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=Text=
=Text=
{{#Wiki_filter:_---__- --                   _ - . - _ _ , - - _ _ - - _-              .
{{#Wiki_filter:_---__- --
                                                ~
~
4:   a Alabama Power Company '
4:
600 NorFs 38th Street                                                                                                                                                   j
a Alabama Power Company '
                          ' Post Offi 3 Box 2641.                                                                                                                                                   '
600 NorFs 38th Street
Birmingham, Alabama 352914400 '
' Post Offi 3 Box 2641.
Telephone 205 250-1835 .
j Birmingham, Alabama 352914400 '
                          . LM%e";%ioent                                                                                                   Abbm hu                                               1 tre southern electncsystem
Telephone 205 250-1835.
                                                                                                                                            -10CFRSO.4                                             ~I September 15, 1987 Docket No. 50-364
. LM%e";%ioent Abbm hu 1
                                                                                                                                                                                                  ]
tre southern electncsystem
                          . V. S. Nuclear Regulatory Commission ATTN: Document Control Desk                                                                                                                                             ,
-10CFRSO.4
Washington,.D. C. 20555                                                                                                                                                 i Gentlemen:
~I September 15, 1987 Docket No. 50-364
]
. V. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington,.D. C. 20555 i
Gentlemen:
Joseph M. Farley Nuclear Plant - Unit 2 Radial Peaking Factor 1.imit Report' Enclosed is the Radial Peaking Factor Limit Report for Cycle 6 of Unit 2.
Joseph M. Farley Nuclear Plant - Unit 2 Radial Peaking Factor 1.imit Report' Enclosed is the Radial Peaking Factor Limit Report for Cycle 6 of Unit 2.
This report 'is provided in accordance with Paragraph 6.9.1.11 of the Unit 2 Technical Specifications. Also enclosed is a copy of the elevation dependent peaking factor versus core height graph for ' Cycle 6 of Unit 2 which is .being submitted in support of the subject report.
This report 'is provided in accordance with Paragraph 6.9.1.11 of the Unit 2 Technical Specifications. Also enclosed is a copy of the elevation dependent peaking factor versus core height graph for ' Cycle 6 of Unit 2 which is.being submitted in support of the subject report.
If you have' any questions, please advise.
If you have' any questions, please advise.
Respectfully subm tted,                                      ,
Respectfully subm tted,
                                                                                                                                                                                            /
/
p W
p L.
L.              ~
W
~
R. P. Mcdonald
R. P. Mcdonald
                          . RPM / JAR: dst-D-T.S.7 Enclosures
. RPM / JAR: dst-D-T.S.7 Enclosures
                          .cc: .Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford h                         DOC 4
.cc:.Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford h
DOC 4


ENCLOSURE                       !
ENCLOSURE FARLEY UNIT 2 CYCLE 6 RADIAL PEAKING FACTOR LIMIT REPORT l
FARLEY UNIT 2 CYCLE 6 RADIAL PEAKING FACTOR LIMIT REPORT               l This Radial Peaking Factor Limit Report is provided in accordance with               ,
This Radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.11 of the Joseph M. Farley Unit 2 Technical Specifications.
Paragraph 6.9.1.11 of the Joseph M. Farley Unit 2 Technical Specifications.         1 The F x        limits for RATED THERMAL POWER within specified core planes for Cycle k shall be:
1 The F limits for RATED THERMAL POWER within specified core planes for Cycle k shall be:
: 1. FpTP less than or equal to 1.77 for all core planes containing Bank "D   control rods,
x 1.
: 2. For all unrodded core planes:
FpTP less than or equal to 1.77 for all core planes containing Bank "D
F[yP less than or equal to 1.77 up to core elevations of 6.9 ft.
control rods, 2.
TP F!y   less than or equal to 1.71 for core elevations above 6.9 ft.
For all unrodded core planes:
These xF v(z) limits are used to confirm that the heat flux hot channel Tactor Fq (z) will be limited to the Technical Specification values of:
P F[y less than or equal to 1.77 up to core elevations of 6.9 ft.
Fq (z) .< _2.31 [K(z)] for P > 0.5 and, 7
F!y less than or equal to 1.71 for core elevations above 6.9 ft.
Fq (z) $ 4,62 [M(z)] for P 1 0.5 assuming the most limiting axial power distributions expected to result from the insertion and removal of Control Banks C and D during operation, including the accompanying variations in the axial xenon and power distributions as described in the " Power Distribution Control and Load Following Procedures," WCAP-8385, September 1974.
TP These F v(z) limits are used to confirm that the heat flux hot x
Therefore, these F xy limits provide assurance that the initial conditions assumed in the LOCA analysis are met and the ECCS acceptance criterion limit of 2200 F for peak clad temperature is not exceeded.
channel Tactor F (z) will be limited to the Technical Specification q
values of:
F (z).< _2.31 [K(z)] for P > 0.5 and, q
7 F (z) $ 4,62 [M(z)] for P 1 0.5 q
assuming the most limiting axial power distributions expected to result from the insertion and removal of Control Banks C and D during operation, including the accompanying variations in the axial xenon and power distributions as described in the " Power Distribution Control and Load Following Procedures," WCAP-8385, September 1974.
Therefore, these F limits provide assurance that the initial xy conditions assumed in the LOCA analysis are met and the ECCS acceptance criterion limit of 2200 F for peak clad temperature is not exceeded.
t
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Latest revision as of 05:01, 2 December 2024

Forwards Radial Peaking Factor Limit Rept for Cycle 6,in Accordance W/Tech Spec Paragraph 6.9.1.11.Elevation Dependent Peaking Factor Vs Core Height Graph for Cycle 6 Also Encl in Support of Rept
ML20239A384
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 09/15/1987
From: Mcdonald R
ALABAMA POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8709170300
Download: ML20239A384 (3)


Text

_---__- --

~

4:

a Alabama Power Company '

600 NorFs 38th Street

' Post Offi 3 Box 2641.

j Birmingham, Alabama 352914400 '

Telephone 205 250-1835.

. LM%e";%ioent Abbm hu 1

tre southern electncsystem

-10CFRSO.4

~I September 15, 1987 Docket No. 50-364

]

. V. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington,.D. C. 20555 i

Gentlemen:

Joseph M. Farley Nuclear Plant - Unit 2 Radial Peaking Factor 1.imit Report' Enclosed is the Radial Peaking Factor Limit Report for Cycle 6 of Unit 2.

This report 'is provided in accordance with Paragraph 6.9.1.11 of the Unit 2 Technical Specifications. Also enclosed is a copy of the elevation dependent peaking factor versus core height graph for ' Cycle 6 of Unit 2 which is.being submitted in support of the subject report.

If you have' any questions, please advise.

Respectfully subm tted,

/

p L.

W

~

R. P. Mcdonald

. RPM / JAR: dst-D-T.S.7 Enclosures

.cc:.Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford h

DOC 4

ENCLOSURE FARLEY UNIT 2 CYCLE 6 RADIAL PEAKING FACTOR LIMIT REPORT l

This Radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.11 of the Joseph M. Farley Unit 2 Technical Specifications.

1 The F limits for RATED THERMAL POWER within specified core planes for Cycle k shall be:

x 1.

FpTP less than or equal to 1.77 for all core planes containing Bank "D

control rods, 2.

For all unrodded core planes:

P F[y less than or equal to 1.77 up to core elevations of 6.9 ft.

F!y less than or equal to 1.71 for core elevations above 6.9 ft.

TP These F v(z) limits are used to confirm that the heat flux hot x

channel Tactor F (z) will be limited to the Technical Specification q

values of:

F (z).< _2.31 [K(z)] for P > 0.5 and, q

7 F (z) $ 4,62 [M(z)] for P 1 0.5 q

assuming the most limiting axial power distributions expected to result from the insertion and removal of Control Banks C and D during operation, including the accompanying variations in the axial xenon and power distributions as described in the " Power Distribution Control and Load Following Procedures," WCAP-8385, September 1974.

Therefore, these F limits provide assurance that the initial xy conditions assumed in the LOCA analysis are met and the ECCS acceptance criterion limit of 2200 F for peak clad temperature is not exceeded.

t

i-i ENCLOSURE 2.4 ll

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-