ML042610122
| ML042610122 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/09/2004 |
| From: | O'Neil E Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BSEP 04-0127 | |
| Download: ML042610122 (3) | |
Text
Progress Energy 10 CFR 50.46(a)(3)(ii)
SEP 0.9 2004 SERIAL: BSEP 04-0127 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket Nos. 50-325 and 50-324/License Nos. DPR-71 and DPR-62 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models Ladies and Gentlemen:
This letter provides the annual report of Emergency Core Cooling System (ECCS) evaluation model changes and errors for the peak cladding temperature (PCT) for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc., is providing this information in accordance with the requirements of 10 CFR 50.46(a)(3)(ii).
10 CFR 50.46(a)(3)(ii) specifies reporting requirements based on the sum of the absolute value of the changes and errors in calculated PCT, including a requirement that the estimated effect of changes and errors on the limiting ECCS analysis be reported at least annually as specified in 10 CFR 50.4. If the change or error is significant, the applicant or licensee is required to provide this report within 30 days and include with the report a proposed schedule for providing a reanalysis or taking other action as may be needed to show compliance with 10 CFR 50.46 requirements.
The previous annual report for BSEP, Units 1 and 2, was submitted by PEC's letter dated July 9, 2003 (i.e., ADAMS Accession Number ML031980462). During the time period since the last annual report, one change notification has been issued by General Electric Nuclear Energy. PEC has reviewed the change notification and concluded that the effect of changes to, or errors in, the evaluation model on the limiting transient PCT is not significant; therefore, the report of the ECCS evaluation model changes continues to be provided on an annual basis.
Enclosed is a copy of Calculation 0B21-0112, Revision 11, 10 CFR 50.46 SAFER/GESTR-LOCA ECCS Analysis Update, which summaries the effects of the currently reported loss-of-coolant accident analysis changes and errors for the GE13 and GE14 fuel types in use in BSEP, Units 1 and 2. This calculation includes changes and errors in the BSEP, Unit 1 and 2 LOCA analysis for the period ending August 10, 2004.
Progress Energy Carolinas. Inc.
Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461
Document Control Desk BSEP 04-0127/ Page 2 No regulatory commitments are provided in this submittal. 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 - Support Services Brunswick Steam Electric Plant WRM/wrm
Enclosure:
Brunswick Steam Electric Plant, Units 1 and 2, Calculation Number OB21-0112, Revision 11, 10 CFR 50.46 SAFER/GESTR-LOCA ECCS Analysis Update
Document Control Desk BSEP 04-0127 / Page 3 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Eugene M. DiPaolo, 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 OWEN 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