ML20033E085
| ML20033E085 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/28/1990 |
| From: | Loflin L CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19293A171 | List: |
| References | |
| NLS-90-050, NLS-90-50, NUDOCS 9003080420 | |
| Download: ML20033E085 (4) | |
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Carolina Power & Light Company
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l FEB 2 81990 SERIAL: NLS-90 050 l
j United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 l
DOCKET No. 50-324/ LICENSE NO. DPR-62 TRANSMITTAL OF LOCA REPORT AND SUPPLEMENTAL REIAAD LICENSING REPORT Gentlemen:
On' November 17, 1988, the Nuclear Regulatory Commission (NRC) approved Amendment 19 to General Electric Company (CE) document NEDE 24011-P A
-(CESTAR II). Amendment 19 to GESTAR II supported the elimination of linear i
- heat generation rate (LHGR) from the Technical Specifications for boiling water reactors. Elimination of LHGR from the Brunswick Unit 2 Technical
-Specifications was approved by the NRC via Amendment No. 161 dated May 25, 1989.
Subsequently, on June 1,1989, the NRC approved the use of the SAFER /GESTR loss of coolant accident (LOCA) methodology for future revisions of the Brunswick Plant LOCA licensing basis. The updated Brunswick Unit 2 LOCA licensing basis for the upcoming cycle which provides
.information'in accordance with the NRC Safety Evaluation for Amendment 19 to GESTAR-II is contained in the enclosed document titled " Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2
' Reload 8, Cycle 9," NEDE-31624P, Supplement 2, Revision 0.
.This report is classified as proprietary by GE; therefore, an affidavit for withholding the report from public disclosure in accordance with 10 CFR 2.790 is also enclosed.
In addition, GE has indicated to the NRC that each non proprietary reload submittal by licensees would include a table of the most limiting and least
~ limiting MAPLHGR for each multiple lattice fuel bundle type.
This
-information 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 8 Cycle 9," 23A6456, Rev. O is enclosed.
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'Please' refer any questions regarding this submittal to Mr. William R.-
'Murray at (919) 546-4661.
Yours very truly.
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-V' Leo I flin Manage Nuclear Licens ng Section-
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Mr. S. D. Ebneter Mr.~ W. H. Ruland Mr. E. G. Tourigny t
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