabilize the RCS using OP 1-1 at 532*F and 2235 PSIG and record the following data. M PLANT SIMULATOR PARAMETER DATA DATA COMMENT
- 1 S/G PRESS 9ao 'fco
- 2 S/G PRESS 9co 9ec
- 3 S/G PRESS 9eo 9eo 5.1.10 Perform main steam line warm up as per OP l-1 and verify proper simulator response as described in the operating procedure. M R 5.2 Reactor Start-up Testing 5.2.1 Record the followin'g data in preparation to performing a reactor start up. M PLANT SIMULATOR PARAMETER DATA DATA COMMENT R00 POSITION O O BORON /750 /Mo _,
CHA N/I 4-, Se CHB N/I / 3 CHC NII 4' 35 CHD N/I / 8 5.2.2 ' Perform followingadata reactor at 5startup*%.using x 10- Procedure 1-2 and record the td 6-PLANT SIMULATOR .
PARAMETER DATA DATA COMMENT R00 POSITION /4 o /#o BORON /256 /2sc ~
CHA-N/I -
Srw4 SX/o Y CHB-N/I 6x/o Y SE/c Y CHC-N/I SE/o-v SE/c f -
CHD-N/I 5 Lic -+' Gk./c 4 RCS TAVE 54 2. 63 2 f R
1195a
Proc. No. ~
18-343-1 Rev. No. 1 Page 6 of 29
'R 5.3 Low Power Physics Testing INITIALS 5.3.1 Critical-Boron Concentration
- a. Reset to 0% burnup, hot standby condition. 04
- b. Insert malfunction RD08A.to prevent inadvertent reactor .
trip. - tD8 tis-
- c. Place "CRONBR" on TDF.
' NOTE: CRDNBR is the approximate value for reactivity in ~
units of % cs/K.
- d. Withdraw all CEAs to establish an ARO conu tion. (D %.
- e. Adjust RCS boron, as necessary to achieve a just critical core condition using remote function RCO3. C @-
NOTE: CRDNBR should be approximately zero.
Record critical boron concentration on the reactor physics f.
data sheet. CO
- g. Take a temporary snap shot of this condition for later use. 60%.
'5.3.2 Rod Worths
- a. Reset to the IC taken in Step 5.3.1(g). O$
- c. g manual group mede, drive groups 5A and SB to zero
OS
_ NOTE:
The value of CRDNBR should be approximately zero. ,
- e. RecordeTRCSboronontoreactorcorephysicsdatasheet. 0%
f.-' Repeat Steps 5.3.2(b) through 5.3.2(e) for group 4. 0%.
- g. Repeat Steps 5.3.2(b) through 5.3.2(e) for group 3. @
- h. Repeat Steps 5.3.2(b) through 5.3.2(e) for group 2. L28
- 1. Repeat Steps 5.3.2(b) through 5.3.2(e) for group 1. L2B
- j. Repeat Steps 5.3.2(b) through 5.3.2(e) for group 0. L2O
- k. Repeat Steps 5.3.2(b) through 5.3.2(e) for group B. O%
.1195a
Proc. No. 18-343-1 Rev. No. 1 Page 7 of 29 INITIALS
- 1. Repeat Steps 5.3.2(b) through 5.3.2(e) for Group A. Og 5.3.3 ITC/MTC Worths
- a. Reset to the IC taken in Step 5.3.1(g). Q4
- b. Stabilize RCS temperature. 0%
- c. Adjust boron to achieve a just critical condition. (DS NOTE: The value of CRDNBR should be approximately zero. E4
physics data sheet.
NOTE: To achieve a more accurate temperature reading, data should be taken from RXTAVG in TDF.
- e. Cooldown the RCS by 10-20 DEG F by operation of the steam bypass and/or atmospheric steam dump systems. Clh
- f. Stab 1IizeRCStemperature. N
- g. Adjust boron to achieve a just critcal condition. @
NOTE: The value of CRDNBR should be approximately zero. 'LO6
R R 5.4 Power Escalation Testing 5.4.1 Commence a plant startup and power increase using OP 1-3 &
OP 1-4.
M R 5.4.2 Perform power escalation testing at 48% power.
- a. Stabilize the plant at 48%. LDS
- b. Place the core in (60X) fast time for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to achieve a xenon equilibrium condition. _ L D ffr
- c. Remove the core from fast time and stabilize the plant at 48% power. OIb (tS
~
- d. Record critical boron onto reactor physics data sheet.
NOTE: Use the value for CRRXEM on TUF for xenon.
- e. Record initial RCS TAVG, xenon and reactor power onto the reactoc s physics data sheet. Cfb 1195a
y , _ _ _ _ _ - _ _ _ , _ - - _ _ _ - _
Proc. No. 18-343-1 Rev. No. 1 Page 8 of 29 INITIALS -
Close governor values until RCS TAVG increases by f.
approximately 10'F. O4 NOTE: The. steam bypass values may open if the set point is not raised above the increased SG pressure values.
- g. Record final RCS TAVG, Xenon, and reactor power onto the reactor core physics data sheet. O4 CAUTION: This test assumes no change.in boron is made and the rods remain at a ARO configuration.
R R 5.4.3 Continue increasing power to 100% and record data on Data Sheet 1 for each of the approximate power levels: 50%, 75%, and 100%. Q4 ;
R~ 5.4.4 Display ability to maintain steady state conditions by running the simulator stability test program.
- a. In "TSM" mode enter "SST". O @r
- b. In "SST" mode enter a time frame of at least 60 minutes.
M
- c. Attach the simulator test report to this procedure. 6 R 5.4.5 Simulator heat balance comparison.
- a. Maneuver the simulator plant to match the power, RCS temperature, and injection temperature of the latest heat balance data. DS-b .- In "TSM" mode, enter "STP". This action will automatically printout the simulator heat balance values, with percent differences as compared to the reference plant. 4df4
- c. Attach the heat balance printout to the procedure. SS R 5.4.6 Maneuver the simulator plant to match the current plant conditions as closely a,s possible. OfA.
- a. In TSM mode enter "INSTCOMP". This action will automatically printout an instrument comparison log sheet with the simulator g values already entered.
- b. Enter the reference plant data onto the log sheet. 28-
- c. Attach the instrument comparison log sheets to this procedure. CO-NOTE: Evaluation of the heat balance and instrument comparison I will be outilned'in the annual report. {
1195a j
Proc. No. 18-343-1 -
'Rev. No. 1 Page 9 of 29 INITIALS R '5.5 P1 ant Shutdown Testing. I
' 5.5.1 For each of the following shutdown tests, reset to R
IC 0% Burn up 100% Power Yr. 1 C4 I l
_ 40% Burn up 100% Power Yr. 2 e/g
~
Burn up 100% Power Yr.'3
~
80% ! ,
_ 100% Burn up 100% Power Yr. 4 v I 5.5.2 Perform a power' reduction and plant shutdown using Procedure 1 and 1-5; verify proper simulator response as described by the- 1 operating procedure. M !
R .
5.5.3 Perform a reactor shutdown using operating Procedure 1-6; verify proper simulator r'esponse as described by the operating procedure. O r
.R 5.5.4 Perform a plant cooldown using operating Procedure 1-7, to the point where the RCS temperature is less than 300*F and RHR is in service. Verify proper simulator response as described by g operating procedure.
6.0. MALFUNCTIONS Perform the following steps of.the ATP and verify proper simulator -
response as described in the simulator cause and effect document.
Steps 060100 - 065105 (AN, CC, CV, ED, EG) QPe>
Year 1:
Year 2: Steps 065200 - 068204 (FW, IA, MS, NI, PC) n/l&
Year 3: Steps C68300 - 072607 (RC, RD, RH, RM, RP)
Year 4: Steps 72700 - 075305 (RX, SW, TC, TU) v NOTE 1: The testing of one fourth of the malfunctions shall be performed each year so as to complete the testing of all malfunctions every 4 years.
NOTE 2: To ensure the simulator response is properly verified, an individual holding a Senior Operator license for Maine Yankee and certified as a simulator operator shall perform or direct all testing.
i 1195a i
Proc. No. 18-343-1 i Rev. No. 1 !
Page 10 of 29 7.0 SURVEILLANCE INITIALS R 7.1 ECCS Routine Testi_n_g 7.1.1 Reset trainer to full power. O @-
7.1.2 Perform ECCS routine testing using Procedure 3.1.2 and record the following data when required by the surveillance procedure. C O-SIHULATOR PLANT DIFF PARAHETER STROKE TIHE DATA (SEC) COMHENT HSI-H-11 4, 5 6,3 o , Ei HSI-M-12 5 5, / o,/
HSI-H-21 5 5< o, :s HSI-H-22 95 h,9 c, 6 HSI-H-31 5 24 c,2 HSI-H-32 9,5 4, /r oi3 HS1-H-50 /o 9 , g' o,2 HSI-H-51 /o .fi 7 r; ,3 HSI-H-54 34 30,7 3,3 x M -89 HSI-H-SS 35' Es', o 4. 0 BP $4 -P 9 LSI-H-40 /0 91, t, S'/, & M 94-fG LSI-M-41 to 99, 3 R9, 3 DeF4-P9 SIA-H-53 3, 6 33,9 Jod .7)p 96 -69 SIA-H-St 3, Y a/, o 27 5 3e Pf, -F9 LSI-H-11 S*,:1 /b > 9 5
- 1' .np F4 -FG LSI-H-21 6,6 /0,5 S*o no ff, -99 LSI-H-31 5", d /0 A y.b DP Pd,-P'9
~CS-H-1 K SL o 46,0 ZP F4 -f4 CS-H-2 N 49, < H.S ZY f&-P9 CS-H-66 4/ 39,6 .39, 6 36f6 -#4
~
CS-H-11 4 38, R 3% F 3ef&-89 R
HS-A-162 / BiR /2> 8 3A %-89 HS-H-161 5/ t'2,9 HM .D B R b - 5 9 8 */
SIHULATOR PLANT l PARAHETER STROKE TIME DATA COMMENT R CH-A-32 29 2 6. /
CH-A-33 24 2V, 6 '
HSI-H-40 //iG foiB HSI-H-41 //,6 /Ci y HSI-H-43 //, 6 /2,5 HSI-H-42 //. N /0,9 __,
1195a
Proc. No. 18-343-1 Rev. No. 1 <
4 Page 11 of 29 R SIMULATOR PLANT 1 l
PARAHETER DATA DATA COMMENT P-14A Dis Press 2'16o 249o CVP14AD l P-14A Amps 67 .07 l P-14B Dis Press 24/ 8c 2 44o CVP14BD P-14B Amps 66 57
) P-14S Dis Press 2uRo 2&M P-14S Amos <n /c#
P-12A Dis Press 2o6 2co RHPDP12A P-12A Amps 23 25 P-12B Dis Press 2c6 2oo RHPDP12B P-12B Amps 23 25 P-61A Dis Press /9 / 2o 9 CSP 61A P-61A Amps ao 25 P-61B Dis Press /9/ 2off CSP 618 i P-618 Amps 24 39 P-9A Flow # #oo Meo P-9A Amos 'f3 34,6 P-98 Amps 43 J t' P-98 Flow EvM 4600 P-10A Flow 2,400 vv.e P-10A Amps 35 A5 P-10B F1ow 2 doo 4toos P-10B Amps 'M g 3 +'
P-29A Flow go 5o Secc P-29A Amps Edo 220 P-29B Flow goso Soco P-29B Amps N 23 2.
P-29C Flow 6c(c 5Ceo _
P-29C Amps rdo 22 P-29D Flow 5cro sco -
P-29D Amps 25 o 233 INITIALS 7.2 Perform diesel generator testing using Proc. 3.1.4; verify proper simulator response as described by the surveillance procedure. C4 R NOTE: DG-1A surveillance shall be performed on even number years and DG-18 on odd number years.
7.3 Perform auxiliary feed pump testing using Proc. 3.1.5; verify proper simulator response as described by the surveillance procedure and record the following data. N 1195a
Proc. No. 18-343-1 Rev. No. I {
Page 12 of 29 !
SIMULATOR PLANT PARAMETER DATA DATA COMMENT '~
P-258 Delta Press /6eo z , 5 // tr 7 04 pg, - g, 2- ( #6- W R
P-25A Delta Press /102, 5 No?
P-25A Amps 3o af P-25A Suc Press 27,6 a76 P-25C Delta Press / 4o 2, 5 / fed 7 P-25C Amps ao 28,5 P-25C Suc Press 2 7, N 27,3 AFH-A-101 Stroke Time ^/ 8 .
AFH-A-201 Stroke Time 7 7 AFH-A-301 Stroke Time 7 7 AFH-A-338 Stroke Time / 'N
- AFH-A-339 '/
/
Stroke Time AFH-A-340 ,g Strcke Time ,/
INITIALS 7.4 Perform CEA exercise using Procedure 3.1.8; verify proper simulator response as described by the surveillance procedure. M 7.5 Perform control room ventilation surveillance using Procedure 3.1.18; l verify proper simulator response as described by the surveillance procedure. @
7.6 Perform reactor e xlant system leakage evaluation using Procedure 3.1.19; verify RJ 1eak rate is less than 0.5 GPM. O@
R 7.7 Turbine Valve Testing R 7.7.1 Reset to a'757. power IC. Q S.
7.7.2 Perform turbine valve testing using Procedure 3.1.3; verify proper simulator response as described by the surveillar,ce dse procedure.
R 7.8 SI Tank Check Valve Testing 7.8.1 Reset the trainer to IC-1 (Cold S/D). u%-
7.8.2 Perform SI tank check valve testing using Procedure 3.1.15.4; verify proper simulator response as described by the surveillance procedure. CDlh.
R 7.9 EDG/ECCS Cold Shutdown Testing ,
R 7.9.1 On even numbered years, perform "A" Train EDG/ECCS cold shutdown test using Procedure 3.1.14A; verify proper simulator response as described by the surveillance procedure. LCib
,1195a
[ - . - - - - - - - - _ - - - - - - - - _ - - - - . - - - _ - _
Proc. No. 18-343-1 Rev No. 1 Page 13 of 29 INITIALS '
R 7.9.2 On odd numbered years, perform "B" Train EDG/ECCS cold shutdown test using Procedure 3.1.14B; verify proper simulator response as ,
described by the surveillance procedure. M/S R 7.10 Containment Isolation Testing 7.10.1 Reset the trainer to IC-1 (Cold S/D). N R 7.10.2 On even numbered years, perform "A" Train containment isolation test using Procedure 3.1.15.1-A; verify proper simulator response CO@
as described by the surveillance procedure.
R 7.10.3 On odd numbered years, perform "B" Train containment isolation test using Procedure 3.1.15.1-B; verify proper simulator response as described by the surveillance procedure. U/A R 7.11 Recirculation Actuation Testing 7.11.1 Reset the trainer to IC-1 (Cold S/0). . (DS 7 11.2 Perform recirculation actuation test using Procedure 3.1.15.2; verify proper simulator response as described by the surveillance procedure.
R 7.12 Safeguard Valve Testing 7.12.1 Reset the trainer to IC-1 (Cold S/D). SPo 7.12.2 Perform safeguards valves testing using Procedure 3.1.20; record the following data and verify proper simulator response as N described by the surveillance procedure.
SIMULATOR PLANT DIFF
'!ALVE STROKE TIME DATA (SEC) COMMENT PS-A-15 2,3 /,4 o,9 PS-A-17 2, 2 /N o, y PS-A-20 2,6 /, 5 /, o PS-A-23 2 /, 3 0, 7 R i C-A-14 / 2d /,t/
BD-Te12 / 6,/ 5, / 36 &6'/ 1 BD-T-22 / &,6 K, 6 D2 F6 -2 9 BD-T-32 / #, 7 J, 7 .3d F6 -4 G PR-A-40 t/ 4, i O,j HPD-A-96 6 d7 o, M PV-A-10 6 5,/ c, 9 LM-A-45 /a 2/o %e Jo 86-69 PD-A-122 2 6, / M/ 2d F6 -AG 1195a
Proc. No. 18-343-1 Rev. No. 1 i Page 14 of 29 SIMULATOR PLANT DIFF VALVE STROKE TIME DATA (SEC) COMMENT C-A-15 1 2, 2 1, z PR-A-41 4 4, 2 6, 2.
PM-A-78 4 3, 3 c.7 N-A-66 3 I, S l , =i' PV-A-12 6 4,9 aI LM-A-43 2 '2 2- o, 2 PD-A-124 4 4, o c.o MS-T-163 6 9,4 't. '+ DB 8G-# G '
HPCi-A-17 -
V 5,3 i, B SA-A-138 9t '7, 7 o, 3 IA-A-98 /,5 2, 6 (,o IA-A-107 L< 3. 2 to7 IA-A-101 f 2, < l.5 DR-A-6 / - 2, 3 i.3 SIA-A-47 4 6,6 1. 6 SIA-A-49 4 %4 5A De E6-69 R
PCC-M-43 64 61. "# 6,8 34 66-A9 SCC-M-165 62 62i? '
Ce7 _
W PR-M-16 12 [6. 3 .3. 9 - 1 PR-M-17 iz 14 , F, 28 CS-N-91 3,6 29, 7 26,2 SB -E6 -6 9 CS-N-92 3.6 A2 A 29.+ Da RV29 RC-M-15 13 9,5 - 3,5 w E6 -69
~
RC-M-25 l5 9a3 ~
52 .7w N- -c9 RC-M-35 (3 LL o W3- o 34 #6 -E,4 CH-M-75 il it , 5 o,5 CH-F-70 %5 G,o 3,5 '3E 86 -69 CH-M-44 IS IS I o1 CH-M-49 13 64., 2 1 2.
LM-A-55 I t, B o. 8 LM-A-56 1_ t,3 o,3 LM-A-57 d36-3 t, l 1.3 LM-A-58 i 1, ~) o,. '7 R
SL-A-53 12.o to.8 1. 2.
SL-M-29 i( , 5 9. e 7e 5 SL-M-40 tI,6 t2,o C,6 SL-M-51 \l, W L 2, r o. L, CH-F-38 ci 4,6 + 4, t 1)4 E6 -89 PCC-M-219 16 t&,6 C,+
SL-P-3 to io , 9 cA LD-M-2 , 7,# t . 2. ~
LD-T-5 l2 't 7 4,3 dB 86 -69 PCC-A-300 tt 9,4 %G PCC-A-252 -7 8,4 I.9 R PCC-A-216 2 ', 5 3b oi 5 1195a
Proc. No. 18-343-1 Rev. No. 1 Page 15 of 29 .
SIMULATOR PLANT DATA */.
VALVE STROKE TIME OF to/t2./M DIFF COMMENT PCC-A-268 15' 6.3 Es , '1 do-86-89 PCC-A-302 'l 9, a oA PCC-A-270 11 9,9 1,l PCC-A-254 i5 i+,a o,7 PCC-A-238 l9 I M, o 4O De26-29 MS-M-10 tz< it-M 4- o . o ,D R 4 6 - # 9 MS-M-20 Ias (64 4c.o no #6-9? _
R MS-M-30 IZD l(o5 4e.o Ae #4 -44 '
FH-M-104 (e 5% zo FW-M-204 Go 5%' 2,o FW-M-304 An 5's 2,o FH-F-107 4 14- 1, o enu.ev ue_. res n << e uAuSC Pos
(- 14 7, o U FW-F-207 FW-F-307 0 [4 7, o u CH-M-1 to to,6 o. 5 CH-M-87 io 4i 7-e; ,3 CH-M-52 in 4,# o2 R
CS-A-55 \ Lo\ W 5*I CS-A-56 6a1 4-re "3 di W
i SCC-A-460 1 2,7 i.7 SCC-A-461 1 3,$ M3 2.5 INITIALS 7.13 Perform auxiliary feed-water cold shutdown flow test using Procedure 3.1.22; record the following data and verify proper simulator response as described by the surveillance procedure. N-@-
SIMULATOR F'L51 T PARAMETER DATA DATA COMMENT P-25A Amps (No Flow) 3I 2'i. 6/2.7
- 1 S/G AFW Flow (,. S o (o66 P-25A Amps 63 59 /6M
- 2 S/G AFW Flow 7% Cec P-25A Amps G3 59 /4 6
- 3 S/G AFW Flow 740 /An P-25A Amps (o 3 6 4 /4 5' P-25C Amps (No Flow) 32 2.9 /.2,7
- 1 S/G AFW Flow (Ao (o 6e P-25C Amps rc 3 57/66
- 2 S/G AFW Flow 71c /_ h P-25C Amps ta 57/06
- 3 S/G AFW Flow 74c (o66 P-25C Amps '(A 57/65 1195a l
-- Proc. No. 18-343-1
- Rev. No. 1 Page 16 of 29 R
R 8.0' SIMULATOR OPERATION TESTING Cry Wolf Annunciator INITIALS 8.1 NOTE: A cry wolf annunciator is a problem that can be created by alarm only, no symptoms to support the alarm are initiated. l l
Cry wolf each annunciator on the panels listed below. @
Year 1 - Elec-Panel Year 2 - MCB-L.
Year 3 - MCB-R -
Year 4 - MCB-C ,
8.2 Time and Memory Usage
~
R 8 ". 2.1 Run " IDLE" and " FRAME" to produce a printout that contains time and memory usage for the simulation system; attach the printout to this procedure. 4 R 8.2.2 Verify the total time usage, including overhead is less than CG,-
R50 msec and at least 157.jpare gg h AE'time 86-/ available.
7(p R 8.3 Operational Time Test 8.3.1 Reset.to a full power initial condition and remove the trainer from freeze. .
6 8.3.2 Ensure rod group 5B is at 181 steps. (Dft
~
8.3.3 Drive group 5B and time how long it takes to reach 0 steps. M 8.3.4 Verify group 5B reaches O steps in 4 minutes, 30 seconds LO@-
(1 2 sec.)
8.4 Emergency Shutdown R 8.4.1 Ensure the simulator complex is in a cold shutdown conditions. CP+.
8.4.2 At instructor station; lift the' cover and depress the emergency power off push button. LUf6-8.4.3 Verify the main circuit breaker trips. - 28,.
8.4.4 Reset and close the main circuit breaker. M 8.4.5 Depress the remote emergency shutdown push button on the following HCB Panels, g A. End of the Elec. Control Panel.
B. End of the MCB Sect A.
C. Rear of the Smoke Det Panel.
D. Rear of the Hz Analyzer Panel.
E. Rear of MCB Sect B.
F. End of MCB Sect C.
G. Rear of the RPS Panel.
Il95a __ -- _ _ _ _ - _ _ - _ - _ _ _ _ __- - -
- Proc. No. 18-343-1
-- Rev. No. 1
- Page 17 of 29 INITIALS-R 9.0 BENCH MARK ANALYSIS
. 9.1 Steam Line Break 9.1.1 Reset to a full power, 80% burnup initial condition and remove the trainer from freeze. SS 9.1.2 In TSM mode,' enter " ANSI test." d .
NOTE: The ANSI test program collects critical plant data at a 0.5 sec. resolution which will later be used to provide transient bench mark plots.
9.1.3 IntheANUtestmode,entertheappropriatetestselectionto 4, be performed. l 9.1.4.AftertheINSItestprogrambeginscollectingdata,beginthe transient... QFA-9.1.5 Insert MSO2A (100% severity). EFA 9.1.6 Secure'the RCPS 60 second after the SIAS is received. k 9.1.7 Allow the simulator to run for at least 15 minutes. Cn3h 902 Loss of Feedwater/ATHS 9.2.1 Repeat Steps 9.1.1 through 9.1.4. N 9.2.2 Insert malfunction RD08A. L%L 9.2.3 Place LD-T-5 control switch in the open position. ST6-9.2.4 Secure all main and e.,ergency Teod fechw$;Tpumpsandplace in PTL. war- _Ofb-9.2.5 Trip P-2C. tdfA.
9 2.6 Allow simulator to run for approximately 15 minutes.
Cf5-NOTE: Data will be evaluated and compared to the bench mark analysis. The results of the evaluation will be outlined in the annual report. LD I
1195a
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Proc. No. 18-343-1 1 Rev. No. I l Page 18 of 29 -
l INITIALS -l R 10.0 SIMULATOR BASE LINE TRANSIENTS R~ 10.1 Test Preparation 10.1.1 Reset to full power, 80% burnup initial condition and remove the trainer from freeze. Olk 10.1.2 Place P-25A and C in the PTL position. LD9.-
10.1.3 Set the turbine bypass controller setpoint to 865 psig. LD8-i 10.1.4 Ensure pzr level is 58% and the controller demand signal is reading 50%. LD 4 l 1
, 10.1.5 In the TSM mode, enter " ANSI test." LDfS- ,
NOTE: The ANSI test program collects critical plant data at a 0.5 second resolution which will later be used to provide transient base line plots. @ l 10.1.6. In the ANSI test mode, enter the appropriate test selection to be performed. Df%
10.1.7 After the ANSI test program begins collecting data, begin the test. N R 10.2 Test #1 10.2.1 Begin test #1 (ANSI B.2.2.1) by manually tripping the reactor. LOfE-10.2.2 Allow the simulator transient to run for at least 15 minutes. @@-
R 10.3 Test #2 10.3.1 Set up to perform test #2 (ANSI B.2.2.2) by repeating Steps 10.1.1 s through 10.1.7. LL 10.3.2 Place the emergency feedwater and main feedwater pumps in PTL. Ld8-
. 10.3.3 Trip P-2C, turbine driven main feedwater pump. LD8-10.3'.4 Allow the simulator transient to run for at least 15 minutes. Ld8-R 10.4 Test #3 10.4.1 Set up to perform test #3 (ANSI B.2.2_.3) by repeating Steps 10.1.1 through 10.1.7.
10.4.2 Place trainer in freeze. LdE4-10.4.3 Enter malfunctions MSO4A, MSO48, and MSO4C with a 1 minute time l
I delay. h I 1195a
Proc. No. 18-343-1 Rev. No. 1
~~
Page 19 of 29 INITIALS 10.4.4 to Remove run for atthe trainer least 15 minutes. from freeze and allow the simulator transient O S-R 10.5 Test #4 l Set up to perform test #4 (ANSI B.2.2.4) by repeating 10.5.1 U3F!r Steps 10.1.1 through 10.1.7.
10.5.2 Place the trainer in freeze.
10.5.3 Enter malfunctions ~RC05A, RC05B and RC05C with a 1 minute time delay. LD % 9 10.5.4 Remove the trainer from freeze and allow the simulator transient LOI4 to run for at least 15 minutes.
R 10.6 Test #5
~
10.6.1 Set up to perform test #5 (ANSI B.2.2.5) by repeating 4 Steps 10.1.1 through 10.1.7.
10.6.2 Manually trip #1 RCP and allow the simulator transient to run for Ldf3, at least 15 minutes.
R 10.7 Test #7 .
10.7.1 Set up to perform test #7 (ANSI B.2.2.8) by repeating Steps 10.1.1 and 10.1.3 through 10.1.7. LN 10.7.2 Place the trainer in freeze. 12 4 10.7.3 Enter malfunctions ED01 and RC01A with a 1 minute time delay. (Of3-10.7.4 Remove the trainer from freeze and allow the simulator transient to run for at least 15 minutes. CO R 10.8 Test #8 ,
10.8.1 Set up to perform test #8 (ANSI B.2.2.9) by repeating A Steps 10.1.l' and 10.1.3 through 10.1.7.
10.8.2 Enter malfunction MS01A and allow the simulator transient to run for at least 15 minutes.
R 10.9 Test #9 10.9.1 Set up to perform Test #9 (ANSI B.2.2.10) by repeating Steps 10.1.1 and 10.1.3 through 10.1.7. d 10.9.2 Enter malfunctions RPO4A, RP04B, and RPO4C. . A 1195a
Proc No. 18-343-1 Rev. No. 1
- Page 20 of 29 INITIALS 10.9.3 Open PR-S-14 and allow the simulator transient to run for at least 15 minutes. . OS 10.9.4 Reset to A 10% power, 80% burnup IC. Cfk 10.9.5 Phase on the generator and load the plant to 14% power. @ @-
R 10.10 Test #6 10.10.1 Set up to perform test #6 (ANSI B.2.2.6) by repeating Steps 10.1.5 through 10.1.7. b S-10.10.2 Manually trip the turbine and allow the simulator transient to run for at least 15 minutes. -SWO R 10.11 Analysis 10.11.1 Notify Tech Assistance of the completion of data collection. LdT9r 10.11.2 Attach the base line plots to this procedure. LCf3-10.11.3 Compare the base line transient trends to the original base lin.e (first year test results). Discrepancies shall be outlined, with justifications, in the Simulttor Annual Report. N/M NOTE: Step 10.11.3 may be N/A for the first year test.
11.0 FINAL CONDITIONS All testing has been completed. All discrepancies noted have been documented using the discrepancy report system. Evaluation of the test data will be outlined in the Simulator Annual Report.
PERFORMED BY ON'd. // Qd6 DATE/TO'E ^&
SIMULATOR SUPERVISOR
/ # DATE/MME 4 1195a
Proc. No. 18-343-1 Rev. No. 1 ,
i Page 21 of 29 DATA SHEET l-(1 of 7) '
Power Level 501.
R PLANT SIM OR PARAMETER DATA MT TAVE 656 g$,4 PIR Press 22y6 22:5o PZR Level 47 S7 Loop 1 Tc gy ,4Q 2 ,
Loop 2 Tc gq3 69 Loop 3 Tc g 5Q 2 Loop 1 TH
$9 670 Loop 2 TH ,
gm 5 70 Loop 3 1H g $o MHTH (S LO l+o5 i R
P-ZA Amps
~
65 o 585 P-2B Amps 96 at$
P-2C Speed 06 g)5 P-27A Amps 1 60 M3 P-27B Amps g3g hyg P-27C Amps d' 16 9 Id P-1-1 Amps 47g 93 $
P-1-2 Amps gg 44y P-1-3 Amps g (9f 1195a
~ Proc. NJ. 18-343-1
- Rev. No. 1 Page2,gof29 9 1-DATA SHEET 1 (2 of 7) i Power Level 501.
PLANT SIMULATOR PARAMETER DATA DATA COMMENT TMLP A Set Pt
$c (6 b TMLP B Set Pt gg%
gg TMLP C Set Pt (gge gg4g TMLP 0 Set Pt g
Total Flow A d/P g .'
Total Flow B d/P 6e Total Flow C d/P g gg Total Flow D d/P g
- 1 S/G Press goo
- 2 S/G Press g egoc > ,
- 3 S/G Press # i 65o 1
MSH Press 84 ) O MWE 43$ 430 Cond. Back Press g,o Turb. Viv Pos. 143'3 0 244-o l%(3 24-C ' * *6 RCS Boron 9, gog3 dere_b
.VyrA WAOMddC-
\
l11955
{-
Proc. No. 18-343-1
~ ' ~ ~
Rev. No. 1 Page 23 of 29 DATA SHEET 1 (3 of 7)
Power Level 75%
~
PLANT SIMULATOR PARAMETER DATA DATA COMMENT 5c't 567 PZR Press g L PZR Level
$47 $L,(p L p 2 Tc g, 7 gj7,7,
**U ' *
$4 ~) 6Q~)b
' P ' I" 694 5S6 Loop 2 TH g L* 9 '" $83 Ss6 MWIH O3 1%4 R
P-2A Amps g gg$ P-2B Amps e 015 P-2C Speed 4 g P-27A Amps P-278 Amps _Z , cpg P-27C Amps A315 K316 P-1-1 Amps 4(ob $ 60 P-1-2 Amps P-1-3 Amps gg 4 ~EATA u.A -A03tLDNC.- Il95a
' Proc. No. 18-343-1 Rev. No.- 1
'Page 24 of 29.
\
DATA SHEET 1 (4 of 7) Power Level '75% l PLANT SIMULATOR DATA- COMMENT l PARAMETER DATA TMLP A Set Pt (gyp _ TMLP B Set Pt ggqo_ 'l TMLP C sit ff g gg4p TMLP D Set Pt gg43 '
' Total flow A d/P g 49 ~
Total. Flow B d/P g gg Total Flow C d/P . g Total Flow D d/P
#1 S/G Press g g
.#2 S/G Press .
g i
#3 S/G Press g qg MSH Press 87_6 8?o
.MWE M5 Oo ~
Cond. Back Press g g Turb. Viv Pos. 153 - too Q4"]* z-IS
'TtCS Boron - - MO NO1 l
l 1195a'
Proc. No. 18-343-1 Rev. No. I Page 25 of 29 DATA SHEET 1 (5 of 7) Power Level 100% R PLANT SIMULATOR PARAMETER DATA DATA COMMENT TAVE 6~)$ $N
'PIR Press 223G 2Z06 ,
PZR Level 66 66 Loop 1 Tc ggl $$/ Loop 2 Tc ggf 66'/ Loop 3 Tc gg/ 71 Loop 1 TH go do/ Loop 2 TH (coe /co / Loop 3 TH /po / Goo MWTH 2(o26 OIb ' RI-3902X # 3oo 4 260 RI-3902.Y gg So RI-1801 i'75 76 RI-3401 po too RI-1701 50 10 RI-2601 goo 3 60 RI-2602 g,po Q CO RI-2603
@ Qoo RI-6101 t{O 46 RI-1601 (co 55 1195a
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Prec. No. 18-343-1 - Rev. No.
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1
~^
Page 26 of 29 i DATA SHEET 1 (6 of 7) , nPower Level 1001. PLANT SIMULATOR PARAMETER DATA DATA COMMENT i RI-3801 '
/20 20 0 RI-3101 7#/06 ,
RI-3102 g gpo2 ,y,p 3 Qst,-gAf RI-3901 (Wa5NCx.d 60 / / 5#to RI-3701 ypc5 % to Y RI-6102X y'gpf 9 x/o 3 &ez. /EM4 ser-t-e v) e, seic 4 /i 3 rio ' is) Pant RI-6106 - #- 2 gigggy / W Ib RI-6103 gjf A;/6 i RI-6106(/rylf) y,y 2i 6 X/0
-2 RI-6105 g ) 7, fyj /,6 F[
R1-6107 - 7y g4 /yif
- RI-610B 9 g/o' (oy/o' RI-6109 j,fy,y/ 3 g je'Y
~RI-6010 g,gi/ ;; g,j 49 /, Q/p'3 P-2A Amps .
g/6 Al/d P-2B Amps y/6 N/6 P-2C Speed. ggp 3740 P-27A Amps 2$o Z80 P-278 Amps 298 3CC ' P-27C Amps 0I5 * ^116 P-1-1 Amps y7o e/go P-1-2 Amps 9yg 4'60 1195a
Proc. No. 18-343-1 Rev No. I Page 27 of 29 DATA SHEET 1 (7 of 8) l Power Level 1001. PLANT SIMULATOR PARAMETER DATA DATA COMMENT P-1-3 Amps qcj o q$o TMLP A Set Pt g TMLP B Set Pt So cmc TMLP C Set Pt 1%o 20 % TMLP 0 Set Pt go Total Flow A d/P g q Total Flow B d/P 45 44 Total Flow C d/P q q Total Flow 0 d/P g qq
~
#1 S/G Press gg,
#2 S/G Press g g7,
#3 S/G Press gg [57 o MSH Press 62.2.
"SQ3 EO MWE gg $g, g Cond. Back Pi .s g g ,74 Turb. Viv Pos. ',23'*c s t 2-ii 3
- ICO
+ -4e 9 = 65 -
RCS Boron , gg[ cere Gv5 Octc9 g 1195a
_. Proc. No. 18-343 . . . _ Rev. No. 1
- Page 28 of 29 3
REACTOR CORE PHYSICS DATA (1 of 2) lRITICAL BORON MEASUREMENT _(Step 5.3.1) i SIMULATOR PLANT BORON IBW DIFF > ACCEFTANCE COMMENTS-BORON BORON DIFF. % dK/K t 2G4, lot o.crg q 1 II UK#K l27 G lo i Boron Diff - Simulator boron - Plant boron IBH = 0% burnup, HZP, no XE, Pk SM froin TDB 2.7.1.2 Diff % dK/K - (Boron diff) * (IBH) lROUP CEA WORTH MEASUREMENT (Step 5.3.2)
. GROUP ' INITIAL FINAL BORON IBH % PLANT ACCEPTANCE COMMENT BORON BORON DIFF dK/K WORTH DIFF i SA&B
+ 10%
1266 (13o (36 Ict 1347 t,4% o,tzq 4 - + 10% llo8 llSo 22 to t o.21 8 o.235 c,en 3 -+ 10% tic 8 to28 80 tot o."l'i 2 o.eu. ~c.o M
%8 6o o, 5% o,64/, 5.o 62 to28 toi I ~
1'
%S 873 95 toI e,14t t o74 ,13 3 I.N7 i IO*
8>73 74'7 L26 le t (.248 o,tzg l B -
-+ 10%
M7 66t 13 tot o Tzt t .oSo o,te9 ;
^
4c5 2 A65 2,770 3,3c5 i'* fo5+ 249 le1 I T^' 4o5 k( 8,5zs 9mq 3.Sqq 2'* 1zc.c :0t Initial Boron - RCS boren prior to rod insertion Final Boron = RCS boron after adjustments are made to bring the reactor critical ; Boron Diff - (Initial boron) - (Final boron) i IBH = 0% burnup. HZP, no XE, PK SM from TDB 2.7.1.2
% dK/K - (Boron diff)/(ISW) % Diff - (Plant worth - % dK/K)/(Plant Worth) 195a
Proc. No. 18-343-1 Rev. No. 1 Page 29 of 2e R-REACTOR CORE PHYSICS DATA (2 of 2) MTC/ITC MEASUREMENTS (Step 5.3.3) INITIAL INITIAL FINAL FINAL IBW % ITC PLANT DIFF. ACCEPTANCE TEMP BORON TEMP BORON dK/K WORTH l
,521 4 l285 6t+.8 1278 to I ,em s .gfg
- , ce3 S , col 587 .5% dK/K Initial Temp = RCS TAVG prior to temp decrease'(Step D)
Initial Boron - RCS boron prior to cooldown (Step D)
-Final Temp = RCS TAVG after cooldown (Step H)
Final _ Boron' = RCS boron after adjustments (Step H) IBM = 0% burnup, HZP, no XE, PK SM from TDB 2.7.1.2
% dK/K = (Final boron - Initial boron)/(IBW)
ITC - (% dK/K)/(final temp - in4tial temp) Diff = (ITC) - (plant worth) - ITC' FTC MTC PLANT WORTH. ACCEPTANCE t-
.co4N7 .ccl6Z .ce6367 + ,o 6M 6 T.S. 3.10.D !
FTC - BOC, 0% power from TDB Figure 2.1.1.1 MTC - (ITC) - (FTC) Plant Worth - Reference plants value for MTC POWER ESCALATION /ITC (Step 5.4) INITIAL FINAL INITIAL FINAL INITIAL FINAL FPC SIM PLANT DIFF
' TEMP TEMP POWER POWER XE XE FFD ITC ITC % dK/K 552,o 5 67,o (27 3 124 o MS Mq 3.eca eces 2. o,c ! cec 62.
POWER ESCALATION /MTC (Step 5.4) , 1 SIM PLANT DIFF ACCEPTANCE COMMENT ITC FTC MTC 1 dK/K N 0 013 cool 8 T.S. 3.10.D dim mm2. i
- to.otalS 1195a
1 VAINE YANA52 SIPLLATCF FAGE 1 THE4FAL'FEFFCHNANC E/29/1986 l LN115 REFE'!NCI S I P' U L A T C E FE1 CENT 2 *4 CCFFENT 1 DARAMETER DATA DATA DIFF. FLAG l >PC EF-tX PChER FWT Et15.C0 251S.1C .12 i
.. -- , 1 y- ry.ra . ,.
u, PCW-n : ,. $E.N LCAD Md E75.ft c73.67 .C2 l !FFICIENCY % 32.e0 32.72 .3! . 'RCS-1CS TAVE dig F 5.72.5C 572.7s .C5 1C S' T C DIG F :4C.50 549.52 .CC IC S Te Di; F 59:.CC 59t.C2 .CC lC S DT DEC F 46.50- 46.5C .C1
. 1 ,.
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.a lA :t.
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)I R TEKF Dd F 6:2.C0 031.35 .1C )IR LtL % 50.C0 35.02 .C4 1CRCN 'FFF 190.CC 191.99 1.05
- E A PCS. STEF 1c1.CJ 131.CC .CC 4 i
>STEAP- 'CTAL FLCL Lib /3EC 3 1;.Cd ?217.5t .
.CI,.
- -u.Ce.
.s
. 4 .;. ._c
./G Fr...::: , .a2-
- /d LbL % e
- .C0 06.11 .1t IS PRESS FSIG __.
523.C0 c23.4Z .15 t .e T:.FP v ;e s a:, m v . .1. a. r.
. .ecu l5 cATn :TL/L.? ~ 1131.10 11!7.c4 .52 IS GLAL % 90.CJ 9c.77 .9i ,
4 s5 mss FL L:P/ sic 212.20 211.04 .54 )F T EXIT F L3v/52C 27!1.21 2745.5C .52 lP T EXIT b iTL/LES 11Cc.1: 1110.44 .21 !S R EXIT F L:F/:EC 2107.57 22iC.It .5d
- S R EXIT T DEG F 4d?.90 e
- 3.32 .12 lS R E)IT F ;TL/L2F 12:3.42 1J:1.35 .12
' FEED- 'CTAL FLCW w:D/EEC 321F.C: 3214.i; .1C lC ND FLOW Ld/ sic 22i2.5- 23 C.44 .23 >D FLC4 L:P/SEC ~ 4, ; . L7 31.4i -1.44 'W EATH iTL/L:M~ 422.40 4:?.:: .24 !11 EXIT T D:3 F *4'. 63 442.7i .Ed !12 EXIT T DEC F 37C.c 373.57 . *C 113 EXIT T DH F 2C5.40 311.25 1.95 DiC F Iid.5 23: .74 .11 i1 e EXIT T SEi NCTE 122 11 5 EXIT T D:0 F 199.10 i;4.29 2.6f
- 142.2; 14i.: 3 14.0:
- IEE NCTE 2
!1 o EXIT T DEG F 4.41 SEE NCTE 1 !17 dKIT T ?iG F 1C5.C0 1:9.71
- GCTWELL T ;EG F 9 .5C ic.;2 .??
lCND EP N LG 1.74 1.71 .91 l >ELiC1 DICAL-iE N sFCS; 'a: i7?.E: :7c.t7 .Ci ti!.?e .3:.75 4C iEN NsT Pai
08/29/E6 15: C1:14 TASK # CECCO3A4 SYSTEFS VcX-32 1.5A PAINE YANKEE SIFLLATCF F4GE 2 THEAFAL Fi;FCR?'ANCE E/29/1966 NCTES: NCTE 1: FEECWATEF HEATED CUTLET TSP 3ERATL S A;E NC1 CESE9VAELE INDICATIONS AND T H E F E F C :- E DCE5 NOT AFFECT TcAINIts. FEECWTEe FEATEs CUTLET TEMFbRATLREE ARE CONEICEFED ACN-07ITICAL A: A P ET E 75 AND AFE CNLY RE0LIREC 10 EE *ITHIN 1C21 TFE;EFCEE THESE ;ARAYITEGE CChfCRF TC THE STAACARCE EET F;FTH hY ANSI 3.3. ACTL 2: PEFE6ENCE PLAhT CATA IS L04EC T F A A. DESIchi i)??CTID CAUSE IS LEAKAGE FAST THE FARTITICN FLATE IN h-10. 1EFI:FNCE PLAhT FEPAIFS AFE EXPsCT6C CN Er1; NEXT REFUELISr;. TFE OCSIGh VALLE CF E-16 CLTLE1 TEMFERATLRE I5 1c;.:3 dig:EES. T1E FE0 CENT DIFFECEhCE EETWEEN TFE SIMLLATCF Aht Di!!Gh IS C.09%. DATA =ASE
REFERENCE:
CCNTRCL FCCM LCSS I 4 II CCNTRCL ACOM CidERVATICNS TOS CLRVE 1.1.1.1 PED hhAT SALANCi CATA CF 4/2/;f
FAINE YANKEE SIFULATCP i ' STABILITY TEST REFORT 9/16/1986 'AAAFETEFS LNITS HIGF AVERAGE L C '<; VtFIAACE FERCENT FLAG VALUES VALLES IX PC'eER PWTF 2014.66 2614.39 2614.13 .53 .02 ! lCS Th LF1 C&G F 597.31 597.3C 597.23 .C4 .01 tCS TF LP2 CdG F 5??.31 597.3C 597.25 .C4 .01 IC S Th LF3 CEG F 507.31 597.3C 597.23 .C4 .01 1C S TC LF1 CEG F 550.9E 550.95 35C.92 .C6 .01 iCS TC LF2 CEG F 551.21 551.04 55C.90 .24 .04 (C S TC LF3 CEG F 55C.97 550.93 55C.?0 .C7 .01 lC S TAVG CEG'F 574.16 574.13- 574.11 .C5 .01 !CS SCROA FPE 135.99 1E3.99 153.99 .CC .00 lCD FCO. STEFS 1E1.00 121.CC 121.00 .CC .00 'ZR. FREES. FSIA 2207.62 2264.66 :259.9? 7.7C .34 R. TEMF. CEG F 652.39 652.22 651.31 .57 .09 'I R . LEVEL % 57.4: 57.44 57.42 .C4 .07 11 S/G LEV. 2 c7.04 66.96 66.32 .22 .32 12 S/C LEV. 2 e5.43 65.27
- 65.05 .35 .58 13 3/0 LEV. 2 67.10 d6.97 66.35 .25 .38 31 S/G TEPP. CdG F 525.15 525.13 525.13 .C2 .C0
$2 S/G TEPP. CES F 525.15 525.13 525.1? .C3 .00 33 S/G TEPP. CEG F 525.15 525.13 525.13 .C2 .00 11 S/G FRESS FSIA 349.36 549.26 349.19 .12 .C2 12 5/C PFE55 F3Is 349.35 E49.24 E49.16 .19 .02 33 3/G PRESS FSIA E47.35 549.25 349.13 .1E .02 is FLCw LLM/SEC 3213.12 3212.33 3211.30 1.32 .04 Un FLCW LEM/5EC 3224.1C 3212.39 3106.73 27.37 2. 5 % ThPP. CEG F 443.E1 443.76 443.72 .CE .02 iEN CLTFLT haE E70.53 57d.24 375.59 1.29 .15 FEST CJRATIOh: dC FINUTES TEST FESULTS SATISFACTORY!!! SLL PEASLFED FARAFETECS V4dI5C LE55 TFAr. 2%. l
nu-- . - _ - - _ _ _ ._ INSTRUMENT COMPARISCN FEP0FT PAGE 1 1 PARAPETEF SCALE SIMULATOF PLANT PERCENT COPMEN15 RAhGE DATA DATA MCG - A 1'VAC PRIM 3C HG 27.30 27.00 1.00 2 3NST AIR-A 15C PSIG 94.55 93.00 1.03 3 IhST AIR-E 15C PSIG 94.55 93.00 1.03 6 RES AIR .15C PSIG 99.26 93.00 4.17 9 CCNT AIR 15C PSIG 97.46 9?.00 .31 6 PCC TEMP '25C DEC 69.1B 69.00 .07 7 SCC TEMP 259 DEG 65.43 71.00 2.23 8 FCRBAY LtL 2C FT 8.40 7.50 4.50 9 TIDE LVL 2C FT 2.80 2.80 .0C JO Rb PRESS 2CC PSIG 60.99 6E.00 3.50 1.1 E-5 FRESS 3C PSIG 25.08 19.00 2C.27 SEE NOTE 1 )2 E-4 FRESS 3C PSIG 25.C8 19.00 2C.27 SEE NOTE 1 13 P-9A AMPS 75 A .C0 .00 .00 ]4 P-98 AMPS 75 A 42.72 42.00 .96 15 P-10A AMFS 75 A .C0 .00' .0C 16 P-10E AMFS 75 A 34.C3 4C.00 7.96 DRAS6-169 )7 P-29A AMPS 4CC A .00 .00 .00 18 P-29E AMFS 4CC A 248.37 262.00 3.41 19-P-29C AMPS 400 A 248.37 268.00 4.91
!O P-29D . AMP S 4CC A .C0 .00 .0C
!1 P-26A AMFS 2CC A 119.17 126.00 3.42 DRA86-172 l2 P-26E AMFS 2CC A 119.22 132.00 6.39 DR486-172 l3 P-26C AMFS 2CC A 119.16 134.00 7.42 DR486-172 l4 P-26C AMFS 2CC A 119.23 126.00 3.39 DR486-172 L5-GEW FREQ 4 FI 60.C0 6C.00 .0C
?6 MEGVARS 60C MVAR 101.87 11C.00 1.36 CT EXC bCLT 15C V 38.10 54.00 1C.60 DRAS6-211
!8 GEN AFPS 30 KA 22.92 22.90 .07
;9 GEN VCLT 3C KV 22.36 22.0C 1.20 l0 EXC AFPS 5CC A 121.72 142.00 4.06 DRA86-211 l1 TLRB8hE SFEEC 25C0 RPM 1E00.00 18CC.CC .00 l2'CCMMCh VCLT 1C V 9.72 9.79 .70
!3 GB-1 POS 10C% 100.00 1CC.00 .00 !
- 4 GV-2 POS 10C% 1C0.00 1CC.00 .00
- 5 GB-3 POS 1CC% 100.C0 1CC.00 .00
'6 GV-4 POS 1CC% 58.77 61.00 2.23 '7 TURa LO FRESS 3C PSIG 21.54 22.00 1.53 l8 2VPULSE FR 12C PEFC 98.96 104.00 4.2C
- 9 Sh ZhJ TEPP DEC 49.34 6C.50 13.95 SEE NOTE 2 0 CCND E/P 6 EG 1.78 2.15 6.17 SEE NCTE 2 1 CCND D/P 6 HG .00 .00 .00
'. 2 G S HCR PRESS 3CC PSIG E28.12 826.00 .71 3 P-27A AMPS- 6CC A 283.27 27E.00 .88 4.P-27E AMPS 6CC A .C0 .00 .0C 5 P-27C AMFS 6CC. A 2S3.41 282.00 .23 6 P-2A AMPS SCC A .C0 .0C .CC ,7.P-2B AMPS SCC A .C0 .00 .0C , ,S P-62S AMFS 3CC A .C0 .00 .00 ,9 P-628 AMPS 3CC A 162.13 169.00 2.29
.u v y u uv w , -uv vvm -__ _ __,_
INSTRUFENT COMPARISCN REPORT PAGE 2
/
PARAFETEF SCALE SIMULATOF FLANT PEFCENT- C0FMEhTS RANGE DATA DATA 30 HC HCR PFESS SCC PSIG 432.77 405.00 3.47 ) 31 HCT LELL LVL 32 IN 1.20 .00 5.63 B2 CCND HDR'FRESS BCC PSIG 391.89 39C.00 .24 B3 HCT, PRESS 8CC PSIG 197.02 20C.00 .37 ] B4 HDT LVL 1CC% 73.00 75.00 2.00 $5 P-2A SUC FR SCC PSIG 305.42 295.00 1.30- - B6 F-28 SUC FR 80C PSIG 305.42 295.00 1.30 -1 ' 17'F-2C SUC FR SCC PSIG 305.42 295.00 2.08 $8 P-2A DIS FR 16C0 FSIG 305.25' 30C.00 .33 l 19-P-28 DIS FR 16CO FSIG 305.25 20C.00 .33 60 P-2C DISFR 2000 PSIG - 1C69.78 1C75.00 .26 l }1.TCFP'SUC FL 3CK GFF 26.54 23.50 1C.13 DRA36-174~ h2lTCFP REC FL . 1CK GFF .C0 .00 .0C !3 Fh HDR PR 15C0 FSIG 1C50.11 105C.00 .01 !4 P-2C SPEEC 60C0 RFM 4536.35 471C.00' 2.89 i5 P-2C % VLt 1CC% 56.89 63.00 6.11 H5 SG1 LVL 1CC% 63.66 66.00 2.34 i'7.SG2 LVL 1CC% 65.69 66.00 .31 l iS SG3 LVL 1CC% 68.45 66.00 2.45 l dLSG1 FRESS 1CCO FSIA 249.C9 245.00 . 41 ; 'O SG2 FRESS 1CCO FSIA 849.13 845.00 41 '1 SE3 FRESS 1CCO FSIA 849.14 245.00 .41 '2 #1 MFRV AC 1CC% 75.C6 73.00 2.06 * '3 #2 MFRV A C- 1CC% 75.90 73.00 2.99 '4 #3 MFRV AC 1CC% 75'90
. 73.00 2.9C MCS - S S'TAVE 1CC F 574.53 576.00 1.47
'6' TREF 10C F 574.49 576.00 1.51 '7.FhE 12C0 wk 531.60 '882.00 .03 MCB - C 'S PZR FRESS 1CC PSIG 2237.31 L235.00 2.31 '9 P2R LVL CCLD 1CC% 35.C6 37.00 1.94 ; l0 PZR LVL hCT 1CC% 53.13 SE.00 .13 !1 GT Lbl 72 IN 4E.55 55.50 9.65 SEE NCTE 2 i l2 GT PRESS 125 PSIG .95 6.00 4.04 !3 GT TEFP 4CC F 36.29 1C3.00 4.03 l4 L/D TEMP 6CC F 301.13 2CC.00 1.86 . !5 CHG TEMP 6CC F 443.54 47C.00 4.41 DRAS6-171 l6 L/D ECRoh SSC PFF 137.99 262.00 13.46 SEE NOTE 2 (7'L/D EYPASS TEFF 2CC F 104.C6 99.00 2.53 !8 CHG FLOW 2CC GFF 65.01 65.00 .00 l9 L/D FLOW 225 GFF 83.67 BC.00 1.63 i0'P-14A AMFS 2CC A .C0 .00 .00 11 P-14E AMFS 2CC A .C0 .00 .00 i2 P-14S AMFS 2CC A 53.10 67.0C 6.95 DRAS6-17C
- 3 #1 SL INJ 1C GFF h.97 5.20 7.7C SEE NCTE 2 4 #2 SL INJ iC GPP 9.C6 E.20 E.6C SEE NCTE 2
>5 43 SL INJ 1C GPF 8.16 6.10 .6C SEE NOTE 2 i
, ~w v. . . . - - .-- ---- -- - - _
INSTRUMENT COVFARISCM FEF0FT PAGE 3~ PSRAVETER SCALE SIMULATOF PLANT PEFCENT CCFMEhTS RAhGE DATA DATA 36 VCT TEMP 2CC F 103.37 92.00 2.68 37 VCT LVL 10C% 67.30 69.00 1.7C 38-VCT FRESS. 1CC PSIG 12.39 2C.00 7.61 SEE NOTE 2 H L/D FRESS 6CC PSIG 301.34 3CC.00 .22 K) SL STR TEFP 2CC F 120.41 12C 00 .21 }1 EAST LVL 15K GAL 10.77 1C.50 1.80 12 SL R1N PR 2CC PSIG 25.42 25.00 .21 13 TC LCCPL1 6CC F 551.46 551.00 .08 l4 TC LCCP 2. 6CC F 551.31 551.00~ .05 i5'TC. LCCP 3 6CC F 551.00 551.00 .00
- 6'TH LCCP 1 6CC F 597.60 599.0C .23 17 TH LCCP 2 6CC F 597.60 599.00 .23 l8.TH LCCP 3 6CC F 597.60 599.00 .23 19 FCI-111 1CC PSID '46.78 45.00 1.78 l0 PDI-121 1CC PSID 46.71 45.00 1.71 11'PCI-131 1CC PSID 46.71 45.00 1.71 12
- RCP 1 AMPS 1.2 KA .52 .46 5.00 DR486-210 13 RCP 2 AMFS 1.2 KA .52 .43 7.50 DR486-210
- 4 RCP 3 AMFS 1.2 KA. .5'2 48 3.33 DR486-210
'S CCNT PREh5 2CC PSIA 15.65 16.00 .18 (6 S2T A1 LVL 1CC% 47.17 4C.00 7.17 SEE NOTE 2 7 S8T A2 LVL 1CC% 46.45 4E.00 1.55 SEE NCTE 2-8:58T 43 LVL 10C% 46.45 35.00 11.45 SEE NCT5 2 9 SIT #1 PFESS 3CC PSIG 219.43 215.00 1.48 !O SIT A2 PFESS 3CC PSIG 221.64 215.00 2.21 !1 SIT #3 PFESS 3CC PSIG 219.36 225.00 1.88 l2 F3-1C2A 10C% 56.CS 46.00 1C.08 DR#66-175-13 F8-1C2B 1CC% 56.CS 46.00 1C.08 DRA86-175 i !4 F1-1C2C 1CC% 56.C8 47.00 ~9.08 DR486-175 !5 FI-1C2D 1CC% 56.C8 47.00 9.08 DR486-175 (6.TMLP A 1200 PSIG 1953.28 196C.00 .56 l7 TMLP E 12C0 PSIG 1972.50 196C.00 1.04 IS TFLP c 12C0 FSIG 1961.C2 196C.00 .09 l9 TFLP D 12C0 PSIG 1977.53 196C.00 1.46 ELEC 4 0 69-M6 3CC MW 35.C0 42.00 4.33 1 c9-VAP 160 MVAR -5.C0 -5.00 .00 2-207-Ph 3CC Mk -35.C0 -47.00 4.00 '3 2C7-bAR \ 16C MVAR 5.C0 5.00 .0C 4 ELS 1 VCLT 3.5 KV 7.C0 6.90 1.18 5 EUS 3 VCLT 5.5 KV 4.22 4.15 1.27 G BUS 5 VOL1 5.5 KV 4.22 4.15 1.27 7X 309 AMF 2CC A 35.C1 27.00 4.00 8X 311 AMF 2CC A 31.13 5E.00 11.56 SEE NCTE 3 9X 313 AMF 2CC A 77.C4 75.00 1.02 9 375 SFP 1.2 KA 1.23 1.30 5.83 I 1X 507 AMF 2CC A 55.82 88.00 1.09 3 X 14 AMP 3KA .C0 .00 .0C 8 X 16R AMF 1.5 <A .C0 .00 .CC 6X 16 AMP' 3 KA .C0 .00 .0C
~ ~ ~ , - - - ~- - . - - - - - , _ . _
.y n v ay w y INSTRUFENT CCFPARISCN FEFORT PAGE 4
'PARAFETER SCALE SIMULAf0F PLANT PEFCENT CCPMENTS RAhGE CATA DATA l145'X 26 AMP 3KA 1.41 1.40 .33 l146 X 24 AMP 3 KA 1.94 1.90 1.33
!147.X 608 AMF 200 A 37.44 -73.00 7.22 ,148:4T6 AFP i 1.2 KA 1.63 1.55 6.67 L149 X 41C AMF 2CC A 62.93 27.00 17.99 SEE NCT E 3 '150 X 412: AMF 20C A 43.C0 67.00 12.00 SEE NOTE 3 .i
- 151 X 414 AMF 200 A 51.C1 4C.00 5.50 f
- 152 ELS.6 VCLTS 5.5 KV 4.22 4.10 2.18
- 153 ELS 4 VOLTS 5.5 KV 4.22 4.10- 2.18
.154lBLS 2 VOL1s 8.5 KV 7.00 7.10 1.12 NCTES.....
- 1. FLAAT DATA'bARIES DEFENDING CN THE CLEAh1 NESS CF THE
~ SERVICE WATER FEAT EXCHANGERS
- 2. SOME DIFFERENCES IN DATA ARE CAUSED EY THE IhSIChIFICANT DISSIMILARITIES EEThEEN THE CONDITIOh CF THE REFEREhCE FLANT AT-THE TIME O F .T FE C AT A COLLECTION AND THE INITI AL- CCNDITIchs SET SY THE SIMLLATCR. THESE DIFFERENCES SHOULC NOT 9E CONSTRUDE AS-EEIhG CALSEC EY DESCFEPAhCIES IN THE SIFOLATCR SCFT6ARE
- 3. INSIGNIFICANT PLANT LOADS ARE NOT FCCELED Ih THE SIFLLATCR.
I I
.A............... . . . . . .
11/06/86 09 07:36- TASK # 090C012C: ' SYSTEPS MPX-32 1.5 A: 1 IME AVALIBALE FC R-. E AC H FRAME IN FILLISECCNDS
- 1 2 3 4 5 6 7 E 9- 10
/RAME#
. 027 3.872- 5.535 6.712. 8.113 4.295 9.784 15.256 3.899 .3C5
@0TAL SPARE. TIME AVAIALBE 57.'80' P ILL I S E C C ND S M e M
11/06/86 09:09:01 TASK # 270C012E SYSTEFS MPX-32 1.5A l i PU' SPARE TIFE IS 7.674% l l 1 1 1 ! l i l l
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(WdO) Mol.d uo!)oe[ut X)ejos / l l l i 9 I i ( 1 l e APPENDIX 0 MAINEYANKEESIMULATOR CORE 9 PHYSICSTESTCOMPARIS0N _ _ _ _ _ _ _______.________m_ i i MAINE YANVEE SIMULATOR CORT 9 PHYSICS TEST COMPARISON I 1626t l l )
1.0 INTRODUCTION
The Maine Yankee simulator core model was updated from Core 6 to Core 9 in May of 1986 by Yankee Atomic Electric Co. This report provides the comparison results between the simulator and the reference plant. The parameters measured include critical boron concentration, CEA group worths, isothermal temperature coefficient, moderator temperature coefficient and xenon behavior. Since the reference plant is currently utilizing Core 9, only the BOC values are compared-to the actual plant data. EOC values are ! compared to the normalized predictions which are outlined in the Maine Yankee Technical Data book. 2.0 ACCEPTANCE CRITERIA Where applicable, the value for the allowed maximum differences between the simulator and the reference plant are the same as the maximum differences allowed between the reference plant and its predicted values from the Core 9 design report. These allowed differences are outlined in the Maine Yankee low power physics test procedure. 3.0 CRITICAL BORON CONCENTRATION The maximum difference in the critical boron concentration occurs at H2P, 10K MHD/MT. The maximum difference of 38 PPM correlates to a reactivity l difference of 0.41% delta RHO, which is well within the acceptance criteria l of 1% delta RHO. l 4.0 CEA GROUP WORTH l The maximum difference for the total rod worth is 0.85% delta RHO. The maximum difference for the total regulating groups is 0.31% delta RH0. These differences are within the acceptance criteria of i 10%. 5.0 ITC & MTC
-The difference between the simulator and the reference plant for the .
measured value of Isothermal Temperature Coefficient is .15X10-* delta RHO. The value is well within the acceptance criteria of 0.5X10-* delta RHO. The difference between the simulator and the reference plant for the measured value of moderator temperature coefficient is .15X10-* delta RH0. Though this difference is within the acceptance criteria of 0.5X10-* delta RHO, the measured value of MTC (.G3x10-*) exceeds the tech spec limit (3.10.D) of .5X10-* delta RH0. The results of the MTC measurement has been presented to the simulator review board to aquire consent for acceptance. 6.0 XENON BEHAVIOR Core 9 xenon behavior duplicates that of the Core 6 simulator model. The initial xeon worth time behavior is well modeled. The only difference noted i is that peak xenon after a reactor trip occurs slightly lower in the simulator than in the plant prediction. 1626t
V
' MAINE YANKEE SIMULATOR CRITICAL BORON COMPARISON FOR CORE 9
-CORE
'BURNUP, CONDITIONS SIMULATOR PLANT DIFFERENCE 0.0 K HZP, GP5-140, NO XE'. 1259 1256 +3 4.5 K HZP, GP5-140, NO XE 931~ 933 -2 10.0 K HZP, GPS-140, N0 XE 576 538 4 38 12.6 K HZP, GPS-140, NO XE 340 351 -11 0.0 K ~HFP, ARO, EQXE 888 888 0 4.5 K HFP, ARO, EQXE 580 580 0 10.0 K HFP,.ARO, EQXE 190 192 -2 12.6 K HFP, ARO, EQXE 20 4 +16 e
'1626t
o . MAINE YANKEE SIMULATOR CORE 9 GROUP WORTH COMPARISON AT HZP BOC: CEA SIMULATOR PLANT i GROUPS WORTH WORTH DIFFERENCE-I- A 2.47 2.77 -0.3 8 0.92 1.02 -0.1 C 1.24 . 1.38 -0.14 REG GPS 3.90 4.21 -0.31
' TOTAL 8.53 9.38 -0.85 EOC:
CEA. SIMULATOR PLANT GROUPS WORTH WORTH DIFFERENCE A 3.042 3.25 -0.21 B 0.922 0.98 -0.06
- C 1.401- 1.58 -0.18 REG GPS 3.976 4.18 .2 TOTAL 9.34 9.99 -0.65 i
I i; 1626t l
MAINE YANKEE SIMULATOR CORE 9 SHUTDOWN GROUP INTEGRAL WORTHS AT EOC HZP CEA STEPS CRITICAL CHANGE INTEGRAL GROUP WITHDRAWN BORON IN BORON WORTH C 181 872 125 1.238 C 150 868 121 1.198 C 120 856 109 1.079 . C 100 845 98 0.970 C 80 828 81 0.802 C 60 801 54 0.535 C 40 770 23 0.228 C 20 750 3 0.030 C 0 747 0 0.000 B 181 747 93 0.921 B 150 745 91 0.901 8 120 735 81 0.802 8 100 724 .70 0.693 8 80 710 56 0.554 8 60 690 36 0.356 B 40 668 14 0.139 8 20 656 2 0.020 B 0 654 0 0.000 A 181 654 249 2.465 A 150 648 243 2.460 A 120 634 229 2.267 A 100 621 216 2.139 A 80 600 195 1.931 A 60 563 158 1.564 A 40 495 90 0.891 A 20 418 13 0.129 A 0 405 0 0.000
\
1626t
MAINE YANKEE SIMULATOR. CORE 9 REGULATING GROUP INTERGRAL HORTH HITH OVERLAP AT EOC, HZP CEA STEPS WITHDRAHN CRITICAL CHANGE IN INTEGRAL GROUP BY GPS TOTAL BORON BORON WORTH 5/4 181/181 612 1266 394 3.900 5/4 150/181 592 1263 391 3.871 5/4 130/181 572 1256 384 3.802 5/4 110/181 552 1247 375 3.713 5/4 90/181 532 1230 358 3.545 5/4 70/181 512 1206 334 3.306 5/4 50/160 492 1170 298 2.950 5/4 30/140 472 1139 267 2.644 5/4 0/80 411 1118 246 2.436 4/3 60/171 391 1113 241 2.386 4/3 40/151 371 1108 236 2.337 4/3 20/131 351 1102 230 2.277 4/3 0/113 333 1094 222 2.198 4/3 0/100 320 1088 216 2.139 4/3 0/80 300 1074 202 2.000 3/2 60/170 280 1056 202 1.822 3/2 40/150 260 1038 166 1.644 3/2 20/130 240 1024 152 1.505 3/2 0/112 222 1017 145 1.436 3/2 0/100 210 1012 140 1.386 3/2 0/80 190 1001 129 1.277 2/1 60/171 170 989 117 1.158 2/1 40/151 150 975 103 1.020 2/1 20/131 130 963 91 0.901 2/1 0/112 112 954 82 0.812 2/1 0/100 100 947 75 0.743 2/1 0/80 80 932 60 0.594 2/1 0/60 60 910 38 0.376 2/1 0/40 40 887 15 0.149 3/1 0/20 20 874 2 0.020 2/1 0/0 0 872 0 0.000 1626t l 1 - - - - - - - - - -
i MAINE YANKEE SIMULATOR l CORE 9 REGULATING GROUP INTERGRAL WORTHS OVERLAP AT E0C, HZP CEA STEPS CRITICAL CHANGE IN INTEGRAL GROUP WITHDRAWN BORON BORON WORTH --- C 181 402 117 1.401 C 153 390 105 1.257 C 143 380 95 1.138 C 133- 370 85 1.018 4 C 122 360 75 0.898
-C 108 350 65 0.778 -
C 76 330 45 0.539 C 53 310 25 0.299 C 36 290 5 0.060 C 0 285 0 0.000 B 181 285 77 . 0.922 8 151 275 67 0.802 B 137 265 57 0.683 B 114 245 37 0.443 B 79 225 17 0.204 B 16 208 0 0.000 B 0 208 0 0.000 A 181 402 254 3.042 A 149 379 231 2.766 A 100 338 190 2.275 A 50 277 129 1.545 l i A 0 148 0 0 l l 1625t
e I 1 i MAINE YANKEE SIMULATOR , CORE 9 REGULATING GROUP INTERGRAL WORTH WITH OVERLAP AT Ef. HZP l CEA STEPS CRITICAL CHANGE IN INTEGRAL GROUP. WITHDRAWN BORON BORON WORTH 5/4 181/181 402 332 3.976 5/4 168/181 399 320 3.940 5/4 156/181 393 323 3.868 5/4 146/181 385 315 3.772
'5/4 135/181 374 304 3.641 5/4 124/181 364 294 3.521 ]
5/4 111/181- 354 284 3.401 5/4 96/181 344 274 3.281 5/4 79/181 334 264 3.162 5/4 65/176 324 254 3.042 5/4 54/166 314 244 2.922 l 5/4 45/156 304 234 2.802 5/4 36/147 294 224 2.683 5/4 18/129 284 214 2.563 5/4 0/107 280 210 2.515 4/3 85/181 -279 209 2.503
'4/3 55/166~' 275 205 2.455 4/3 35/146 265 195 2.335 4/3 21/133 255 185 2.216 4/3 8/119 245 175 2.096 ,
4/3 0/104 235 165 1.976 3/2 83/181 225 155 1.856 3/2 57/167 215 145 1.737 3/2 38/148 205 135 1.617 3/2 22/133 195 125 1.497 3/2 7/117 185 115 1.377 3/2. 0/96 175 105 1.257 2/1 62/173 165 95 1.138 2/1 42/152 155 85 1.018 2/1 32/142 145 75 0.898 2/1 22/132 135 65 0.778 2/1 12/122 125 55 0.659 2/1 0/111 115 45 0.539 < 2/1 0/96 105 35 0.419 2/1 0/79 95 25 0.299 2/1 0/62 85 15 0.180 2/1 0/46 75 5 0.060 2/1 0/0 70 0 0.000 1626t
MAINE YANKEE SIMULATOR CORE 9 MTC/ITC MEASUREMENTS COMPARISON FOR BOC, HZP k l ITC MEASUREMENT: i M00. CRITICAL % 1EAP BORON IBW dK-K ITC (10-* dk/*F) 529.4 1285 101 SIM PLANT DIFF . 514.8 1278 101 +.47 +.32 +.15' 14.6 7 - .0693 MTC MEASUREMENT: ITC - FTC - MTC- MTC (10-* dk/*F)
+ 47 -
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+.63 +.48 + 15 l
1 1626t
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4 J MAINE YANKEE SIMULATOR XENON BEHAVIOR FOR -] x .Rx TRIP FROM FULL POWER TIME XENON HRS. % dk/k 0 - 2.544 1 - 2.987
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3 -3.597 4- -3.780-
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-3.811 12 -3.714 13 -3.600
.14 -3.478 15 -3.335 16 -3.2211 17- -3.085 -i' 18 -2.951
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e APPENDIXE SINULATORBENCHMARKANALYSIS EVALUATION
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'e TABLE OF CONTENTS PAGE I
_f I INTRODUCTION 2 II STEAM LINE BREAX TRANSIENT 3 III LOSSOFFEEDWATER/ATHSTbNSIENT 6 - IV
SUMMARY
AND CONCLUSIONS 8
. t LIST OF FIGURES -
PAGE ! FIGURE 2-2 MSLB TH0T RESPONSE - ORIGINAL 9 FIGURE 2-2A MSLB TH0T RESPONSE - REPERFORMED 10 FIGURE 2-3 MSLB TCOLD RESPONSE - ORIGINAL 11 FIGURE 2-3A MSLB TCOLD RESPONSE - REPERFORMED 12 ..- 3 FIGURE 2-4 MSLB TAVG RESPONSE - ORIGINAL 13 k FIGURE 2-4A MSLB TAVG RESPONSE - REPERFORMED 14 FIGURE 2-5 MSLB PZR. PRESSURE RESPONSE - ORIGINAL 15 FIGURE 2-5A MSLB PZR. PRESSURE RESPONSE - REPERFORMED 16 FIGURE 2-6 MSLB. PZR. LEVEL RESPONSE - ORIGINAL 17 FIGURE 2-6A MSLB'PZR. LEVEL RESPONSE - REPERFORMED 18 l FIGURE 2-7 MSLB SG PRESS. RESPONSE - ORIGINAL 19 FIGURE 2-7A MSLB SG PRESS. RESPONSE - REPERFORMED 20 l FIGURE 2-9 MSLB SG LEVEL RESPONSE - ORIGINAL 21 FIGURE 2-9A MSLB SG LEVEL RESPONSE - REPERFORMED 22 FIGURE 2-11 MSLB CORE POWER RESPONSE - ORIGINAL 23 FIGURE 2-11A MSLB CORE POWER RESPONSE - REPERFORMED 24 I FIGURE 2-118 MSLB CORE POWER RESPONSE - REPERFORMED 25 i FIGURE 2-12 MSLB SI FLOW RESPONSE - ORIGINAL 26 FIGURE 2-12A MSLB SI FLOW RESPONSE - REPERFORMED 27
~ FIGURE 2-128 MAINE YANKEE HPSI DELIVERY CURVES 28 i FIGURE 3-1 ATHS THOT RESPONSE - ORIGINAL 29 l FIGURE 3-2 ATHS TCOLD RESPONSE - ORIGINAL 30 l FIGURE 3-3 ATHS TAVG RESPONSE - ORIGINAL 31 l FIGURE 3-4 ATHS PZR. PRESS RESPONSE - ORIGINAL 32 l FIGURE 3-5 ATHS PZR. LEVEL RESPONSE - ORIGINAL 33 FIGURE 3-6 ATHS SG PRESS RESPONSE - ORIGINAL 34 FIGURE 3-8 ATHS SG LEVEL RESPONSE - ORIGINAL 35 FIGURE 3-10 ATHS CORE POWER RESPONSE - ORIGINAL 36 I FIGURE 3-11 ATHS CONT FRESS RESPONSE - ORIGINAL 37 l FIGURE 3-11A ATHS CONT PRESS RESPONSE - RESCALED 38 l l
0157s l
MAINE YANKEE SIMULATOR BENCHMARK ANALYSIS
, EVALUATION i I. INTRODUCTION:
A benchmark analysis was performed by the Yankee Atomic Electric Company. The report (YAEC-1445) presented a result comparison of i three transients performed on the Maine Ya ^c Simulator with best-estimate models of Maine Yankee using the RETRAN-02, CONTEMPT AND RELAPSYA. The transients performed were:
- 1. A steam line break in the 30 inch header down stream of the excess flow check valves (EFCV) at 100% power.
- 2. A complete loss of main feed with a failure of all reactor trips to cause a scram (ATHS) at 100% power.
- 3. A steam generator tube rupture at 100% power.
NOTE: Due to the difficulty in interpreting the results of the steam generator' tube rupture analysis and the limited benefit which could be received by reperforming the analysis, it was decided to drop the transient from the report. Maine Yankee does not consider this transient as part of the bencFmark and therefo're will not evaluate the results in this report. The purpose of this report is to evaluate the result comparison of the transients performed in the benchmark analysis and det mine if modifications to the Maine Yankee Simulator software are necessary. One item which must be kept in mind, is that one prediction is not necessarily more correct than the other. It is simply a comparison to indicate where potential problems may exist in the Maine Yankee Simulator software. i 0157s
II. STEAM LINE BREAK TRANSIENT: The break occurred in the 30 inch header outside of containment, downstream of che excess flow check valves (malfunction MS02). All other systers were allowed to respond normally. No operator actions were taken except securing of the RCPs 30 Sec. after receiving SIAS. A. RCS TEMPERATURE RESPONSE DIFFERENCE: As can be seen in Figures 2-2, 2-3 and 2-4, the RCS temperatures calculated by the Simulator did not decrease as rapidly I initially as that predicted by RETRAN. At the 300-500 seconds range, j the temperatures calculated by the Simulator dropped below the j temperatures calculated by the RETRAN Code. I EVALUATION: The initial differences between the two predictions is believed to be caused by the poor graphing techniques employed, which ) caused the starting points of the two trends to be off slightly. The differences in the RCS temperature. predictions at the 300-500 seconds range was caused by excessive steam generator feedwater flow in the Simulator tr> del, which tended'to cool the Simulator RCS temperatures more than the Retran predictions. The difference la the feed water flow was caused by having excessive leakage modeled on the Simulator's main feed regulating valves.' This leakage was reduced with DR No. 85-0034. The transient was performed again on the Simulator, paying particular attention to the starting points on the graph. The results of the second run as displayed on Figures 2-2A, 2-3A and 2-4A show very little differences between the two predictions. B. PRESSURIZER PRESSURE RESPONSE
/
DIFFERENCE: As can be seen by Fig. 2-5, the Simulator's predicted pressure did not initially decrease as rapid as the pressure predicted by RETRAN. As the pressurizer started to refill (approximately 200 second mark) the RETRAN code showed a gradual - increase in pressure, while the Simulator pressure prediction remained relatively constant until the pressurizer was nearly full. EVALUATION: the Simulator pressure res;,onse upon a pressurizer . reflood event was believed to be incorrect. The Simulator
- pressurizer model was modified by the Singer Link Company, with DR-105W. It was also discovered that by leaving the RCPs running for a greater length of time, the Simulator could more closely duplicate RETRAN's prediction. We believe that there exists a difference in head bubble modeling techniques between the two codes, which _
contributes to the differences in the initial drop. The transient was performed a second time on the Simulator. The results are displayed on Figure 2-5A. The difference which exist during the refill event in the figure is due to the variations in the pressurizer level response (see Item C). The pressure response relates quite well to the rate of level increase. 1
)
0157s _--____
O C. PRESSURIZER LEVEL RESPONSE DIFFERENCES: As can be seen by Figure 2-6, the pressurizer level j decrease predicted by the RETRAN code is more rapid than the response of the Simulator. The rate of the pressurizer level increase predicted by RETRAN is more rapid than the response of the Simulator. EVALUATION: The differences observed in the rate of level decrease for the two predictions is believed to be caused by the small differences in the rate of the RCS temperature decrease (see Item j A). The difference in the rate of increase between the two codes is - caused by a calculated difference in HPSI flow (see Item G). Figure 2-6A shows the results of the second run of transient performed on the Simulator. The pressurizer level rate increase, by the Simulator ! is even less than initially seen. This is caused by correcting the ! pressurizer pressure response upon a reflood event, (see Item B) which increases pressure as level increases and lowers the rate of HPSI flow; thereby lowering the rate of increase in pressurizer level. D. STEAM GENERATOR PRESSURE RESPONSE j EVALUATION: As can be seen in Figure 2-7, the steam generator pressure response are essentially the same and both codes predicted the same approximate values. The small differences that did exist are attributed to the differences that existed in the RCS temperatures (see Item A). The transient was performed again on the Simulator after remedying the RCS temperature discrepancy. The results, as displayed in Figure 2-7A show a slightly improved match between the two codes. E. STEAM GENERATOR LEVEL RESPONSE EVALUATION: As can be seen in Figure 2-10, responses are very similar as predicted by both RETRAN and the Simulator. Steam ! i generator levels in the Simulator continue to drop after Retran predicts a leveling off. This is due to the steam generator pressure prediction dropping slightly slower in the Simulator calculation than in the RETRAN calculation, causing the excess flow check valves to auto close later and, thus, the leveling off to occur later. During the second run of the transient performed on the Simulator (see Figure 2-10A), the level decreased more than the initial transient but remained symmetric. This is caused by the reduction of the main feed regulating valve leakage, as described in Item A. F. CORE POWER RESPONSE 1 l DIFFERENCE: As can be seen by Figure 2-11, both the Simulator and the RETRAN calculated power predictions drop off rapidly after a trip. But, the Simulator model showed a very low value for decay l heat power. 0157s l
EVALUATION: It was discovered that N/I power was used for the Simulator data rather than core power. The transient was performed a second time on the Simulator, using the correct data. As seen in Figures 2-IIA and 2-11B the core power responses correspond well and show a close match. G. SAFETY INJECTION RESPONSE DIFFERENCES: As can be seen in Figure 2-12, the RETRAN code predicts the initiation cf HPSI flow approximately 20 seconds earlier than the Simulator. The RETRAN code predicts peak HPSI flow to be l approximately 500 GPM higher than the peak flow calculated by the i Simulator. After approximately 200 seconds, the Retran code predicts that HPSI flow will decrease while the Simulator's value remained relatively unchanged. I EVALUATION: The iifference of HPSI flow initiation start times is due to a more dro.atic RCS pressure drop predicted by the Retran code i l and therefore it reaches the safety injection actuation setpoint (1585 PSIG) earlier than what the Simulator predicted. This . difference is believed to be caused by differences in model ! techniques for reactor vessel head bubble formation (see Item B). The RETRAN code predicts peak flow to be approximately 500 gallons per minute higher than that calculated by the Simulator. This is believed to be caused for two reasons: A. RETRAN code predicts a lower RCS pressure than the Simulator, which creates a lower pump head and therefore increased flow. B. It appears that the RETRAN code assumes pump runout to be at 870 PSIA in the RCS rather than at the discharge of the pump (i.e., no pressure drop in the HPSI line). In fact runout of the HPSI pump is 870 PSI at the discharge of the pump (i.e. O PSI in the RCS). Figure 2-128 shows the Maine Yankee HPSI pump delivery curves, developed by Combustion Engineering. According to these curves the I l Simulator calculated HPSI flow is well predicted. After the 200 Sec mark, the HPSI flow calculated by the_ Simulator remained relatively constant, while the HPSI flow calculated by the Retran code decreased. This was due to a relatively constant l pressurizer pressure calculation by the Simulator during the pressurizer reflood event (see Figure 2-5). This poor pressure response was corrected (see Item B) and the transient was performed a second time. As seen in Figure 2-12A the Simulator flow now decreases due to the RCS pressure increasing. 0157s
III. LOSS OF FEEDWATER/ATWS TRANSIENT A loss of all feed water occurred, coupled with a failure of the reactor to automatically trip (ATHS). All other systems were allowed to operate normally with no operator action. A. RCS TEMPERATURE RESPONSE DIFFERENCES: The RCS temperatures calculated by the Simulator are similar to the temperature response predicted by the RETRAN code. Except, the Simulator's temperature response immediately starts to increase, while the temperature predicted by RETRAN remains relatively constant for about the first 50 seconds. The Simulator calculates the peak temperature to be approximately 40*F higher than that predicted by the Retran code (see Figures 3-1, 3-2, 3-3). EVALUATION: After consolidation with YNSD, it was determined that the Simulator and RETRAN used two different initial assumptions for the transient, which. caused the Retran code predictions to lag the Simulator's calculation. When performing the transient on the Simulator, the main turbine was immediately tripped; while the Retran code did not assume a turbine trip, until a low S/G RPS trip was received (30.5 seconds later). The differences in peak temperature predictions is believed to be due to potential differences in the ' moderator and fuel temperature reactivity coefficients. B. PRESSURIZERPRESSUIERESPONSE DIFFERENCES: The pressurizer pressure response predicted by the RETRAN code is similar to the Simulator's performance. Except, the Simulator's response lagged the RETRAN code's predicted response by approximately 50 seconds (see Figure 3-4). EVALUATION: Both the Simulator's performance and the RETRAN calculation reacted well as compared to their respective changes in pressurizer level. The differences noted in the pressure responses between the two calculations is primarily due to differences in the pressurizer level response between the RETRAN code and the Simulator's predictions (see Item C). C. PRESSURIZER LEVEL RESPONSE _ DIFFERENCES: The pressurizer level response predicted by the Simulator and the RETRAN code are essentially the same. Except, the level response calculated by the Simulator immediately starts to increase, while the Retran code lags by approximately 50 seconds. EVALUATION: Both pressurizer level predictions responded well relative to their respective changes in RCS temperature. The reason j for the differences is primarily due to differences in the calculated i temperatures (see Item A). l l 0157s
D. STEAM GENERATOR PRESSURE DIFFERENCES: The steam generator pressure predicted by the Simulator remains at the safety valve setpoint for approximately 50 seconds longer than that predicted by the RETRAN code. EVALUATION: The steam generator pressure response in the Retran and Simulator calculations agree quite well. The lag in the pressure decrease by the Simulator is due to reaching a S/G dryout condition approximately 50 seconds later than the Retran prediction. This is caused by the differences in time assumed for a turbine trip. When performing the Simulator transient, the main turbine was immediately ' tripped. While, Retran waited until a low S/G level trip was received before initiating a main turbine trip (30.5 sec. later). F. CORE POWER DIFFERENCES: For the first 50-100 seconds the Simulator power prediction is lower than that of Retran. At about 100 seconds, the power predicted by Retran drops rapidly while the Simulator power drops more slowly. EVALUATION: The cause for the differences noted is due to the
' differences in times assumed for a main turbine trip. The Simulator assumed an immediate turbine trip, which caused an immediate power reduction. The RETRAN code assumed a turbine trip at some later time followed by a S/G dry out condition at approximately the 100 second mark.
G. CONTAINMENT PRESSURE RESPONSE DIFFERENCE: As seen in Figure 3-11, the CONTEMPT code predicts an earlier rise in containment pressure than that calculated by the Simulator. Peak containment pressure predicted by the Simulator is approximately 2.6 PSIA higher than that predicted by the CONTEMPT code. EVALUATION: All though not obvious by Figure 3-11, the CONTEMPT code and Simulator calculations match quite well. Figure 3-11 shows a pressure range of only 5 PSIA; bearly observable by the operator. The transient results were redrawn, using the same scale as the pressure instrument used by the operators (0-200 PSIA). The results are displayed on Figure 3-llA. The CONTEMPT code does not have a pressurizer quench tank included in its' model and therefore is the 1 cause of a earlier pressure increase. i 0157s
r IV. CONCLUSION: ,
. Comparison measures of the transients were used to identify significant differences in parameter behavior. This comparison measure revealed two areas in the Simulator software in which improvements were made. These improvements were made to the pressurizer and fcedwater dynamic models (DR-105W & 85-034).
The benchmark analysis demonstrates that the effect of the Simulator's fidelity for training has not been jepordized. The differences noted in ' the comparison will not affect the operator's judgement and will not result in an incorrect course of actions to be taken. The benchmark analysis also demonstrates that the Simulator transient performance far surpass the requirements of ANSI 3.5-1985; which requires that the observable change in parameters correspond in the same direction to those expected from a best estimate simulated transient and do not violate the physical laws of nature. l l
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