ML18096A623
| 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 VERIFIER:
L. Green Core Design C (J.O. W-~
R.. A. Wiley ()
Core Design C
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PDR ADOCK 05000311 p
PDR Date:
Date:
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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.
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 w~th the ECCS acceptance criteria of 10CFR.50.46.
- T See Figure 1 for a plot of (FQ PRel] versus Axial. Core Height.
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- Pael J VERSUS AXIAL CORE HEIGHT DURING NORMAL OPERATION 3 of 3