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| number = ML070990198 | | number = ML070990198 | ||
| issue date = 04/02/2007 | | issue date = 04/02/2007 | ||
| title = | | title = Submittal of Cycle 18 Core Operating Limits Report, Supplemental Reload Licensing Report, and Loss-of-Coolant Accident Analysis Report | ||
| author name = Ivey R | | author name = Ivey R | ||
| author affiliation = Progress Energy Carolinas, Inc | | author affiliation = Progress Energy Carolinas, Inc | ||
| addressee name = | | addressee name = | ||
| Line 20: | Line 20: | ||
==Subject:== | ==Subject:== | ||
Brunswick Steam Electric Plant, Unit No. 2 Docket No. 50-324/License No. DPR-62 Unit 2 Cycle 18 Core Operating Limits Report, Supplemental Reload Licensing Report, and Loss-of-Coolant Accident Analysis Report Ladies and Gentlemen: | Brunswick Steam Electric Plant, Unit No. 2 Docket No. 50-324/License No. DPR-62 Unit 2 Cycle 18 Core Operating Limits Report, Supplemental Reload Licensing Report, and Loss-of-Coolant Accident Analysis Report Ladies and Gentlemen: | ||
Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc., herein submits the latest revision of the Core Operating Limits Report, Supplemental Reload Licensing Report, and Loss-of-Coolant Accident Analysis Report for the Brunswick Steam Electric Plant (BSEP), Unit No. 2.Technical Specification 5.6.5.d requires that the Core Operating Limits Report be provided to the NRC, upon issuance, for each reload cycle. Enclosure 1 provides a copy of Brunswick Unit 2, Cycle 18 Core Operating Limits Report, dated March 2007.A copy of 0000-0052-0675-SRLR, Revision 0, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 17 Cycle 18, dated February 2007, is provided in Enclosure | Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc., herein submits the latest revision of the Core Operating Limits Report, Supplemental Reload Licensing Report, and Loss-of-Coolant Accident Analysis Report for the Brunswick Steam Electric Plant (BSEP), Unit No. 2. | ||
Technical Specification 5.6.5.d requires that the Core Operating Limits Report be provided to the NRC, upon issuance, for each reload cycle. Enclosure 1 provides a copy of Brunswick Unit 2, Cycle 18 Core Operating Limits Report, dated March 2007. | |||
GNF-A requests that the enclosed proprietary information be withheld from public disclosure in accordance with the provisions of 10 CER 2.390 and 9.17.Progress Energy Carolinas, Inc.Brunswick Nuclear Plant P0 Box 10429 Southport, NC 2B461 Document Control Desk BSEP 07-0026 / Page 2 No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Ms. Annette H. Pope, Supervisor | A copy of 0000-0052-0675-SRLR, Revision 0, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 17 Cycle 18, dated February 2007, is provided in Enclosure 2. A copy of NIEDC-31624P, Supplement 2, Revision 10, Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2 Reload 17 Cycle 18, dated January 2007, is provided in Enclosure 3. contains information that Global Nuclear Fuel - Americas, LLC (GNF-A) considers to be proprietary as defined by 10 CER 2.390. GNTF-A, as the owner of the proprietary information, has executed the affidavit provided in Enclosure 4, which identifies that the enclosed proprietary informnation has been handled and classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure. GNF-A requests that the enclosed proprietary information be withheld from public disclosure in accordance with the provisions of 10 CER 2.390 and 9.17. | ||
-Licensing/Regulatory Programs, at (910) 457-2184.Sincerely, Zey c j Randy C. Ivey Manager -Support Services Brunswick Steam Electric Plant WRMV~wrm | Progress Energy Carolinas, Inc. | ||
Brunswick Nuclear Plant P0 Box 10429 Southport, NC 2B461 | |||
Document Control Desk BSEP 07-0026 / Page 2 No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Ms. Annette H. Pope, Supervisor - Licensing/Regulatory Programs, at (910) 457-2184. | |||
Sincerely, Zey c j Randy C. Ivey Manager - Support Services Brunswick Steam Electric Plant WRMV~wrm | |||
==Enclosures:== | ==Enclosures:== | ||
: 1. Brunswick Unit 2, Cycle 18 Core Operating Limits Report, March 2007 2. 0000-0052-0675-SRLR, Revision 0, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 17 Cycle 18, February 2007 3. NEDC-31624P, Supplement 2, Revision 10, Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2 Reload 17 Cycle 18, January 2007 (Proprietary Information | : 1. Brunswick Unit 2, Cycle 18 Core Operating Limits Report, March 2007 | ||
-Withhold from Public Disclosure In Accordance With 10 CFR 2.390 and 10 CFR 9.17)4. Global Nuclear Fuels Affidavit Regarding Withholding NEDC-31624P, Supplement 2, Revision 10, from Public Disclosure Document Control Desk BSEP 07-0026 / Page 3 cc (with enclosures): | : 2. 0000-0052-0675-SRLR, Revision 0, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 17 Cycle 18, February 2007 | ||
U. S. Nuclear Regulatory Commission, Region 11 ATTN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-893 1 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: Mr. Stewart N. Bailey (Mail Stop OWFN 8B1)11555 Rockville Pike Rockville, MID 20852-273 8 cc (without enclosures): | : 3. NEDC-31624P, Supplement 2, Revision 10, Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2 Reload 17 Cycle 18, January 2007 (Proprietary Information - Withhold from Public Disclosure In Accordance With 10 CFR 2.390 and 10 CFR 9.17) | ||
Chair -North Carolina Utilities Comm-ission P.O. Box 29510 Raleigh, NC 27626-05 10}} | : 4. Global Nuclear Fuels Affidavit Regarding Withholding NEDC-31624P, Supplement 2, Revision 10, from Public Disclosure | ||
Document Control Desk BSEP 07-0026 / Page 3 cc (with enclosures): | |||
U. S. Nuclear Regulatory Commission, Region 11 ATTN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-893 1 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: Mr. Stewart N. Bailey (Mail Stop OWFN 8B1) 11555 Rockville Pike Rockville, MID 20852-273 8 cc (without enclosures): | |||
Chair - North Carolina Utilities Comm-ission P.O. Box 29510 Raleigh, NC 27626-05 10}} | |||
Latest revision as of 02:24, 15 January 2025
| ML070990198 | |
| Person / Time | |
|---|---|
| Site: | Brunswick |
| Issue date: | 04/02/2007 |
| From: | Ivey R Progress Energy Carolinas |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| BSEP 07-0026 | |
| Download: ML070990198 (3) | |
Text
kg~Progress Energy APR 0.2 200 7 SERIAL: BSEP 07-0026 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit No. 2 Docket No. 50-324/License No. DPR-62 Unit 2 Cycle 18 Core Operating Limits Report, Supplemental Reload Licensing Report, and Loss-of-Coolant Accident Analysis Report Ladies and Gentlemen:
Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc., herein submits the latest revision of the Core Operating Limits Report, Supplemental Reload Licensing Report, and Loss-of-Coolant Accident Analysis Report for the Brunswick Steam Electric Plant (BSEP), Unit No. 2.
Technical Specification 5.6.5.d requires that the Core Operating Limits Report be provided to the NRC, upon issuance, for each reload cycle. Enclosure 1 provides a copy of Brunswick Unit 2, Cycle 18 Core Operating Limits Report, dated March 2007.
A copy of 0000-0052-0675-SRLR, Revision 0, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 17 Cycle 18, dated February 2007, is provided in Enclosure 2. A copy of NIEDC-31624P, Supplement 2, Revision 10, Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2 Reload 17 Cycle 18, dated January 2007, is provided in Enclosure 3. contains information that Global Nuclear Fuel - Americas, LLC (GNF-A) considers to be proprietary as defined by 10 CER 2.390. GNTF-A, as the owner of the proprietary information, has executed the affidavit provided in Enclosure 4, which identifies that the enclosed proprietary informnation has been handled and classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure. GNF-A requests that the enclosed proprietary information be withheld from public disclosure in accordance with the provisions of 10 CER 2.390 and 9.17.
Progress Energy Carolinas, Inc.
Brunswick Nuclear Plant P0 Box 10429 Southport, NC 2B461
Document Control Desk BSEP 07-0026 / Page 2 No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Ms. Annette H. Pope, Supervisor - Licensing/Regulatory Programs, at (910) 457-2184.
Sincerely, Zey c j Randy C. Ivey Manager - Support Services Brunswick Steam Electric Plant WRMV~wrm
Enclosures:
- 1. Brunswick Unit 2, Cycle 18 Core Operating Limits Report, March 2007
- 2. 0000-0052-0675-SRLR, Revision 0, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 17 Cycle 18, February 2007
- 3. NEDC-31624P, Supplement 2, Revision 10, Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2 Reload 17 Cycle 18, January 2007 (Proprietary Information - Withhold from Public Disclosure In Accordance With 10 CFR 2.390 and 10 CFR 9.17)
- 4. Global Nuclear Fuels Affidavit Regarding Withholding NEDC-31624P, Supplement 2, Revision 10, from Public Disclosure
Document Control Desk BSEP 07-0026 / Page 3 cc (with enclosures):
U. S. Nuclear Regulatory Commission, Region 11 ATTN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-893 1 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: Mr. Stewart N. Bailey (Mail Stop OWFN 8B1) 11555 Rockville Pike Rockville, MID 20852-273 8 cc (without enclosures):
Chair - North Carolina Utilities Comm-ission P.O. Box 29510 Raleigh, NC 27626-05 10