ML16336A559

7 to Updated Final Safety Analysis Report, Chapter 3, Table 3.1-2

ML16336A559
Person / Time
Site:	Cook
Issue date:	10/24/2016
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML16336A263	List: AEP-NRC-2016-42, Fire Protection Program Change Summary ML16336A225 ML16336A228 ML16336A238 ML16336A291 ML16336A292 ML16336A294 ML16336A295 ML16336A297 ML16336A298 ML16336A299 ML16336A300 ML16336A301 ML16336A302 ML16336A303 ML16336A304 ML16336A305 ML16336A306 ML16336A308 ML16336A309 ML16336A310 ML16336A311 ML16336A312 ML16336A313 ML16336A314 ML16336A315 ML16336A316 ML16336A317 ML16336A318 ML16336A319 ML16336A320 ML16336A322 ML16336A323 ML16336A324 ML16336A325 ML16336A327 ML16336A328 ML16336A329 ML16336A330 ML16336A332 ML16336A333 ML16336A334 ML16336A336 ML16336A337 ML16336A338 ML16336A339 ML16336A340 ML16336A341 ML16336A342 ML16336A345 ... further results
References
AEP-NRC-2016-42
Download: ML16336A559 (2)

Text

IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:

16.4 Table:

3.1-2 Page:

1 of 2 Unit 2 ANALYTIC TECHNIQUES IN CORE DESIGN Analysis Technique Computer Code Section Referenced Mechanical Design of Core Internals Loads, Deflections, and Stress Analysis Static and Dynamic Modeling Blowdown code, FORCE, Finite element structural analysis code, and others 14.3.3 Fuel Rod Design Fuel Performance Characteristics (temperature, internal pressure, clad stress, etc.)

Semi-empirical thermal model of fuel rod with consideration of fuel density changes, heat transfer, fission gas release, etc.

Westinghouse fuel rod design model 3.2.1.3.1 3.3.3.1 3.4.2.2 3.4.3.4.2 Nuclear Design

1. Cross Sections and Group Constants Microscopic data Macroscopic constants for homogenized core regions Modified ENDF/B-V or ENDF/B-VI library PHOENIX-P 3.3.3.2 3.3.3.2 Group constants for control rods with self-shielding PHOENIX-P 3.3.3.2 Nuclear Design (Continued)

2. X-Y Power Distributions, Fuel Depletion, Critical Boron Concentrations, X-Y Xenon Distributions, 3D, 2-Group Nodal Expansion Method ANC 3.3.3.3

IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:

16.4 Table:

3.1-2 Page:

2 of 2 Unit 2 ANALYTIC TECHNIQUES IN CORE DESIGN Analysis Technique Computer Code Section Referenced Reactivity Coefficients

3. Axial Power Distributions, Control Rod Worths, and Axial Xenon Distribution 1-D, 2-Group Diffusion Theory APOLLO 3.3.3.3

4. Fuel Rod Power Integral Transport Theory LASER 3.3.3.1 Effective Resonance Temperature Monte Carlo Weighting Function REPAD Thermal-Hydraulic Design

1. Steady-State Subchannel analysis of local fluid conditions in rod bundles, including inertial and crossflow resistance terms, solution - progresses from core-wide to hot assembly to hot channel THINC-IV 3.4.3.4.1

2. Transient Departure from Nucleate Boiling Analysis Subchannel analysis of local fluid conditions in rod bundles during transients by including accumulation terms in conservation equations solution progresses from core-wide to hot assembly to hot channel THINC-I (THINC-III) 3.4.3.4.1