ML20236W355
| ML20236W355 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/29/1998 |
| From: | Sorensen J NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9808050227 | |
| Download: ML20236W355 (23) | |
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Northern ststes Power Company 1717 Wakonade Dr. E.
Welch, MN 55089 Telephone 612 388-1121 July 29,1998 10 CFR Part 50.59 U S Nuc' ear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Response to June 29,1998, Request for Additional Information on Proposed Revision to Main Steam Line Break Methodology dated June 26,1997 The information in the attachment is provided in response to an NRC staff request dated June 29,1998, for additional information related to our proposed revision to the Main Steam Line Break Methodology dated June 2.6,1997.
In this submittal we have made no new NRC commitments. If you have any questions related to this matter, please contact John Stanton at 612-388-1121.
Joel P. Sorense 1
Plant Manager Prairie Island Nuclear Generating Plant I
i 9808050227 980729 PDR ADOCK 05000282 P
PM w_________.
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USNRC NORTHERN STATES POWER COMPANY July 14,1998 Prge 2
Attachment:
Response to June 29,1998, Request for Additional Information on Proposed Revision to Main Steam Line Break Methodology dated June 26,1997 c:
Regional Administrator-ill, NRC NRR Project Manager, NRC Senior Resident inspector, NRC Kris Sanda, State of Minnesota J E Silbca i
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July 29,1998 NORTHERN STATES POWER COMPANY 4
Attachment Response to June 29,1998, Request for Additional information on Proposed Revision to Main Steam Line Break Methodology dated June 26,1997 l
Question 1:
The revised methodology described in NSPNAD-97002-P (" Northern States Power Company Steam Line Break Methodology") includes taking credit for operation of the steam line non-return check valve to isolate the non4ffected steam generator after the rupture. Explain the basis for the l
assumptions made for check valve operation in this case. Specifically address the following:
a.
The basis for assuming that the check valve will withstand the loads generated during l
a main steam line break b.
The basis for the assumed cicsing time of the check valve for the ficw rates generated over the range of main steam line break sizes considered. The response should focus l
on whether predicted reverse steam flow is sufficient in all cases to close the check valve in the time assumed for the analysis.
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Response
The non-retum check valves are designed to eliminate blowdown from the intact SG for steam line ruptures upstream of the non-return check valve. Section 11.7.3 of Prairie Island's Updated Safety Analysis Report (USAR) contains the reference to the structural analysis report for the l
main steam check valves, NSC-Pl0-01-06 titled " Analysis Report - Structural Analysis of Main l
Steam check and Isolation Valves for Prairie Island Unit 1". Copies of these analyses had been sent to the Atomic Energy Commission in 1973. Based on the results of these analyses it has been concluded that the non-return check valves will withstand the loads generated during a i
main steam line break.
The main steam non-return check valves are free swinging check valves held open by the forward steam flow. There are no mechanical or pneumatic devices that must actuate for the valve to close, or that will slow its closure. Therefore, as soon as forward flow ceases, the valve will swing shut. As reverse flow begins, the steam flow will accelerate the closure of the valvo.
Topical report PIO-02-03 titled: " Analysis Report - Maximum Energy of Disc Impact - Main Steam Check and Isolation Valves for Kewaunee Unit 1," referenced in Prairie Island's USAR i
section 11.7.3, 'contains calculations of check valve closure times for various operating conditions. The calculations show that the maximum calculated closure time is 0.0687 seconds for a double ended guillotine main steam line break. Simple calculations relying only on gravity to close the valve show that it will close in less than 0.5 seconds after forward flow ceases.
Based on this information, the assumption that the non-return check valves closes 16econd i
after forward flow ceases is conservative for all cases.
July 29,1998 NORTHERN STATES POWER COMPANY l
Att chm:nt Pag 3 2 Question 2:
NSPNAD 97002-P explains that the modeling includes liquid entrainment in the steam blowdown from the steam line break. Reference is made to WCAP-8822 (Reference 10 in NS?NAD-97002-P),
and the NSP report says that the WCAP entrainment data was used in the Prairie Island analysis.
Appendix A to WCAP-8822 contains blowdown data for 3. and 4-loop Westinghouse plants.
Explain the basis and methods for applying the 3-and 4-loop blowdown data to the 2-loop design at Prairie Island.
Response
Appendix A of WCAP-8822 contains the mass and energy releases that were obtained by combining the effluent quality vs. time information from section 2 of the WCAP with variations of l
plant operation, safety system performance, break sizes and plant designs. The intention of the appendix was to provide sufficient latitude in the range of variables significantly affecting the releases such that a large number of Westinghouse plants would be able to utilize the results to determine the mass and energy releases from a steam line break. The methodology in NSPNAD-97002-P does not utilize the results or methods in appendix A of WCAP-8822 in j
determining the mass and energy release during a steam line break.
The DYNODE-P code does not have the capability to calculate the quality of the steam at the break location; therefore, the amount of entrainment, or quality, must be manually inserted via a table in the input deck. The methodology in NSPNAD-97002-P utilizes the Effluent Quality vs.
Time data in figures 2.4-2 through 2.4-5 of WCAP-8822 as input into the DYNODE-P code. This was accomplished by tabulating the figures, including the recommended uncertainty, and inserting the appropriate table (quality vs. time) for the case being run. The code uses this information along with the other inputs and assumptions described in NSPNAD-97002-P to calculate the steam generator blowdown, i.e. mass and energy release. This approach allows the methodology to explicitly account for the effects of entrainment while modeling the plant specific systems and interactions. WCAP-8822 section 2.0 contains information on why figures 2.4-2 through 2.4-5 are conservative for model 51 steam generators. The steam generators at Prairie Island are model 51 steam generators.
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I July 29,1998 NORTHERN STATES POWER COMPANY Attachmint Prg3 3 i
l Question 3:
NSPNAD-97002-P references NSP VIPRE Version 95325, Revision 0, March 1996 as the documentation for the VIPRE code. Available documentation Indicates that the most recent NRC l
review of the code for Prairie Island was associated with the approval for NSPNAD 8102-P, the reload safety evaluation methods report (NRC Safety Evaluation dated May 30,1986). Discuss changes to VIPRE, relevant to the analysis of main steam line breaks, since the most recent NRC-approved revision as applied to the Prairie Island units.
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Response
Prior to VIPRE version 95325, NSP used versions of VIPRE-01 Mod-01 which had been modified by the Nuclear Analysis and Design (NAD) department. In version 95325, NSP discontinued use of the VIPRE-01 Mod-01 based version and started using an NAD modified version of the EPRI issued version' of VIPRE-01 Mod-02. The following page lists the changes made to this EPRI issued version of VIPRE-01 Mod-02. Prior to being used for reload safety evaluations, the new version was thoroughly checked-out and tested in accordance with Nuclear Analysis and Design (NAD) department's procedures. These pacedures assure that computer codes used for safety related applications are consistent with the approved topical reports and related NRC Safety Evaluation Reports (SERs). The conclusion was that the changes were not a deviation from the methodology in our NRC approved topical reports.
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' NRC approval in SER issued October 30,1993.
July 29,1998 NORTHERN STATES POWER COMPANY Attachment Page 4 Changes Made to VIPRE - 01 MOD - 02 resulting in VPR 95325 High Rod Power Calculations This modification prevents a failure in the calculation of the properties for the film due to exceeding the range of the properties functions in the iteration of film enthalpy. This change incorporated EPRI's VIPRE-01/ MOD-02 modification / error change #179.
Axial Node Divide by Zero Error This modification corrected a divide by zero error that occurred if the number of axial nodes on GEOM 3 was different than the number of axial nodes entered on GEOM 1. This change incorporated EPRl's VIPRE-01/ MOD-02 modification / error change #198.
VIPRE-DYNODE Interface This modification reprocesses the data from DYNODE (double precision) and formats the data in a VIPRE format (single precision). This change is similar to the recommended change in EPRI's VIPRE-01/ MOD-02 modification / error change #205.
Iteration on Inlet temperature Error This modification corrected an error that occurred in the iteration on inlet temperature to a specified MDNBR, if the inlet flow boundary condition was specified using the option for the uniform inlet velocity. This change incorporated EPRI's VIPRE-01/ MOD-02 modification / error change #199.
Incorporated WRB-1 Heat Flux Correlation and VPR-DNP Interface.
This modification to VIPRE-01/ MOD-02 incorporated the necessary coding for the WRB-1 heat flux correlation, and interfaces with the DYNODE-P code.
July 29,1998 NORTHERN STATES POWER COMPANY Attrchm:nt Pag) 5 Question 4:
NSPNAD 97002-P references NSP DYNODE-P Version 94305, Revision 0, January 1995 as the documentaGon for the DYNODE-P code. Available documentation indicates that the most recent NRC review of the code for Prairie Island was documented in the NRC Technical Evaluation Report, dated February 17,1983. Discuss changes to DYNODE-P since the most recent NRC-approved revision as applied to the Prairie Island units.
Response
The NRC Technical Evaluation Report, dated February 17,1983, was part of the original SER for NSP's Reload Safety evaluation methods in NSPNAD-8102 Rev.1. The DYNODE-P version used in that report was 81275, since that time NSP has updated DYNODE-P ten times. Prior to being used for reload safety evaluations, each new version was thoroughly checked-out and tested in accordance with Nuclear Analysis and Design (NAD) department's procedures. These procedures assure that computer codes used for safety related applications are consistent with the approved topical reports and related NRC SERs. The following pages contain a listing of all the changes made to each version update. Many of the changes involved programming enhancements such as adding plotting subroutines or s vitching styles used for common blocks.
Other changes involved adding options to the code that are not used for reload safety evaluation analyses, such as detailed modeling of the steam dump system. The remainder of the changes j
do not result in deviations from the methodology in our NRC approved topical reports.
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i July 29,1998 NORTHERN STATES POWER COMPANY Att: chm:nt P:ge 6 Changes Made to DNP 81275 resulting in DNP 82060 NAl/CDC Code Specific Char.ges This modification converted severallines of code into IBM FORTRAN.
Added Calls This modification added calls to several subroutines to get additional information on l
program execution and to create control cards for Datagraphicx COM recorders. Read statements were added to capture plot titles, and additional error messages were added for clarity.
Restructuring to Allow for Double Precision This modification restructured common blocks to allow for double precision.
i Function Calls Changed to Reflect Double Precision Tnis modification changed the function calls to reflect double precision. A generic statement was added to allow the function to determine if the variables are real, double f
precision or integer.
l Page Ejection Improvement This modification improved page ejection to allow more information.
Output Formats Exceeded 133 Characters l
This modification changed all of the output characters to 133 characters or less.
COMDECKS to REPLACE for Common Blocks i
1 This modification switches the style used for common blocks from COMDECK to REPLACE.
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l Addition Data Captured for Plotting l
This modification captures addition data for the plotting subroutine.
Integer Versions of MEMOVE and MEMSET were created This modification created integer versions of the MEMOVE and MEMSET subroutines.
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July 29,1998 NORTHERN STATES POWER COMPANY Att:chmmt Pag) 7 f
Assumption That All Common Blocks end in a Single Precision Word This modification added a single precision variable to the end of all of the common blocks l
so that the lengths of the common blocks may be correctly calculated for restart cases.
l Program Summary Written to FORTRAN Unit 6 This modification writes the program summary to F.)RTRAN unit 6 and 61 so that when the output is microfiches, the summary a ways appears on paper.
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Steam Generator Tube Rupture Error L
This modification corrected an error in the rupture flow. The rupture flow was being added i
to the SG twice, once into the downcomer and once into the riser.
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Main Steam Line Non Return Check Valve l
This modification added the option to have the check valves fail.
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July 29,1998 NORTHERN STATES POWER COMPANY Att: chm:nt P ge 8 Changes Made to DNP 82060 resulting in DNP 82270 l
l Variable Low Pressure Trip Logic This modification changed the low pressure trip logic.
l Space -Time Kinetics Model l
l This modification provided a self-initialization of the space - time kinetics model.
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Metal Heat Modes This modification is a correction in the heat transfer correlations used in the metal l
structure model.
l The Subcritical Option This rnodification allows the option for the core to be initially suberitical.
l Oxide Heat Capacity Table This modification provided a table set of inputs for fuel heat capacity.
l Time Dependant Gap Heat Transfer Coefficient This modification provided a transient gap heat transfer coefficient multiplier option.
Time or Volume Dependent SG UA l
This modification provides the option of either a time dependant or volume dependant steam generator UA (universal heat transfer coefficient x the surface area of the U -
tubes).
Turbine Flow Dependence on Steam Generator Pressure This modification causes the turbine steam flow to be dependent upon the steam generator pressure.
Sensed Pressurizer Level This modification adds a calculation of the sensed pressurizer liquid level.
l Steam Generator Non-Equilibrium Model This modification provided a non-equilibrium model for the pressure on the secondary side of the steam generators.
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July 29,1998 NORTHERN STATES POWER COMPANY Attachment P ge 9 Explicit Representation of Pressurizer Heaters This modification provided the modeling of the heaters in the pressurizer Ex-Core Detectors This modification added modeling of the ex-core detectors.
Auxillary Spray Lines This modification provided a model for the pressurization of the auxiliary spray lines.
Small Break LOCA This modification added the option to simulate a small break LOCA in the cold leg.
Detailed Dump and Bypass Option This modification added the detailed dump / bypass option.
Surge Line This modification added the model for the surge line pressure drop.
Loop Pressure Loss Coefficients l
This modification added a flow dependence for the loop pressure loss coefficient.
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July 29,1998 NORTHERN STATES POWER COMPANY Attachment Page 10 Changes Made to DNP 82270 Resulting in DNP 82340 Plot Subroutine The plot subroutine was corrected to pick up different variables.
Low Pressure Trip The variable low pressure trip logic was changed back to the original logic.
July 29,1998 NORTHERN STATES POWER COMPANY Attachm:nt P ge 11 Changes Made to DNP 82340 resulting in DNP 83120 Pressurizer Refill Option This modification provides an option to allow the pressurizer to refill.
Option to Set Turbine Trip Time This modification allows the option to set the turbine trip time equal to the scram time.
Error Correction This modification fixed the check for a negative square root.
Correct Time Step This modification limits the size of the time step for the heat conductors on the secondary side when the non-equilibrium modelis used.
Addition of Flux Rate Trip This modification provides the option for a flux rate trip.
Separate Integration of Heat Conductors This modification separates the Integration of the heat conductors.
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July 29,1998 NORTHERN STATES POWER COMPANY Att: chm:nt P:ge 12 l
Changes Made to DNP 83120 resulting in DNP 83280 Minimum Pump Speed Stop 1
This modification adds a minimum speed at which the pump will stop.
Secondary Side Correction
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This modification corrected an error in a subroutine for the detailed SG model where the steam generator riser outlet flow is calculated.
Steam Generator UA Vold Dependant Multiplier Option This modification provides the option to include a steam generator UA void fraction dependent table set (UA is the overall heat transfer coefficient times the surface area of the u - tubes).
One-Loop RCS Low Flow Pump Trip Option This modification provides an option to use a low flow pump trip on individual loops.
Steam Generator Drift Flux Mixture Level This modification provides a drift flux model to calculate mixture level on the secondary side of the steam generators.
i Steam Generator Heat Transfer Model This modification provides an option to calculate the heat transfer through the portion of the steam generator tubes above the mixture level.
Non-Equilibrium Steam Generator Model for Dried Out Steam Generator Condition This modification provides the ability to model complete dry out and refill of the secondary side of the steam generators when the non-equilibrium model is used.
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July 29,1998 NORTHERN STATES POWER COMPANY l
Att chm:nt l
Page 13 Changes Made to DNP 83280 resulting in DNP 84163 Plotting Option This modification added conversion factors between Si and English units to the plot.
1 Steam Generator Level Calculation Correction This modification corrected the discontinuity problems with the steam generator level calculations.
Rate Flux Trip Option i
This modification provides an option to use ex core detectors in flux rate trip.
l Rod Controller Options
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This modification provides the option to model ex-core detectors for controller, i
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July 29,1998 NORTHERN STATES POWER COMPANY Attacliment Page 14 Changes Made to DNP 84163 resulting in DNP 87114 Moisture Carryover Option This modification provides the option of modeling entrainment for the steam line break cases.
DNB Calculation Omission Option This modification allows the user to disable the DNB calculation in the DYNODE code.
Steam Dump Arming Logic This modification provided the option of when to arm the steam dump system: before the turbine trip, or only after the turbine trip.
Variable RCS Temperature Delay Times This modification allows the user to input the RCS loop temperature sensors delay times to be a function of the loop's flow.
New Restart Code Series This modification relates to the ability to modify steam line and turbine valve input parameters for restart cases.
Steam line Pressure Balancing Line Option This modification models the pressure balancing line between the two steam lines.
Increased Number of Decay Heat Groups This modification increased the dimension of the arrays for the heat decay groups:
Steam /Feedwater Mismatch Colncident with Low Steam Generator Level Trip This modification adds the reactor trip for low steam generator level coincident with a steam flow feedwater flow mismatch.
Turbine Runback Model.
This modification allows for the modeling of the turbine run back signal, which is generated from the OPAT and OTAT signals.
July 29,1998 NORTHERN STATES POWER COMPANY Attachmsnt Page 15 Sl Model Modification This modification allows for the explicit modeling of the Boric Acid Storage Tank (BAST) and subsequent transfer to the Refueling Water Storage Tank (RWST).
Aux. Feedwater Flow Split Calculation Option This modification provides the option to calculate the flow based on a user specified head-capacity curve, pump suction, pressure, and line losses from each pump to the steam generator.
1 MSIV Status edit This modification provides an edit of the MSIV status.
Plotting Frequency 1
This modification changed the frequency that the data for the plots is collected from each print interval to each time step.
Added variables to summary output This modification added the core inlet temperature and integrated power to the summary output.
Summary put to separate file This modification placed the summary output into a separate output unit or file.
Change the edit of the reactivity components This modification adds edits for the various reactivity components.
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July 29,1998 NORTHERN STATES POWER COMPANY Attachment Page 16 l
Changes Made to DNP 87114 resulting in DNP 89306 ADFCS This modification installed the capability to accurately model the logic and operation of the new feedwater control system (ADFCS, Automated Digital Feedwater Control System) that had been installed at the Prairie Island plant. It also provides the option to calculate the feedwater flow based on a user specified head-capacity curve, pump suction, pressure, and line losses.
Error Correction in the optional pressure balancing line This modification corrected a typo in the initialization of the optional pressure balanc7g line.
Calculation of Water Properties This modification changed the coding of the calculation of the water properties to speed l
them up. No changes were made to the equation or the coefficients.
System Pressure Recalculation This modification provides an option to recalculate the system pressure from the coolant temperature after the pressurizer and upper plenum inactive region are both emptied of
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liquid. This modification improves DYNODE's best-estimate modeling capabilities for SLB j
and small break LOCA.
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July 29,1998 NORTHERN STATES POWER COMPANY Attachment -
Page 17 1~
Changes Made to DNP 89306 resulting in DNP 91204
~ VIPRE Interface rile i
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This modification added a file containing forcing functions that served as input to VIPRE.
CONTEMPT Interface File This modification created a -file of mass and energy release for direct input into l
CONTEMPT.
Table Data for UO Thermal Conductivity This modification allows the user to specify UO thermal conductivity as a function of 2
temperature in tabular format.
l Table Data for Cladding Thermal Conductivity and Heat Capacity This modification allows the user to specify cladding conductivity and heat capacity as a function of temperature in a tabular format.
Reactivity Coefficient Options t
This modification allows the user to specify different reactivity tables for the conditions in which the neutron power rate is positive and negative.
l Scram Reactivity Option This modification allows the user to specify scram reactivity in $.
Pressurizer Relief Valve PID Controller Option This' modification provides an option to control the operation of each relief valve using the l
output signal from a PID controller whose input is the sensed pressurizer pressure.
Steam Generator Rollef Valve PID Controller Option l'
This modification provides an option to control the steam generator relief valves with a PID controller.
i Steam Generator Time Dependant Multiplier Option l
l This modification allows the option to specify a time dependant multiplier of the steam h
generator's UA (universal heat transfer coefficient x the area of the steam generator if tubes) relative to the initial value through an input table set.
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July 29,1998 NORTHERN STATES POWER COMPANY Attachment Page 18 Steam Generator Relief and Safety Valve Assignment Option t
This modification is an option to assign each relief and safety valve bank to a particular steam generator.
Pressurizer Pressure Sensor Lead-Lag Composition This modification provides an option to campensate for the pressure sensor lead or lag time.
Containment Back Pressure Option This modification provides an option to limit blowdown during a steam line break based on containment back pressure. If this option is used, the user specifies the containment back pressure as a function of time.
Time Dependant Auilliary Feedwater Enthalpy This modification provides an option to specify auxiliary feedwater flow enthalpy as a function of time.
Feedwater Valve Option This modification provides an option to set the valve position equal to the demand signa!.
Ex-Core Detector Gain Option This modification allows the gain for the ex-core detectors to be specified as a function of time.
Dump and Bypass Valve Options This modification allows each dump or bypass valve bank to be used on all loops or assigned to a particular steam line. The flow may optionally be specified as pressure dependant.
Decay Heat Option This modification allows the user to include the actinides in the decay tables.
Feedwater Control System Option This modificatsoi. silows the user to intemally compute the ratio of separator exit quality to the riser average quality.
Feedwater Isolation Option This modification allows the option to obtain feedwater isolation when specifying feedwater flow as a function of time.
July 29,1998 NORTHERN STATES POWER COMPANY AttachmInt Pege 19 ADFCS Options TNs modification option allows for ADFCS (Advanced Digital Feedwater Control Systems) data to be provided for the feedwater and condensate pumps and the heater drain flow.
Comment Cards This modification allows the user to insert comment cards throughout the input deck.
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July 29,1998 NORTHERN STATES POWER COMPANY Attachment
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Page 20 Changes made to DNP 91204 resulting in DNP 94305 l
Transfer DNP code from IBM platform to HP workstation platform l
This modification made the necessary coding changes so that the DYNODE code would run on the HP workstation platform.
Changes to Turbine and Reactor Over speed Trip Messages This modification separates the messages for turbine and reactor trips on over speed.
Correct Divide by Zero Error This modification prevents a divide by zero error in the calculation of one subroutine.
ADFCS Return to Auto Switch This modification inserts a time switch to allow the Automatic Digital Feedwater Control System (ADFCS) to be returned to Auto.
Improve Convergence Schemes This modification improves the Convergence Schemes of the AFW and MFW flows.
Improve Pressure Guesses This modification prevents bad pressure guesses and includes time in the non-convergence edit. The affected subroutine calculates the pressure drop from the steam generator dome to the break plane assuming isentropic expansion for saturated steam blowdown.
Incorporate Containment Response Option This modification included the option to calculate the containment response during a steam line break. If used it will limit the blowdown during the transient based on the calculated containment back pressure.
Correct Errors in Containment Calculation This modification corrects errors in the containment calculations, including correction of initialization, removal of potential to divide by zero.
Time-Dependent Gain for Flux Trip Signals This modification added the option to use a time dependant control rod controller gain for the flux trip signals, or input a table for ex-core detector gain, instead of a constant value.
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j Neutron Flux Edit 1
This modification adds an output edit for neutron flux signals.
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Dump and Bypass Valve Closure Signal Change l
l This modification adds dump and bypass valve closure on low T-ave or time signal.
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Correct error in Subroutine s1pg52 i
This modification corrects the error in subroutine s1pg52 wh!ch occurs when IOUNIT = 0 (card 0).. IOUNIT determines whether the first or second set of units specified for a variable will be used. Added output edit for detailed dump and bypass control mode l
option, auto or manual.
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Generate RETRAN Interface File This modification creates a RETRAN interface file.
Modify subroutine for ADFCS Flow Split Calculation.
. This modification allows the subroutine to use individual steam pressures instead of the average pressure to calculate the ADFCS (Advanced Digital Feedwater Control System) flow split.
Correct Space-Time Kinetics Calculation l
This modification corrects a programming error. The coding designates the value of K-l infinity (variable KIN) to be a real*4. To be read correctly, the value should be a real'8.
The code was able to run and compile on the mainframe, but would not run on the work station.
I Insert Option for Thermal Conductivity on Heat Conductors 4 and 10, SG Tubes j
This modification would add an option that would allow the user to input a thermal l-conductivity for Steam Generator tubes. The input value would be held constant throughout the case.
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Add Option for Uchida Correlation This modification adds an option to use either the Uchida correlation for condensing steam heat transfer, or the NAD topical correlation in the containment pressure response model.
Add Edits for Control Rod Controller This modification will allow the control roo controller bias to be echoed in the initialization summary. In addition the variable avsg (steam generator average void fraction) will be recalculated if fwrq (quality) is recomputed during the initialization.
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