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=Text=
=Text=
{{#Wiki_filter:i I
{{#Wiki_filter: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:
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:==
==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.
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:
The table below provides a brief summary of the changes:
Description -       ;Previous Range                     New Range--
Description -
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.
;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.
Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, t4'tLC_
Very truly yours, t4'tLC_
Line 28: Line 30:


==Attachment:==
==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
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       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
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:==
== Description:==
RCS TOTAL FLOW CH A Generic / Condition
Generic / Condition


== Description:==
== 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  
Analog / Digital:
ENGR Units / Digital States:
ENGR Units Conversion:
Minimum Instrument Range:
Maximum Instrument Range:
Zero Point  


==Reference:==
==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
Reference Point Notes Proc or Sens:
-for DP -Transmitters:                 N Level Reference Leg:                 N/A Unique System
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:==
== Description:==
REACTOR COOLANT FLOW IS DETERMINED BY THE DIP ACROSS THE STEAM GENERATORS. WHERE TOTAL FLOW IS THE SUM OF BOTH LOOP FLOWS.
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       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
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:==
== Description:==
RCS TOTAL FLOW CH A Generic / Condition
Generic / Condition


== Description:==
== 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  
Analog I Digital:
ENGR Units I Digital States:
ENGR Units Conversion:
Minimum Instrument Range:
Maximum Instrument Range:
Zero Point  


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

Latest revision as of 06:42, 16 January 2025

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)
v • d • e


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.

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