BSEP-99-0062, Forwards Latest Revs of COLR & Suppl Reload Licensing Rept, for Bsep,Unit 2.Proprietary Rev 6,Suppl 2 to NEDC- 31624P & EMF-2168P,included.Proprietary Encls Withheld, Per 10CFR2.790 & 10CFR9.17

Forwards Latest Revs of COLR & Suppl Reload Licensing Rept, for Bsep,Unit 2.Proprietary Rev 6,Suppl 2 to NEDC- 31624P & EMF-2168P,included.Proprietary Encls Withheld, Per 10CFR2.790 & 10CFR9.17

ML20206N151
Person / Time
Site:	Brunswick
Issue date:	05/11/1999
From:	Jury K CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20137N757	List: BSEP-99-0062, Forwards Latest Revs of COLR & Suppl Reload Licensing Rept, for Bsep,Unit 2.Proprietary Rev 6,Suppl 2 to NEDC- 31624P & EMF-2168P,included.Proprietary Encls Withheld, Per 10CFR2.790 & 10CFR9.17 ML20206N179 ML20206N183
References
BSEP-99-0062, BSEP-99-62, NUDOCS 9905170152
Download: ML20206N151 (3)

Text

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e CP&L Carolina Power & Light Company P.O. Box 10429 Southport. NC 28461-0429 MAY 111999 SERIAL: BSEP99-0062 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NO. DPR-62 TRANSMITTAL OF CORE OPERATING LIMITS REPORT, SUPPLEMENTAL RELOAD LICENSING REPORT, AND LOSS-OF-COOLANT ACCIDENT ANALYSIS RFPORT Gentlemen:

The purpose of this letter is to submit a copy of the latest revision of the Core Operating Limits  ;

Report for the Brunswick Steam Electric Plant (BSEP), Unit No. 2. The report is being 5 submitted in accordance with Technical Specification 5.6.5.

A copy of " Brunswick Unit 2, Cycle 14 Core Operating Limits Report," dated April 1999 is provided in Enclosure 1. A plot of the limiting value of Average Planar Linear Heat Generation Rate (APLHGR), as a function of planar exposure for each reload fuel type, is included in the Core Operating Limits Report.

A copy of " Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 13 Cycle 14," J11-03412SRLR, Revision 0, Class I, dated February 1999, is provided in Enclosure 2. The most limiting and least limiting Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) values for the new reload fuel types are provided in a table

[

included in the Supplemental Reload Licensing Report for BSEP, Unit 2.

]

Enclosure 3 to this letter provides a copy of " Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2 Reload 13 Cycle 14," NEDC-31624P, Supplement 2, Revision 6, Class III, February 1999. This report contains MAPLHGR and hot uncontrolled local peaking factor values for the General Electric Nuclear Energy fuel designs which have been i M

loaded into BSEP, Unit 2 for Cycle 14. '

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 9.17 and 10 CFR 2.790. An affidavit supporting the request for withholding the document is provided in Enclosure 4.

@CC"j: Lir 800f M l '(Nf.M u c n, -

4 p PDR s.

Document Control Desk BSEP 99-0062 / Page 2 The reactor core for BSEP, Unit 2, Cycle 14 will also include pur ATRIUM -10 lead qualification assemblies (LQAs) manufactured by Siemens Power Corporation. The design approach used for the ATRIUM -10 LQA bundles results in the LQA bundles performing comparable to a GE13 fuel bundle and allows the LQA bundles to be monitored as GE13 fuel bundles. Enclosure 5 provides a copy of the Siemens Power Corporation report entitled

" Brunswick ATRIUM -10 lead Qualification Assemblies Safety Analysis," EMF-2168(P),

Revision 0, dated March 1999. The report summarizes evaluations of the ATRIUM -10 LQAs relative to the GE13 fuel bundles and supports the application of modified gel 3 reload fuel bundle operating limits to the LQAs.

The document contained in Enclosure 5 is considered Siemens Power Corporation proprietary information and should be withheld from public disclosure in accordance with 10 CFR 9.17 and 10 CFR 2.790. An affidavit supporting the request for withholding the document is provided in l Enclosure 6.

Please refer any questions regarding this submittal to Mr. Warren J. Dorman, Supervisor -

Licensing, at (910) 457-2068.

Sincerely,

& - 0-Keith R. Jury Manager- Regulatory Affairs Brunswick Steam Electric Plant WRM/wrm

Enclosures:

1. " Brunswick Unit 2, Cycle 14 Core Operating Limits Report," April 1999

2. " Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 13 Cycle 14," Jl1-03124SRLR, Revision 0, Class I, February 1999

3. "I.oss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2 Reload 13 Cycle 14," NEDC-31624P, Supplement 2, Revision 6, Class III, February 1999

[ PROPRIETARY INFORMATION]

4. Affidavit From General Electric Nuclear Energy Regarding Withholding From Public Disclosure In Accordance With 10 CFR 9.17 and 10 CFR 2.790

5. " Brunswick ATRIUM -10 Lead Qualification Assemblies Safety Analysis," EMF-2168(P),

Revision 0, March 1999 [ PROPRIETARY INFORMATIONJ

6. Affidavit From Siemens Power Corporation Regarding Withholding From Public Disclosure In Accordance With 10 CFR 9.17 and 10 CFR 2.790

E ,

Document Control Desk BSEP 99-0062 / Page 3 cc (with all enclosures):

U. S. Nuclear Regulatory Commission, Region 11 i ATTN: Mr. Luis A. Reyes, Regional Administrator l Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-3415-U. S. Nuclear Regulatory Commission ATrN: Mr. Theodore A. Eastick, NRC Senior Resident Inspector 8470 River Road (

Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mr. Al!en G. Hansen (Mail Stop OWFN 8G9)

I 11555 Rockville Pike Rockville, MD 20852-2738 cc (with Enclosures 1,2,4, and 6):

Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 l Raleigh, NC 27626-0510 l

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! ENCLOSUREl l

l l BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 1 DOCKET NO. 50-324

! LICENSE NO. DPR-62 l TRANSMITTAL OF CORE OPERATING LIMITS REPORT, SUPPLEMENTAL RELOAD LICENSING REPORT, AND LOSS-OF-COOLANT ACCIDENT ANALYSIS REPORT BRUNSWICK UNIT 2, CYCLE 14 I

, CORE OPERATING LIMITS REPORT APRIL 1999 I

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