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| * 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: 1. For all core planes containing Bank "D" control rods: _RTP r--< 2.26 for all core elevations |
| ',INCORE axial points xy -1 through 61, inclusive). | | ',INCORE axial points xy -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). | | : 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*32] (K( )] f P > 0 5 d Q z . or . an , 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 the ECCS acceptance criteria of lOCFR.50.46. | | 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*32] (K( )] f P > 0 5 d Q z . or . an , 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 the ECCS acceptance criteria of lOCFR.50.46. |
Revision as of 16:05, 25 April 2019
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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 VERIFIER:
L. Green Core Design C (J.O. R.. A. Wiley () Core Design C -----c::--------------,--,, ,r-9204160043 920409 I PDR ADOCK 05000311 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.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
',INCORE axial points xy -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: F (z) < (2*32] (K( )] f P > 0 5 d Q z . or . an , 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 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
* * **-'* ' ._,' L I I I r 11 6, 2. 321 i I I ! I ! ' ' -I 1 2 .... I I 1 I ! .........
.._ 2. 2 I CIC I I r ,, . I\ 10.8,2. 181 I ll I I I c : I ' c c c ... .. r"l*C C ape M CJ C CJ I CCC cc *-I ; .... i :I ,., I -2.0 I I I -I I I I I ! i ! --:.1. 8 . I ; I : ! Cl a i I ! \ ' ; I ! ' \ ! i I : I I i I I I I : I I ! 12, 1.5 : I i ! i I 1.4 ' ' ! I I I i c I I I ! I .. i I ' 1.2 i I I .1 ! I I I : 2 4 6 8 10 12 CORE 1£ I GHT (FEET) FICUU 1 T MAXIMUM (FQ
- Pael J VERSUS AXIAL CORE HEIGHT DURING NORMAL OPERATION 3 of 3
