BSEP 02-0113, No. 1 - Notification of Emergency Response Data System Modification

No. 1 - Notification of Emergency Response Data System Modification

ML021680082
Person / Time
Site:	Brunswick
Issue date:	06/06/2002
From:	O'Neil E Carolina Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 02-0113 C51C0010
Download: ML021680082 (4)

Text

n~ CP&L A Progress Energy Company JUN 0 6 2002 SERIAL: BSEP 02-0113 10 CFR 50, Appendix E U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 DOCKET NO. 50-325/LICENSE NO. DPR-71 NOTIFICATION OF EMERGENCY RESPONSE DATA SYSTEM MODIFICATION Ladies and Gentlemen:

On June 9, 1992 (Serial: NLS-92-140), Carolina Power & Light (CP&L) 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. On June 1, 2002, CP&L implemented extended power uprate on Unit 1. As a result, the "Engr Units Conversion" field for data point C51COO10, "NI POWER RNG," has been revised to reflect the uprated thermal power level. The enclosure to this letter provides an updated Data Point Library Reference File sheet for Unit 1.

Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor Licensing/Regulatory Programs, at (910) 457-2073.

Sincerely, Edward T. O'Neil Manager - Regulatory Affairs Brunswick Steam Electric Plant MAT/mat

Enclosure:

Revised Data Point Library File Sheet - Unit 1 - Data Point C51CO010 Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461

Document Control Desk BSEP 02-0113 / Page 2 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, MID 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 NO. 1 DOCKET NO. 50-325/LICENSE NO. DPR-71 NOTIFICATION OF EMERGENCY RESPONSE DATA SYSTEM MODIFICATION REVISED DATA POINT LIBRARY FILE SHEET - UNIT 1 DATA POINT C51CO010

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.:

06/01/02 BKI N/A NI POWER RNG C51CO010 RX VALIDATED POWER - - READOUT Nuclear Instruments, Power Range A

Linear (APRM reading); 1% = 29.23 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+1 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.