ML20101M459
| 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 DOCUMENT TRANSMITTAL 4
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224352 RETURN ACKNOWLEDGED TRANSMITTAL AND TO CONTROL NUMBER: 338 SUPERSEDED DOCUMENTS (IF APPLICABLE) TO: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 TRAN DOC RET ALT ALT a
j CODE TYPE DOCUMENT NiTMBER REV REV MED COPY MED COPY AFFECTED DOCUMENT l
R DRAW J-26060A 001 000 C 1
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DATE:
\\0 $8 56 6g[
i 9207080242 920626 A
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NRC EMERGENCY RESPONSE DATA SYSTEM DATA POINT LIBRARY J-26060A Rev. 1 a
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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 Steam Generator (o
A) Water Level RELO404A SG LEVEL 2/B Steam Generator 2 (or B) Water Level 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
- ~... -. -.
j J-26060A t
Rev. 1 1
DATA POINT LIBRARY REFERENCE FILE i
i Date:
06/25/92 Reactor Unit:
CW1 Data Feeder:
N/A 1
NRC ERDS Parameter:
NL
'i Point ID:
SEN0701 Plant Spec Point Desc:
POST ACCIDENT WIDE RANGE 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 Maximum Instr Dange:
2.000E+0?
3 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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