ML20117F967
| ML20117F967 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/29/1996 |
| From: | Lemons J BALTIMORE GAS & ELECTRIC CO. |
| To: | John Jolicoeur NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9609040361 | |
| Download: ML20117F967 (3) | |
Text
'
< Q l.=
=
J Aucs R. LeMoms Baltimore Gas and Electric Compan, Afanager Calven Clifs Nuclear Power Plant Nuclear Support Services 1650 Calvert Clifs Parkway Lusby, Afaryland20657 410 586-2200 Ext. 3693 Local 4to 260-3693 Baltimore August 29,1996 U. S. Nuclear Regulatory Commission Washington, DC 20555 t
/.TTENTION:
Mr. John R. Jolicoeur, ERDS Project Manager
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Emergency Resnonse Data System i
The attached revision to the Emergency Response Data System (ERDS) Data Point Library for the Calvert Cliffs Nuclear Power Plant is provided pursuant to 10 CFR Part 50, Appendix E, Section VI.3.a.
This revision changes data point F131 A, Reactor Coolant System Total Flow Channel A.
+
Unit 1 F131 A instrument range changes from -56:160% to -52:145.85%.
i
+
Unit 2 F131 A instrument range changes from -56:160% to -54:153.064%.
Revised ERDS Data Point Library sheets are attached.
Should you have questions regarding this matter, please cc.'. tact our ERDS administrative contact, Mr. Thomas E. Forgette, at (410) 495-4996.
Very truly yours, 9609040361 960829 PDR ADOCK 05000317 p
PDR vvv JRUDWM/bjd Attachments f
cc:
D. A. Brune, Esquire
- 11. J. Miller, NRC j
f J. E. Silberg, Esquire Resident inspector, NRC Director, Project Directorate I-1, NRC
? 1. McLean, DNR A. W. Dromerick, NRC J t1. Walter, PSC
i e
PWR DATA POINT LIBRARY REFERENCE FILE
.e s
REV DATE: 08/24/96 PAGE DATE:
08/14/96 REACTOR UNIT CC1 DATA EEEDER CC11 NRC ERDS PARAMETER:
CORE FLOW POINT ID:
F131A l
PLANT SPEC POINT DESC.:
RCS TOTAL PLOW CH A GENERIC /COND DESC.:
TOTAL REACTOR COOLANT FIDW l
ANAIDO/ DIGITAL:
A l
ENOR UNITS /DIO STATES:
t FIDW l
ENCR UNITS CONVERSION:
100% RX COOLAprf FLOW = 370,000 GPM MINIMLN INSTR RANGE:
-51.58 MAXIMUM INSTR RANGE:
145.85 ZE'tO POINT
REFERENCE:
N/A REFERENCE POIh"t NOTES:
N/A PROC OR SENS:
S NUMBER OF SENSORS:
9 1
HOW PROCESSED:
N/A SENSOR LOCATIONS:
N/A l
ALARM / TRIP SET PGINTS:
N/A NI DETECTOR POWER SUPPLY Citr-OFF POWER LEV N/A NI DETECTOR POWER SUPPLY TURN-ON POWER LEV N/A INSTRUMENT FAILURE MODE: N/A TEMPERATURE COMPENSATION FOR DP TRANMITTERS:
N LEVEL REFERENCE LEG N/A UNIQUE SYSTEM DESC.:
REACTOR COOLANT FIDW IS DETERMINED BY THE D/P ACROSS THE STEAM GENERATORS. WHERE TOTAL PLOW IS I
THE SUM OF BOTH 100P FIDWS.
t 4
i i
8 1
J n
em
l 4
PWR DATA POINT LI1RARY REFERENCE FILE
,e REV DATE: 08/14/96 I
PAGE 5
DATE:
08/14/96 REACTOR Lnd T CC2 DATA FEEDER:
CC21 NRC ERDS PARAMETER:
CORE FI4W POINT ID:
F131A PLANT SPEC POINT DESC,a RCS TOTAL FLOW CH A GENERIC /COND DESC.:
TOTAL REACTOR COOLANT FIDW ANAI4G/ DIGITALS A
ENC 2 UNITS / DIG STATES:
% FLOW ENGR UNITS CONVERSION:
100% RX COOLANT FLOW = 370.000 GPM l
MINIMth INSTR RANGE:
-54,157 MAXIMUM INSTR RANGE:
153.064 EERO POINT
REFERENCE:
N/A REFERENCE POINT NOTES:
N/A PROC OR SENS:
S I
NUMBER OF SENSORS:
1 1
HOW PROCESSED:
N/A SENSOR LOCATIONS:
N/A ALARM / TRIP SET POINTS:
N/A NI DETECTOR POWER SUPPLY CUT-OFF POWER LEV N/A l
NI DETECTOR POWER SUPPLY TURN-ON POWER LEV N/A INSTRUMENT FAILURE MODE: N/A TEMPERAIURE COMPENSATION FG2 DP TRANSMITTERS:
N l
LFVEL REFERENCE LEG N/A EUI7JE SYSTEM DESC. :
REACTOR COOIANT FIDW IS DETERMINED BY THE D/P l
1 ACROSS THE STEAM GENERATORS. WHERE TOTAL FLOW IS
)
THE SUM OF BOTH LOOP FLOWS.
i l
[
I t
I 4
see