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{{#Wiki_filter:* CDC-92-076 Ref.: PSK-92-011-0 SALEM UNIT 1 CYCLE 11 PEAKING FACTOR LIMIT REPORT J 1Jffi | {{#Wiki_filter:* | ||
R. A. Wiley () Core Design C 9205040299 920424 PDR ADOCK 05000272 P PDR | CDC-92-076 Ref.: PSK-92-011-0 SALEM UNIT 1 CYCLE 11 PEAKING FACTOR LIMIT REPORT J 1Jffi J. S. Schmidt Core Design C Date: | ||
02- . a. c;,r~ | |||
VERIFIED BY: R. A. Wiley () | |||
Core Design C Date: | |||
1 of 3 9205040299 920424 ~ | |||
PDR ADOCK 05000272 P PDR | |||
* 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. | * 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 | The Fxy limits for RATED THERMAL POWER within specific core planes for Cycle 11 shall be: | ||
: 2. For all unrodded planes: < 1.67 for all core elevations (INCORE axial points | : 1. For all core planes containing Bank "D" control rods: | ||
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: | ~TP xy - | ||
See Figure 1 for a plot of [FQT . PRel] versus Axial Core Height. 2 of 3 | < 2.28 for all core elevations (INCORE axial points 1 through 61, inclusive). | ||
: 2. For all unrodded planes: | |||
~TP xy - | |||
< 1.67 for all core elevations (INCORE axial points 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: | |||
FQ( z ) < [ 2. 32] [K(z)] for P > 0.5 and, p | |||
[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. | |||
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 2.2 Cc I | |||
r-.. ....... | |||
- - -n i--.. | |||
10.82.181 c .... " ., - ... | |||
' | |||
_ | |||
ll ... | |||
~ UC I" r a [ | |||
.., '- n c* - OL.J ,_ | |||
Cl n * | |||
-.;;[ | |||
- \ | |||
2.0 .., ID | |||
\ | |||
[ \ | |||
-. Lj 1.8 | |||
,E- | |||
\ | |||
...1 | |||
..... \ | |||
-~ | |||
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::II 1.6 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}} | |||
Revision as of 10:19, 21 October 2019
| 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) | |
Text
CDC-92-076 Ref.: PSK-92-011-0 SALEM UNIT 1 CYCLE 11 PEAKING FACTOR LIMIT REPORT J 1Jffi J. S. Schmidt Core Design C Date:
02- . a. c;,r~
VERIFIED BY: R. A. Wiley ()
Core Design C Date:
1 of 3 9205040299 920424 ~
- 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 Fxy limits for RATED THERMAL POWER within specific core planes for Cycle 11 shall be:
- 1. For all core planes containing Bank "D" control rods:
~TP xy -
< 2.28 for all core elevations (INCORE axial points 1 through 61, inclusive).
- 2. For all unrodded planes:
~TP xy -
< 1.67 for all core elevations (INCORE axial points 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:
FQ( z ) < [ 2. 32] [K(z)] for P > 0.5 and, p
[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.
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 2.2 Cc I
r-.. .......
- - -n i--..
10.82.181 c .... " ., - ...
'
_
ll ...
~ UC I" r a [
.., '- n c* - OL.J ,_
Cl n *
-.;;[
- \
2.0 .., ID
\
[ \
-. Lj 1.8
,E-
\
...1
..... \
-~
~
- II 1.6 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