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{{#Wiki_filter:_---__- -- | {{#Wiki_filter:_---__- -- | ||
~ | |||
4: | 4: | ||
600 NorFs 38th Street | a Alabama Power Company ' | ||
600 NorFs 38th Street | |||
Birmingham, Alabama 352914400 ' | ' Post Offi 3 Box 2641. | ||
Telephone 205 250-1835 . | j Birmingham, Alabama 352914400 ' | ||
Telephone 205 250-1835. | |||
. LM%e";%ioent Abbm hu 1 | |||
tre southern electncsystem | |||
-10CFRSO.4 | |||
Washington,.D. C. 20555 | ~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. | ||
W | |||
~ | |||
R. P. Mcdonald | 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 | ENCLOSURE FARLEY UNIT 2 CYCLE 6 RADIAL PEAKING FACTOR LIMIT REPORT l | ||
FARLEY UNIT 2 CYCLE 6 RADIAL PEAKING FACTOR LIMIT REPORT | 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 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 | |||
F[ | control rods, 2. | ||
For all unrodded core planes: | |||
These | 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 | |||
Therefore, these F | 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 | t | ||
i-i ENCLOSURE 2.4 | i-i ENCLOSURE 2.4 ll | ||
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Rl FXY LIMITS Il | |||
.I II LP TO 6.9 FT. | |||
1,77 l | |||
lll IllI Il I I I l I, 11. | |||
I FGOVE 6.9 FT. | |||
1.71 lll{l l l | |||
jl l | |||
}l lilllil lillll lilllll lillll! | |||
Illilll I l i l l l ll | |||
.!!Illli il11i | |||
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til i | |||
111lll1 Ililili il lit litilli litilitt | |||
'O 2 | |||
4 6 | |||
8 10 12 CORE HEIGHT (FEET) | |||
I MAXIMUM F XP VERSUS CORE HEIGHT O | |||
REL DURING NORMAL OPERATION | |||
-}} | |||
Latest revision as of 05:01, 2 December 2024
| ML20239A384 | |
| Person / Time | |
|---|---|
| Site: | Farley |
| 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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Rl FXY LIMITS Il
.I II LP TO 6.9 FT.
1,77 l
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I FGOVE 6.9 FT.
1.71 lll{l l l
jl l
}l lilllil lillll lilllll lillll!
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til i
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'O 2
4 6
8 10 12 CORE HEIGHT (FEET)
I MAXIMUM F XP VERSUS CORE HEIGHT O
REL DURING NORMAL OPERATION
-