ML20247H832: Difference between revisions

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=Text=
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                                                          . Carolina Power & Ught Company
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                                                                      'JUL 2 51989                                                                                                                       >
. Carolina Power & Ught Company
SERIAL: NLS-89-214.
'JUL 2 51989 SERIAL: NLS-89-214.
2                  'linited States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington,LDC -20555.
'linited States Nuclear Regulatory Commission 2
                      ' BRUNSWICK. STEAM ELECTRIC FLANT,' UNIT NOS. 1-AND 2 DOCKET NOS. 50-325'& 50-324/ LICENSE NOS. DPR-71 & DPR-62
ATTENTION: Document Control Desk Washington,LDC -20555.
                      . TRANSMITTAL OF LOCA REPORTS:
' 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:
Gentlemen:
On November- 17., 1988 the Nuclear Regulatory Commission approved Amendment 19 to General Electric Company (CE) document NEDE-24011-P-A (CESTAR II).
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.
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
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 '
-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.
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:
!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.
1.
                                '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.
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.
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.
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
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.
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;
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.
enclosed.
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.PDR ADOCK 0500 4
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dit Fayettevme Street
dit Fayettevme Street
* P. O. Box 1551
* P. O. Box 1551
* Raleigh. N. C. 27602 m.,n . y: wn y,4.qggiggMWMT!gg L=__-                   __---_:--____--_-_-_--______-_a__-____-____             - _ _ _ - - _ _ _ _ _ _ _ _ - _ - _ - _ - - _ - _ _ _ _ _ - _ - _ _ - - - _ _ - _ - - _ _ _ _ - - _ _ _
* 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
Document Contre >l Desk NLS-89-214 / Page 2 i
  " 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,"
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.
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.
Enclosed are affidavits for withholding the above referenced Loss-of-Coolant l
Please refer any questions regarding this submittal to Mr. William R. Murray                       '
Accident Analysis Reports for Unit 1 and Unit 2 as information proprietary to GE.
at (919) 546 6561.
Please refer any questions regarding this submittal to Mr. William R. Murray at (919) 546 6561.
Yours very truly,
Yours very truly, O
                                                              >P   O s
>P s
Leon r       oflin Manage -
Leon r oflin Manage -
Nuclear Licens ng Section WRM/wrm     (\cor\1ocaltr)
Nuclear Licens ng Section WRM/wrm
Enclosures cc:   Mr. S. D. Ebneter Mr. W. H. Ruland Mr. E. G. Tourigny
(\\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
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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Latest revision as of 20:22, 1 December 2024

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:
References
NLS-89-214, NUDOCS 8907310149
Download: ML20247H832 (3)
v • d • e


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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.

89073iOi49 890725 fi

[g

.PDR ADOCK 0500 4

f {

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 NLS-89-214 / Page 2 i

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, O

>P 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

h

.,E__________.

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