BSEP-96-0353, Forwards non-proprietary Rev 0 to 24A5376, Suppl Reload Licensing Rept for Bsep,Unit 1 Reload 10 Cycle 11, COLR, Dtd Sept 1996 & Proprietary Rev 3,Suppl 1 to NEDC-31624P, LOCA Analysis Rept & Rev 0,Suppl 3 to NEDC-31624

Forwards non-proprietary Rev 0 to 24A5376, Suppl Reload Licensing Rept for Bsep,Unit 1 Reload 10 Cycle 11, COLR, Dtd Sept 1996 & Proprietary Rev 3,Suppl 1 to NEDC-31624P, LOCA Analysis Rept & Rev 0,Suppl 3 to NEDC-31624

ML20129J089
Person / Time
Site:	Brunswick
Issue date:	11/01/1996
From:	Turkal M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19353D955	List: BSEP-96-0353, Forwards non-proprietary Rev 0 to 24A5376, Suppl Reload Licensing Rept for Bsep,Unit 1 Reload 10 Cycle 11, COLR, Dtd Sept 1996 & Proprietary Rev 3,Suppl 1 to NEDC-31624P, LOCA Analysis Rept & Rev 0,Suppl 3 to NEDC-31624 ML20129J169 ML20129J191
References
BSEP-96-0353, BSEP-96-353, NUDOCS 9611060134
Download: ML20129J089 (7)

Text

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CP&L

- 1 Carolina Power & Light Company P.O. Box 10429 Southport, NC 28461-o429 l

November 1,1996 SERIAL: BSEP 96-0353 1

U. S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 DOCKET NO. 50-325 LICENSE NO. DPR-71 TRANSMITTAL OF CORE OPERATING LIMITS REPORT, SUPPLEMENTAL RELOAD LICENSING REPORT, AND LOSS-OF-COOLANT-ACCIDENT ANALYSIS REPORT 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 1. A copy of the

" Brunswick Unit 1, Cycle 11 Core Operating Limits Report, September 1996," Revision 0, ,

approved October 1996 for Brunswick Unit 1, Cyc'a 11 is provided in Enclosure 1. )

With each non-proprietary reload submittal, licensees must include a table 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 1. A copy of the " Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 1 Reload 10 Cycle 11," 24A5376, 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 1, Reload 10 Cycle 11"(NEDC-31624P, Supplement 1, I Revision 3). This report contains MAPLHGR values for the General Electric Nuclear Energy fuel designs which have been loaded into Brunswick Unit 1 for Cycle 11. 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.

l Enclosure 5 to this letter provides a copy of the " Brunswick Steam Electric Plant Units 1 and 2 l

l 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 'l public disclosure in accordance with 10 CFR 2.790 An affidavit attesting to this fact is provided

! in Enclosure 6. q b i j0 Y OR0090 C(d'y [yj ,

9611060134 961101 ---

PDR ADOCK 05000325 /

P PDR (it M f (UnLs O b K. \ \ tk 0

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L Document Control Desk

BSEP 96-0353 / Page 2 l

' Please refer any questions regarding this submittal to Mr. William Murray at (910) 457-2842. i 1

' Sincerely, l- , .

l: Mark A. Turkal i Supervisor- Licensing  ;

i Brunswick Nuclear Plant '

L WRM/wrm Enclosures . ,

1. Brunswick Unit 1, Cycle 11 Core Operating Limits Report, October 1996, Revision 0 l 2. Supplemental Reload Licensing Report for Brunswick Unit 1 Reload 10 Cycle 11 ,

! 3. Loss-of-Coolant Accident Analysis Report for the' Brunswick Steam Electric Plant, Unit 1,.

Reload 10 Cycle 11 '

4. . General Electric Nuclear Energy Affidavit Regarding Withholding from Public Disclosure in Accordance with 10 CFR 2.790 I 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 f l l -

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Document Control Desk BSEP 96-0353 / Page 3

- cc (with all enclosures): q

' U. S. Nuclear Regulatory Commission ATTN.: Mr. Stewart D. Ebneter, Regional Administrator l 101 Marietta Street, N.1N., Suite 2900  !

Atlanta, GA 30323-0199 Mr. C. A. Patterson NRC Senior Resident inspector - Brunswick Units 1 and 2:

U.S. Nuclear Regulatory Commission ATTN.: Mr. David C. Trimble, Jr. (Mail Stop OWFN 14B20) l 11555 Rockville Pike i Rockville, MD 20852-2738 cc (without enclosures 3 and 5):

The Honorable H. Wells Chairman - North Carolina Utilities Commission l P.O. Box 29510 Raleigh, NC 27626-0510 -

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