ML082660147

Transmittal of Emergency Response Data System (ERDS) Data Point Library (Dpl), Revision 2

ML082660147
Person / Time
Site:	Watts Bar
Issue date:	09/17/2008
From:	Brandon M Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML082660147 (77)

Text

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 September 17, 2008 10 CFR 50, Appendix E U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:

In the Matter of

)

Docket No. 50-390 Tennessee Valley Authority

)

WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 - EMERGENCY RESPONSE DATA SYSTEM (ERDS) DATA POINT LIBRARY (DPL), REVISION 2 Enclosed is ERDS Data Point Library, Revision 2, provided pursuant to 10 CFR 50, Appendix E, Section Vl.3.a. TVA revised the DPL to update descriptive statements and explanatory notes, such as steam generator dimensions and water level at the top of the U-tubes. These descriptive changes became applicable following the steam generator replacement project during WBN's cycle 7 refueling outage, Fall 2006. The delay in this update has been documented in the WBN corrective action process.

The enclosure to this letter, Data Point Library, Revision 2, supersedes the Data Point Library, Revision 1 provided in TVA's letter dated May 14, 1999.

There are no regulatory commitments associated with this submittal. If you have any questions concerning this matter, please call me at (423) 365-1824.

Sincerely, M. K. Brandon Manager, Site Licensing and Industry Affairs Enclosure cc: See Page 2

U.S. Nuclear Regulatory Commission Page 2 September 17, 2008 Enclosures cc (Enclosures):

NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 ATTN: Patrick D. Milano, Project Manager U.S. Nuclear Regulatory Commission Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation MS 0-8 H4 Washington, DC 20555-0001 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 E-1

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 NRC POINT ID PLANT SPECIFIC ERDS ERDS POINT DESCRIPTION POINT PARAMETER NO.

1 SIMULATION 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 28 29 30 31 32 33 34 35 36 37 38 39 40 NI POWER RNG NI INTER RNG NI SOURC RNG REAC VES LEV TEMP CORE EX SUB MARGIN SG LEVEL 1/A SG LEVEL 2/B SG LEVEL 3/C SG LEVEL 4/D SG PRESS 1/A SG PRESS 2/B SG PRESS 3/C SG PRESS 4/D MN FD FL 1/A MN FD FL 2/B MN FD FL 3/C MN FD FL 4/D AX FW FL 1/A' AX FW FL 2/B AX FW FL 3/C AX FW FL 4/D HL TEMP 1/A HL TEMP 2/B HL TEMP 3/C HL TEMP 4/D CL TEMP 1/A CL TEMP 1/A CL TEMP 2/B CL TEMP 3/C CL TEMP 4/D RCS PRESSURE PRZR LEVEL RCS CHG/MU HP SI FLOW LP SI FLOW CNTMT SMP WR EFF GAS RAD EFF GAS RAD EFF LIQ RAD UN2000 UN1015 UN1014 QC0117 QC0509 QCO107 UL1001 UL1002 UL1003 UL 1004 UP 1002 UP 1003 UP 1004 UP 1005 U0410 U0430 U0450 U0470 Y0708A Y0704A Y0703A Y0709A T0419A T0439A T0459A T0479A T0406A T0406A T0426A T0446A T0466A UP 1000 QiO111 UF1016 UF1010 UF1011 UL1011 R9101A R9102A R1022A INDICATES REAL OR SIMULATED DATA POWER RNG AVG INTER RNG FLUX SOURCE RNG FLUX RVLIS MINIMUM CORE EXIT TEMP MAX MIN SUBCOOL SG 1 NR LEVEL AVG SG 2 NR LEVEL AVG SG 3 NR LEVEL AVG SG 4 NR LEVEL AVG SG 1 MS PRESSURE AVG SG 2 MS PRESSURE AVG SG 3 MS PRESSURE AVG SG 4 MS PRESSURE AVG SG 1 FW FLOW AVG SG 2 FW FLOW AVG SG 3 FW FLOW AVG SG 4 FW FLOW AVG STM GEN 1 AFW INLET FLOW STM GEN 2 AFW INLET FLOW STM GEN 3 AFW INLET FLOW STM GEN 4 AFW INLET FLOW RCS LOOP 1 HOT LEG TEMP RCS LOOP 2 HOT LEG TEMP RCS LOOP 3 HOT LEG TEMP RCS LOOP 4 HOT LEG TEMP RCS LOOP 1 COLD LEG TEMP RCS LOOP 1 COLD LEG TEMP RCS LOOP 2 COLD LEG TEMP RCS LOOP 3 COLDLEG TEMP RCS LOOP 4 COLD LEG TEMP RCS WIDE RNG PRESS AVG PRZR LEV AVG NET CHG FLO SI FLOW TOTAL RHR FLO TO TOTAL COLD LEG CNTMT SUMP LEV AVG SHIELD BLDG VENT MON EFF RATE SHIELD BLDG VENT MON EFF RATE WDS LIQUID EFFLUENT MON E-2

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 COND AlE RAD COND A/E RAD COND A/E RAD CNTMNT RAD CNTMNT RAD MAIN SL 1/A MAIN SL 2/B MAIN SL 3/C MAIN SL 4/D SG BD RAD IA SG BD RAD 2B CTMNT PRESS CTMNT TEMP H2 CONC RWST LEVEL WIND SPEED WIND SPEED WIND SPEED WIND DIR WIND DIR WIND DIR STAB CLASS STAB CLASS STAB CLASS SG LEVEL 1/A SG LEVEL 2/B SG LEVEL 3/C SG LEVEL 4/D NL NL NL NL R9061A R0001A

/

R9062A QZO1O4 QZo 111 R9055A R9056A R9057A R9058A R1020A R1021A UP6000 U2515 UY1005 UL 1000 MET001 MET002 MET003 MET004 MET005 MET006 MET007 MET008 MET009 L0403A L0423A L0443A L0463A U0400 U0420 U0440 U0420 COND VAC VENT NOBLE GAS RAD MON COND VAC VENT NOBLE GAS RAD MON COND VAC VENT NOBLE GAS RAD MON UPPER CONTAINMENT RADIATION LOWER CONTAINMENT RADIATION ST GEN I DISCH RAD MON ST GEN 2 DISCH RAD MON ST GEN 3 DISCH RAD MON ST GEN 4 DISCH RAD MON STEAM GEN BLDN MON STEAM GEN BLDN MON CNTMT PRESSURE AVG CTMNT HIGHEST TEMP H2 CONC AVG RWST LEVEL AVG 91M VECTOR WIND SPEED (15 MIN AVG) 46M VECTOR WIND SPEED (15 MIN AVG) 1OM VECTOR WIND SPEED (15 MIN AVG) 91M VECTOR WIND DIR (15 MIN AVG) 46M VECTOR WIND DIR (15 MIN AVG) 10M VECTOR WIND DIR (15 MIN AVG)

STABILITY CLASS UPPER STABILITY CLASS INTERMEDIATE STABILITY CLASS LOWER STM GEN #1 LEVEL XMTR STM GEN #2 LEVEL XMTR STM GEN #3 LEVEL XMTR STM GEN #4 LEVEL XMTR RC LOOP #1 AVG FLOW RC LOOP #2 AVG FLOW RC LOOP #3AVG FLOW RC LOOP #4AVG FLOW E-3

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 1.

SIMULATION INDICATES REAL OR SIMULATED DATA Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoint:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

11/01/95 WB1 N/A Not Listed SIMULATION INDICATES REAL OR SIMULATED DATA Real or Simulated Data D

REAL/SIMUL N/A N/A N/A N/A N/A P

0 0 IF REAL, 1 IF SIMULATED N/A N/

N/A N/A N/A N

N/A This point is used to indicate whether the data is coming from the unit or from the simulator.

E-4

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 2.

NI POWER RNG UN2000 Reactor Power Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoint:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

11/01/95 WB1 N/A NI POWER RNG UN2000 POWER RNG AVG Reactor Power A

0 - 1OV 0

120 N/A N/A 0 - 120% power (linear)

P 4

Average Excore detectors Overpower reactor trip = 109%

N/A N/A Probable downscale (no forcing function)

N N/A From ICS inputs for 1-NE-92-41,42,43,44.

Unique System Desc:

E-5

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 3.

NI INTER RNG UN1015 Reactor Power - Intermediate Rng Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoint:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

11/01/95 WB1 N/A NI INTER RNG UN1015 INTER RNG FLUX Reactor Power - Intermediate Rng A

0 V - 1E 200% power (log) 1E-8 200 N/A N/A P

2 Average AZ 0 degree and 180 degree excore Reactor trip - 25% power N/A N/A Probable downscale (no forcing function)

N N/A Unique System Desc:

Average ofNMD-92-135-D and NMD-92-136-E (channel N36).

E-6

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 4.

NI SOURC RNG UN1014 Reactor Power - Source Rng Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoint:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

11/01/95 WB1 N/A NI SOURC RNG UN 1014 SOURCE RNG FLUX Reactor Power - Source Rng A

CPS 0 - 5V 1 - 1E+06 CPS (log) 1 1E+06 N/A N/A P

2 Average AZ 0 degree and 180 degree excore Reactor trip - 10E5 CPS 1.66 x 10-4 1.49 x 10-4 Probable downscale (no forcing function)

N N/A Average of NMD-92-13 1-D and NMD-92-132-E detectors.

E-7

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 5.

REAC VES LEV QCO117 Reactor Vessel Water Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A REAC VES LEV QC0117 RVLIS MINIMUM Reactor Vessel Water Level A

0 - 10V = 0 - 100% (linear) 0 100 RV BOT TAF = 62%

P 2

Minimum Remote location in the penetration rooms N/A N/A N/A Out of Range Y

WET This is provided by D/A output from the Westinghouse ICCM system. Minimum of LCP-94-7902 and LCP-94-8002. Top of core = 62%.

E-8

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 6.

TEMP CORE EX QC0509 Highest Core Exit Temp Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A TEMP CORE EX QC0509 CORE EXIT TEMP MAX Highest Core Exit Temp A

DEGF 0 - 10V = 40 - 2300 DEGF (linear) 40 2300 N/A N/A P

65 Highest Core exit N/A N/A N/A Low N

N/A Unique System Desc:

Provided through Westinghouse ICCM system. Highest of 65 incore thermocouples.

E-9

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 7.

SUB MARGIN QC0107 Saturation Temp - Highest CET Date:

Reactor Unit:

Data feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A SUB MARGIN QCO 107 MIN SUBCOOL Saturation Temp - Highest CET A

DEGF 0 - 10V = 200 DEGF (linear)

-35 200 N/A N/A P

2 Minimum N/A N/A N/A N/A Low N

N/A Unique System Desc:

Provided by Westinghouse ICCM system. Minimum of LCP-94-7902 (T4003) and LCP-94-8002 (T4004).

E-10

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 8.

SG LEVEL 1/A UL1001 Steam Generator 1 Water Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

08/19/08 WB1 N/A SG LEVEL 1/A UL1001 SG 1 NR LEVEL AVG Steam Generator 1 Water Level A

0 - 100% NR = 0" - 233" NR = 381" -614" WR 0

100 See "Unique System Desc."

22% NR = Top of "U" tubes at no load P

2 Average Remote location outside of polar crane wall Low at 17%

N/A N/A Out of Range Y

WET Steam Generator 1 water level. Average of I-LT-3-39 and -42.

0-100% span on steam generator narrow range level transmitters correspond to 62-100% span on wide range level instrumentation.

E-11

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 9.

SG LEVEL 2/B UL1002 Steam Generator 2 Water Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

08/19/08 WBI N/A SG LEVEL 2/B UL1002 SG 2 NR LEVEL AVG Steam Generator 2 Water Level A

0 - 100% NR = 0" - 233" NR = 381" -614" WR 0

100 See "Unique System Desc."

22% NR = Top of"U" tubes at no load P

2 Average Remote location outside of polar crane wall Low at 17%

N/A N/A Out of Range Y

WET Steam Generator 2 water level. Average of 1-LT-3-52 and -55.

0-100% span on steam generator narrow range level transmitters correspond to 62-100% span on the wide range level instrumentation.

E-12

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 10.

SG LEVEL 3/C UL1003 Steam Generator 3 Water Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

08/19/08 WB1 N/A SG LEVEL 3/C UL 1003 SG 3 NR LEVEL AVG Steam Generator 3 Water Level A

0 - 100% NR = 0" - 233" NR = 381"- 614" WR 0

100 See "Unique System Desc."

22% NR = Top of "U" tubes at no load P

2 Average Remote location outside of polar crane wall Low at 17%

N/A N/A Out of Range Y

WET Steam Generator 3 water level. Average of 1-LT-3-94 and -97.

0-100% span on steam generator narrow range level transmitters correspond to 62-100% span on the wide range level instrumentation.

E-13

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 11.

SG LEVEL 4/D UL1004 Steam Generator 4 Water Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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:

NID power cutoff level:

NID power cut-on level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

08/19/08 WBl N/A SG LEVEL 4/D UL 1004 SG 4 NR LEVEL AVG Steam Generator 4 Water Level A

0 - 100% NR = O" - 233" NR = 381"- 614" WR 0

100 See "Unique System Desc."

22% NR = Top of "U" tubes at no load P

2 Average Remote location outside of polar crane wall Low at 17%

N/A N/A Out of Range Y

WET Steam Generator 4 water level. Average of 1-LT-3-107 and -110.

0-100% span on steam generator narrow range level transmitters corresponds to 62-100% span on the wide range level instrumentation.

E-14

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 12.

SG PRESS 1/A UP1002 Steam Generator 1 Pressure Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

11/01/95 WB1 N/A SG PRESS 1/A UP 1002 SG 1 MS PRESSURE AVG Steam Generator 1 Pressure A

PSIG N/A 0

1300 N/A N/A P

2 Average Remote location in penetration room N/A N/A N/A Out of Range N

WET Steam Generator 1 pressure. Average of 1-PT-1 -2A and 1-PT-1-2B.

Unique System Desc:

E-15

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 13.

SG PRESS 2/B UP 1003 Steam Generator 2 Pressure Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

11/01/95 WB1 N/A SG PRESS 2/B UP1003 SG 2 MS PRESSURE AVG Steam Generator 2 Pressure A

PSIG N/A 0

1300 N/A N/A P

2 Average Remote location in north valve room N/A N/A N/A Out Of Range N

WET Steam Generator 2 pressure. Average of 1-PT-1-9A and 1-PT-1-9B.

Unique System Desc:

E-16

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 14.

SG PRESS 3/C UP 1004 Steam Generator 3 Pressure Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power'Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

11/01/95 WB1 N/A SG PRESS 3/C UP 1004 SG 3 MS PRESSURE AVG Steam Generator 3 Pressure A

PSIG N/A 0

1300 N/A N/A P

2 Average Remote location in north valve room N/A N/A N/A Out of Range N

WET Steam Generator 3 pressure. Average of 1-PT-1-20A and 1-PT-i -20B.

.E-17

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 15.

SG PRESS 4/D UP1005 Steam Generator 4 Pressure Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

11/01/95 WB1 N/A SG PRESS 4/D UP 1005 SG 4 MS PRESSURE AVG Steam Generator 4 Pressure A

PSIG N/A 0

1300 N/A N/A P

2 Average Remote location in penetration room N/A N/A N/A Out of Range N

WET Steam Generator 4 pressure. Average of 1-PT-1 -27A and 1-PT-i -27B.

E-18

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 16.

MN FD FL 1/A U0410 Stm Gen 1 Main Feedwater Flow Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A MN FD FL 1/A U0410 SG 1 FW FLOW AVG Stm Gen 1 Main Feedwater Flow A

MBH N/A 0

4.50 N/A N/A P

2 Average Stm Gen Feedwater Line 1, Aux Bldg N/A N/A N/A Out of Range Y

WET Steam Generator 1 main feedwater flow. Average of 1-FT-3-35A and 1-FT-3-35B.

Unique System Desc:

E-19

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT. 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 17.

MN FD FL 2/B U0430 Stm Gen 2 Main Feedwater Flow Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A MN FD FL 2/B U0430 SG 2 FW FLOW AVG Stm Gen 2 Main Feedwater Flow A

MBH N/A 0

4.50 N/A N/A P

2 Average Stm Gen Feedwater Line 2, Aux Bldg N/A N/A N/A Out of Range Y

WET Steam Generator 2 main feedwater flow. Average of l-FT-3-48A and 1-FT-3-48B.

E-20

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 18.

MN FD FL 3/C U0450 Stm Gen 3 Main Feedwater Flow Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A MN FD FL 3/C U0450 SG 3 FW FLOW AVG Stm Gen 3 Main Feedwater Flow A

MBH N/A 0

4.50 N/A N/A P

2 Average Stm Gen Feedwater Line 3, Aux Bldg N/A N/A N/A Out of Range Y

WET Steam Generator 3 main feedwater flow. Average of l-FT-3-90A and 1-FT-3-90B.

Unique System Desc:

E-21

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 19.

MN FD FL 4/D U0470 Stm Gen 4 Main Feedwater Flow Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A MN FD FL 4/D U0470 SG 4 FW FLOW AVG Stm Gen 4 Main Feedwater Flow A

MBH N/A 0

4.50 N/A N/A P

2 Average Stm Gen Feedwater Line 4, Aux Bldg N/A N/A N/A Out of Range Y

WET Steam Generator 4 main feedwater flow. Average of 1-FT-3-103A and 1-FT-3-103B.

E-22

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 20.

AX FW FL 1/A Y0708A Stm Gen 1 Auxiliary FW Flow Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A AX FW FL 1/A Y0708A STM GEN 1 AFW INLET FLOW Stm Gen 1 Auxiliary FW Flow A

GPM 100-500 MV = 0-700 GPM 0

700 N/A N/A S1 N/A Downstream of MDAFW, TDAFW tie to S/G 1 N/A N/A N/A Low N

N/A There are two (2) electric and one (1) turbine-driven AFWPS.

Each electric pump feeds two (2) steam generators and the turbine-driven pump feeds all four (4) steam generators. The electric and turbine-driven AFWPs share the same piping to each steam generator. The flow element is located in the shared piping.

E-23

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 21.

AX FW FL 2/B Y0704A Stm Gen 2 Auxiliary FW Flow Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A AX FW FL 2/B Y0704A STM GEN 2 AFW INLET FLOW Stm Gen 2 Auxiliary FW Flow A

GPM.

100-500 MV = 0-700 GPM 0

700 N/A N/A S

1 N/A Downstream of MDAFW, TDAFW tie to S/G 2 N/A N/A N/A Low N

N/A There are two (2) electric and one (1) turbine-driven AFWPS.

Each electric pump feeds two (2) steam generators, and the turbine-driven pump feeds all four (4) steam generators. The electric and turbine-driven AFWPs share the same piping to each steam generator. The flow element is located in the shared piping.

E-24

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 22.

AX FW FL 3/C Y0703A Stm Gen 3 Auxiliary FW Flow Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A AX FW FL 3/C Y0703A STM GEN 3 AFW INLET FLOW Stm Gen 3 Auxiliary FW Flow A

GPM 100-500 MV = 0-700 GPM 0

700 N/A N/A S1 N/A Downstream of MDAFW, TDAFW tie to S/G 3 N/A N/A N/A Low N

N/A There are two (2) electric and one (1) turbine-driven AFWPS.

Each electric pump feeds two (2) steam generators and the turbine-driven pump feeds all four (4). steam generators. The electric and turbine-driven AFWPs share the same piping to each steam generator. The flow element is located in the shared piping.

E-25

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 23.

AX FW FL 4/D Y0709A Stm Gen 4 Auxiliary FW Flow Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A AX FW FL 4/D Y0709A STM GEN 4 AFW INLET FLOW Stm Gen 4 Auxiliary FW Flow A

GPM 100-500 MV = 0-700 GPM 0

700 N/A N/A S

1 N/A Downstream of MDAFW, TDAFW tie to S/G 4 N/A N/A N/A Low N

N/A There are two (2) electric and one (1) turbine-driven AFWPS.

Each electric pump feeds two (2) steam generators, and the turbine-driven pump feeds all four (4) steam generators. The electric and turbine-driven AFWPs share the same piping to each steam generator. The flow element is located in the shared piping.

E-26

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 24.

HL TEMP 1/A T0419A Stm Gen 1 Inlet Temp Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A HL TEMP 1/A T0419A RCS LOOP 1 HOT LEG TEMP Stm Gen 1 Inlet Temp A

DEGF 1-5 VDC = 0-700 DEGF 0

700 N/A N/A S

1 N/A On Loop 1 RCS hot leg piping N/A N/A N/A Low N

N/A RCS hot leg temperature is used in event of recovery to provide information for manual control of RCS temperature, control of the Emergency Core Cooling System (ECCS) pumps and Reactor Coolant Pumps (RCPs), and to verify natural circulation or increase blow down. The temperature indication is also used to control RCS pressure and temperature within required limits.

E-27

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 25.

HL TEMP 2/B T0439A Stm Gen 2 Inlet Temp Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A HL TEMP 2/B T0439A RCS LOOP 2 HOT LEG TEMP Stm Gen 2 Inlet Temp A

DEGF 1-5 VDC = 0-700 DEGF 0

700 N/A N/A S

1 N/A On Loop 2 RCS hot leg piping N/A N/A N/A Low N

N/A RCS hot leg temperature is used in event of recovery to provide information for manual control of RCS temperature, control of the ECCS pumps and RCPs, and to verify natural circulation or increase blow down. The temperature indication is also used to control RCS pressure and temperature within required limits.

E-28

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 26.

HL TEMP 3/C T0459A Stm Gen 3 Inlet Temp Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A HL TEMP 3/C T0459A RCS LOOP 3 HOT LEG TEMP Stm Gen 3 Inlet Temp A

DEGF 1-5 VDC = 0-700 DEGF 0

700 N/A N/A S

1 N/A On Loop 3 RCS hot leg piping N/A N/A N/A Low N

N/A RCS hot leg temperature is used in event of recovery to provide information for manual control of RCS temperature, control of ECCS pumps and RCPs, and to verify natural circulation or increase blow down. The temperature indication is also used to control RCS pressure and temperature within required limits.

E-29

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 27.

HL TEMP 4/D T0479A Stm Gen 4 Inlet Temp Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A HL TEMP 4/D T0479A RCS LOOP 4 HOT LEG TEMP Stm Gen 4 Inlet Temp A

DEGF 1-5 VDC = 0-700 DEGF 0

700 N/A N/A S

1 N/A On Loop 4 RCS hot leg piping N/A N/A N/A Low N

N/A RCS hot leg temperature is used in event of recovery to provide information for manual control of RCS temperature, control of ECCS pumps and RCPs, and to verify natural circulation or increase blow down. The temperature indication is also used to control RCS pressure and temperature within required limits.

E-30

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 28.

CL TEMP 1/A T0406A Stm Gen 1 Outlet Temp Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A CL TEMP 1/A T0406A RCS LOOP 1 COLD LEG TEMP Stm Gen 1 Outlet Temp A

DEGF 1-5 VDC 0-700 DEGF 0

700 N/A N/A S1 N/A On Loop 1 RCS cold leg piping N/A N/A N/A Low N

N/A RCS cold leg temperature is used in event of recovery to maintain proper relationship between RCS pressure and temperature while cooling down, and to provide information to manually control RCS temperature by controlling Auxiliary Feedwater (AFW) flow, steam generator pressure, and Residual Heat Removal (RHR). The temperature indication is also used in maintaining stable plant conditions and verifying natural circulation.

E-31

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 29.

CL TEMP 2/B T0426A Stm Gen 2 Outlet Temp Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:.

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A CL TEMP 2/B T0426A RCS LOOP 2 COLD LEG TEMP Stm Gen 2 Outlet Temp A

DEGF 1-5 VDC = 0-700 DEGF 0

700 N/A N/A S

1 N/A On Loop 2 RCS cold leg piping N/A N/A N/A Low N

N/A RCS cold leg temperature is used in event of recovery to maintain proper relationship between RCS pressure and temperature while cooling down, and to provide information to manually control RCS temperature by controlling AFW flow, steam generator pressure, and RHR. The temperature indication is also used in maintaining stable plant conditions and verifying natural circulation.

E-32

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 30.

CL TEMP 3/C T0446A Stm Gen 3 Outlet Temp Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A CL TEMP 3/C T0446A RCS LOOP 3 COLD LEG TEMP Stm Gen 3 Outlet Temp A

DEGF 1-5 VDC = 0-700 DEGF 0

700 N/A N/A S

1 N/A On Loop 3 RCS cold leg piping N/A N/A N/A Low N

N/A RCS cold leg temperature is used in event of recovery to maintain proper relationship between RCS pressure and temperature while cooling down, and to provide information to manually control RCS temperature by controlling AFW flow, steam generator pressure, and RHR. The temperature indication is also used in maintaining stable plant conditions and verifying natural circulation.

E-33

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS point number 31.

CL TEMP 4/D T0466A Stm Gen 4 Outlet Temp Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A CL TEMP 4/D T0466A RCS LOOP 4 COLD LEG TEMP Stm Gen 4 Outlet Temp A

DEGF 1-5 VDC = 0-700 DEGF 0

700 N/A N/A S

1 N/A On Loop 4 RCS cold leg piping N/A N/A N/A Low N

N/A Unique System Desc:

RCS cold leg temperature is used in event of recovery to maintain proper relationship between RCS pressure and temperature while cooling down, and to provide information to manually control RCS temperature by controlling AFW flow, steam generator pressure, and RHR. The temperature indication is also used in maintaining stable plant conditions and verifying natural circulation.

E-34

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 32.

RCS PRESSURE UP 1000 Reactor Coolant System Pressure Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

11/01/95 WB1 N/A RCS PRESSURE UP 1000 RCS WIDE RNG PRESS AVG Reactor Coolant System Pressure A

PSIG 1-5 VDC = 0-3000 PSIG 0

3000 N/A N/A P

2 Average RCS Hot Legs 1 and 3 Low: 1970 psig, Rx trip; High:2385 psig, Rx trip N/A N/A Low N

N/A RCS pressure determined by this point is the average of two (2) signals which measure wide range hot leg pressures (1-PT-68-63 and -64). RCS pressure indication is utilized by the operators to identify events for Safety Injection (SI) actuation and termination, starting and stopping RHR pumps, and controlling cooldown to prevent PTS. The alarm trip setpoints are actuated by pressurized pressure transmitters at the given setpoints.

E-35

ENCLOSURE WATTS BARNUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 33.

PRZR LEVEL QI0l11 Primary System Pressurizer Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A PRZR LEVEL QIO 11 PRZR LEV AVG Primary System Pressurizer Level A

1-5 V = 0-100%

0 100 See "Unique System Desc."

Top of Heater = 14%

P 3

Average TAPs from Pressurizer High at 92% reactor trip N/A N/A Low N

WET The pressurizer level is an averaged signal from three (3) level transmitters (1-LT-68-320, -335, -339). Zero reference is bottom of cylindrical shell.

E-36

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS point number 34.

RCS CHG/MU UF1016 Primary System Charging/Makeup Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

11/01/95 WB1 N/A RCS CHG/MU UF1016 NET CHG FLO Primary System Charging/Makeup A

GPM N/A

-200 176 N/A N/A P

6 Subtraction Charging pump, RCP seal/return, RCS letdown N/A N/A N/A Multiple, due to number of sensors N

N/A The net charging flow is calculated by subtracting RCP seal return and CVCS letdown flow from the discharge flow of the charging pump.

Unique System Desc:

E-37

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 35.

HP SI FLOW UF11010 High Pressure Safety Injection Flow Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

11/01/95 WB1 N/A HP SI FLOW UF1010 SI FLOW TOTAL High Pressure Safety Injection Flow A

GPM N/A 0

1600 N/A N/A P

2 Sum Discharge of Safety Injection (SI) pumps N/A N/A N/A Low N

N/A Unique System Desc:

The total flow is measured by adding the discharge flow rates from two (2) SI pumps. The total accident flow rates for cold leg injection or recirculation and hot leg recirculation can be monitored by this point (sum of 1-FT-63-20 and -151).

E-38

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 36.

LP SI FLOW UF1011 Low Pressure Safety Injection Flow Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

11/01/95 WB1 N/A LP SI FLOW UF1011 RHR FLO TO TOTAL COLD LEG Low Pressure Safety Injection Flow A

GPM N/A 0

11000 N/A N/A P

4 Average RHR Cold Legs 2,3, and 1,4 Piping N/A N/A N/A Low N

N/A Unique System Desc:

The RHR cold leg flow rate value is calculated by summing the flow from Cold Legs 2 and 3 with the flow from Cold Legs 1 and

4. Flow sensors include 1-FT-63-91A and -91B, 1-FT-63-92A and -92B.

E-39

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS point number 37.

CNTMT SMP WR UL1O0 1 Containment Sump Wide Rng Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A CNTMT SMP WR UL 1011 CNTMT SUMP LEV AVG Containment Sump Wide Range Level A

INCHES 1-5 V = 0-200 INCHES 0

200 CNTFLR N/A P

4 Average, redundant sensor algorithm Containment sump N/A N/A N/A Low N

N/A The containment average sump level is calculated by a redundant sensor algorithm using four (4) sump level transmitters (LT-63-180, -181, -182 and -183).

E-40

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN).UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 38.

EFF GAS RAD R9101A Release Rate of Radioactive Gases Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A EFF GAS RAD R9101A SHIELD BLDG VENT MON EFF RATE Release Rate of Radioactive Gases A

mCi/sec N/A 1.OE-2 mCi/sec 1.OE 10 mCi/sec N/A N/A S

1 Sample activity times exhaust flow rate Auxiliary Building N/A N/A N/A Low on loss of power N

N/A Unique System Desc:

Release rate for Unit 1 Shield Building exhaust via Purge-A, Purge-B, ABGTS-A, EGTS and Waste Gas. See R9102A for ABGTS-B via Unit 2 Shield Building exhaust.

E-41

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 39.

EFF GAS RAD R9102A Release Rate of Radioactive Gases Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A EFF GAS RAD R9102A SHIELD BLDG VENT MON EFF RATE Release Rate of Radioactive Gases A

mCi/sec N/A 1.OE-2 mCi/sec L.OE10 mCi/sec N/A N/A S

1 Sample activity times exhaust flow rate Auxiliary Building N/A N/A N/A Low on loss of power N

N/A Unique System Desc:

Release rate for ABGTS-B through Unit 2 Shield Building exhaust.

E-42

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 40.

EFF LIQ RAD R1022A Radioactivity of Released Liquid Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A EFF LIQ RAD R1022A WDS LIQUID EFFLUENT MON Radioactivity of Released Liquid A

CPM N/A 1.0El 1.0E7 N/A N/A S

1 Antilog Auxiliary Building N/A N/A N/A Low on loss of power N

N/A Waste Disposal System liquid effluent. This computer point is in counts per minute (cpm).

E-43

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)-

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 41.

COND A/E RAD R9061A Cond Air Ejector Radioactivity Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A COND A/E RAD R9061A COND VAC VENT NOBLE GAS RAD MON Cond Air Ejector Radioactivity A

CPM N/A 10 1.0E6 N/A N/A S

1 N/A Turbine Building N/A N/A N/A Low on loss of power N

N/A Condenser Air Ejector Mid-Range Noble Gas Monitor. This is one of three computer points needed to cover full range, required for Condenser Air Ej ector Radiation.

E-44

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 42.

COND A/E RAD R0001A Cond Air Ejector Radioactivity Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A COND A/E RAD R0001A COND VAC VENT NOBLE GAS RAD MON Cond Air Ejector Radioactivity A

CPM N/A 10 L.0E7 N/A N/A S

1 Antilog Turbine Building N/A N/A N/A Low on loss of power N

N/A Condenser Air Ejector Low Range Noble Gas Monitor. This is one of three computerpoints needed to cover full range, required for Condenser Air Ejector Radiation.

Unique System Desc:

E-45

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 43.

COND A/E RAD R9062A Cond Air Ejector Radioactivity Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A COND A/E RAD R9062A COND VAC VENT NOBLE GAS RAD MON Cond Air Ejector Radioactivity A

CPM N/A 10 L.0E6 N/A N/A S

1 N/A Turbine Building N/A N/A N/A Low on loss of power N

N/A Condenser Air Ejector High-Range Noble Gas Monitor. This is one of three computer points needed to cover full range, required for Condenser Air Ejector Radiation.

Unique System Desc:

E-46

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 44.

CNTMNT RAD QZO 104 Containment Radiation Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A CNTMNT RAD QZO 104 UPPER CONTAINMENT RADIATION Containment Radiation Level A

R/hour N/A 1.OEO R/hour l.0E8 R/hour N/A N/A P

2 Average of Antilog Upper containment N/A N/A N/A Low on loss of power N

N/A Upper Containment High Range Area Monitor. Inputs are 1-RE-90-271 and 1-RE-90-272.

E-47

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 45.

CNTMNT RAD QZ01 11 Lower Containment Radiation Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A CNTMNT RAD QZO 111 LOWER CONTAINMENT RADIATION Lower Containment Radiation Level A

R/hour N/A 1.OEO R/hour 1.0E8 R/hour N/A N/A P

2 Average of Antilog Lower containment N/A N/A N/A Low on loss of power N

N/A Unique System Desc:

Lower Containment High Range Area Monitor. Inputs are 1-RE-90-273 and 1-RE-90-274.

E-48

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM.(ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 46.

MAIN SL 1/A R9055A Stm Gen 1 Steam Line Rad Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A MAIN SL 1/A R9055A ST GEN 1 DISCH RAD MON Stm Gen 1 Steam Line Rad Level A

mR/hr N/A 1.OE-02 1.0E+07 N/A N/A S

1 Antilog Main Steam Line Loop 1 prior to ATM reliefs N/A N/A N/A Low on loss of power N

N/A Main Steam Line 1 radioactivity monitor (Rad Monitor 1-RM-90-42 1). Sensitivity is 3.72E-03 mCi/cc per mR/hr.

E-49

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 47.

MAIN SL 2/B R9056A Stm Gen 2 Steam Line Rad Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:.

Temperature Compensation:

Level Reference Leg:

04/30/99 WBl N/A MAIN SL 2/B R9056A ST GEN 2 DISCH RAD MON Stm Gen 2 Steam Line Rad Level A

mR/hr N/A 1.OE-02 1.OE+07 N/A N/A S

1 Antilog Main Steam Line Loop 2 prior to ATM reliefs N/A N/A N/A Low on loss of power N

N/A Main Steam Line 2 radioactivity monitor (Rad Monitor 1-RM-90-422). Sensitivity is 3.72E-03 mCi/cc per mR/hr.

Unique System Desc:

E-50

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 48.

MAIN SL 3/C R9057A Stm Gen 3 Steam Line Rad Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

04/30/99 WB1 N/A MAIN SL 3/C R9057A ST GEN 3 DISCH RAD MON Stm Gen 3 Steam Line Rad Level A

mR/hr N/A 1.OE-02 1.0E+07 N/A N/A S

1 Antilog Main Steam Line Loop 3 prior to ATM reliefs N/A N/A N/A Low on loss of power N

N/A Main Steam Line 3 radioactivity monitor (Rad Monitor 1-RM-90-423). Sensitivity is 3.72E-03 mCi/cc per mR/hr.

E-51

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 49.

MAIN SL 4/D R9058A Stm Gen 4 Steam Line Rad Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A MAIN SL 4/D R9058A ST GEN 4 DISCH RAD MON Stm Gen 4 Steam Line Rad Level A

mR/hr N/A 1.OE-02 1.OE+07 N/A N/A S

1 Antilog Main Steam Line Loop 4 prior to ATM reliefs N/A N/A N/A Low on loss of power N

N/A Main Steam Line 4 radioactivity monitor (Rad Monitor 1-RM-90-424). Sensitivity is 3.72E-03 mCi/cc per mR/hr.

Unique System Desc:

E-52

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 50.

SG BD RAD IA R1020A Stm Gen Header Blowdown Rad Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A SG BD RAD IA R1020A STEAM GEN BLDN MON Stm Gen Header Blowdown Rad Level A

CPM N/A 1.OEl 1.0E7 N/A N/A S

1 Antilog Turbine Building N/A N/A N/A Low on loss of power N

N/A Steam Generator Blowdown Effluent Liquid Monitor.

Unique System Desc:

E-53

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 51.

SG BD RAD 2B R1021A Stm Gen Header Blowdown Rad Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A SG BD RAD 2B R1021A STEAM GEN BLDN MON Stm Gen Header Blowdown Rad Level A

CPM N/A 1.OE1 L.0E7 N/A N/A S

1 Antilog Turbine Building N/A N/A N/A Low on loss of power N

N/A Steam Generator Blowdown Effluent Liquid Monitor.

Unique System Desc:

E-54

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 52.

CTMNT PRESS UP6000 Containment Pressure Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

11/01/95 WB1 N/A CTMNT PRESS UP6000 CNTMT PRESSURE AVG Containment Pressure A

PSIG N/A

-2 15 N/A N/A P

2 Average Annulus N/A N/A N/A Out of Range N/A N/A Unique System Desc:

Containment pressure. Average of 1-PDT-30-44 and -45.

E-55

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 53.

CTMNT TEMP U2515 Containment Temperature Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

11/01/95 WB1 N/A CTMNT TEMP U2515 CTMNT HIGHEST TEMP Containment Temperature A

DEGF N/A 40 175 N/A N/A P

16 Maximum value Various areas inside containment N/A N/A N/A Fail low N

N/A Unique System Desc:

Maximum containment air temperature. Maximum of TE 21 OA through TE-30-2 OP from ICS computer E-56

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 54.

H2 CONC UY1005 Containment H2 Concentration Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

11/01/95 WB1 N/A H2 CONC UY1005 H2 CONC AVG Containment H2 Concentration A

N/A 0

10 N/A N/A P

2 Average Sample line from upper/lower containment N/A N/A N/A Downscale on loss of power N

N/A Samples H2 gas concentration in containment. Maximum of 1-XM-43-200 and 1-XM-43-210.

E-57

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 55.

RWST LEVEL UL1000 Refueling Water Storage Tank Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

11/01/95 WB1 N/A RWST LEVEL UL 1000 RWST LEVEL AVG Refueling Water Storage Tank Level A

1% is 3500 gallons 0

100 27.6" 25,000 GAL below zero reference P

2 Average, redundant sensor algorithm RWST taps 25,000 GAL in tank below buttn N/A N/A N/A Low N

N/A The RWST average level is calculated by a redundant sensor algorithm from two (2) RWST level transmitters (LT-63-50 and

-51).

E-58

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 56.

WIND SPEED MET001 Wind Speed - Upper Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:.

Plant Spec 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 Setpoints:

NID power cutoff level:

NID power cut-on level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

11/01/95 WB1 N/A WIND SPEED MET001 91M VECTOR WIND SPEED (15 MIN AVG)

Wind Speed - Upper Level A

m/sec N/A 0

44.6 N/A N/A S

1 N/A At the 91 meter level of the met tower N/A N/A N/A Low N/A N/A N/A E-59

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 57.

WIND SPEED MET002 Wind Speed - Intermediate Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:,

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

11/01/95 WB1 N/A WIND SPEED MET002 46M VECTOR WIND SPEED (15 MIN AVG)

Wind Speed - Intermediate Level A

m/sec N/A 0

44.6 N/A N/A S

1 N/A At the 46 meter level of the met tower N/A N/A N/A Low N/A N/A N/A E-60

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 58.

WIND SPEED MET003 Wind Speed - Lower Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

11/01/95 WB1 N/A WIND SPEED MET003 1OM VECTOR WIND-SPEED (15 MIN AVG)

Wind Speed - Lower Level A

m/sec N/A 0

44.6 N/A N/A S

1 N/A At the 10 meter level of the met tower N/A N/A N/A Low N/A N/A N/A E-61

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 59.

WIND DIR

.MET004 Wind Direction - Upper Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

11/01/95 WB1 N/A WIND DIR MET004 91M VECTOR WIND DIR (15 MIN AVG)

Wind Direction - Upper Level A

DEG N/A 0

360 N/A N/A S1 N/A At the 91 meter level of the met tower N/A N/A N/A Low N/A N/A N/A E-62

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 60.

WIND DIR MET005 Wind Direction - Intermediate Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID power cut-on level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

11/01/95 WB1 N/A WIND DIR MET005 46M VECTOR WIND DIR (15 MIN AVG)

Wind Direction - Intermediate Level A

DEG N/A 0

360 N/A N/A S1 N/A At the 46 meter level of the met tower N/A N/A N/A Low N/A N/A N/A E-63

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 61.

WIND DIR MET006 Wind Direction - Lower Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

11/01/95 WB1 N/A WIND DIR MET006 1OM VECTOR WIND DIR (15 MIN AVG)

Wind Direction - Lower Level A

DEG N/A 0

360 N/A N/A S

1 N/A At the 10 meter level of the met tower N/A N/A N/A Low N/A N/A N/A E-64

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 62.

STAB CLASS MET007 Air Stability Upper Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

11/01/95 WB1 N/A STAB CLASS MET007 STABILITY CLASS UPPER Air Stability Upper N/A STABA N/A N/A N/A N/A N/A P

2 N/A N/A N/A N/A N/A Low N/A N/A Differential temperature upper-lower (degrees C).

Unique System Desc:

Difference

-1.9

-1.7

-1.5

-0.5 1.5 4.0

-1.9

-1.7

-1.5

-0.5 1.5 4.0 Stability Class A

B C

D E

F G

Point Value 1

2 3

4 5

6 7

E-65

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 63.

STAB CLASS MET008 Air Stability Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

11/01/95 WB1 N/A STAB CLASS MET008 STABILITY CLASS INTERMEDIATE Air Stability N/A STABA N/A N/A N/A N/A N/A P

2 N/A N/A N/A N/A N/A Low N/A N/A Differential temperature upper-intermediate (degrees C).

Unique System Desc:

Difference

-1.9

-1.7

-1.5

-0.5 1.5 4.0

-1.9

-1.7

-1.5

-0.5 1.5 4.0 Stability Class A

B C

D E

F G

Point Value 1

2 3

4 5

6 7

E-66

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 64.

STAB CLASS MET009 Air Stability Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

Difference

-1.9

-1.7

-1.5

-0.5 1.5 4.0 11/01/95 WB1 N/A STAB CLASS MET009 STABILITY CLASS LOWER Air Stability N/A STABA N/A N/A N/A N/A N/A P

2 N/A N/A N/A N/A N/A Low N/A N/A Differential temperature intermediate-lower (degrees C).

-1.9

-1.7

-1.5

-0.5 1.5 4.0 Stability Class A

B C

D E.

F G

Point Value 1

2 3

4 5

6 7

E-67

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 65.

SG LEVEL 1/A L0403A Stm Gen 1 Wide Rng Water Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

08/19/08 WB1 N/A SG LEVEL 1/A L0403A STM GEN #1 LEVEL XMTR Stm Gen 1 Wide Rng Water Level A

0 - 100% WR = 0 - 614 inches WR 0

100 LOWTAP See "Unique System Desc."

S 1

Scanned See "Unique System Desc."

N/A N/A N/A Sensor out low N

WET LT is calibrated for design operating conditions. 0% corresponds to lower tap on steam generator located approximately one (1) foot above bottom tube plate. 100% corresponds to the upper tap which is 179" above the top of"U" tubes. Top of the "U" tubes is approximately 71% WR level span.

E-68

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 66.

SG LEVEL 2/B L0423A Stm Gen 2 Wide Rng Water Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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:

NID power cutoff level:

NID power cut-on level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

08/19/08 WB1 N/A SG LEVEL 2/B L0423A STM GEN #2 LEVEL XMTR Stm Gen 2 Wide Rng Water Level A

0 - 100% WR = 0 - 614 inches WR 0

100 LOWTAP See Below S

1 Scanned See "Unique System Desc."

N/A N/A N/A Sensor out low N

WET LT is calibrated for design operating conditions. 0% corresponds to lower tap on steam generator located approximately one (1) foot above bottom tube plate. 100% corresponds to the upper tap which is 179" above the top of"U" tubes. Top of the "U" tubes is approximately 71% WR level span.

E-69

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 67.

SG LEVEL 3/C L0443A Stm Gen 3 Wide Rng Water Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

08/19/08 WB1 N/A SG LEVEL 3/C L0443A STM GEN #3 LEVEL XMTR Stm Gen 3 Wide Rng Water Level A

0 - 100% WR = 0 - 614 inches WR 0

100 LOWTAP See "Unique System Desc."

S 1

Scanned See "Unique System Desc."

N/A N/A N/A Sensor low out N

WET Unique System Desc:

LT is calibrated for design operating conditions. 0% corresponds to lower tap on steam generator located approximately one (1) foot above bottom tube plate. 100% corresponds to the upper tap which is 179" above the top of"U" tubes. Top of the "U" tubes is approximately 71% WR level span.

E-70

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 68.

SG LEVEL 4/D L0463A Stm Gen 4 Wide Rng Water Level Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

Unique System Desc:

08/19/08 WB1 N/A SG LEVEL 4/D L0463A STM GEN #4 LEVEL XMTR Stm Gen 4 Wide Rng Water Level A

0 - 100% WR = 0 - 614 inches WR 0

100 LOWTAP See "Unique System Desc."

S 1

Scanned See "Unique System Desc."

N/A N/A N/A Sensor out low N

WET LT is calibrated for design operating conditions. 0% corresponds to lower tap on steam generator located approximately one (1) foot above bottom tube plate. 100% corresponds to the upper tap which is 179" above the top of"U" tubes. Top of the "U" tubes is approximately 71% WR level span.

E-71

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 69.

NL U0400 RC LOOP #1 AVG FLOW Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A NL U0400 RC LOOP #1 AVG % FLOW Average RC Loop #1 Flow %

A N/A 0

100 N/A N/A P

3 Averaged From ICS Process Computer.

N/A N/A N/A Low N

N/A Unique System Desc:

Average Reactor Coolant Loop #1 flow comprised of the ICS Process Computer Reactor Coolant Loop #1 flow points F0400A, F0401A, and F0402A.

E-72

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 70.

NL U0420 RC LOOP #2 AVG FLOW Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A NL U0420 RC LOOP #2 AVG % FLOW Average RC Loop #2 Flow %

A N/A 0

100 N/A N/A P

3 Averaged From ICS Process Computer.

N/A N/A N/A Low N

N/A Unique System Desc:

Average Reactor Coolant Loop #2 flow comprised of the ICS Process Computer Reactor Coolant Loop #2 flow points F0420A, F0421A, and F0422A.

E-73

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 71 NL U0440 RC LOOP #3 AVG FLOW Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WB1 N/A NL U0440 RC LOOP #3 AVG % FLOW Average RC Loop #3 Flow %

A N/A 0

100 N/A N/A P

3 Averaged From ICS Process Computer.

N/A N/A N/A Low N

N/A Unique System Desc:

Average Reactor Coolant Loop #3 flow comprised of the ICS Process Computer Reactor Coolant Loop #3 flow points F0440A, F0441A, and F0442A.

E-74

ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 EMERGENCY RESPONSE DATA SYSTEM (ERDS)

DATA POINT LIBRARY (DPL)

REVISION 2 ERDS Point Number 72 NL U0460 RC LOOP #4 AVG FLOW Date:

Reactor Unit:

Data Feeder:

NRC ERDS Parameter:

Point ID:

Plant Spec 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 Setpoints:

NID Power Cut-Off Level:

NID Power Cut-On Level:

Instrument Failure Mode:

Temperature Compensation:

Level Reference Leg:

04/30/99 WBI N/A NL U0460 RC LOOP #4 AVG % FLOW Average RC Loop #4 Flow %

A N/A 0

100 N/A N/A P

3 Averaged From ICS Process Computer.

N/A N/A N/A Low N

N/A Unique System Desc:

Average.Reactor Coolant Loop #4 flow comprised of the ICS Process Computer Reactor Coolant Loop #4 flow points F0460A, F0461A, and F0462A.

E-75