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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 | |||
-----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. | * 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--< 2.26 for all core elevations | The Fxy limits for RATED THERMAL POWER within specific core planes for Cycle 7 shall be: | ||
',INCORE axial points | : 1. For all core planes containing Bank "D" control rods: | ||
: 2. For all unrodded planes: 1-TP < 1.68 for all core elevations (INCORE axial points xy -1 through 61, inclusive). | _RTP r--xy -< 2.26 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: F (z) < (2* | : 2. For all unrodded planes: | ||
*T See Figure 1 for a plot of (FQ PRel] versus Axial. Core Height. 2 of 3 | 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 lOCFR.50.46. | |||
*T See Figure 1 for a plot of (FQ PRel] versus Axial. Core Height. | |||
2 of 3 | |||
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* Pael J VERSUS AXIAL CORE HEIGHT DURING NORMAL OPERATION 3 of 3}} | * Pael J VERSUS AXIAL CORE HEIGHT DURING NORMAL OPERATION 3 of 3}} |
Revision as of 11:20, 21 October 2019
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 lOCFR.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 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