ML033080099

Emergency Response Data System

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

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Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Constellation Generation Group, LLC Lusby, Maryland 20657 Constellation Energy Group October 29, 2003 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

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 H. J. Miller, NRC J. E. Silberg, Esquire Resident Inspector, NRC Director, Project Directorate I-1, NRC R. I. McLean, DNR G. S. Vissing, NRC J. R. Jolicoeur, NRC MOLi9

PWR Data Point Library Reference File Report Date 09-30-2003 Page: 5 Il Date: 9/27/2001 Reactor Unit: CC2 Data Feeder: CC21 NRC ERDS Parameter: CORE FLOW Point ID: F131A Plant Specific Point

Description:

RCS TOTAL FLOW CH A Generic / Condition

Description:

TOTAL REACTOR COOLANT FLOW Analog / Digital: A ENGR Units / Digital States:  % FLOW ENGR Units Conversion: 100% RX COOLANT FLOW = 370,000 GPM Minimum Instrument Range: -52.63 Maximum Instrument Range: 148.83 Zero Point

Reference:

N/A Reference Point Notes N/A Proc or Sens: S Number of Sensors: 1 How Processed: N/A Sensor Locations N/A Alarm I Trip Setpoints: 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: NIA Temperature Compensation

-for DP -Transmitters: N Level Reference Leg: N/A Unique System

Description:

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 09-30-2003 Page: 5 11tj f- 71 t Date: 9/30/2003 Reactor Unit: CC2 Data Feeder: CC21 NRC ERDS Parameter: CORE FLOW Point ID: F131A Plant Specific Point

Description:

RCS TOTAL FLOW CH A Generic / Condition

Description:

TOTAL REACTOR COOLANT FLOW Analog I Digital: A ENGR Units I Digital States:  % FLOW ENGR Units Conversion: 100% RX COOLANT FLOW = 370,000 GPM Minimum Instrument Range: -54.35 Maximum Instrument Range: 153.68 Zero Point

Reference:

N/A Reference Point Notes N/A Proc or Sens: S Number of Sensors: 1 How Processed: N/A Sensor Locations N/A Alarm I Trip Setpoints: 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: N/A Temperature Compensation for DP Transmitters: N Level Reference Leg: N/A Unique System

Description:

REACTOR COOLANT FLOW IS DETERMINED BY THE D/P ACROSS THE STEAM GENERATORS. WHERE TOTAL FLOW IS THE SUM OF BOTH LOOP FLOWS.