ML20247H832
| ML20247H832 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/25/1989 |
| From: | Loflin L CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19292J340 | List: |
| References | |
| NLS-89-214, NUDOCS 8907310149 | |
| Download: ML20247H832 (3) | |
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. Carolina Power & Ught Company
'JUL 2 51989 SERIAL: NLS-89-214.
'linited States Nuclear Regulatory Commission 2
ATTENTION: Document Control Desk Washington,LDC -20555.
' BRUNSWICK. STEAM ELECTRIC FLANT,' UNIT NOS. 1-AND 2 DOCKET NOS. 50-325'& 50-324/ LICENSE NOS. DPR-71 & DPR-62
. TRANSMITTAL OF LOCA REPORTS:
Gentlemen:
On November-17., 1988 the Nuclear Regulatory Commission approved Amendment 19 to General Electric Company (CE) document NEDE-24011-P-A (CESTAR II).
Amendment 19 to GESTAR-II supports the elimination of linear heat generation rate (LHGR) from the Technical Specifications for boiling water reactors.
Elimination of'UlGR from the Brunswick Plant Technical Specifications was
-approved by Amendments 131 and'161 dated May 25, 1989. To coincide with implementation of Amendments 131 and 161 to the Brunswick Technical Specifications, Carolina Power & Light Company is providing information/ as described below.. in accordance with the Safety Evaluation for Amendment' 19 to '
CESTAR-II.
!In conjunction with Amendment 19 to GESTAR-II, GE committed licensees to submit to the NRC, on a proprietary basis, a copy of the information that will be'available to the operator in the plant control room. This.information for each fuel bundle-type consists of:
1.
The axial location of each lattice in the bundle.
'2.
The. composite MAPLHGR, considering both thermal-mechanical and emergency core cooling system requirements, as a function of average exposure for each lattice in the bundle.
General' Electric airo committed licensees to provido a bundle description including tho'same type of information found in GESTAR-II for any fuel bundle type included in.a reload which is not included in CESTAR-II or one of its approved amendments.
The above information is contained in the Loss-of-Coolant Accident Analysis.
Reports for Unit 1, Cycle 7 and Unit 2, Cycle 8, the current cycles for each unit. These reports are classified as proprietary by GE.
One copy each of the " Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric i
Plant Unit 1," NEDE-24165-P, Rev. 1 and the " Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2," NEDE-24053-P, Rev. 2 are p;
enclosed.
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Document Contre >l Desk NLS-89-214 / Page 2 i
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In addition, GE indicated that each non-proprietary reload submittal would include a table of the most limiting and least limiting MAPLHGR for each j
multiple lattice fuel bundle type. This information is located in the Supplemental Reload Licensing Report for each Brunswick Unit.
A copy of the
" Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 1 Reload 6 Cycle 7," 23A5896, Rev. 1 and the " Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 7 Cycle 8,"
23A5855, Rev. I are enclosed.
Enclosed are affidavits for withholding the above referenced Loss-of-Coolant l
Accident Analysis Reports for Unit 1 and Unit 2 as information proprietary to GE.
Please refer any questions regarding this submittal to Mr. William R. Murray at (919) 546 6561.
Yours very truly, O
>P s
Leon r oflin Manage -
Nuclear Licens ng Section WRM/wrm
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Enclosures cc:
Mr. S. D. Ebneter Mr. W. H. Ruland Mr. E. G. Tourigny
I ENCIDSURE 4 SUPPLEMENTAL RE1 DAD LICENSING REPORT BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 RELOAD 6, CYCLE 7 23A5896, REV. 1 s
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