View source for BSEP-96-0026, Forwards Rev 0 to NF-2495.0080, Brunswick Unit 2,Cycle 12 Core Operating Limits Rept,non-proprietary Rev 0 to 24A5195, Proprietary Rev 3 to NEDC-31624P & Rev 0 to NEDC-31624P. Encls Withheld (Ref 10CFR2.790)

{{Adams
| number = ML20101B622
| issue date = 03/04/1996
| title = Forwards Rev 0 to NF-2495.0080, Brunswick Unit 2,Cycle 12 Core Operating Limits Rept,non-proprietary Rev 0 to 24A5195, Proprietary Rev 3 to NEDC-31624P & Rev 0 to NEDC-31624P. Encls Withheld (Ref 10CFR2.790)
| author name = Hicks G
| author affiliation = CAROLINA POWER &amp; LIGHT CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000324
| license number = 
| contact person = 
| document report number = BSEP-96-0026, BSEP-96-26, NUDOCS 9603140391
| package number = ML19355C768
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 4
}}

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CP&L Carolina Power & Light Company P.O. Box 10429 Southport, NC 28461-0429                                                                               l MAR     4 1996                                                                                        !
SERIAL: BSEP 96-0026                                                                                   i U. S. Nuclear Regulatory Commission                                                                    ,
ATTENTION: Document Control Desk                                                                       '
Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NO. DPR-62                                                                  1 TRANSMITTAL OF CORE OPERATING LIMITS REPORT, SUPPLEMENTAL RELOAD LICENSING REPORT, AND LOSS-OF-COOLANT-ACCIDENT ANALYSIS REPORT i
Gentlemen:
The purpose of this letter is to submit, in accordance with Technical Specification 6.9.3.4, a copy of the Core Operating Limits Report for the Brunswick Steam Electric Plant, Unit 2. A copy of the
       " Brunswick Unit 2, Cycle 12 Core Operating Limits Report, February 1996," Revision 0, approved February 1,1996 for Brunswick Unit 2, Cycle 12 is provided in Enclosure 1.
With each non-proprietary re?oad submittal, licensees must include a tab!e of the most limiting and least limiting Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for each multiple lattice fuel type. This information for each fuel type is located in the Supplemental Reload Licensing Report for Brunswick Unit 2. A copy of the " Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 11 Cycle 12," 24A5195, Revision 0 is provided in Enclosure 2.
Enclosure 3 to this letter provides a copy of the " Loss-of-Coolant Accident Analysis Report for the Brunswick Steam Electric Plant, Unit 2, Reload 11 Cycle 12"(NEDC-31624P, Supplement 2, Revision 3). This report contains MAPLHGR values for the General Electric Nuclear Energy fuel designs to be loaded into Brunswick Unit 2 for Cycle 12. The document contained in Enclosure 3 is considered General Electric Nuclear Energy proprietary information and should be withheld from public disclosure in accordance with 10 CFR 2.790. An affidavit attesting to this fact is provided in Enclosure 4.
Enclosure 5 to this letter provides a copy of the " Brunswick Steam Electric Plant Units 1 and 2 SAFER /GESTR-LOCA Loss-Of-Coolant Accident Analysis: Application to GE13 Fuel" (NEDC-31624P, Supplement 3, Revision 0). The document contained in Enclosure 5 is considered General Electric Nuclear Energy proprietary information and should be withheld from public disclosure in accordance with 10 CFR 2.790. An affidavit attesting to this fact is provided in Enclosure 6.
9603140391 960304 h
i PDR     ADOCK 05000324 P                       PDR
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Document Control Desk BSEP 96-0026 / Page 2 Please refer any questions regarding this submittal to Mr. George Honma at (910) 457-2741.
Rincorel N
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                                                                        /
C. D. l l;ar Manager- Regulatory Affairs Brunswick Nuclear Plant WRM/wrm Enclosures
: 1. Brunswick Unit 2, Cycle 12 Core Operating Limits Report, February 1996, Revision 0
: 2. Supplemental Reload Licensing Report for Brunswick Unit 2 Reload 11 Cycle 12
: 3. Loss-of-Coolant Accident Analysis Report for the Brunswick Steam Electric Plant, Unit 2, Reload 11 Cycle 12
: 4. General Electric Nuclear Energy Affidavit Regarding Withholding from Public Disclosure in Accordance with 10 CFR 2.790
: 5. SAFER /GESTR-LOCA Loss-of-coolant Accident Analysis: Application to GE13 Fuel
: 6. General Electric Nuclear Energy Affidavit Regarding Withholding from Public Disclosure in Accordance with 10 CFR 2.790 i
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Document Control Desk BSEP 96-0026 / Page 3 cc (with enclosures):
U. S. Nuclear Regulatory Commission                            l ATTN.: Mr. Stewart D. Ebneter, Regional Administrator          '
101 Marietta Street, N.W., Suite 2900 Atlanta, GA 30323-0199 Mr. C. A. Patterson NRC Senior Resident inspector- Brunswick Units 1 and 2:
U.S. Nuclear Regulatory Commission                             l ATTN.: Mr. David C. Trimble, Jr. (Mail Stop OWFN 14B20)        q 11555 Rcckville Pike Rockville, MD 20852-2738 cc (without enclosures 3 and 5):
The Honorable H. Wells Chairman - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 l
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ENCLOSURE 1 1
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NO, DPR-62 TRANSMITTAL OF CORE OPERATING LIMITS REPORT, SUPPLEMENTAL RELOAD                     l LICENSING REPORT, AND LOSS-OF-COOLANT-ACCIDENT ANALYSIS REPORT P
BRUNSWICK UNIT 2, CYCLE 12 CORE OPERATING LIMITS REPORT t
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