ML19322A074

Suppl Reload Licensing Submittal,Reload 1 Describing Reload & Previous Cycle Exposures

ML19322A074
Person / Time
Site:	Brunswick
Issue date:	12/31/1978
From:	Freemon A CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19322A071	List: ML19322A070 ML19322A074
References
NEDO-24166, NUDOCS 7901020170
Download: ML19322A074 (31)

Text

'O' NEDO-24166 78NED298 Plass I 3 Decemb er 197fs SUPPLEMENTAL RELOAD LICENSING SUBMITTAL FOR BRUNSWICK STEAM ELECTRIC PLANT UNIT 1 RELOAD 1

' s Pr e pa r ed : .'- - M % L- n , h %

A. M. Freemon Os

-m f3 Approved: A .

d ',7) 7 '

R. O. Brugge, Manager Operating Licenses II

, b NUCLEAR ENERGY PROJECTS DIVIS3ON e GENERAL ELECTRIC COMPANY l 3 SAN JOSE. CALIFORhi A 95123 GENER AL $ ELECTRIC

a e NEDO-24166 1

INPORTANT NOTICE REGARDING ggg CONTENTS OF THIS REPORT PLEASE READ CAREFULLY This report was prepared by General Electric solely for Carolina Power and Light Company (CPL) for CPL's use with the U.S. Nuclear Regulatory Commission (USNRC) for amending CPL's operating license of the Brunswick Steam Electric Plant Unit 1. The information contained in this report is believed by General Electric to be an accurate and true representation of the facts known, obtained or provided to General Electric at the time this report was prepared.

The only undertakings of the General Electric Company respecting information in this document are contained in the contract between Carolina Power and Light Company and General Electric Company for nuclear fuel and related services for the nuclear system for Brunswick Steam Electric Plar.ts Units 1 and 2, dated January 28, 1974, and nothing contained in this document shall be construed as changing said contract. The use of this information except as defined by said contract, or for any purpose other than that for which it is intended, is not authorized; and with respect to any such unauthorized use, neither General Electric Company nor any of the contributors to this document makes any repre-sentation or warranty (express or implied) as to the completeness, accuracy or usefulness of the information contained in this document or that such use of such information may not infringe privately owned rights; nor do they assume &

any responsibility for liability or damage of any kind which may result from W such use of such information.

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NEDO-24166

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1. PLANT-UNIQUE ITEMS (1.0)*

Rotated Bundle Analysis Procedure: Appendix A Fuel Loading Error LHGR: Appendix B 1

2. RELOAD FUEL BUNDLES (1.0, 3.3.1 and 4.0)

Fuel Type Number Number Drilled Irradiated Initial Core Center 308 308 Irradiated Initial Core Peripheral 76 76 New 8DRB265L 52 52 New 8DRB283 124 124 Total 560 560

3. REFERENCE CORE LOADING PATTERN (3.3.1)

Nominal previous cycle exposure: 9760 mwd /t.

Assumed reload cycle exposure: 12220 mwd /t.

Core loading pattern: Figure 1.

4. CALCULATED CORE EFFECTIVE MULTIPLICATION AND CONTROL SYSTEM WORTH - No VOIDS, 200C (3.3.2.1.1 AND 3.3.2.1.2) 1 1

80C k,ff Uncontrolled 1.102 j Fully Controlled 0.941

. Strongest Control Rod Out 0.968

$ R, Maximum Increase in Cold Core Reactivity 0.013 with Exposure Into Cycle, Ak

• ( ) refers to areas of discussion in " Generic Reload Fuel Application,"

NEDE-24011-P-A, Revision , August 1978.

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NEDO-24166

5. STANDBY LIQUID CONTROL SYSTEM Sl!UTDOWN CAPABILITY (3.3.2.1.3) llh Shutdown Margin (Ak) ppm (200C, Xenon __ Free) 600 0.045

6. RELOAD UNIQUE TRANSIENT ANALYSIS INPUTS (3.3.2.1.5 AND 5.2)

EOC- EOC-EOC2 1000 mwd /t 2000 mwd /t Void Ccefficient N/A* (C/% Rg) -7.682/-9.592 -8.223/-10.27 -7.819/-9.758 Void Fraction (%) 41.60 41.60 41.60 Doppler Coefficient N/A (c/% F) -0.227/-0.216 -0.221/-0.210 -0.214/-0.203 Average Fuel Temperature ( F) 1343 1343 1343 Scram Worth N/A ($) -38.53/-30.82 -37.02/-29.62 -36.26/-29.00 Scran Reactivity vs Time Figure 2a Figure 2b Figure 2c

7. RELOAD UNIQUE CETAB TRANSIENT ANALYSIS INITIAL CONDITION PARAMETERS (5.2)

O 8x8 8x8R EOC- EOC- EOC- EOC-Exposure EOC 1000 mwd /t 2000 mwd /t EOC 1000 mwd /t 2000 mwd /t Peaking factors 1.22 1.22 1.22 1.20 1.20 1.20 (local, radial 1.371 1.415 1.452 1.50 1.548 1.584 and axial) 1.4 1.4 1.4 1.4 1.4 1.4 R-Factor 1.094 1.094 1.094 1.05. 1.051 1.051 Bundle Power 5.846 6.034 6.192 6.393 6.597 6.752 (MWt)

Bundle Flow 114.77 113.25 112.00 115.3 113.79 112.67 (103 lb/hr)

Initial MCPR 1.28 1.24 1.20 1.28 1.23 1.20

• N = Nuclear Input Data A =

Used in Transient Analysis O

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