ML20235T214

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Revised Tech Spec Page B 3/4 2-4, Heat Flux Hot Channel Factor & Nuclear Enthalpy Rise. Page Corrected to Indicate That Vantage 5 DNB Transition Core Penalty Increases from 11% to 12.5% & DNB Margin Decreases to 4%
ML20235T214
Person / Time
Site: Callaway Ameren icon.png
Issue date: 10/06/1987
From:
UNION ELECTRIC CO.
To:
Shared Package
ML20235S971 List:
References
NUDOCS 8710090294
Download: ML20235T214 (2)


Text

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ULNRC-1643

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3L4.2.2 and."$f4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHAlpY RISE

,H_0T QMNMEL FiLCRR (Continued)

Each of tlyese is measurable but will normally only be detemined period-

i ically as specified in Specifications 4.2.2 and 4.2.3.

This periodic surveil-lance is sufficient to ensure that the lioits are maintained provided:

a.

Ca1 trol rods in a single group move together with no individual rod insertion differing by more than i 12 steps, indicated, from the group demand position.

b.

Os Caltml rod banks are sequenced with overlapping groups as described in Specification 3.1.3.6.

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c.

The entrol rod insertion limits of specification 3.1.3.6 are maintained.

d.

The axial power distribution, expressed in tems of AXIAL FLUX DI;FF$,tENCE, is maintained within the limits.

M Fu wil-1 he maintained within its 1 its provided conditions a. through d.

above stil maintained. The relaxation of u as a function of THERNAL POWER allows changes in the radial pouler shape P all permissible rod insertion limits.

When an Fa measurement is taken, an allowance for both experimental error and annufactur14g tolerance must' be made. An allowance of 5% is appropriate for a full-core asp :taken with the incore detector flux ma allowance is. appropriate for manufacturing tolerance. pping system and a 35 O'

n Whan Fu is measured. (i.e., inferred), no additional allowances are necessary prhr :to comparison with the limits of Section 3.2.3.

An error allow-ance of 45 has tteen included in the limits of Section 3.2.3.

B l2.5 To

~

Margin between the safety lysis DNBR limits (1.42 and 1.45 for the Optimized fuel thimble and ty ' cal cells, respectively, and 1.61 and 1,69 for the VANTAGE 5 tMoble and cal cells) and the design DNBR limits (1.32 and 1.34 for the 20ptimized fuel inble and typical cells and 1.32 and 1.33 for the VANTAGE 5 thtable and typi al cells, respectively) is maintained. A (raction of this margin is util accommodate the transition core DNBR penalty (25 for Optimized fue 4

,for VANTAGE 5 fuel) and the appropriate fuel rod l

bow DNBR penalty (less 1.5% per WCAp-8691, Rev.1). The margin between

. desi n and safety analysis ONBR limits of 7% for Optimized fuel and 18% for VANT S fuel includes greater than 3% margin for Optimized fuel and sreta

//% 45 (A rgin for VANTAGE 5 fuel for plant design flexibility. ~

l The hot channel factor d(z) is measured periodically and increased by a cycle and height dependent power factor appropriate to either Wormal Operation or RESTRICTEG AFD OPERATION, W(z)h(or W(z)N to provide assurance tha limit on the hot channel factor, z).is W(z)NO accounts for the effects 8710090294 871006 PDR ADOCK 05000483 P

PDR CALLAMAY - UNIT 1 B 3/4 2-4 Amendment No. D.

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.u ULNRC-1643 A rTACHMENT 3

22. Lee, N., Rupprecht, S. D., Schwartz, W. R., Tauche, W. D., " Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," WCAP-10054-P-A (Proprietary) and WCAP-10081-A (Non-Proprietary) August 1985.
23. Esposito, V. J., Kesavan, K., and Naul, B. J.; "W-FLASH-A Fortran-IV Computer Program for Simulation of Transients in-a Multi-Loop PWR,"

WCAP-8200 (Proprietary), July 1973.

24. Meyer, P. E.

"NOTRUMP, A Nodal Transient Small Break and General Network Code," WCAP-10079-P-A (Proprietary) and WCAP-10080-A (Non-Proprietary),

August 1985.

1 25.

Letter C. E. Rossi (NRC) to E. P. Rahe,'Jr. (W), " Acceptance for Referencing of Licensing Topical Report WCAP-10266," November 1986.

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26. Letter W. Johnson E) to J. Lyons (NRC), " Submittal of WCAP-10266

' Addendum 1, BASH Power Shape Sensitivity Studies," January 1987.

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27. Letter from W. J. Johnson (Westinghouse) to M. W. Hodges (NRC) dated October 2, 1987, NS-NRC-87-3268,

Subject:

" VANTAGE 5 Transition Core Effects".

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28. ULNRC - 1643 dated October 6, 1987, " Revised Vantage 5 Transition Core Effects for Cycle 3".

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