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* CDC-92-014 Ref. 1: CDC-91-307 2: PNG-92-005 PEAKING FACTOR LIMIT REPORT EVALUATION FOR SALEM UNIT 2 CYCLE 7 REDESIGN | * CDC-92-014 Ref. 1: CDC-91-307 2: PNG-92-005 PEAKING FACTOR LIMIT REPORT EVALUATION FOR SALEM UNIT 2 CYCLE 7 REDESIGN L. Green Core Design C Date: | ||
L. Green Core Design C (J.O. R.. A. Wiley () Core Design C -----c::--------------,--,, ,r-9204160043 920409 I PDR ADOCK 05000311 p PDR | (J.O. W-~ | ||
VERIFIER: R.. A. Wiley ( ) | |||
Core Design C Date: /-/o-'f~ | |||
1 of 3 | |||
The Fxy limits for RATED THERMAL POWER within specific core planes for Cycle 7 shall be: 1. For all core planes containing Bank "D" control rods: _RTP r--< 2.26 for all core elevations | -----c::- -------------,--,, | ||
',INCORE axial points | ,r- 9204160043 920409 I PDR ADOCK 05000311 p PDR | ||
: 2. For all unrodded planes: 1-TP < 1.68 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 (z) < (2* | RADIAL PEAKING FACTOR LIMIT REPORT This radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.l.10 of the Salem Unit 2 Nuclear Plant Technical Specifications. | ||
*T See Figure 1 for a plot of (FQ PRel] versus Axial. Core Height. 2 of 3 | The Fxy limits for RATED THERMAL POWER within specific core planes for Cycle 7 shall be: | ||
: 1. For all core planes containing Bank "D" control rods: | |||
.._ | _RTP r--xy -< 2.26 for all core elevations ',INCORE axial points 1 through 61, inclusive). | ||
: 2. For all unrodded planes: | |||
1-TP < 1.68 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: | |||
32 F (z) < ( 2 * ] (K( z )]. f or P > 0 . 5 and , | |||
Q p FQ(z) ~ (4.64] (K(z)J for P < 0.5 assuming the most limiting axial power distributions expected to result from the insertion and removal of control Banlcs 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 I..OCA analysis are met, along w~th the ECCS acceptance criteria of 10CFR.50.46. | |||
*T See Figure 1 for a plot of (FQ PRel] versus Axial. Core Height. | |||
2 of 3 | |||
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i i I I .1 I I I 2 4 6 8 10 12 CORE 1£ IGHT (FEET) | |||
FICUU 1 MAXIMUM (FQT | |||
* Pael J VERSUS AXIAL CORE HEIGHT DURING NORMAL OPERATION 3 of 3}} | * Pael J VERSUS AXIAL CORE HEIGHT DURING NORMAL OPERATION 3 of 3}} |
Latest revision as of 06:35, 3 February 2020
ML18096A623 | |
Person / Time | |
---|---|
Site: | Salem ![]() |
Issue date: | 01/10/1992 |
From: | Green L, Wiley R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
To: | |
Shared Package | |
ML18096A622 | List: |
References | |
CDC-92-014, CDC-92-14, NUDOCS 9204160043 | |
Download: ML18096A623 (3) | |
Text
- CDC-92-014 Ref. 1: CDC-91-307 2: PNG-92-005 PEAKING FACTOR LIMIT REPORT EVALUATION FOR SALEM UNIT 2 CYCLE 7 REDESIGN L. Green Core Design C Date:
(J.O. W-~
VERIFIER: R.. A. Wiley ( )
Core Design C Date: /-/o-'f~
1 of 3
c::- -------------,--,,
,r- 9204160043 920409 I PDR ADOCK 05000311 p PDR
RADIAL PEAKING FACTOR LIMIT REPORT This radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.l.10 of the Salem Unit 2 Nuclear Plant Technical Specifications.
The Fxy limits for RATED THERMAL POWER within specific core planes for Cycle 7 shall be:
- 1. For all core planes containing Bank "D" control rods:
_RTP r--xy -< 2.26 for all core elevations ',INCORE axial points 1 through 61, inclusive).
- 2. For all unrodded planes:
1-TP < 1.68 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:
32 F (z) < ( 2 * ] (K( z )]. f or P > 0 . 5 and ,
Q p FQ(z) ~ (4.64] (K(z)J for P < 0.5 assuming the most limiting axial power distributions expected to result from the insertion and removal of control Banlcs 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 I..OCA analysis are met, along w~th the ECCS acceptance criteria of 10CFR.50.46.
- T See Figure 1 for a plot of (FQ PRel] versus Axial. Core Height.
2 of 3
- -'* ' ._,' L 2....
I I I r 11 6, 2. 321 i I I !
I !
- I 1 I I 1 ~
......... .._ I !
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~
,, . r I \ 10.8,2. 181 I
I ll I
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.. r"l*C C ape CJ I M CJ C CCC cc
' I I
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- ~
--:.1. 8 Cl
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I 12, 1.5 I I !
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!' I I i c I I I
! I ..
1.2 I
~
i i I I .1 I I I 2 4 6 8 10 12 CORE 1£ IGHT (FEET)
FICUU 1 MAXIMUM (FQT
- Pael J VERSUS AXIAL CORE HEIGHT DURING NORMAL OPERATION 3 of 3