|
---|
Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20198G4491998-07-31031 July 1998 Rev 1 to WCAP-15015, Specific Application of Laser Welded Sleeves for SCE San Onofre Units 2 & 3 Sgs ML20135A2961996-02-29029 February 1996 Annual Rept on Abb CE ECCS Performance Evaluation Models, Final Rept ML20058A4121993-08-31031 August 1993 Rev 1 to Suppl 4 to CENPD-279, Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46 ML20073H8181991-03-30030 March 1991 WCAP-12920, Analysis of Southern California Edison Co San Onofre Unit 3 Reactor Vessel Surveillance Capsule Removed from 97 F Location ML20062G8021990-11-30030 November 1990 Applicability of Notrump to San Onofre Nuclear Generating Station Unit 1 ML20055H2451990-06-25025 June 1990 Overheads/Passouts from NRC Review of San Onofre Nuclear Generating Station 1 Thermal Shield Design Analysis ML19324C4241989-10-31031 October 1989 Rev 0 to San Onofre Units 2 & 3 Fuel Rack Seismic Analysis for Final Pool Layout. ML20073K6781989-06-30030 June 1989 Risk Evalution of Removal of Shutdown Cooling Sys Autoclosure Interlock, Prepared for C-E Owners Group ML20235K9371989-02-28028 February 1989 Engineering Evaluation of San Onofre Nuclear Generating Station I Thermal Shield Supports ML20235Z0931989-02-28028 February 1989 Fuel Rack Seismic Analysis Methods & Parameters ML20154A6351988-07-31031 July 1988 Steam Generator U-Bend Tube Fatigue Evaluation ML20155J5231986-05-31031 May 1986 Rev 1 to Functional Design Requirement for Core Protection Calculator ML20155J5051986-05-31031 May 1986 Rev 1 to Functional Design Requirements for Control Element Assembly Calculator ML20155J4911986-05-31031 May 1986 Rev 0 to Core Protection Calculator/Control Element Assembly Calculator Software Mods for CPC Improvement Program Reload Data Block ML20205Q4601986-05-31031 May 1986 Nonproprietary SONGS 2 End of Cycle 2 Shoulder Gap Evaluation ML20151Z0521986-01-31031 January 1986 Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure ML20151Z0641986-01-31031 January 1986 Rev 0 to CEN-323-NP Reload Data Block Constant Installation Guidelines ML20154L6991985-12-31031 December 1985 Spray Additive Tank Deletion Analysis for San Onofre Nuclear Generating Station Units 2 & 3 ML20134M7891985-08-31031 August 1985 Nonproprietary Rev 0 to Cpc/Ceac Software Mods for CPC Improvement Program ML20134N3021985-07-31031 July 1985 Rev 00 to Functional Design Requirement for Core Protection Calculator ML20134N2941985-07-31031 July 1985 Rev 00 to Functional Design Requirement for Control Element Assembly Calculator ML20126H8321985-04-30030 April 1985 Nonproprietary Core Protection Calculator Improvement Program:Detailed Presentation to Nrc ML20112K0551985-03-31031 March 1985 Evaluation of Steam Generator Tube & Diagonal Spacer Strip Interaction & Wear,San Onofre Unit 2 ML20114C3771985-01-31031 January 1985 Nonproprietary End of Cycle 1 Shoulder Gap Evaluation ML20114B8211985-01-31031 January 1985 Nonproprietary Addendum to CEN-291(S) Response to NRC Questions on San Onofre Nuclear Generating Station Units 2 & 3,Cycle 2 ML20099C2851984-11-30030 November 1984 Nonproprietary Rev 1 to Core Protection Calculator/Control Element Assembly Calculator Software Mods ML20214E4801984-11-30030 November 1984 Review & Evaluation of Tdi Diesel Engine Reliability & Operability - San Onofre Nuclear Generating Station Unit 1, Technical Evaluation Rept ML20099C2321984-10-31031 October 1984 Nonproprietary Rev 1 to San Onofre Nuclear Generating Station Unit 2 Core Protection Calculator & Control Element Assembly Calculator Data Base Listing ML20204H4281984-10-31031 October 1984 Nonproprietary Statistical Combination of Uncertainties, Part Ii,Uncertainty Analysis of Limiting Safety Sys Settings ML20204H4971984-10-31031 October 1984 Nonproprietary Statistical Combination of Uncertainties, Part Iii,Uncertainty Analysis of Limiting Conditions for Operation ML20093N2661984-07-31031 July 1984 Nonproprietary Cpc/Ceac Software Mods for San Onofre Nuclear Generating Station Units 2 & 3. Info Deleted ML20093N2501984-06-30030 June 1984 Nonproprietary Safety Analysis & CPC Methodology Changes for San Onofre Nuclear Generating Station,Units 2 & 3. Info Deleted ML20095F9411984-03-31031 March 1984 Nonproprietary Version of Rev 0 to SONGS-2 Cycle 1,CPC & Ceac Data Base ML20080K3231983-09-30030 September 1983 Suppl 1,Rev 1,to PRA of Effects of PORVs on Depressurization & Dhr ML20072J5071983-06-30030 June 1983 Depressurization & Dhr,Responses to NRC Questions ML20072J5371983-06-30030 June 1983 Suppl 1 to CEN-239, PRA of Effects of PORVs on Depressurization & Dhr,San Onofre Nuclear Generating Station,Units 2 & 3 ML20070M1291983-01-31031 January 1983 Natural Circulation Test Program,San Onofre Nuclear Generating Station,Unit 2,Natural Circulation Cooldown ML20052B6411982-03-31031 March 1982 Effects of Vessel Head Voiding During Transients & Accidents in C-E Nsss.Prepared for C-E Owners Group. ML20039F8601981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for San Onofre 2 & 3 Reactor Vessels. ML20010F2971981-09-0303 September 1981 Errata Pages to CEN-160-(S)-P, CETOP-D Code Structure & Modeling Methods for San Onofre Nuclear Generating Station, Units 2 & 3. Formal Submittal Will Be Provided ML20010C7781981-08-0505 August 1981 Nonproprietary Version of San Onofre Nuclear Generating Station 2,Cycle 1,CPC & Ceac Data Base Document. ML20010A2931981-07-31031 July 1981 to Comprehensive Vibration Assessment Program Final Rept. ML20126L3571981-05-31031 May 1981 Nonproprietary Version of, Responses to NRC Concerns on Applicability of CE-1 Correlation to SONGS Fuel Design ML20004D8231981-05-31031 May 1981 Nonproprietary Version of CETOP-D Code Structure & Modeling Methods for San Onofre Nuclear Generating Station,Units 2 & 3. ML20010C7701981-03-31031 March 1981 Nonproprietary Functional Design Spec for Core Protection Calculator,Response to NRC Questions 221.18 & 221.20. ML20010C7721981-03-31031 March 1981 Nonproprietary, Functional Design Spec for Control Element Assembly Calculator,Response to NRC Questions 221.18 & 221.20. ML13312A5661980-06-30030 June 1980 Response to NRC Question 222.34, Nonproprietary Version, June 1980 ML20010H7041979-11-15015 November 1979 Plant Protection Sys Selection of Trip Setpoint Valves, Revision 00 1998-07-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E3381999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Songs,Units 2 & 3 ML20212A1471999-09-13013 September 1999 Special Rept:On 990904,condenser Monitor Was Declared Inoperable.Difficulties Encountered During Component Replacement Precluded SCE from Restoring Monitor to Service within 72 H.Alternate Method of Monitoring Was Established ML20211N0511999-09-0303 September 1999 SER Approving Exemption from Certain Requirements of 10CFR50.44 & 10CFR50 App A,General Design Criterion 41 to Remove Requirements from Hydrogen Control Systems from SONGS Units 2 & 3 Design Basis ML20211Q8201999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Songs,Units 2 & 3. with ML20211H8621999-08-23023 August 1999 Safety Evaluation Accepting Licensee Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20210P4791999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 3 ML20210P4731999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 2 ML20210Q6521999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Songs,Units 2 & 3 ML20210L2771999-07-30030 July 1999 SONGS Unit 3 ISI Summary Rept 2nd Interval,2nd Period Cycle 10 Refueling Outage U3C10 Site Technical Services ML20209C9281999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Songs,Units 2 & 3. with ML20195D3061999-06-0202 June 1999 Safety Evaluation of TR SCE-9801-P, Reload Analysis Methodology for San Onofre Nuclear Generating Station,Units 2 & 3. Rept Acceptable ML20195H5491999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Songs,Units 2 & 3 ML20196L3221999-05-11011 May 1999 SONGS Unit 2 ISI Summary Rept 2nd Interval,2nd Period Cycle-10 Refueling Outage ML20206H2611999-05-0505 May 1999 Part 21 Rept Re Defect Found in Potter & Brumfield Relays. Sixteen Relays Supplied in Lot 913501 by Vendor as Commercial Grade Items.Caused by Insufficient Contact Pad Welding.Relays Replaced with New Relays ML20206S7281999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Songs,Units 2 & 3 ML20205Q6221999-04-19019 April 1999 Safety Evaluation Authorizing Proposed Alternative to Use Wire Penetrameters for ISI Radiography in Place of ASME Code Requirement ML20205R0371999-04-16016 April 1999 SER Approving Proposed Deviation from Approved Fire Protection Program Incorporating Technical Requirements of 10CFR50,App R,Section III.0 That Applies to RCP Oil Fill Piping ML20205G2611999-04-0101 April 1999 Special Rept:On 990328,3RT-7865 Was Removed from Service. Monitor Is Scheduled to Be Returned to Service Prior to Mode 4 Entry (Early May 1999) Which Will Exceed 72 H Allowed by LCS 3.3.102.Alternate Method of Monitoring Will Be Used ML20205Q0981999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Songs,Units 2 & 3 ML20204F8101999-02-28028 February 1999 Monthly Operating Repts for Songs,Units 2 & 3.With ML20203J1981999-02-12012 February 1999 Safety Evaluation Supporting Amends 149 & 141 to Licenses NPF-10 & NPF-15,respectively ML20202F7041999-01-21021 January 1999 Special Rept:On 990106,SCE Began to Modify 2RT-7865.2RT-7865 to Allow Monitor to Provide Input to New Radiation Monitoring Data Acquisition Sys.Monitor Found to Exceeds 72 H Allowed Bt LCS 3.3.102.Alternate Monitoring Established ML20199F0771998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Songs,Units 2 & 3 ML20206H2101998-12-31031 December 1998 SCE 1998 Annual Rept ML20198A6731998-12-11011 December 1998 Special Rept:On 981124,meteorological Sys Wind Direction Sensor Was Observed to Be Inoperable.Caused by Loss of Communication from Tower to Cr.Sensor Was Replaced & Sys Was Declared Operable on 981204 ML20196D8901998-11-30030 November 1998 Non-proprietary Reload Analysis Methodology for Songs,Units 2 & 3 ML20198C3471998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Songs,Units 2 & 3 ML20195H2471998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Songs,Units 2 & 3 ML20154B7211998-10-0101 October 1998 Safety Evaluation Approving Licensee Request to Implement Alternatives Contained in Code Case N-546 for Current Interval at Songs,Units 2 & 3 Until Code Case Approved by Ref in Reg Guide 1.147 ML20154M7921998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Songs,Units 2 & 3 ML20155F6081998-09-17017 September 1998 Non-proprietary Version of San Onofre 2 & 3 Replacement LP Rotors ML20151Z9851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Songs,Units 2 & 3 ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20198G4491998-07-31031 July 1998 Rev 1 to WCAP-15015, Specific Application of Laser Welded Sleeves for SCE San Onofre Units 2 & 3 Sgs ML20237B8571998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Songs,Units 2 & 3 ML20236N3871998-07-0909 July 1998 Part 21 Rept Re Deficiency Identified in Event 32725, Corrected by Mgp Instruments Inc.Licensee Verified,Affected Equipment Has Been Reworked & Tested at Sce.Design Mod Completed ML20236R1031998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Songs,Units 2 & 3 ML20249A9431998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Songs,Units 2 & 3 ML20248B8981998-05-26026 May 1998 Updated SG Run Time Analysis Cycle 9 ML20248B9221998-04-30030 April 1998 Rev 0 to AES 98033327-1-1, Updated Probabilistic Operational Assessment for SONGS Unit 2,Second Mid Cycle Operating Period,Cycle 9 ML20247L5181998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Songs,Units 2 & 3 05000361/LER-1998-003, LOCA Evaluation of Safety Significance of Failure of Emergency Sump Valve Linestarter (LER 1998-003)1998-04-0606 April 1998 LOCA Evaluation of Safety Significance of Failure of Emergency Sump Valve Linestarter (LER 1998-003) ML20217Q6161998-04-0505 April 1998 Failure Analysis Rept 98-005,Failure Analysis of 2HV9305 Motor Starter ML20217A0141998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Songs,Units 2 & 3 ML20217D4701998-03-0202 March 1998 Rev 1 to 90459, Failure Modes & Effects Analysis DG Cross- Tie,DCP7048.00SE ML20216J3551998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Songs,Units 2 & 3 ML20203E7301998-02-17017 February 1998 SER Accepting 980105 Request to Use Mechanical Nozzle Seal Assembly as Alternate Repair Method,Per 10CFR50.55a(a)(3)(1) for Plant,Units 2 & 3 ML20203K9141998-02-0303 February 1998 Rev 0 to ESFAS Radiation Monitor Single Failure Analysis. W/96 Foldout Drawings ML20202F9731998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Songs,Units 2 & 3 1999-09-30
[Table view] |
Text
'
I
. SOUTHERN CALIFORNIA EDISON, SAN ONOFRE i NUCLEAR GENERATING STATION 2 AND 3 (SONGS 2 & 3)
DOCKETS 50-361 AND 50-362 CEN-281(S)-NP REVISION 01-NP CPC/CEAC SOFTWARE MODIFICATIONS ,
NOVEMBER, 1984 COMBUSTION ENGINEERING, INC.
NUCLEAR POWER SYSTEMS POWER SYSTEMS GROUP WINDSOR, CONNECTICUT 8411190460 841115 PDRADOCK05000g P
LEGAL NOTICE This report was prepared as an account of work sponsored by Combustion Engineering, Inc. Neither Combustion Engineering nor any person acting on its behalf:
- a. Makes any warranty or representation, express or implied' including the warranties of fitness for a particular purpose or merchantability, with respect to the accuracy,
. completeness, or usefulness of the information contained in this response, or that the use of any information, apparatus, method, or process disclosed in this response 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 response.
G e
o O
s fi l
l 1
I
TABLE OF CONTENTS Section Title Pace No.
1.0 INTRODUCTION
1.1 Report Scope 1-1 1.2 Report Summary 1-1 1.3 References for Section 1.0 1-3 2.0 SOFTWARE MODIFICATION 2.1 Changes Derived from Implementation of PVNGS 2-1 Cycle 1 Software 2.2 Additional Core Protection Calculator (CPC)
Algorithm Changes 23 2.3 CPC Addressable Constant Changes 2 13 2.4 Typical Data Base Constants for SONGS Unit 2 2 14 2.5 References for Section 2.0 2 18 J O e
t iii
1.0 INTRODUCTION
l 1.1. REPORT SCOPE The Core Protection Calculator (CPC) System developed by Comcustion Engineering is a digital mini-computer system which calculates the minimum Departure from Nucleate Boiling Ratio (DNBR) and the peak Local Power Density (LPD) on-line and generates a reactor trip if either the minimum DNBR or the peak LPD approaches the appropriate Specified Acceptable Fuel Design Limit. The CPC System has been reviewed by NRC and approved for operation in Arkansas Nuclear One (ANO) Unit 2, Waterford-3, San Onofre Nuclear Generating Station (SONGS) Units 2 and 3 and Palo Verde Nuclear Generation Station (PVNGS) Units 1, 2 and 3. The CPC/CEAC software for SONGS Unit 2 and 3 is being modified for operation in Cycle 2. This modification is being made using the PVNGS Cycle 1 CPC/CEAC software (Reference 1.3-3) as a basis since it is the latest NRC approved software. The modification for SONGS Units 2 and 3 Cycle 2 includes algorithm changes derived from the implementation of the PVNGS Cycle 1 software as well as other algorithm changes. These changes were made to the CPC System in accordance with the NRC-approved CPC software change procedure (References 1.3-1 and 1.3-2).
This report describes the changes to the SONGS software for Cycle 2.
Changes derived from the implementation of the PVNGS Cycle 1 software are described briefly since they have been approved and implemented previously (Reference 1.3-3) while other changes are
. described in detail.
1.2 REPORT
SUMMARY
The modifications to the CPC/CEAC software which will be applicable to Cycle 2,of SONGS Units 2 and 3 are:
1-1
l
- 1) Modification of the temperature shadowing factor algorithm.
- 2) Modification of the CPC core power bias algorithm.
- 3) Improvement to the UPDATE algorithm.
. 4) Modification of the heat flux distribution extrapolation in STATIC.
- 5) Addition of new addressable constants.
- 6) Modification of the four linear heat distributions in STATIC program to account for differences between the hot channel and hot pin relative powers.
- 7) Upgrade of the non-uniform heating correction factors (FK) in the UPDATE program.
The general format used in describing each software modification contair.ed in this report is a statement of the change, the reason for the change, and a detailed description of the change including algorithm descriptions in symbolic algebra. This is the same format used in Reference 1.3-3.
l 1-2
1.3 REFERENCES
FOR SECTION 1.0
- 1. CEN-39(A)-NP, Revision 02, The CPC Protection Algorithm Software Change Procedure, December 21, 1978.
- 2. CEN-39(A)-NP, Supplement 1-NP, Revision 01, January 5, 1979.
- 3. Dockets STN-50-470F, Enclosure 1-NP to LD-82-039, CPC/CEAC Software Modifications for System 80, March, 1982.
4 L
e a
I 1-3 l
1
1 l
l 2.0 SOFTWARE MODIFICATIONS 2.1 CHANGES DERIVED FROM IMPLEMENTATION OF PVNGS CYCLE 1 SOFTWARE The changes in CPC software for SONGS Units 2 and 3 Cycle 2 that have been derived from implementation of the PVNGS Cycle 1 software are described in the following' summaries. These changes were submitted previously to the NRC (Reference 2.5-1).
- 1. The non'-uniform heating correction factor (F g) in the UPDATE progr,am was adjusted by the_ addition of constants based on the in quality margin.
- 2. The calculation of the four linear heat rate (LHR) distributions in the STATIC program was modified to account for the difference between the hot channel and hot pin relative powers.
- 3. The positivegange limit on t,be CEAC penalty facpr .,
mul t_ipliers ,' -
, was shifted from L - .
to .
4 Algorithms were added to the CPC and CEAC (Control Element .
Assembly Calculator) for detecting the actuation of a Reactor Power Cutback (RPC) event, for using off-line calculated RPC penalty factors, and for allowing the CPC calculation to more closely model core conditions without generating an inadvertent trip in the event of a RPC. Since SONGS Units 2 and 3 do not have a RPC system, the effect of these algorithms will be nullified thrcugh the appropriate data base constants.
- 5. Addressable constants have been added to the CPC and CEAC to define the duration that the RPC flags can remain set. (For SONGS these addressable constants will be set to a),
2 . _ -_
- 6. An algorithm was added to the FLOW Program to account for forward flow through'a reactor coolant (RC) pump at or near zero revolution per minute (RPM). Since SONGS Units 2 and 3 do not have a very rapid occurrence of negative head across an RC l
pump with a locked rotor, the effect of this algorithm will be l nullified through the appropriate data base constants.
9 0
a G
2-2
I 2.2 ADDITIONAL CORE PROTECTION CALCULATOR (CPC) ALGORITHM CHANGES 2.2.1 Modification of the Temperature Shadowing Factor Algorithm Change:
l l Implement for cycle 2 a the T,emperature Shado. wing Factor (TSF) on moderator temperature using a inlet modgator temperature. The slope of the _
lorrection for tEper_atures will Ig. chosen to bound all expected TSF datal -
Including uncertdnti"es. A ., , will be used for temperatures . Tlie excore detector calibration procedures will be modiffeit to be consistent with this determination of the TSF and its use in adjusting the neutron flux power.
Reason:
The ter.iperature shadowing factor (TSF) is used to correct the CPC neutron flux power for decalibration effects resulting from changes in inlet coolant density. A moderator temperature-dependent multiplier is applied to the neutron flux power calculation to corrgt excore detector reponse. In the current algorithm. the TSF is a of the change in moderator temperature the slope of which is measured at start-up. The uncertainty in the measurement of the TSF is currently accomodated in the CPC Departure from Nucleate 81,iling (DNB) andjinear Heat Rate (LHR) overall uncertainty terms .
~
This change will allow the TSF uncertainty to be included directly in the factor itself. This insures a conservative correction for temperature at moderator temperatures above or below the inlet moderator temperature at which the neutron flux power was calibrated (calibration temperature) while removing unnecessary penalties for uncertainty at the calibration temperature (which is anticipated to be near nominal conditions).
2-3
Description:
lM i
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l 2.2.2 Modification of the CPC Core Power Bias Algorithm Change:
Implement to adjust the thermal power
~
and neutr65 flux power level in the CPCs.
2-4
_ _ _ _ _ _ _ ___. . -. ~ . - _. . . -_ - - .. - .-_ _ __
Reason:
I 1
Description (See Figure 1):
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. y 1 I m
2
._ i e
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,r - - - _ , _ _ . . _ , _ - _ _ _ _ , . _ - _ - .. . , . .,m_ _ _. ,, , _ , __ , _ , ,,__, . _ , , , -_.,, ._ - _ . _ . _ , . . , _______m_.
au. es Where
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2.2.3 Improvement to UPDATE Algorithm Change:
ThepenaltyonDNBRinUPDATEwillbemodelledmorerealistically.
When the M
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2-9
l Reason:
The UPDATE algorithm of CPC provides rapid and conservative recalculation of DNBR based upon the detailed DNBR calculation contained in the STATIC algorithm and updated state parameters.
During the CPC overall DNS uncertainty analysis, off-line , _
comparisons of UPDATE and STATIC-predicted DNBRs based on
] period are used to quantify the conservatism. Presently, the UPDATE algorithm of CPC applies a penalty to the updated DNBR at all times.
This change provides greater margin to pre-trip alams during steady state operation and is justified by the high accuracy of the UPDATE algorithm for small changes in conditions. The safety margin of the CPC's during transients is preserved by the larger conservative penalty factors which are applied when the UPDATE DNBR changes significantly from the STATIC value.
Description:
l
=
= R4y. 01 2-10
1 l
l
- - 4e_ .,
where ,
l
- - ste.et 2.2.4 Modification of Heat Flux Distribution Extrapolation in STATIC Change:
Modify the heat flux distribution extrapolation in STATIC nodal heat flux distribution values.
Reason:
For certain CEA configurations, radial peaking factor assignments, and/or radial peaking factor multipliers, it is possible to i
2-11
l l
Descrintion: '
l This change is applied in the section of the STATIC program whgre l D
~
A check is performed for values. If any are detected. .
Where:
$c5i) node hot pin normalized heat flux distribution 2.2.5 Modification of DNBR Penalty for ASGT in UPDATE Change:
, Modify the calculation of
~
- - with an additional test for small number.
Reason:
~
- J
Description:
i i
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where:
2-12 - Rev. ei
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l 2.3 CPC ADDRESSAELE CONSTANT CHANGES
- 1. Change:
Addressabje_ constant
, replaces .
Reason:
Consistent with TSF algorithm change described in section 2.2.1.
Description:
L -
- 2. Change Addressable constant has been added to the CPC in relation to the core power level 7 Reason:
To implement n,ew algorithm using 6 -
and L -
bias terms described in section 2.2.2.
Description:
2-13
l 1
I 1
l 2.4 - TYPICAL DATA BASE CONSTAf;TS CHANGES FOR SONGS UNIT 2 2.4.1 Data Base Constants for the Temoerature Shadowing Factor Algorithm Constants.
- 9 2.4.2 Data Base Constants for Power Dependent Biases e
P
'W g 2-14
~
l 2.4.3 Data Base Constants for DNBR Penalty in UPDATE men -
mmme =
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2.4.4 Chance in UPDATE ON8R Uncertainty and Threshold Constants M m I
2-15
--- - , , , - , . , , , , , , , - - , - - - - - ,,------wg,,,n- ,- -- , -, - , - , - . . -----w-- - ---- , , - -,, -
r- ---- , , -, ,c.. ,- - -, , -n----
2.4.5 Data Base Constants for RPC Algorithm M
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2-17 l
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2.5 REFERENCES
FOR SECTION 2.0
- 1. Dockets STN-50-470F, Enclosure 1-NP to LD-82-039, CPC/CEAC Software Modifications for System 80, March, 1982.
. 2. CEN-147(S)-NP, Functional Design Specification for a Core Protection Calculator, January 1981.
- 3. CEN-148(S)-NP, Functional Design Specification for a Control Element Assembly Calculator, January 1981.
1 i
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! COMBUSTION ENGINEERING, INC.
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