ML20247H832

Forwards Proprietary LOCA Analysis Repts for Unit 1,Cycle 7 & Unit 2,Cycle 8 & Nonproprietary Reload Repts Re LHGR for Bwr.Proprietary Repts Withheld

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: ML20247H832 ML20247H841 ML20247H851
References
NLS-89-214, NUDOCS 8907310149
Download: ML20247H832 (3)

Text

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. Carolina Power & Ught Company

'JUL 2 51989 >

SERIAL: NLS-89-214.

2 'linited States Nuclear Regulatory Commission 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 i

the " Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric 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.

89073iOi49 890725 4 fi [g

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dit Fayettevme Street

• P. O. Box 1551

• Raleigh. N. C. 27602 m.,n . y: wn y,4.qggiggMWMT!gg L=__- __---_:--____--_-_-_--______-_a__-____-____ - _ _ _ - - _ _ _ _ _ _ _ _ - _ - _ - _ - - _ - _ _ _ _ _ - _ - _ _ - - - _ _ - _ - - _ _ _ _ - - _ _ _

Document Contre >l Desk i NLS-89-214 / Page 2 f 4 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,

>P O s

Leon r oflin Manage -

Nuclear Licens ng Section WRM/wrm (\cor\1ocaltr)

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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