ML20134M789

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Nonproprietary Rev 0 to Cpc/Ceac Software Mods for CPC Improvement Program
ML20134M789
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 08/31/1985
From:
ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:
Shared Package
ML19269B630 List:
References
CEN-308-NP, CEN-308-NP-R, CEN-308-NP-R00, NUDOCS 8509040258
Download: ML20134M789 (82)


Text

________

CPC/CEAC SOFTWARE MODIFICATIONS FOR THE CPC IMPROVEMENT PROGRAM CEN-308-NP Revision 00-NP AUGUST, 1985 COMBUSTION ENGINEERING, INC.

Nuclear Power Systems Power Systems Group Windsor, Connecticut a*.8509040258 850830 fDR ADOCK 05000361 PDR _

PROPRIETARY INFORMATION l COMBUSTION ENGINEERING,INC. '

l LEGAL NOTICE '

This report was n apared as an account of work sponsored by Combustion Engineering,*Inc. Neither Combustion Engineering nor any person acting on its behalf:

a. Makes any warrant implied including the'ywarranties or representation, express of fitness for a or particular purpos.e or merchantability, with respect to the accuracy, completeness, or usefulness of the information contained in this report, or that the use of any information, apparatus, method, or process disclosed in this report may not infringe privately owned rights; or
b. Assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method or process disclosed in this report.

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TABLE OF CONTENTS Title Page No.

. Section No.

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TABLE OF CONTENTS LIST OF FIGURES,' TABLES 4 5

l

1.0 INTRODUCTION

5 1.1 REPORT SCOPE 6

1.2 REPORT

SUMMARY

7 2.0 CPC SOFTWARE MODIFICATION 7

2.1 MODIFICATIONS TO FLOW ALGORITHM 17 2.2 MODIFICATIONS TO UPDATE ALGORITHM Variable Overpower Trip (V0PT) 17 2.2.1 Asymmetric Steam Generator Trip (ASGT) 20 2.2.2 CEAC Penalty Factor Interpretation 26 2.2.3 Algorithm Simplification 41 2.2.4 43 2.3 MODIFICATIONS TO POWER ALGORITHM Power Synthesis 43 2.3.1 ASI Dependent Parameters 52 2.3.2 ASI Calculation 54 2.3.3 2.3.4 Elimination of the Augmentation Array 58 2.3.5 CEAC Desensitization 59 2.4 MODIFICATIONS TO TRIP SEQUENCE ALGORITHM 64 71 3.0 CEAC SOFTWARE MODIFICATION 4.0 ADDRESSABLE CONSTANTS 73 5.0 DATA BASE CONSTANTS FOR CCIP 77 o

6.0 REFERENCES

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I Title Page No.

Table No.

Core Spline Regions 50 1

Addressable Cons'tants 75 2

LIST OF FIGURES Figure No. Title Page No.

4-1 Schematic of Primary System Showing 12 Approximate Location of Temperature Sensors 4-2 Penalty Components for Temperature 25 Difference and Power Level 1

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1.0 INTRODUCTION

1.1 REPORT SCOPE The Core Protection Calculator System (CPCS) is designed to provide the low DNBR and high Local Power Density (LPD) trips to (1) ensure that the specified acceptable fuel design limits on departure from nucleate boiling and centerline fuel melting are not exceeded during Anticipated Operational Occurrences (A00s) and (2) assist the Engineered Safety Features System in limiting the consequences of certain postulated accidents.

The COLSS/CPC Oversight Committee, consisting of Arizona Nuclear Power Project, Arkansas Power and Light Company, Louisiana Power and Light Company and Southern California Edison, with Combustion Engineering as its technical consultant, has developed the CPC Improvement Program (CIP), a program of CPC Modifications and Methodology Improvements scheduled to be implemented in 1986 and 1987. An initial presentation of concepts was provided on November 8, 1984, the schedule for implementation of the program was presented to the NRC on March 8, 1985 and a detailed presentation of the portions of the program scheduled for implementation in early 1986 was provided on April 18, 1985. Reference 3 describes the program as presented in April.

The CPC Improvement Program consists of three major areas:

- Part A - Optimization of CPC/CEAC Software for Reloads

- Part B - CEAC Desensitization to Spurious Signals

- Part C - Reload Data Block Constants This document provides a detailed description of the CPC algorithm changes for Parts A and B.  ;

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....:.......,,..........-..-.-~.----.-~-. . . - . . . . . . . . .-- l The modifications described in this document will apply to Arkansas Nuclear One Unit 2 (ANO-2); Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2 and 3; San Onofre Nuclear Generating Station (SONGS) Units 2 and 3; and Waterford Unit 3 and are intended to be implemented at each plant at the next available software change.

1.2 REPORT

SUMMARY

Algorithm modifications for the CPC Improvement Program will affect the following programs:

6 Changes are described as revisions relative to the algorithms currently in place at SONGS-2 Cycle 2 and ANO-2 Cycle 5 (References 1and2). The general format used in describing each modification contained in this report is a statement of the change, the reason for the change, and a detailed description of the algorithm in symbolic algebra. All equation numbers and figure numb'ers are consistent with those in References 1 and 2.

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2.0 CPC SOFTWARE MODIFICATIONS 2.1 MODIFICATIONS TO FLOW ALGORITHM Change .

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A complete revised FLOW algorithm is as follows:

Algorithm Input 1

The FLOW algorithm requires the following process parameters from other CPC programs:

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4.0 ADDRESSABLE CONSTANTS Certain CPC constants are addressable so that they can be changed as required during operation. Addressable constants include (1) ,,,,

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090 X (common multiplier for DNBR and LPD) 091 X , PF time delay 092 093 094 095 096 X f , ASGT AT Trip setpoint 097 X 098 099 100 101 102 103 104

  • Type 1 addressable constants Page 76

3 i

h h 5.0 TYPICAL VALUES OF DATA BASE CONSTANTS FOR MODIFIED ALGORITHMS

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i 3

r 4;

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4 g

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L

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t
t w

t 6

2 7

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L k

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t p Page 77

t W

Page 78

m _.

r Page 79 ,

. . ... ... ..----c,----~.- _._ . _ . . _ . . . . _ . . ._ . . _ ,

m f

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Page 80

,. .. _..... .... . - = ::----:. . . . -- - . ..-- -- . -- -.- -- -

~

  • Page 81

6.0 REFERENCES

1. Functional Design Requirement for a Core Protection Calculator, CEN-305-NP, July,1985.
2. Functional Design Requirement for a Control Element Assembly Calculator, CEN-304-NP, July 1985.
3. CPC Improvements Program, Detailed Presentation to the NRC, CEN-302(S)-NP, April,1985.
4. "CEPAN Method of Analyzing Creep Collapse of Oval Cladding, Volume 5: Evaluation of Interpellet Gap Formation and Clad Collapse in Modern PWR Fuel Rods," EPRI NP-3966-CCM, Volume 5, Project 2061-6, Computer Code Manual, April 1985.

Page 82

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COMBUSTION ENGINEERING, INC.

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