ML19341E016
| ML19341E016 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/30/1992 |
| From: | Baron R, Ratliff S TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9205190339 | |
| Download: ML19341E016 (13) | |
Text
.
.
May 11, 1992
.
L Eur=.\lf' rin 33 ,
U. S. Nuclear Regulatory Commission Attn: Document Control Desk ;
Mail Station P1-137 Washington, D.C. 20555 Gentlemen:
ULNRC-2632 DOCKET NUMBER 50-483 CALLAWAY PLANT EMERGENCY RESPONSE DATA SYSTEM DATA POINT ETBRARY CHANGES The attached pages are changes made to Callaway's DPL. The following is a list of the DPL computer points which were changed and faxed to Mr. John Jolicoeur, the NRC ERDS i project manager on April 9, and April 15, 1992. These changes were in response to Mr. Jolicouer's questions to !
Mr. Eric Schulte on April 8, 1992.
- 1) REUO523 8) GHR0010B
- 2) RELO404A 9) HBR0018
- 3) RELO424A 10) SPDS0012
- 4) RELO444A 11) SJR0001
- 5) RELO464A 12) SPDS0013
- 6) REUO483 13) SPDS0053
- 7) SP250038 14) REUO511 The following computer point has an additional change which rust be made to the DPL due to a enange in the cc=puter point instrument ranges at callaway.
,
- 1) SPDS0041
- :
.>
bh
,,
'
D._e' m ,, n g7 f/fC ,
ff9fk ;1% '~
l
[ ' s\ \
? DOS 290337 920521
{DR ADOCK 05000483 I PDR
}
. _ - - -
.
'
ULNRC-2632 May 11, 1932 Page 2 ;
!
Please contact Mr. Al White, Supervisor, Emergency Prepared-ness, (314) 676-4961 or Mr. Eric Schulte, Engineer, Computer Support, (314) 676-8486 for follow-up discussion or ;
questions. '
Very truly"yours, '
,
ly ,
Milton A. Stiller Manager, Nuclear Safety and Emergency Preparedness MAS /AEW/dch Attachments cc: A. B. Davis, Regional Aduinistrator, USNRC Region III R. L. Hague, Chief, Reactor Projects Section 3C, USNRC Region III L. R. Wharton, USNRC Licensing Project Manager (2 copies)
Manager, Electric Department, Missouri Public Service Commission, w/o ,
- 3. L. Bartlett, Senior Resident Inspector Shaw, Pittman, Potts, & Trowbridge, w/o
.
6
l l
1
- . _. _ .. _ - . . ._. __
..
-l
.
- !
t i
.i i
t
,
i
!
!
4 I
.
,
i
!
!
3
.
!
DATA POINT LIBRARY CHANGES IN RESPONSE TO -
,
MR. JOLICOEUR'S QUESTIONS ;!
!
!
l
l t
!
.!
t t
m r i
.
!
I t
!
l-
!
!
!
,
l
. . . .
.
.
t
,
DATA POINT LIBRARY REFERENCE PILE Page 6 of 61 '
!
i i
Date: 04/09/92 :
Reactor Unit: CW1 [
Data Feeder: N/A NRC ERDS Parameter: REAC VES LEV {
i Point ID:. REUO523 '
Plant Spec Point Desc: RV WR A/B LEVEL AVG [
Generic /Cond Desc: REACTOR VESSEL WATER LEVEL ;
Analog / Digital: A >
Engr Units / Dig States: % '
Engr, Units Conversion: TOTAL INSIDE FLUID HEIGHT 494.9 INCHES Minimum Instr Range: l
-2.500E+00 !
Maximum Instr Range: 1.250E+02 Zero Point
Reference:
COMPLX ;
Reference Point Notes: BOTTOM OF VESSEL PROC or 3 ENS: P l
Number of Sensors: 2 l
-How Procersed: AVERAGE i Sensor Locations: REACTCR VESSEL !
- Alarm / Trip Set Points: N/A NI Detector Power Supply (
Cut-off Power Level: N/A r NI Detector Power Supply ;
Turn-on Power Level: N/A :
Instrument Failure Mode: LOW !
Temperature Compenst.tica
For ET fransmitters: Y !
Level deference Leg: WFP j Unigts Systen Desc: USES DIFFERENTIAL PRESSURE ACROSS THE VESSEL TO DETERMINE VESSEL LEVEL OR RELATIVE VOID CONTENT OF THE CIRCULATING PRIMARY COOLANT SYSTEM FLUID.
_ MAY FAIL HIGH. :
. .
h I
!
t b
I r
f I
!
,
.
!
,-
,
t DATA POINT LIBRARY REFERENCE FILE Page 30 of 61 Date: 04/15/92 i Reactor Unit: CW1 '
Data Feeder: N/A NRC ERDS Parameter: SG LEVEL 1/A Point ID: RELO404A Plant Spec Point Desc: SG A WR LEVEL Generic,'Cond Desc: STEAM GEN A WATER LEVEL Analog / Digital:. A Engr Units / Dig States: % >
Engr Units Conversion: 100% = 566 INCHES '
Minimum Instr Range: 0.000E+00
- Maximum Instr Range: 1.000E+02 ;
Zero Point
Reference:
TUBSHT i Reference Point Notes: 7 INCHES ABOVE TUBE SHEET '
PROC or SENS: S '
Number of Sensors: 1 ;
How Processed: N/A Sensor Locations: STEAM GEN':RATOR A Alarm / Trip Set Foints: HIHI/ HI / LO /LOLO 71.0/70.0/43.0/NA NI Detector Power Supply Cut-off Power Level: N/A NI Detector Power Supply ,
Turn-on Power Level: N/A I Instrument Failure' Mode: LOW ,
Temperature Compensation For DP Transmitters: !
Y '
Level Reference Leg: WET ,
Unique System sesc: 60% IS TOP OF HIGHEST TUBE. -
MAY FAIL HIGH.
i
+
.
L l
1
?
f L
>
[
,
s
,
.
.
DATA POINT LIBRARY REFERENCE FILE Page 11 of 61 i
Date:
Reactor Unit:
04/15/92 CW1 t Data Feeder: N/A NRC ERDS Parameter: SG LEVEL 2/B
Point ID: RELO424A ;
Plant Spec Point Desc: SG B WR LEVEL Generic /Cond Desc: STEAM GEN B WATER LEVEL Analog / Digital: A !
Engr Units / Dig States:. %
Engr Units Conversion: i 100% = 566 INCHES Minimum Instr Range: 0.000E+00 Maximum Instr Range: 1.000E+02
Zero Point
Reference:
TUBSHT Reference Point Notes: 7 INCHES ABOVE TUBE SHEET PROC or SENS: S L
Number of Sensors: 1 [
'
How Processed: N/A Sensor Locations? !
STEAM GENERATOR B Alarm / Trip Set Points: l HIHI/ HI / LO /LOLO t NI Detector Power Supply 71.0/70.0/43.0/NA i t
Cut-off Power Level: N/A NI Detector Power Supply Turn-on Power Level: N/A Instrument Failure Mode: LOW Temperature Compensation For DP Transmitters: Y i
Level Reference Leg: WET Unique System Desc: 60% IS TOP OF HIGHEST TUBE.
MAY FAIL HIGH.
t em 9
!
I i
!
l I
l
,
.
I
.
t DATA POINT LIBRARY REFERENCE FILE Page 12 of 61 t
Date: 04/1S/92 Reactor Unit: CW1
.
f Data Feeder: N/A !
NRC ERDS Parameter: SG LEVEL 3/C Point ID: RELO444A Plant Spec Point Desc: SG C WR LEVEL :
Generic /Cond Desc: STEAM GEN C WATER LEVEL Analog / Digital: A i Engr Units / Dig States: % '
Engr Units Conversion: 100% = S66 INCHES Minimum Instr Range:- 0.0COE+00 [
Maximum Instr Range: 1.000E+02 l Zero Point
Reference:
TUBSHT '
Reference. Point Notes: 7 INCHES ABOVE TUBE SHEET PROC cr SENS: l S
l Number of Sensors: 1 '
,
How Processed: N/A !
Sensor Locations: STEAM GENERATOR C [
Alarm / Trip Set Points: HIHI/ HI / LO /LOLO i 71.0/70.0/43.0/NA NI_ Detector Power Supply ;
!
Cut-off Power Level: N/A '
NI Detector Power Supply
!
Turn-on Power Level: N/A '
,
Instrument Failure Mode: LOW '
Temperature Compensation j For DP Transmitters: Y j Level Reference Leg: WET '
,
Unique System Desc: 60% IS TOP OF HIGHEST TUBE.
MAY FAIL HIGH.
!
--
.
)
r
.
l
,
I l
&
$
!
. ?
.
!
DATA POINT LIBRARY REFERENCE FILE Page 13 of 61 I
,
Date: 04/15/92 !
Reactor Unit: CW1 l Data Feeder: N/A NRC ERDS Parameter: SG LEVEL 4/D '
,
Point ID: RELO464A Plant Spec Point Desc: SG D WR LEVEL G@neric/Cond Desc: STEAM GEN D WATER LEVEL Analog / Digital: A !
Engr Units / Dig States: %
Engr Units Conversion: 100% = 566 INCHES Minimum Instr Range: 0.000E+00 Maximum Instr Range: 1.000E+02 '
,
.
Iero Point
Reference:
TUBSHT ;
Reference Point Notes: 7 INCHES ABOVE TUBE SHEET !
PROC or SENS: S !
Number of Sensors: I How Processed: N/A
' Sensor Locations: STEAM GENERATOR D '
Alarm / Trip Set Points: HIHI/ HI / LO /LOLO ;
71.0/70.0/43.0/NA l NI~ Detector Power Supply ;
Cut-off Power Level: N/A NI Detector Power Supply l i
Turn-on Power Level: N/A }
Instrument Failure Mode: LOW !!
Tenperature Conpensation For DP Transmitters: N/A [
Level Reference Leg: N/A Unique System Desc: l 60% IS TOP OF HIGHEST TUBE. r MAY FAIL HIGH. !
i
-
!
,
I i
,
!
i
'
t t
.
..
,
P i
DATA POINT LIBRARY REFERENCE FILE Page 35 of 61
,
Date: 04/09/92 Reactor Unit: CW1 Data Feeder: N/A NRC ERDS Parameter: PRZR LEVEL Point ID: REUO483 Plant Spec Point Desc: PRESS LEVEL 1/2/3 AVG Generic /Cond Desc: PRIMARY SYSTEM PRESSURIZER LEVEL-Analog / Digital: A Engr Units / Dig States: %
Engr Units Cont rsion: 100% = 555 INCHES Minimum Instr Range: 0.000E+00 Maximum Instr Range: 1.000E+02 Zero Point
Reference:
COMPLX ;
Reference Point Notes: 40 INCHES ABOVE PRESSURIZER BOTTOM
'
PROC or SENS: P Number of Sensors: 3 !
How Processed: AVERAGE Sensor Locations: PRESSURIZER ,
Alarm / Trip Set Points: N/A NI' Detector Power Supply !
i Cut-off Power Level: N/A NI Detector Power Supply !
Turn-on Power Level: N/A ;
Instrument Failure Mode: LOW Temperature Compensation For DP Transmitters: Y ,
Level Reference Leg: WET I Unique System Desc: PRESSURIZER VOLUME IS 1800 CUBIC FEET. HEATER TOPS AT 17.5% LEVEL.
MAY FAIL HIGH.
t
.
!
1
!
!
I i
l
.
.
.
.
DATA POINT LIBRARY REFERENCE FILE Page 41 of 61 *
,
Date: 04/09/92 Raactor Unit: CW1 -
Data Feeder: N/A ;
NRC ERDS Parameter: EFF GAS RAD Point ID: SPDS0038 Plant Spec Point Desc: STACK EFFLUENT RADIATION Generic /Cond Desc: RADIOACTIVITY OF RELEASED GASSES
' Analog / Digital: A Engr Units / Dig States: UCI/ML Engr Units Conversion: N/A Minimum Instr Range: 1.000E-07 l Maximum Instr Range: 1.000E+05
- Iero Point
Reference:
N/A Reference Point Notes: N/A PROC or SENS: S '
' Number of Sensors: 1 How Processed: N/A Sensor Locations: UNIT VENT DWNSTRM LAST PNT OF RAD ENTRY Alarm / Trip Set _ Points: N/A r NI Detector-Power Supply !
Cut-off Power Level: N/A NI Detector Power Supply i Turn-on Power Level: N/A '
Instrument Failure Mode: LOW '
~ Temperature Compensation For DP Transmitters: N/A Level Reference Leg: N/A l Unique System Desc: UNIT VENT FLOW RATES (CFM)
'
15508 A MN STM ENCLOSURE BLD EXHAUST '
15282 B 34642 A FULL SPEED AUX / FUEL BLD EXHAUST
~
29704 B FULL SPEED ,
.
14118 A SLOW SPEED '
14187 B SLOW SPEED i 6152 A ACCESS CONTROL ,
6163 B 1052 A COND AIR REMOVAL FILTRATION 935 B ,
19679 CONT. SHUTDOWN PURGE EXHAUST ;
'
3637 CONT. MINIPURGE EXHAUST 8760 A FUEL BLD EMERG EXHAUST [
8820 B
'
'
ALERT /HIGH ALARMS PER CDCM ON EMS RM-11.
MAY FAIL HIGH.
-
l
i
i
.
,
DATA POINT LIBRARY REFERENCE FILE Page 42 of 61 i
Date: 04/09/92 '
Reactor Unit: CW1 Data Feeder: N/A NRC ERDS Parameter: EFFS GAS RAD Point ID: GER0010B Plant Spec Point Desc: RADWASTE VENT GAS RAD MON Generic /Cond Desc: RADIOACTIVITY OF RELEASED GASSES Analog / Digital: A Engr Units / Dig States: UCI/ML Engr Units Conversion: 2.039E+10 ML/HR Minimum Instr Range: 1.000E-07 Maximum Instr Range: 1.000E+05 tero Point
Reference:
N/A Reference Point Notes: N/A PROC or SENS: S
,
-
Number of Sensors: 1 How Processed: N/A Sensor Locations: DOWNSTREAM OF EXHAUST FILTER AND FANS ,
Alarm / Trip Set Points: N/A NI Detector Power Supply Cut-off Power Level: N/A !
NI Detector Power Supply Turn-on Power Level: N/A l Instrument Failure Mode: LOW !
Temperature Compensation '
For DP Transmitters: N/A Level Reference Leg: N/A Unique System Desc: MONITORS GASEOUS RADIOACTIVITY IN THE EFFLUENT RADWASTE BUILDING DUCT. ISOLATES ,
WASTE GAS DECAY TANK DISCHARGE LINE ON HIGH t ALARM.
__ FLOW IS 12000 SCFM.
ALERT /HIGH ALARMS PER ODCM ON RMS RM-11.
MAY FAIL HIGH. *
,
P
_ _ - . . . . _ . _ _ _ _ _ _ _
- !
l J
-
,
i i
- v. .
L DATA. POINT LIBRARY REFERENCE FILE Page 44 of 61
,
l Date:- 04/09/92 1 Reactor Unit: CW1 l
' Data Feeder: . N/A ;
NRC ERDS Parameter: EFF LIQ RAD ,
Point ID:. HBR0018 >
~ Plant Spec Point Desc: RADWASTE LIQUID DIS RAD MON !
Generic /Cond Desc: RADIOACTIVITY OF RELEASED LIQUID Analog / Digital: A
.i
' Engr Units / Dig States:- UCI/ML lI
. Engr ~ Units Conversion: MAX,2.082E+06 ML/ MIN Minimum Instr Range: 1.000E-07
Maximum Instr Range: 9.990E-02
,
,
Zero: Point
Reference:
N/A i Reference Point Notes: N/A ;
PROC or SENS:- S -
Number of Sensors: 1 !
How Processed: N/A f
_
Sensor Locations: . UPSTREAM OF DISCHARGE VALVE j
. Alarm / Trip, Set Points: N/A i NI Detector Power Supply .j Cut-off-Power Level: N/A NI Detector Power Supply Turn-on Power Level: l N/A !
Instrument' Failure Mode:' LOW !
Temperature Compensation-
-For.DP Transmitters: l N/A !
Level Reference Leg: N/A l Unique System Desc:- HIGH RADIOACTIVITY ALARM CLOSES THE LIQUID
'- l RADWASTE SYSTEM DISCHARGE VALVE. '
FLOW IS 0-550 GPM.
ALERT /HIGH ALARMS PER ODCM ON RMS RM-11.
. .
. MAY FAIL HIGH.
,
!
,
!
!
i l
!
i t
i l'
. . _ ,- - - _ _
4
'
DATA POINT LIBRARY REFERENCE FILE Page 45 of 61 i
Date: 04/09/92 Reactor Unit: CW1 Data Feeder: N/A NRC ERDS Parameter: COND A/E RAD Point ID: SPDS0012 '
Plant Spec Point Desc: CONDENSER AIR DISCHARGE RAD Generic /Cond Desc: CONDESER AIR EJECTOR RAD Analog / Digital: A Engr Units / Dig States: UCI/ML Zngr Units Conversion: 1.699E+09 ML/HR Minimum Instr Range: 1.000E-07 Maximum Instr Range: 1.000E-02 Zero Point
Reference:
N/A Reference Point Notes: N/A PROC or SENS: S Number of Sensors: 1 How Processed: N/A Sensor Locations: UPSTREAM OF COND AIR REMOVAL SYS FILTERS Alarm / Trip Set Points: N/A NI Detector Power Supply Cut-off Power Level: N/A NI Detector Power Supply Turn-on Power Level: N/A Instrument Failure Mode: LOW Tcmperature Compensation For DP Transmitters: N/A Level Reference Leg: N/A Unique System Desc: THIS MONITOR CLOSES STEAM GENERATOR BLOWDOWN ISOLATION VALVE ON HIGH ALARMS. DISCHARGES THROUGH UNIT VENT.
FLOW IS 1000 SCFM.
~~ ALERT /HIGH = 2.0E-06/2.0E-05 UCI/ML ON RMS
-
RM-11.
MAY FAIL HIGH.
u
.
.
DATA POINT LIBRARY REFERENCE FILE Page 47 of 61 Date: 04/09/92 Reactor Unit: CW1 Data Feeder: N/A NRC ERDS Parameter: RCS LTDN RAD Point ID: SJR0001 Plant Spec Point Desc: CVCS LETDOWN RAD MON Ganeric/Cond Desc: RAD LVL OF RCS LETDOWN LINE pmalog/ Digital: A Engr Units / Dig States: UCI/ML Engr Units Conversion: MAX 640 ML/ MIN Minimum Instr Range: 1.000E-03 Maximum Instr Range: 1.700E+03 Zerc Point
Reference:
N/A Reference Point Notes: N/A PROC or SENS: S Number of Sensors: 1 How Processed: N/A Sensor Locations: UPSTREAM OF CVCS LETDOWN DEMINERALIZERS Alarm / Trip Set Points: N/A NI Detector Power Supply Cut-off Power Level: N/A NI Detector Power Supply Turn-on Power Level: N/A Instrument Failure Mode: LOW Temperature Compensation For DP Transmitters: N/A Level Reference Leg: N/A Unique System Desc: VARIABLE ALERT /HIGH ALARMS ON RMS RM-11.
MAY FAIL HIGH.
~
.
r
)
i
!
. _ . _ _ _ - - _ _ . - - - - - - _ - - . _ -
4 DATA POINT LIBRARY REFERENCE FILE Page 52 of 61 i
Date: 04/09/92 Reactor Unit: CW1 Data Feeder: N/A NRC ERDS Parameter: SG BD RAD 1A '
Point ID: SPDS0013 Plant Spec Point Desc: STM GEN BLOWDOWN RADIATION Generic /Cond Desc: STM GEN BLOWDOWN RADIATION LEVEL ,
Analog / Digital: A !
Engr Units / Dig States: UCI/ML Engr Units Conversion: MAX 640 ML/ MIN Minimum Instr Range: 1.000E-07 Maximum Instr Range: 1.000E-02 Zero Point
Reference:
N/A Reference Point Notes: N/A !
PROC or SENS: S Number of Sensors: 1 i
How Processed: N/A Sensor Locations: DOWNSTREAM OF SAMPLE SYS HEAT EXCHANGER Alarm / Trip Set Points: N/A NI Detector Power Supply ,
Cut-off Power Level: N/A NI Detector Power Supply Turn-on' Power Level: N/A Instrument Failure Mode: LOW
,
Temperature Compensation
- For DP Transmitters: N/A
!
Level Peference Leg: N/A Unique. System Desc: MONITOR CLOSES STEAM GENERATOR BLOWDOWN ISOLATION TO PREVENT THE DISCHARGE OF :
RADICACIVE FLUID AND TO LIMIT RADIAOCTIVE CONTA!!INATION OF THE BLOWDOWN
,, DEMINERALIZERS. '
- '
MONITORS DOWNSTREAM COMB OF 4 LOOPS.
RMS RM-11 ALERT /HIGH ALARMS = '
1.0E-05/1.0E-04 UCI/ML.
MAY FAIL HIGH. i
I
!
.
k
>
l
.
L DATA POINT LIBRARY REFERENCE FILE Page 55 of 61 [
Date:
04/09/92 Reactor Unit: CW1 Data Feeder: N/A i NRC ERDS Parameter: H2 CONC Point ID: SPDS0053
'
Plant Spec Point Desc: CONTAINMENT HYDROGEN CONC Generic /Cond Desc: CONTAINMENT HYDROGEN CONC Analog / Digital: A Engr Units / Dig States: %
Yngr Units Conversion:
Minimum Instr Range: CONTAINMENT VOLUME = 2.5E+06 CUBIC FEET 0.000E+00 Maximum InOtr Range: 1.000E+01 ,
'
2ero Point
Reference:
N/A Reference Point Notes: N/A
,
PROC or SENS: P 4
Number of Sensors: 2 j
How Processed: AVERAGE Sensor Locations:
Alarm / Trip Set _ Points: CONTAINMENT BLDG 2047' ELEVATION N/A NI. Detector Power Supply ,
!
Cut-off Power' Level: N/A NI Detector Power Supply .
Turn-on Power Level: N/A Instrument Failure Mode: LOW '
Temperature Compensation For.DP Transmitters: N/A Level Reference Leg: N/A
,
Unique System Desc: MAY FAIL HIGH.
,
-
em t
I
!
!
!
.
l L
i
.
4 DATA POINT LIBRARY REFERENCE FILE Page S6 of 61 Date:- f 04/09/92 Reactor Unit: CW1 Data Feeder: N/A s
NRC ERDS Parameter: BWST LEVEL ,
Point ID: REUO511 '
Plant Spec Point Desc: RWST LEVEL Generic /Cond Desc: BORATED WATER STORAGE TANK LEVEL Analog / Digital: A Engr. Units / Dig States: % '
Engr Units Conversion: 100% = 41944S GALLONS .
- Minimum Instr Range: 0.000E+00 Maximum Instr Range: 1.000E+02
- Zero Point
Reference:
COMPLX !
Reference Point Notes: 0% = 18722 GALLONS i PROC or SENS: P !
Number of Sensors: 4 How Processed: AVERAGE Sensor Locations: REFUELING WATER STORAGE TANK ,
Alarm / Trip Set Points: N/A NI Detector Power Supply Cut-off Power Level: N/A NI Detector Power Supply ,
'
Turn-on Power Level: N/A Instrument Failure Mode: LOW Temperature Compensation For DP Transmitters: Y
- Lovel Reference Leg: WET Unique System Desc: MAY FAIL HIGH.
,
,
6e
,
t
!
t
!
.
i J + r J 4__. _ A. .m a a 2
. I
,
I f
i r
f i
>
>
-
t t
!
f I
k
!
DATA POINT' LIBRARY CHANGE l DUE TO !
!
CHANGE IN COMPUTER POINT !
INSTRUMENT RANGES AT CALLAWAY ;
-i i
f f
!
,
t
!
l
i 5
l
!
'
i
)
I
'
t r
L
,
!
. .
.
'
!
. ,
DATA POINT LIBRARY REFERENCE FILE Page 3 of 61
.
.
.Date: 04/20/92 R: actor Unit: CW1 -
Data. Feeder: N/A NRC ERDS Parameter: NI SOURC RNG -
. Point ID: SPDS0041 L Plant Spec Point Desc: SOURCE RANGE POWER LEVEL l Gcneric/Cond Desc: NUCLEAR INSTR SOURCE RANGE i Analog / Digital: A Engr Units / Dig States: . CPS
Engr Units Conversion: N/A Minimum Instr Range:
,
2.500E-01 Maximum Instr Range: 1.000E+06 i Zero Point
Reference:
N/A Reference Point Notes: N/A
PROC or SENS: P !
Number of Sensors: 2 i How Processed: AVERAGE !
Sensor Locations: REACTOR CAVITY Alarm / Trip Set Points: N/A l NI Detector Power. Supply Cut-off Power Level: i 1E-10 AMPS '
NI Detector Power Supply Turn-on Power Level: >1E-10 AMPS Instrument Failure Mode: LOW Temperature Compensation '
For DP' Transmitters: N/A !
Lovel Reference Leg: N/A i Unique System Desc: MAY FAIL HIGH. !
!
I
. ?" ,
!
.
!
!
I
,
,
i
!
>
4
%
E. I. HATCH - UNITS 1 AND 2 NRC - EMERGENrY RESPONSE DATA SYSTEM Data Point Library Abbreviations Following is a list of abbreviations and acronyms used in the Hatch Units 1 and 2 Data Point Libraries (DPL) and the corresponding terms. Included are all abbreviations and acronyms wt.ch are not defined at some point in either the DPL or NUREG-1394, Rri. 1.
,
ACCEPT Acceptable APPROX Approximately APRM Average Power Range Monitor AUTO Automatically AVAIL Available AVE Average AVG Average BLDG Building CALC Calculated CHAMB Chamber CHEM Chemistry CHMBR Chamber CONC Concentration DEPT Department-DIFF Difference or Differential DIR Direction DT Differential Temperature DW Drywell
ECCS Emergency Core Cooling System EE Scientific Notation for X 10
'
EL Elevation ELEY Elevation EXCH _ Exchanger FISS -
.GE. Greater Than or Equal To GM Geiger Muller !
.. GT. Greater Than HP Health Physics l HI High INDIV Individual INFO Information INST Instrument INSTR- Instrument '
.LE. Less Than or Equal To '
LEV' Level ,
LO Low LOCA Loss of Coolant Accident
.. . - _-- . ._ - . .
,
,
j t
'
i i
!
E. I. HATCH - UNIT 1 NRC - EMERGENCY RESPONSE DATA SYSTEM
!
Data Point Library -l Abbreviations LPRM Local Power Range Monitor LYL Level !
MAX. Maximum MET Meteorological !
i MSIV Main Steam Isolation Valve MSL Mean Sea Level NONACCEPT Nonacceptable *
,
'
-NORM Normal NUC' Nuclear' !
NUM !
Numerical '
PMP. Pump POSS Possible ;
PRESS Pressure-PSW Plant Service Water [
.QLTY Quality QUAD Quadrant }
,
. QUAL Quality t RECIRC -Recirculation System l
~
REF. Reference RNG Range RPV Reactor Pressure Vessel j RTD . Resistance Temperature Detector 1 RWL Reactor Water Level !
RX Reactor- !
SMPL Sample !
i SMP. Samp1e SRM . N ource Range Monitor }
i SUPP _ Suppression
- TAF- Top of Active Fuel i TEMP . Temperature l j
TRANS Transmitter '
TWR- Tower UNACCEPT Unacceptable VAL - Value
- WTR Water i
!
XMTR ' Transmitter I
,
!
,
'
.-. .,
.
,
E. I. HATCH - UNITS 1 AND 2 NRC - EMERGENCY RESPONSE DATA SYSTEM PLANT ATTRIBUTE LIBRARY NUREG 1394 REY. 1 APPENDIX B SECTION III. SELECTION OF DATA FEEDERS A. How many data feeders are there (six maximum)?
Two; one per plant unit. Systems are identical except for plant unit number.
B. Identify the selected data feeders and provide the following for each:
(1) A short description of the categories of data points it will provide (e.g., met, rad, or plant data points, by unit) and ,
(2) The rationale for selecting it if another system can also provide
-
its categories of data points.
Presently installad SPDS/ERF computers will feed information to new NRC-ERDS microproce. ors. The NRC-ERDS data feeders will provide -
information on all categories in the Critical Safety Function Parameters List for BWRs as well as the similar BWR Parameter List.
Computer burden was the rationale for. selecting new microprocessors to convert and transmit the NRC data.
C. Which data feeder is the site time determining feeder? This should be i the feeder which is providing the majority of the data points.
The NRC-ERDS microprocessors will be the site-time determining devices.
-- !
.
f
!
t
>
3073
.
I
'
.
I NUREG .1394 REV. 1 APPENDIX B '
SECTION IV. DATA FEEDER INFORMATION Note: A new Section IV must be filled out for each feeder system selected.
,
(The following applies to both plant units)
- L
.
General Questions I. Identification of Data feeder !
a.
What is the name in local parlance given to this data feeder (e.g.,
Emergency Response Information System)? Please give both the acronym and the words forming it.
NRC-ERDS System Nuclear Regulatory Commission-Emergency Response Data System i
- b. Is this the site time deternining feeder?
yes
,
c.
How often will this feeder transmit an update set to the ERDS (in ,
seconds)?
Every 15 seconds i
- 2. Hardware / Software Environment
!
- a. Identify the manufacturer and model number of the data feeder L hardware. ;
,
,
Data. General Corporation MV/9300 - ECLIPSE ! '
- b. Identify the operating system.
A05/VS II t
- c. !
What method.of timekeeping is implemented on this feeder system '
(Daylight Savings, Standard, Greenwich)?
Central Standard Time l I
- d. In wnat time zone is this feeder located? ,
i Eastern r 3073
. _
-.
.
. 1
NUREG 1394 REV. I !
APPENDIX B i SECTION IV. DATA FEEDER INFORMATION (Continued)
- 3. Data Communication Details
- a. Can this data feeder provide asynchronous serial data communications
!
(RS-232-C) with full-modem control?
Yes
- b. Will this feeder transmit in ASCII or EBCDIC?
ASCII i
- c. Can this feeder transmit at a serial baud rate of 2400 bps? If not, at what baud rate can it transmit?
Yes ,
- d. Does the operating system support XON/X0FF flow control? !
Yes ;
.
- 1. Are any problems foreseen with the NRC using XON/XOFF to control ,
the transmission of data? '
!
No
'
e.
,
If it is not feasible to reconfigure a serial port for the ERDS I linkup (i.e., change in baud rate, parity, etc.), please explain why. <
Not applicable !
i
- f. Do any gorts currently exist for the ERDS. linkup? i Yes i
- 1. If not, is it possible to add additional ports? l
- 2. If yes, will the port be used solely by the ERDS or shared with other nonemergency-time users? Give details. i The serial port will be dedicated to the NRC. The serial ;
controller is multi-ported, and with computer interface, capable of supporting several users concurrently. i i
.
i
)
!
3073 l
.
__
.
.
.
NUREG 1394 REV. 1 APPENDIX B SECTION IV. DATA FEEDER INFORMATION (Continued)
- 4. Data Feeder Physical Environment and Management
Main Control Room
- b. Is the data feeder protected from loss of supply of electricity?
The power supply for Unit I and Unit 2 NRC-ERDS computer systems is intended to be the same as that presently used for SPDS at Plant I Hatch. Inverter backup is used in this case. ,
L t
- c. Is there a human operator for this data feeder? I
Only to initiate the data link to the NRC if required. The system is designed to remain "on-line". !
- 1. If so, how many hours a day .3 the feeder attended?
!
!
l t
,
==
i
!
!
!
!
l l
t i
r f
i 3073 j
1
- - - -
,
_
_ ,
I
,,
!
!
4 DOCUMENT APPROVAL
!
U. S. Nuclear Regulatory Commission i ERDS Document Name: ESS User's Manual Document Number: NRC-329 Date Issued: May 15, 1992 Revision Level: Rev. O This acknowledges approval of the document listed above.
EBE6PrgetOfficer
-
-
Date Sf2-/ffL ,
i
'
Document Status f
- 1. Work may proceed. !
[2. Revise and resubmit. Work may proceed subject to incorporation of changes indicated. i
- 3. Revise and resubmit. Work may not proceed.
- 4. Reyiernot required. Work may proceed. !
i
- 5. Information only. -
!
COMMENTS Ad W Rc/ A ce m e=~ny i
i
!
!
!
f
,
. -- ..
.
- y. - , -
- v. -
ms . ,y qp
- * *pp W ~ ,
.
_ , . , 3! ~
- .
,
.,
. . - _
%'
< ., s p - _ -
~.
[ L .$ '
>s w I' ? .+ NN . e .. ! %. +.-s...
qq : q yl ; :. . . -* g =qW -[;~
~
~ " '
- T -. , & * :.% n ,
-+2 ti $ D .= ,
' * *
- _~ -.
.i COMMENTS ON ESS USER'S PJMdAL (NRC-329, REV. 0)
- 1. In the last two nessages on page C-2 and the first four messages on page C-3, the last sentence is not well written.
Either this action is recommended cr it is not. Don't say "you will probably want to..." Ee more definitive and also tell why you would want to perform this task.
- 2. In the next to the last message on page C-4 no corrective action is given. Should the user do anything in this case?
- 3. In the first message on page C-7 we state that "You may also want to turn the modem power on and off." We should tell the user why, or what this action is intended to accomplish. !
i
- 4. In the first sentence of the solution to the last problem ;
listed on page D-4, the word "be" should be replaced by;the word "been".
.
- 5. On page D-5 in the next to the last paragraph, we tell,the user, "You should not use this command when ESS is runnitig. " r It is not clear which command we are referring to . If'this is a problem, it should be set off as a warning alerting >the. ,
user to the potential problem that using this command 'with'ESS' i j
running could cause. ~
- 6. On page H-1, the incorrect value is listed for the ASCII hex value for *. It should read 42 instead of 2A.
i
- 7. As a general co= ment in Appendices C and D we often say'"you may want to. . . " or "you will probably want to. . . " This advice is usually given with no indication of why this may be helpful ,
or what this action will accomplish. The users will find themselves asking "why?" in these situations. In situations like- this , _t nay be appropriate to say "you may want to...", y however, we should tell the user what would be accomplished
'y the-task : hcw the Operation might help solve the problem l at hand. -
P i
!
,
l
!
!
!
!
l l
l I
m
-______ _
.
e.vz
% 27 32 erez e:a= :o%s ::mo E" N 6"'"P duHALLIBURTON NUS P.O. BOX w. .*o
. ,c,y,g,tg g,,no sees my Ennronmenal Corporanon nu l 18, nv- uw
\
l
{
f EUI'P 1 APPF0VM i
U. S. "uclear Regulatory Commission ERDS Document fiame: ESS User's Manual l
Occurent humoer- NRC 329 Date Issued: May 27, 1992 Revision Level: Rev. O This acknowledges approval of the dccument listed above.
,, /r WZ7h 2-Date
~
EFif5PAjectOfficer Document Status
- 1. Work may proceed.
- 2. Revise and resubm.it. Work may proceed subject to incorscration of_ changes indicated.
- 3. Pevise ird resubmit. Work :y not proceed.
- 4. Review not required. Werk may prJceed.
- 5. Information only.
COMMft4TS __ _
_
-- e
.e-
%
--.mw-MM'