BSEP 02-0073, Notification of Emergency Response Data System Modification
| ML021070571 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/02/2002 |
| From: | Dicello D Carolina Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| BSEP 02-0073 | |
| Download: ML021070571 (5) | |
Text
C P&L A Progrews Energy Company APR 0 2 2002 SERIAL: BSEP 02-0073 10 CFR 50, Appendix E U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 NOTIFICATION OF EMERGENCY RESPONSE DATA SYSTEM MODIFICATION Ladies and Gentlemen:
On June 9, 1992 (Serial: NLS-92-140), Carolina Power & Light Company submitted the Emergency Response Data System (ERDS) Data Point Library for the Brunswick Steam Electric Plant, Units 1 and 2. In accordance with 10 CFR 50, Appendix E, Section VI.3.a, this letter provides notification of a change to a transmitted data point in the Unit 1 ERDS Data Point Library. As a result of installation of a new digital Power Range Neutron Monitoring (PRNM) system on Unit 1, the number of Average Power Range Monitor (APRM) inputs to data point C51C0010, "NI POWER RNG," was changed from six to four.
This change was made on March 27, 2002. Additionally, it was noted that the "Engr Units Conversion" field required updating to accurately reflect rated thermal power of the units.
The Enclosure to this letter provides: (1) an updated Data Point Library Reference File sheet for Unit 1, revising the "Number of Sensors" field and the "Engr Units Conversion" field, and (2) an updated Data Point Library Reference File sheet for Unit 2, revising only the "Engr Units Conversion" field.
Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor Licensing/Regulatory Programs, at (910) 457-2073.
Sincerely, David C. DiCello Manager - Regulatory Affairs Brunswick Steam Electric Plant MAT/mat 6>49 Brunswick Nuclear Plant
'* \\c P.O. Box 10429 Southport, NC 28461
Document Control Desk BSEP 02-0073 / Page 2
Enclosure:
Revised Data Point Library File Sheets - Units 1 and 2 - Data Point C51COO10 cc:
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Theodore A. Easlick, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Ms. Brenda L. Mozafari (Mail Stop OWFN 8G9) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510
ENCLOSURE BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 NOTIFICATION OF EMERGENCY RESPONSE DATA SYSTEM MODIFICATION REVISED DATA POINT LIBRARY FILE SHEETS - UNITS 1 AND 2 DATA POINT C51COO10
Page 10 DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Spec 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.:
05/27/02 BK1 N/A NI POWER RNG C51CO010 RX VALIDATED POWER - - READOUT Nucleair Instruments. Power Range A
Linear (APRM reading); 1% = 25.58 MWt 0.OOE+00
- 0. 125E+03 N/A N/A P
4 (APRM inputs)
APRM Weighted average
- Gain Adj Factor APRM signals to Control Room meters LOW = 0.300E+l N/A N/A N/A, need > 2 inputs for GOOD N/A N/A Gain Adj Factor is processed from various heat-balance related sensors. APRM input points default to actual values when inputs exceed signal ranges.
Page 61 DATA POINT LIBRARY REFERENCE FILE Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Spec 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.:
05/27/02 BK2 N/A NI POWER RNG C51CO010 RX VALIDATED POWER - - READOUT Nuclear Instruments, Power Range A
Linear (APRM reading); 1% = 25.58 MWt 0.00E+00
- 0. 125E+03 N/A N/A P
6 (APRM inputs)
APRM Weighted average