GO2-02-035, Emergency Response Data System, Change to Data Point Library
| ML020720053 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/28/2002 |
| From: | Coleman D Energy Northwest |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GO2-02-035 | |
| Download: ML020720053 (2) | |
Text
ENERGY NORTH WEST PO. Box 968 n Richland, Washington 99352-0968 February 28, 2002 G02-02-035 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
COLUMBIA GENERATING STATION, OPERATING LICENSE NPF-21 EMERGENCY RESPONSE DATA SYSTEM, CHANGE TO DATA POINT LIBRARY The following information is provided to the NRC in accordance with Title 10 of the Code of Federal Regulation (CFR) Part 50, Appendix E,Section VI.3a requirements. This regulation requires, in part, that hardware and software changes that affect the transmitted data points identified in the Emergency Response Data System (ERDS) Data Point Library be submitted to the NRC within 30 days after the changes are completed.
On February 18, 2002, the Main Steam Line A Rad Level (NRC ERDS Parameter: MN-STM-RAD 1) setpoints were changed.
The Upscale HiHi Trip was changed from 2570mR/hr to 3093mR/hr and the Upscale Hi Alarm Trip was changed from 1500mR/hr to 2400mR/hr.
Please see the attached ERDS Data Point Library reference file with the changes noted above.
Should you have any questions or desire additional information regarding this matter, please contact Ms. CL Perino at (509) 377-2075.
Respectfully, DW Coleman, Manager Performance Assessment and Regulatory Programs Mail Drop PE20
Attachment:
as noted cc:
EW Merschoff - NRC RIV TC Poindexter - Winston & Strawn JS Cushing - NRC NRR DL Williams - BPA - 1399 NRC Senior Resident Inspector - 988C 04 9(5
DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point Desc.:
Generic/Cond Desc.:
Analog/Digital:
Engr Units/Dig States:
Engr Units Conversion:
Minimum Instr Range:
Maximum Instr Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Set Points:
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 Desc.:
18-Feb-02 WP2 N/A MN-STM-RAD I X169 MAIN STEAM LINE A RAD LEVEL Main Steam Line Rad Level 1 A
MR/H N/A 1
1000000 N/A N/A S
1 N/A Reactor Building, 508' Level See description N/A N/A Cannot be predicted N
N/A One of four MS Line Monitors which provide trips to RPS in the event of high rad conditions. Alarm/Trip setpoints: Upscale HiHi Trip = 3093 MR/HR (RPS trip). Upscale Hi Alarm Trip = 2400 MR/HR S:AEPWORK\\ERDS\\ERDSDP revised.DOC 20