ML051290107
| ML051290107 | |
| Person / Time | |
|---|---|
| Site: | Columbia |
| Issue date: | 04/06/2005 |
| From: | Coleman D Energy Northwest |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| G02-05-071 | |
| Download: ML051290107 (34) | |
Text
SENERGY NORTHWEST People *Vision* Solutions P.O. Box 968 - Richland, WA
- 99352-0968 April 6, 2005 G02-05-071 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 EMERGENCY RESPONSE DATA SYSTEM CHANGE TO DATA POINT LIBRARY
Dear Sir or Madam:
The following information is being supplied in accordance with 10 CFR 50, Appendix E, Section VI.3 requirements that any changes that could affect the transmission format and computer communication protocol to the ERDS must be provided to the NRC at least 30 days prior to the modification. The Columbia Generating Station ERDS data point library is being revised to change the reactor unit name from WP2 to CG1. This change affects the communication protocol between the Columbia Generating Station ERDS software and the NRC ERDS system.
In addition to the change in reactor unit name, other changes were identified during a review of the data point library. These changes do not modify the point IDs but do affect the supporting reference information. Energy Northwest has worked with Scientech in Idaho Falls to test the change to the reactor unit name to ensure the communication protocol will be correctly implemented. ~The acceptance testing conducted with Scientech the week of March 21, 2005 was successful and all issues were resolved.
Following incorporation of the new data points on the NRC ERDS computer, the revised programs will be available for final implementation the week of May 30, 2005.
If you have any questions, please contact Greg Cullen at (509) 377-6105.
Respectfully, DW Coleman Manager, Regulatory Programs Mail Drop PE20 Ac&
Enclosure cc: BS Mallett-NRC RIV RN Sherman-BPAN1399 BJ Benney - NRC NRR WA Horin - Winston & Strawn NRC Senior Resident Inspector/988C
D ATi PN R
N I
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CGI N/A Wind Dir 2 F143 MET TWR WIND DIRECT EL 245' -AVERAGE Wind direction 2 at the Reactor A
DEGFR N/A 0
540 N/A N/A S
1 N/A Met Tower, at 245' above grade N/A N/A N/A Cannot be Predicted N
N/A Wind direction at 245' level on the Met Tower. 15 min. average.
CVI 1025-00,1 Rev. 001 11 of43
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A Wind-Speed I F144 MET TWR WIND SPEED EL 33 -AVERAGE Wind Speed 1 at the Reactor Site A
MPH N/A 0
90 N/A N/A S
1 N/A MET Tower, at 33' above grade N/A N/A N/A Low N
N/A Wind speed at 33' level on the Met Tower. 15 min. average.
I CVI 1025-00,1 Rev. 001 12 of 43
Ia F.,;.v DT POINT L
R 4
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
AlarmlTrip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A WIND-DIR I F145 MET TWR WIND DIRECT EL 33' -AVERAGE Wind direction 1 at the Reactor A
DEGFR N/A 0
540 N/A N/A
,S 1
N/A MET Tower, at 33' above grade N/A N/A N/A Cannot be predicted N
N/A Wind direction at 33' level on the Met Tower. 15 min. average.
I I
CVI 1025-00,1 Rev. 001 13 of 43
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CGI N/A STAB-Class 1 F146 MET TWR DELTA T EL 245-33' -AVERAGE Air Stability at the Reactor A
DEGF N/A
-15 15 N/A J N/A P
2 Average Difference MET Tower at 33' and 245' above grade.
N/A N/A N/A Cannot be predicted N
N/A Temperature difference (245' - 33') levels on the MET Tower.
15 min. average.
I CVI 1025-00,1 Rev. 001 14 of 43
. P,'0
-. I!
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A LPCI-Flow I X043 RHR B LOOP FLOW Low Pres Coolant Inj Flow 1 A
GPM N/A 0
10,000 N/A N/A S
1-N/A Reactor Building, 501' Level N/A N/A N/A Cannot be predicted N
N/A Rated flow = 7450 GPM. One of three LPCI loops used to provide core cooling subsequent to vessel depressurization.
System initiations occur at -129" (Level 1) reactor water level.
CVI 1025-00,1 Rev. 001 15 of 43
DITA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CGI N/A LPCI-Flow 3 X058 RHR C LOOP FLOW Low Pres Coolant Inj Flow 3 A
GPM N/A 0 '
10,000 N/A N/A S
1 N/A Reactor Building, 501' Level N/A N/A N/A Cannot be predicted N
N/A Rated flow = 7450 GPM. One of three LPCI loops used to provide core cooling subsequent to vessel depressurization.
System initiation occurs at -129' (Level 1) reactor water level.
CVI 1025-00,1 Rev. 001 16 of 43
DT.
POINT LIBRR R
I DATA POIN LEBRAY REERENCE F LE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Referenre Leg:
Unique System Desc.:
1/21/05 CG1 N/A COND-AE-RAD1 X088 OFFGAS POST-TREAT ACTIVITY Condenser Air Ejec Rad 1 A
1 N/A Rad Waste Building, 452' Level 6E + 5 CPM (NOM) HiHiHi N/A N/A Cannot be predicted N
N/A Post treatment radiation monitoring of off gas sample from the Off Gas charcoal adsorbers I
CVI 1025-00,1 Rev. 001 17 of 43
DAA P
T LI DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CGI N/A REAC-VES-LV1 X159 DFWLC RX WTR LVL Fuel RNG A (Comp)
Rx Vessel Water Level 1 - Comp.
A INCH N/A
-310
-110 MSSKRT See Description S
1 N/A Reactor Building 471' Level SCRAM = 13" N/A N/A Cannot be predicted y
Wet Water level indication from 51" above TAF to BAF. DP transmitters calibrated for operating condition. Zero point reference: 0" = MSSKRT. Reference Point Notes: 0" = 527.5" from bottom of RPV. -161" = TAF. 13" = SCRAM I
I CVI 1025-00,1 Rev. 001 18 of 43
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
- PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Dece.:
1/21/05 CGI N/A DW-TEMP 1 X118 DRYWELL AVERAGE TEMP DIV 1 Drywell Temperature 1 A
DEGF N/A 50 400 N/A N/A p.
4 Average Containment Building, 517' Level Alarm = 333.4 Deg F N/A N/A Cannot be predicted N
N/A Drywell average temperature monitoring of the RPV head area.
Cont. Recirc Air Fan Coil 2A air inlet, recirc pump motor air inlet, and recirc pump motor A area.
CVI 1025-00,1 Rev. 001 19 of 43
DT, PIiBA R
EC DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CGI N/A CR-SPRAY-FL2 X122 HPCS FLOW Core Spray Cooling System Flow 1 A
GPM N/A 0
8000 N/A N/A S
1 N/A Reactor Building, 471' Level See Description N/A N/A Cannot be predicted N
N/A 6350 GPM @ 200 PSID above suction to RPV. System initiation occurs at -50" (Level 2) reactor water level and trips at +54.5" (Level 8) reactor water level.
CVI 1025-00,1 20 of 43 Rev. 001
D-AA P L;A-
.R.NC DATA POINT LIBRARY REFEZRENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
AlarmlTrip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A REAC-VES-LV2 X130 RX WATER LEVEL WIDE RANGE DIV 1 Reactor Vessel Water Level 2 A
INCH N/A
-150 60 MSSKRT See Description S
1 N/A Reactor Building 522' Level Alarm = 12.2" +/- 2.1" Above Inst. Zero N/A N/A Cannot be predicted y
Wet Provides water level indication from 11" to 221" above TAF and encompasses all RPV water level-related equipment initiations and trips. The bottom of the wide range overlaps the top of the fuel zone range by 40". DP transmitters calibrated for operating conditions. Zero point reference: 0" = MSSKRT. Reference Point Notes: 0" = 527.5" from bottom of RPV. -161" = TAF, 13" = SCRAM. Alarm/Trip setpoints: Level alarm setpoint =
+ 12.2" +/- 2.1" above instrument zero.
I CVI 1025-00,1 Rev. 001 21 of 43
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A MAIN-FD-FLWI X135 DFWLC FEED FLOW LOOP B Reactor Feedwater Flow 1 A
LB/HR N/A 0
8.5E + 6 N/A N/A S.
N/A Turbine Building, 471' Level N/A N/A N/A Cannot be predicted y
N/A DP transmitters calibrated for operating conditions. Monitors flow through Venturi section in one of two 24" reactor feedwater lines into the reactor. Flow signals are used for both monitoring and control of reactor feedwater flow.
I CVI 1025-00,1 Rev. 001 22 of 43 i
I
DATA POINT LIBRARY REFERENCE FILE Date:
1/21/05 Reactor Unit:
CG1 Data Feeder:
N/A NRC ERDS Parameter:
RCIC-FLOW I Point ID:
X142 Plant Specific Point Desc.:
RCIC PUMP DISCH FLOW Generic/Cond Desc.:
Reactor Core Isol Cool Flow I Analog/Digital:
A Engr Units/Dig States:
GPM Engr Units Conversion:
N/A Minimum Instr Range:
3 Maximum Instr Range:
700 Zero Point
Reference:
N/A Reference Point Notes:
N/A PROC or SENS:
S Number of Sensors:
1 How Processed:
N/A Sensor Locations:
Reactor Building, 471' Level AlarmnTrip Set Points:
See Description NI Detector Power Supply N/A Cut-off Power Level:
NI Detector Power Supply N/A Turn-on Power Level:
Instrument Failure Mode:
Cannot be predicted Temperature Compensation N
For DP Transmitters:
Level Reference Leg:
N/A Unique System Desc.:
Rated flow = 600 GPM to RPV. System initiation occurs at -50" (Level 2) reactor water level and trips at +54.5" (Level 8) reactor water level.
CVI 1025-00,1 Rev. 00 1 23 of 43
DATA POIT L
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CGI N/A MAIN-FD-FLW2 X149 DFWLC FEED FLOW LOOP A Reactor Feedwater Flow 2 A
LB/H N/A 0
8.5E + 6 N/A N/A S
,1 N/A Turbine Building N/A N/A N/A Cannot be predicted y
N/A Monitors flow through Venturi section in one of two 24" reactor feedwater lines into the reactor. Flow signals are used for both monitoring and control of reactor feedwater flow. DP transmitters calibrated for operating conditions.
CVI 1025-00,1 Rev. 001 24 of 43
DAA POIT LR R
C L
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximurn Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CGl N/A RCS-Pressure X151 RX PRESS WIDE RANGE DIV 1 Reactor Coolant System Pressure A
PSIG N/A 0
1,500 N/A N/A S
N/A Reactor Building, 522' Level Press alarm = 1050 +/- 15 PSIG N/A N/A Cannot be predicted N
N/A Pressure transmitter on I of 4 reference legs used for RPV level.
Provides monitoring of reactor pressure during the course of an accident. Pressure and reactor water level share a common recorder in each of 2 trains.
CVI 1025-00,1 Rev. 001 25 of 43
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A LPCI-FLOW 2 X163 RHR A LOOP FLOW Low Pressure Coolant Inj Flow 2 A
GPM N/A 0
10,000 N/A N/A S
1*'
N/A Reactor Building 501' Level N/A N/A N/A Cannot be predicted N
N/A Rated Flow = 7450 GPM. One of three LPCI loops used to provide core cooling subsequent to vessel depressurization system, initiation occurs at -129" (Level 1) reactor water level or DW Press > 1.68 PSIG.
I CVI 1025-00,1 Rev. 001 26 of 43
rfel T,-A P IBA R
FILE DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A CR-SPRAY-FL1 X164 LPCS PUMP DISCH FLOW Core Spray Cooling System Flow 1 A
GPM N/A 0
10,000 N/A N/A S
N/A Reactor Building, 471' Level See Description N/A N/A Cannot be predicted N
N/A Rated flow 6,350 GPM at 128 PSID above suction to RPV.
System initiation occurs at -129" (Level 1) Reactor Water Level or DW Press > 1.68 PSIG.
I CVI 1025-00,1 Rev. 001 27 of 43
DAT P
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CGI N/A DW-FD-SP-LV2 X167 FDR FLOOR DRAIN SUMP FLOW Drywell Floor Drain Sump Level 2 A
GPM N/A 0
10 N/A N/A S
1 N/A Reactor Building, 422' Level Alarm = 5 GPM N/A N/A Cannot be predicted N
N/A Monitors Reactor Building Floor Drain Flow to sump.
CVI 1025-00,1 Rev. 001 28of43
tt..,
k-,. '.;,.
.4 DAA O DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
AlarmITrip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A MN-STM-RAD 1 X169 MAIN STEAM LINE A RAD LEVEL Main Steam Line Rad Level 1 A
mrK/H N/A I
lE + 6 N/A N/A S
1 N/A Reactor Building, 508' Level See description N/A N/A Cannot be predicted N
N/A One of four MS Line Monitors which provide trips to RPS in the event of high rad conditions. Alarm/Trip setpoints: Upscale HiHi Trip = 3093 mR/HR (RPS trip). Upscale Hi Alarm Trip =
2400 mR/HR CVI 1025-00,1 Rev. 001 29 of 43
s:
- DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
AlarmlTrip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CGI N/A DW-FD-SP-W 1 X181 EDR EQUIPMENT DRAIN SUMP FLOW Drywell Floor Drain Sump Level 1 A
GPM N/A 0
30 N/A N/A S
1 N/A Containment Building, 422' Level Alarn = 25 GPM N/A N/A Cannot be predicted N
N/A Monitors reactor building equipment drain floor to sump.
CVI 1025-00,1 30 of 43 Rev. 001
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
AlarmlTrip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A NI-INTER-RNG X184 IRM CHANNEL A LEVEL Nuclear Inst., Intermediate Rng.
A N/A 0
125 N/A N/A S
1 N/A Reactor Core during sys operation Sce description N/A N/A Cannot be predicted N
N/A 8 IRM channels monitor neutron flux from the upper portion of the SRM range to the lower portion of the power range of RX power.
Each IRM channel contains circuits that provide SCRAM inputs to the RX protection sys when abnormally high flux levels are detected over this range. These circuits are bypassed when the RX mode switch is in the run position. 8 detectors are inserted into the core for a RX startup and are withdrawn after the RX mode switch is placed in the "run" position. Alarm/Trip setpoints: Upscale trip 120%/125% (nom setpoint) upscale alarm 108%/125% (nom setpoint).
CVI 1025-00,1 Rev. 001 31 of 43
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CGI N/A NI-POWER-RNG X194 APRM A FLUX LEVEL Nuclear Instruments, Power Range A
% PWR N/A 0
125 N/A N/A P
21 Average Reactor Core See Description N/A N/A Cannot be predicted N
N/A 6 APRM channels monitor neutron flux in the power range of RX power. Each channel contains circuits which provide SCRAM inputs to the RX protection sys when abnormally Hi flux levels are detected in this range. The LPRM detectors that provide input to each APRM channel are fixed in the core at 4 discrete core elevations. The APRM RX trip circuits are engaged when the RX mode switch is in the "run" position. Alarm/Trip setpoints:
Neutron flux upscale 118% (nom setpoint) Thermal power upscale
.66W + 51 % (nom setpoint) Neutron flux upscale alarm.66W +
42% (nom setpoint)
I I
CVI 1025-00,1 Rev. 001 32 of 43
48if I a1 DATA POIN LIBRAY REERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Des-.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm//Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A NI-SOURC-RNG X296 SRM A NEUTRON LEVEL Nuclear Inst., Source Range A
CPS N/A
.1 lE + 6 N/A N/A S
1 N/A Reactor Core during sys operation See description N/A N/A Cannot be predicted N
N/A Four SRM channels monitor neutron flux in the startup range of reactor power. Each of 4 SRM channels contain circuits which provide SCRAM inputs to the reactor protection system when abnormally high flux level conditions are detected. These circuits are used only when reactor mode switch is in "Refuel". Detectors are retracted at power levels above the startup range. Alarm/Trip setpoints: Upscale trip 2 X 10E5 CPS (nom setpoint) Upscale alarm 1 X 10E5 CPS (nom setpoint)
CVI 1025-00,1 Rev. 001 33 of 43
.t I
D IB R
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
AlarnmTrip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A REAC-VES-LV3 X327 RX WATER LEVEL UPSET RANGE Reactor Vessel Water Level 3 A
INCHES N/A 0
500 MSSKRT 0" = 527.5" from bottom of RP'V S
1 N/A Reactor Building 522' Level N/A N/A N/A Cannot be predicted y
Wet Provides monitoring of water level ranging from 120.5" below to 59.5" above the main steam line nozzle level. The bottom of the upset range overlaps the top of the wide range by 60".
CV] 1025-00,1 Rev. 001 34 of 43
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
AlarmlTrip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A SP-LEVEL I X354 SUPP POOL WATER LVL WIDE RANGE DIV 1 Suppression Pool Water Level 1 A
FEET N/A 2
52 30 FT 30 FT corresp to 0" or norm SP depth S
I-N/A Containment building, 437' level See Description N/A N/A Cannot be predicted N
N/A Provides coarse level indication of suppression pool depth. High and low level alarms are provided by narrow range instrumentation and are +0.73" and -0.73" respectively.
I CVI 1025-00,1 Rev. 001 35 of 43
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A SP-TEMP 1 X355 SUPP POOL AVERAGE TEMP DIV 1 Suppression Pool Temperature I A
DEGF N/A 50 400 N/A N/A P
4 Average Containment Building 466' Level See Description N/A N/A Cannot be predicted N
N/A Monitors suppression pool average temp at a depth of < 1 foot below the pool surface. Alarm 2 = 96.4 Deg F, Alarm 3 = 101.4 Deg F, Alarm 4 = 111.4 Deg F CVI 1025-00,1 36 of 43 Rev. 001
J -
1
- 4.
D L
R R
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Peints:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A CST-LEVEL 1 X373 COND STORAGE TANK LEVEL B Condensate Storage Tank Level 1 A
FEET 1 FT= 11,900 Gal 0
35 TNKBOT 446' 6" Instrument zero S
1, N/A Condensate Storage Tank, 471' Level 458' 9' Low level N/A N/A Cannot be predicted N
Wet Each of the two condensate storage tanks have nominal capacity of 400,000 gal. Low level alarms from each tank are provided to prevent the water level from dropping below the required reserve level for RPV makeup (67,500 GL/Tank, 135,000 gal for both tanks). The low level alarm occurs at 12' indicated water level, providing for both RPV makeup and required static head for RCIC operation.
I II CVI 1025-00,1 Rev. 001 37 of 43
I i;
.* I I
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CGI N/A EFF-GAS-RAD1 X392 RX BLDG ELEV RELEASE HI RNG RAD MON Radioactivity Of Released Gas 1 A
-N/A S
1 N/A Reactor Building, 617' Level N/A N/A N/A Cannot be predicted N
N/A Reactor Building effluent monitor CVI 1025-00,1 Rev. 001 38 of 43
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A DW-RAD 1 X432 CONTAINMENT LOCA RAD MON DIV 1 Drywell Radiation Level 1 A
R/HR N/A 1
lE+07 N/A N/A S
N/A Containment Building, 516' Level See description N/A N/A Cannot be predicted.
N N/A High range containment radiation monitoring. Alarm/Trip setpoints: Alert setpoint = 1GE4 +/- 3.6 X 10E3 RIHR.
High setpoint = 2E +6 +/- 7.2E +3 R/HR.
I CVI 1025-00,1 Rev. 001 39 of 43
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A CST-Level 2 X434 COND STORAGE TANK LEVEL A Condensate Storage Tank Level 2 A
FEET 1 Ft = 11,900 Gal 0
35 TNKBOT 446' 6" Instrument zero S
I N/A Condensate Storage Tank, 471' Level Low Lev= 458' 9" N/A N/A Cannot be predicted N
N/A Each of two condensate storage tanks have nominal capacity of 400,000 Gal. Two low level alarms for each tank are provided to prevent the water level from dropping below the required reserve level for RPV makeup (67,500 Gal/Tank, 135,000 Gal for both tanks). The low level alarm occurs at 12' indicated water level, providing for both RPV makeup and required static head for RCIC operation.
I CVI 1025-00,1 Rev. 001 40 of 43
'-1 I
DATA POINT LIBRARY REFERENCE FILE Date:
1/21/05 Reactor Unit:
CGl Data Feeder:
N/A NRC ERDS Parameter:
DW-PRESS I Point ID:
X442 Plant Specific Point Desc.:
DRYWELL PRESS HIGH RANGE DIV Generic/Cond Desc.:
Drywell Pressure 1 Analog/Digital:
A Engr Units/Dig States:
PSIG Engr Units Conversion:
N/A Minimum Instr Range:
0 Maximum Instr Range:
180 Zero Point
Reference:
N/A Reference Point Notes:
N/A PROC or SENS:
S Number of Sensors:
1 How Processed:
N/A Sensor Locations:
Reactor Building, 548' Level Alarm/Trip Set Points:
N/A NI Detector Power Supply N/A Cut-off Power Level:
NI Detector Power Supply N/A Turn-on Power Level:
Instrument Failure Mode:
Cannot be predicted Temperature Compensation N
For DP Transmitters:
Level Reference Leg:
N/A Unique System Desc.:
One of two instrument trains which provic of upper drywell pressure.
1 le wide range monitoring CVI 1025-00,1 Rev. 001 41 of 43
I '
I DATA POINM Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locaticns:
Alarm/Trip Set Points:
NI Detector Power Supp'y Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Conpensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
[ LIBRARY REFERENCE FILE 1/21/05 CGI N/A 02-CONC X456 DRYWELL 02 CONCENTRATION DIV 1 Oxygen Concentration A
N/A 0
30 N/A N/A S
1-N/A Reactor Building, 522' Level N/A N/A N/A Cannot be predicted N
N/A One of two trains used to monitor 02 concentration in primary containment subsequent to design basis accident.
CVI 1025-00,1 Rev. 001 42 of 43
"I
/J I..'
DATA POINT LIBRARY REFERENCE FILE
, Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation For DP Transmitters:
Level Reference Leg:
Unique System Desc.:
1/21/05 CG1 N/A H2-CONC 1 X471 DRYWELL H2 CONCENTRATION DIV I Hydrogen Concentration 1 A.
N/A 0.
20 N/A N/A S
1 N/A Reactor Building, 522' Level N/A N/A N/A Cannot be predicted N
N/A One of two trains used to monitor H2 concentration in primary containment subsequent to design basis accident.
CVI 1025-00,1 Rev. 001 43 of 43