05000324/LER-2013-003, Cancellation of LER 13-003-00 for Brunswick, Units 1 and 2
| ML14176A133 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/13/2014 |
| From: | Hamrick G Duke Energy Carolinas, Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BSEP 14-0059 LER 13-003-00 | |
| Download: ML14176A133 (2) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat |
| 3242013003R00 - NRC Website | |
text
George T. Hamrick Vice President ENERGY.
Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461 o: 910.457.3698 JUN 13 2014 10 CFR 50.73 Serial: BSEP 14-0059 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Cancellation of Licensee Event Report 1-2013-003
Reference:
Letter from George T. Hamrick (Duke Energy) to U. S. Nuclear Regulatory Commission (Serial: BSEP 13-0123), Licensee Event Report 1-2013-003, Operation Prohibited by Technical Specifications - Service Water System Inoperability, dated November 14, 2013, ADAMS Accession Number ML13338A580 On November 14, 2013, Duke Energy Progress, Inc., submitted Licensee Event Report (LER) 1-2013-003 in accordance with 10 CFR 50.73 (a)(2)(i)(B) as a condition prohibited by the plant's Technical Specifications (TSs) and 10 CFR 50.73(a)(2)(v)(B) as a condition that could have prevented fulfillment of the safety function of a system needed to remove residual heat.
This report was made based on a determination that the aggregate effect of identified openings in the service water (SW) building could have resulted in submergence of the motor operated discharge valves for the ten Unit 1 and Unit 2 SW system pumps in the event of a design basis probable maximum hurricane (PMH).
The original evaluation of the aggregate effect of identified openings in the SW building was based on an overly conservative estimate of the design basis PMH duration. A more detailed evaluation, which included use of a corrected design basis PMH duration that is consistent with the original design basis analysis and the original Final Safety Analysis Report (FSAR), has demonstrated that a design basis PMH does not submerge the SW discharge valves. Therefore, there was no associated TS inoperability nor was there a condition that could have prevented fulfillment of the SW system safety function. As such, LER 1-2013-003 is formally withdrawn.
This letter contains no regulatory commitments. Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager - Regulatory Affairs, at (910) 457-2487.
Sincerely, George T. Hamrick MAT/mat
U.S. Nuclear Regulatory Commission Page 2 of 2 cc:
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Victor M. McCree, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510