ML18096A664: Difference between revisions

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| number = ML18096A664
| number = ML18096A664
| issue date = 03/18/1992
| issue date = 03/18/1992
| title = Cycle 11 Peaking Factor Limit Rept.
| title = Cycle 11 Peaking Factor Limit Rept
| author name = Schmidt J, Wiley R
| author name = Schmidt J, Wiley R
| author affiliation = WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
| author affiliation = WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:* CDC-92-076 Ref.: PSK-92-011-0 SALEM UNIT 1 CYCLE 11 PEAKING FACTOR LIMIT REPORT J 1Jffi VERIFIED BY: J. S. Schmidt Core Design C 02-. a .
{{#Wiki_filter:*
R. A. Wiley () Core Design C 9205040299 920424 PDR ADOCK 05000272 P PDR Date: Date: 1 of 3
CDC-92-076 Ref.: PSK-92-011-0 SALEM UNIT 1 CYCLE 11 PEAKING FACTOR LIMIT REPORT J 1Jffi VERIFIED BY:
* RADIAL PEAKING FACTOR LIMIT REPORT This radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.9 of the Salem Unit 1 Nuclear Plant Technical Specifications.
J. S. Schmidt Core Design C 02-. a. c;,r~
The F limits for RATED THERMAL POWER within specific core planes for xy Cycle 11 shall be: 1. For all core planes containing Bank "D" control rods: < 2.28 for all core elevations (INCORE axial points xy -1 through 61, inclusive).
R. A. Wiley
: 2. For all unrodded planes: < 1.67 for all core elevations (INCORE axial points xy -1 through 61, inclusive).
()
These F (z) limits were used to confirm that the heat flux hot xy channel factor FQ(z) will be limited to the Technical Specification values of: F ( ) < [2. 32] Q z p [K(z)] for P > 0.5 and, [K(z)] for P < 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. Therefore, these F limits provide assurance that the initial xy conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of lOCFRS0.46.
Core Design C 9205040299 920424  
See Figure 1 for a plot of [FQT . PRel] versus Axial Core Height. 2 of 3
~
* * '.i < 2.4 LI 0.2.32 I I 6.2.32 I r-.. ....... Cc -i--.. -10.82.181 I -n 2.2 c _ .... " ., -' UC I" r a ll ... ... [ OL.J .., '-n c* -,_ 2.0 Cl n -.;;[ -\
PDR ADOCK 05000272 P
* ID \ .., [ \ \ -Lj 1.8 ... 1 ,E-. ..... \ -1.6 ::II c \ \ ... \ 12.1.5 I 1.4 [] Cl 1.2 2 4 6 8 10 12 CORE HEIGHT (FEET) FIGURE 1 MAXIMUM CFaT*PRELJ VS AXIAL CORE HEIGHT DURING NORMAL OPERATION 3 of 3}}
PDR Date:
Date:
1 of 3  
 
RADIAL PEAKING FACTOR LIMIT REPORT This radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.9 of the Salem Unit 1 Nuclear Plant Technical Specifications.
The F limits for RATED THERMAL POWER within specific core planes for xy Cycle 11 shall be:
: 1.
For all core planes containing Bank "D" control rods:  
~TP < 2.28 for all core elevations (INCORE axial points xy -
1 through 61, inclusive).
: 2.
For all unrodded planes:  
~TP < 1.67 for all core elevations (INCORE axial points xy -
1 through 61, inclusive).
These F (z) limits were used to confirm that the heat flux hot xy channel factor FQ(z) will be limited to the Technical Specification values of:
F ( ) < [2. 32]
Q z p
[K(z)]
for P > 0.5 and,
[K(z)]
for P < 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.
Therefore, these F limits provide assurance that the initial xy conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 10CFRS0.46.
See Figure 1 for a plot of [FQT. PRel] versus Axial Core Height.
2 of 3  
 
'.i 2.4 LI 0.2.32 I I 6.2.32 I r-.........
Cc  
-i--.. -
10.82.181 I  
-n 2.2 c  
~
UC I" r a ll...  
... [
OL.J  
.., '- n c* -
2.0 Cl n  
-.;;[  
- \\
ID  
\\
[ \\  
\\
Lj 1.8  
... 1  
,E-.  
\\  
~ -
~ 1.6
::II c  
\\  
\\
... \\
12.1.5 I 1.4
[]
Cl 1.2 2
4 6
8 10 12 CORE HEIGHT (FEET)
FIGURE 1 MAXIMUM CFaT*PRELJ VS AXIAL CORE HEIGHT DURING NORMAL OPERATION 3 of 3}}

Latest revision as of 02:28, 6 January 2025

Cycle 11 Peaking Factor Limit Rept
ML18096A664
Person / Time
Site: Salem 
Issue date: 03/18/1992
From: Jeffrey Schmidt, Wiley R
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML18096A663 List:
References
CDC-92-076, CDC-92-76, PSK-92-011-0, PSK-92-11, NUDOCS 9205040299
Download: ML18096A664 (3)
v • d • e


Text

CDC-92-076 Ref.: PSK-92-011-0 SALEM UNIT 1 CYCLE 11 PEAKING FACTOR LIMIT REPORT J 1Jffi VERIFIED BY:

J. S. Schmidt Core Design C 02-. a. c;,r~

R. A. Wiley

()

Core Design C 9205040299 920424

~

PDR ADOCK 05000272 P

PDR Date:

Date:

1 of 3

RADIAL PEAKING FACTOR LIMIT REPORT This radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.9 of the Salem Unit 1 Nuclear Plant Technical Specifications.

The F limits for RATED THERMAL POWER within specific core planes for xy Cycle 11 shall be:

1.

For all core planes containing Bank "D" control rods:

~TP < 2.28 for all core elevations (INCORE axial points xy -

1 through 61, inclusive).

2.

For all unrodded planes:

~TP < 1.67 for all core elevations (INCORE axial points xy -

1 through 61, inclusive).

These F (z) limits were used to confirm that the heat flux hot xy channel factor FQ(z) will be limited to the Technical Specification values of:

F ( ) < [2. 32]

Q z p

[K(z)]

for P > 0.5 and,

[K(z)]

for P < 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.

Therefore, these F limits provide assurance that the initial xy conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 10CFRS0.46.

See Figure 1 for a plot of [FQT. PRel] versus Axial Core Height.

2 of 3

'.i 2.4 LI 0.2.32 I I 6.2.32 I r-.........

Cc

-i--.. -

10.82.181 I

-n 2.2 c

~

UC I" r a ll...

... [

OL.J

.., '- n c* -

2.0 Cl n

-.;;[

- \\

ID

\\

[ \\

\\

Lj 1.8

... 1

,E-.

\\

~ -

~ 1.6

II c

\\

\\

... \\

12.1.5 I 1.4

[]

Cl 1.2 2

4 6

8 10 12 CORE HEIGHT (FEET)

FIGURE 1 MAXIMUM CFaT*PRELJ VS AXIAL CORE HEIGHT DURING NORMAL OPERATION 3 of 3

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