ML033080099
| ML033080099 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/29/2003 |
| From: | Roach E Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML033080099 (3) | |
Text
iI Calvert Cliffs Nuclear Power Plant Constellation Generation Group, LLC 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 Constellation Energy Group October 29, 2003 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
SUBJECT:
Document Control Desk Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 Emergency Response Data System 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.
The table below provides a brief summary of the changes:
Description -
- Previous Range New Range--
Reactor Coolant System Total
-52.63:148.83 percent
-54.35:153.68 percent Flow Channel A The "before" and "after" ERDS Data Point Library sheets are attached.
Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, t4'tLC_
Edward H. Roach Director - Emergency Planning EHR/CAN/bjd
Attachment:
As Stated cc:
J. Petro, Esquire J. E. Silberg, Esquire Director, Project Directorate I-1, NRC G. S. Vissing, NRC H. J. Miller, NRC Resident Inspector, NRC R. I. McLean, DNR J. R. Jolicoeur, NRC MOLi9
PWR Data Point Library Reference File Report Date Page:
09-30-2003 5
Il Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point
Description:
Generic / Condition
Description:
Analog / Digital:
ENGR Units / Digital States:
ENGR Units Conversion:
Minimum Instrument Range:
Maximum Instrument Range:
Zero Point
Reference:
Reference Point Notes Proc or Sens:
Number of Sensors:
How Processed:
Sensor Locations Alarm I Trip Setpoints:
NI Detector Power Supply Cut-Off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation
-for DP -Transmitters:
Level Reference Leg:
Unique System
Description:
9/27/2001 CC2 CC21 CORE FLOW F131A RCS TOTAL FLOW CH A TOTAL REACTOR COOLANT FLOW A
% FLOW 100% RX COOLANT FLOW = 370,000 GPM
-52.63 148.83 N/A N/A S
1 N/A N/A N/A N/A N/A NIA N
N/A REACTOR COOLANT FLOW IS DETERMINED BY THE DIP ACROSS THE STEAM GENERATORS. WHERE TOTAL FLOW IS THE SUM OF BOTH LOOP FLOWS.
PWR Data Point Library Reference File Report Date Page:
09-30-2003 5
11 tj f-71 t
Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point
Description:
Generic / Condition
Description:
Analog I Digital:
ENGR Units I Digital States:
ENGR Units Conversion:
Minimum Instrument Range:
Maximum Instrument Range:
Zero Point
Reference:
Reference Point Notes Proc or Sens:
Number of Sensors:
How Processed:
Sensor Locations Alarm I Trip Setpoints:
NI Detector Power Supply Cut-Off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation for DP Transmitters:
Level Reference Leg:
Unique System
Description:
9/30/2003 CC2 CC21 CORE FLOW F131A RCS TOTAL FLOW CH A TOTAL REACTOR COOLANT FLOW A
% FLOW 100% RX COOLANT FLOW = 370,000 GPM
-54.35 153.68 N/A N/A S
1 N/A N/A N/A N/A N/A N/A N
N/A REACTOR COOLANT FLOW IS DETERMINED BY THE D/P ACROSS THE STEAM GENERATORS. WHERE TOTAL FLOW IS THE SUM OF BOTH LOOP FLOWS.