ML20101M459

Rev 1 to J-26060A, Critical Safety Function Parameters

ML20101M459
Person / Time
Site:	Callaway
Issue date:	06/26/1992
From:	UNION ELECTRIC CO.
To:
References
J-26060A, NUDOCS 9207080242
Download: ML20101M459 (5)

Text

i DATE: 0'6/26/92 UNION ELECTRIC COMPANY PAGE: 1 TIME: 13:58:47

• DOCUMENT CONTROL SYSTEM ARDC8811 4 DOCUMENT TRANSMITTAL TRANSMITTNL NUMBER: 224352 RETURN ACKNOWLEDGED TRANSMITTAL AND TO CONTROL NUMBER: 338 SUPERSEDED DOCUMENTS (IF APPLICABLE) TO:

TITLE: OTHER ADhfNISTRATION RECORDS DEPT: NUCLEAR REGULATORY COMM. UNION ELECTRIC COMPANY LOCATION: WASHINGTON, DC CALLAWAY PLANT TRANSMITTAL DATE: 920626 P.O. BOX 620 FULTON, MO 65251 a TRAN DOC RET ALT ALT j CODE TYPE DOCUMENT NiTMBER REV REV MED COPY MED COPY AFFECTED DOCUMENT R DRAW J-26060A 001 000 C 1 l

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3 d NRC EMERGENCY RESPONSE DATA SYSTEM DATA POINT LIBRARY a J-26060A Rev. 1 a

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s NRC EMERGENCY RESPONSE DATA SYSTEM DATA POINT LIBRARY J-26060A Rev. 1 REV. AFFECTED PAGES 0 NEW DOCUMENT i 1 Page 2 & 9 change SEN0701 units from PCM to %

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J-26060A CRITICAL SAFETY FUNCTION PARAMETERS COMPUTER PARAMETER PARAMETER DESCRIPTION UNITS POINT REACTIVITY CONTROL NI POWER RNG Nuclear Instruments, Powcr Range  % SPDS0059 NI IhTER RNG Nuclear Instruments, Intermediate Range AMPS SPDS0060 NI SOURC RNG Nuclear Instruments, Source Range CPS SPDS0041 >

NL Post Accident Wide Range  % SEN0701 NL Post Accident Source Range CPS SEN0702 CORE COOLING i REAC VES LEV Reactor Vessel Water Level  % REUO523 TEMP CORE EX Highest Temperature at the Core Exit DEGF AEU0090 SUB MARGIN Saturation Temperature-Highest CET DEGF SPDS0006 CORE FLOW Total Reactor Coolant Flow 4 REUO497 STEAM GENERATORS

( SG LEVEL 1/A SG LEVEL 2/B Steam Generator Steam Generator 2 (or B) Water Level (o A) Water Level  %

RELO404A RELO424A SG LEVEL 3/C Steam Generator 3 (or C) Water Level  % RELO444A SG LEVEL 4/D Steam Generator 4 (or D) Watcr Level  % RELO 4 'J4 A SG PRESS 1/A Steam Genere. tor 1 (or A) Pressure PSIG SPDS0022 SG PRESS 2/B Steam Generator 2 (or B) Pressure PSIG SPDS0023 SG PRESS 3/C Steam Generator 3 (or C) Pressure PSIG SPDS0024 SG PRESS 4/D Steam Generator 4 (or D) Pressure PSIG SPDS0025 MN FD FL 1/A Stm Gen 1 (or A) Main Feedwater Flow KLB/HR SPDS0026 MN FD FL 2/B Stm Gen 2 (or B) Main Feedwater Flow KLB/HR SPDS0027 MN FD FL 3/C Stm Gen 3 (or C) Main Feedwater Flow KLB/HR SPDS0028 MN FD FL 4/D Stm Gen 4 (or D) Main Feedwater Flow KLB/HR SPDS0029 AX FD FL 1/A Stm Gen 1 (or A) Auxillary FW Flow KLB/HR SPDS0054 AX FD FL 2/B Stm Gen 2 (or B) Auxiliary FW Flow "LB/HR SPDS0055 AX FD FL 3/C Stm Gen 3 (or C) Auxiliary FW Flow sB/HR SPDS0056 AX FD FL 4/D Stm Gen 4 (or D) Aux!.li9ry FW Flow KLB/HR SPDS0057 HL TEMP 1/A Stm Gen 1 (or A) Inlet temperature DEGF SPDS0030 HL TEMP 2/B Stm Gen 2 (or B) Inlet Temperature DEGF SPDS0031 HL TEMP 3/C Stm Gen 3 (or C) Inlet Temperature Dr1F SPDS00?2 HL TEMP 4/D Stm Gen 4 (or D) Inlet Temperature DEGF SPDS0033 CL TEMP 1/A Stm Gen 1 (or A) Outlet Temperature DEGF SPDS0034 CL TEMP 2/B Stm Gen 2 (or B) Outlet Temperature DEGF SPDS0035 CL TEMP 3/C Stm Gen 3 (or C) Outlet Temperature DEGF SPDS0036 CL TEMP 4/D Stm Gen 4 (or D) Outlet Temperature DEGF SPDS0037 O

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DATA POINT LIBRARY REFERENCE FILE i i

Date

06/25/92 Reactor Unit: CW1 Data Feeder: N/A 1

NRC ERDS Parameter: NL Point ID: SEN0701

'i POST ACCIDENT WIDE RANGE Plant Spec Point Desc:

, Generic /Cond Desc: POST ACCIDENT WIDE RANGE

Analog / Digital: A 1 s'ngr Units / Dig States:  %

j Engr Units Conversion: N/A Minimum Instr Re'.ge: 1.000E-08 3

Maximum Instr Dange: 2.000E+0?

Zero Point

Reference:

N/A

Reference Point Notes

N/A j PROC or SENS: P

Nunber of Sensors

2 i How Processed: AVERAGE Sensor Locations: REACTOR CA7ITY

Alarm / Trip Set Points: N/A i HI Detector Power Supply Cut-off Power Level N/A

,  !!I Detector Power Supply Turn-on Power Level: N/A t Instrument Failure Mode: LOW

', Temperature Compenstdon l

For DP Transmitters: N/A Level Reference Leg: N/A Unique System Dest: MAY FAIL HIGil.

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