ML20133J137
| ML20133J137 | |
| Person / Time | |
|---|---|
| Issue date: | 05/31/1985 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2320, NUDOCS 8508090677 | |
| Download: ML20133J137 (34) | |
Text
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hg jl '3 i f.J DATE ISSUED: 5/31/85 bd s $31 kblJ ACRS ECCS SUBCOMMITTEE MEETING MINUTES MAY 31, 1985 WASHINGTON, DC
Purpose:
The purpose of the meeting was to review selected portions of the NRC Thennal Hydraulic research Program for the Comittee's Report to the Comission en the FY 87 budget.
Attendees: Principal meeting attendees include:
ACRS NRC D. Ward, Chairman L. Shotkin, RES J. Ebersole, Member B. Sheron, NRR H. Etherington, Member W. Beckner, RES I. Catton, Consultant F. Odar, RES P. Boehnert, Staff D. Solberg, RES
- 1. Dr. L. Shotkin noted that the FY 87 budget is not yet fixed. He said that RES is limited by the budget restrictions in what it can e
do and seeks ACRS advice on what should or should not be done. The DESIGNATED ORIGINAL RS 850531 Certified By $4 =
ECCS Meeting Minutes May 31, 1985 FY 87 RES budget will be cut by tw $13.7 M. RES has cut the T/H ,
budget by a#S6.8 M. NRR has requested that $4 M be restored for future integral testing. RES wants ACRS advise on: (1) the need
'for future integral system testing; (2) the need for future university research; and (3) the need for fast running codes or a fast-running desk top nuclear plant analyzer, RES is in disagree-ment with NRR on items 2 and 3. RES has also made a choice between TRAC and RELAP-5 for future code develorment as discussed below.
RES stated that the " final product" of the T/H Transients Program is user-friendly plant analyzers based on codes whose accuracy has been quantified by assessment against integral and separate effects
- tests. A Technical Integration Center will be set up at INEL to maintain thermal hydraulic expertise. Figure 1 shows a schematic of how the plant analyzers will be developed.
The current T/H budget for FY 87 was discussed (Fig. 2). RES has reduced the FY 87 budget by $6.8 M as shown in Figure 2. The largest single cut is $3.7 M out of $4.0 M for the proposed Advanced Test Facility leaving $0.3 M.
Regarding the choice between TRAC and RELAP-5 for future develop-ment, RES has chosen TRAC. RELAP-5 will have continued improvement and maintenance support; however, NRC will decrease its support and User support will increase to make up the difference.
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ECCS Meeting Minutes May 31, 1985
- 2. An overview of the separate effects program was given by W. Beckner. For FY 87 the University Program is being reduced by
$0.8 M ($2.0 M to $1.2 M - Fig. 3). Figures 4-6 detail the SE Program plans. In response to Mr. Ebersole, Dr. Beckner said one of the studies will address the issue of boron mixing in a BWR vessel, given an ATWS. Further discussion pointed out that some studies (Figure 5 - asterisked) will address modeling of radioactive release rates for SGTR accidents.
RES believes a stable funding level ofr# $4 M/ year for SE work is desirable. This would be broken down as follows: Universities (e# $2 M/yr), DOE Laboratories ( **'$1-1.5 M/yr). Others($0.5-1.0 i
M/yr). Given the budget cutback, it now looks impractical to maintain this level of support.
- 3. RES plans for continued integral testing capability were reviewed by D. Solberg (RES). Key points noted were:
- Most US facilities are scheduled to be shut down by the end of FY 86 (Fig. 7), therefore there will be no domestic T/H integral testing capability in FY 87, or beyond for W. CE or GE geometry s reactors.
- NRC must depend on foreign facilities, such as ROSA-IV, for testing on new safety issues, or on US industry.
ECCS Meeting Minutes May 31, 1985
- Foreign facilities, though cooperative, have their own agenda.
- Industry testing could result in plant delays and greater costs.
1 Mr. Ward indicated that the last bullet appears to be an Industry, not a NRC, problem.
4 i A number of alternate approaches for future integral testing are being explored by RES (Figs. 8-9). Two ideas that look promising are: (1) move MIST and FIST to INEL to join Semiscale, and/or (2) buildanATF(atINEL?). RES noted that the Modular Test Facility, proposal of 1984 was dropped due to scaling and funding problems.
RES has established a number of criteria for the ATF study (Fig.
10). Results of a scaling study under way as part of the joint NRC/B&W IST program, as well as a ATF scaling study (Fig. 11), will i
be used to evaluate the most feasible ATF alternative. RES is
Mr. Ward said RES should be looking for phenomena or " surprises" in their T/H programs in an attempt to preclude these surprises showing up in a power plant.
- _. . . ~ _,-. _-
ECCS Meeting Minutes May 31, 1985 4 F. Odar discussed the status of the code maintenance program. Key points noted were:
- Goals of the program are: (1) to maintain capabilities for auditing vendor analyses, evaluating operator guidelines, and addressing safety and licensing issues for NRR; (2) provide User assistance to NRC; (3) improve physical models as requested by NRC (but with no major change in basic code
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structure or models); and (4) update documentation.
- The end points of the program will come around 1990 when User .
convenience features and physical model improvements are deemed sufficient.
e
' RES believes a minimum of three people will be needed for this Program. Dr. Catton cautioned that the same people maintaining the codes should be using the code as well. RES agreed.
- TRAC PF1/M00-1, DB1/ MOD-1 and RELAP-5/M00-2 have been frozen for 2 years as part of the International Code Assessment Program (ICAP). The known/needed improvements for TRAC and RELAP were detailed (Figs. 12-18).
ECCS Meeting Minutes May 31, 1985
- 5. D. Bessette overviewed the ICAP. The final goals include:
4
- Quantify uncertainties of TRAC-PF1/M00-1, TRAC-BF1 and RELAP-5/
4 MOD-2 for all transients.
- Correct code errors.
- Provide improved User guidelines.
- Identify code limitations.
- Identify remaining deficiencies.
The program will end around 1990, f
l I
The key basis of the program is for foreign countries to assess the US codes (TRAC, RELAP, etc.) and provide the results to NRC. Code i
uncertainty is to be determined by a judicious selection of key ;
parameters (Fig. 19). Figures 20-21 show the foreign countries
- participating in ICAP and the codes these countries plan to use.
Validation matrices have been defined for PWR and BWR codes.
- 6. The nuclear plant analyzer (NPA) and plant data bank (PDB) was r discussed by C. Troutman. Figures 22-23 overview the NPDB status
. for FY 85-89. The NPA status for the same FYs is given in Figures
, 24-25. The expected Users for this program are: RES Staff (in-house),I&EOperationsCenter,DOEContractors,HumanFactors experts and others.
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l ECCS Meeting Minutes May 31, 1985
) 7. B. Sheron (NRR) provided the following comments on the RES T/H 2 Program:
1 i
- NRR agrees that continued availability of an integral systems j test facility is desirable but they do not yet have results of 1
any studies which justify need for a new facility. Costs vs
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benefits should determine whether a new facility is built, old facilities maintained, modified, etc. NRR recommend a " Test i Advisory Group" (TAG) be set up, similar to that done on MIST Program, composed of government and industry representatives, to 1
recommend the best approach. -
)
' 20/0D Program - NRR strongly urges UPI upper internals be reinstated and a suitable number of UPI experiments planned i h
l and scheduled for UPTF. The UPI plant ECCS model is not in con-
- formance with Appendix K. Data is needed to bring data base 4
up to par with bottom core flood data.
- For future code development, we agree only one code (TRAC) should be supported; however, until this transition is made, we will rely cn both TRAC and RELAP-5. Some reduction in FY 87 RELAP-5 support is justified.
- For ROSA-IV - assessment of the test data by codes should be limited to use of TRAC.
t ECCS Meeting Minutes May 31, 1985
- For the Separate Effects Program - university funding reduction from $2 M to $1.5 M is considered appropriate
]
and funding for the visual loop could be reduced, since it i has low priority.
- Code Assessment and Applications Program - RES has an extensive international code assessment and application program. We propose up to $0.5 M reduction in this area unless this program supports code improvement identified by assessment and agreed to by NRR.
- Desk Top Analyzer- NRR sees no need for self-contained desk ,
top analyzers, therefore, $0.7 M would be saved since NRR does not support this program.
- Nuclear Plant Data Bank (NPDB) - the NPDB still doesn't work; the NPDB is only useful if it has data in it. We would like to see a program in place to put 4-6 decks per year into the NPDB.
- 8. The meeting was adjourned at 1:05 pm. The Subcommittee Members then watched a presentation of the BNL BWR NPA.
J
ECCS Meeting Minutes May 31, 1985 x
NOTE: Additional meeting details can be obtained from a transcript ,
a of this meeting available in the NRC Public Document Room, 1717 H Street, N.W., Washington, D.C., or can be purchased from Ann Riley & Associates, Ltd., 1625 I Street, N.W., Suite
- 921. Washington, DC 20006 (202/293-3950).
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, IllERMAL llYDRAbLIC TPAUSIEliTS (C0lill))UED1 l MMd TEST FACILITY ASSESSMEliT NID (VEliDOR GE0 METRY) COMPUTER CODE QilANTIFICAT!Dft 0F ACCUHACI PitdlLAHILYZER SEhlSCALE (W, CE) TRAC-PWR i i
> liPA-PWR ROSA-IV (11, CE) RELAPS l ,
MIST /UiilV. OF MD. (h&W) /s ? COBRA / TRAC i i i
2D/3D (W, CE, B&W) i i ATF-PL'R (W, CE, B&W) !
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liPA-BWR COEP0iiEriT TESTS i ATF-BWR (GD v) RAM 0liA/illFA '
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FIST (GE) i i "IfiTERNATIONAL CODE ASSESSfiEHT PROGRAM (USillG DATA FROH INTERNATIONAL TEST FACILITIES) -
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THERMAL HYDRAULIC TRANSIENTS
($ - MILL 10llS) -
RE0 MARK i EY_1985 FY 1986 FY 1987 FY ICG7 A 9.8 INTEGRAL FACILITIES Ll62 5 12.0(33,j y &
1.1 1.7(1.4) 2.0 1.6 - 0.4 ROSA-IV 4.3 2.9 0.5 0.5 SEMISCALE 0.3 0.5 4.0 0.3 - 3.7 CONTINUING INTEGRAL TESTiliG 5.3 3.4 1.5 1.5 MIST FACILITY 0 0 3.0* 2.1 - 0.9 NIST FULL-POWER UPGRADE 4.6 3.2 3.6 3.6 2D/3D 0.6 0.3 0.2 0.2 FIST FACILITY 2d 32 Of,i 3_di SEPARATE EFFECTS l ViilVERSITIES 0.9 1.3 2.0 1.2 -08 1.4 1.9 2.0 2.0 DOE LABS AND OTHERS 1RAllSIENT MODELS AND CODES bl 6.di Z4 6d CODE ASSESSMEi1T/APPLICAT10ii 2.0 3.1(2.9) 3.1 2.7 - 0.t O,6
_32 _3A (3.1) _LZ 4.1 CODE MAINTEiiAllCE/PLAliT AllALY2.ER
$ 23.7 ~ 6*8
$ 21.7 (*2*$9 )2b'b {b10'b TOTAL FUNDIliG REQUIRED FOR MIST FULL-POWER TESTil1G (
BE DISCUSSED WITH IllDUSTRY).
50.8M FY 1986 ALLOCAT10tl TO CONTAlllMEliT RESEARCH
SEPARATE EFFECTS PROGRAM FUNDING CATEGORY FY85 FY86 FY87 (REQ) FY87 (MARK)
UNIVERSITY O.9 1.3 2.0 1.2 DOE LABS 0.7 1.1 1.3 1.3 OTHERS 0.7 0.8 0.7 0.7 TOTAL 2.3 3.2 4.0 3.2 p i 2 _
a-
?Y87 SI?A3 ATE EHECTS P30G3AY PLANS l i
1 UNIVE3SITY PROGRAYS l$ 1.EE) i
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- U o:! Md. FACLITY i
- 0"SG T~3REAL HYD3A' LICS
- B030X EIXING & P"S
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- CONDENSA" ION
- VISUA" "00PS & ANALYS"S C3N"33S (REDUCED BY BEDG3" YA3X}
ACRS3 J F Y 9' )
FYB7 S3PA3A"3 EZ?ECTS PROGRAM PLANS 4
DOE LABS ($ 1.3%
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- :N3L S3:? ARA"3 EFF3 CTS T3S"S
- F"CD M:XING
$ - CCFL IX SG TUB 3S 1
- - ST3AM SEPARAT03 PE3:?0RMANCE I
- HIGE TEM:?ERATURE CI3CULAT"0X
- I0 DINE PAR"I" ION
- AX:1 FLOW REG 3fE/SCAEG ACRS 4 _
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' ALTEiWATIVE APPADADES ,
COST ($M)
_ CON _
INITIAL AfMUAL_ M A
_ LTERNATIW
- 1. EXISTING FACILITIES AT PESENT LOCATION
- MAX OPERATING COST 0 *CONTIRE 100N TEONOLOGY SEMISCALE *ELATIVELY IWLEXIBLE 0 10-15
- FULL CAPABILITY FROM EAGI MIST FACILITY 0
- MET EXPERT OPERATING STAFF FIST J
- 2. OfE OR PUE EXISTIfE FACILITIES AT IEL *EED FOR GE, BsW AIO O *MINIMM OPERATING EXPENSES SEMISCALE EPRI C(NCURENCE
- SGE LOSS OF TEST CAPABILITY LNC
- PRNIDES MET EXPERT MIST [~3-5 CONTRACTOR STAFF POSSIBLE
- lN00N COST TO PGE, INSTALL
% LNC FIST
'y AIO GEOOJT FACILITY k *EUTIWLY IWLEXIKE m th
ALTERNATIVE MNDACHES (CONT'D)
COST ($M)
PRD gN INITIAL _AP5_0_AL_
ALTEIWATlW
- 3. CONSTRUCTION
- LOW INITIAL COST RESULTS IN l 13-$90 + 3-5 SA E AS PREVIOUS ROSA IV-TtPEMR LOSS OF CAPABIL11Y; TO MAINTAIN OPfl0NS CAPABILITY IS HIGH COST
- FLEXIBLE AT lilGH COST
- LIMITED APPLICABILITY TO
<1 <1
- RAPID RESPONSE
- SELECTIVELY IPHOVES tnt.us TESTING AS NEEDED)
Lf0 ERST #0 LNG
- lNITIALLY LIMITED TO DE VEF00R
<5 4 3-5 *BEST SCALING APPRDACH f
- 5. ADVANCED TlONL/ DESIGN
- itA.TIPLE FACILITIES AT HYDRALLIC FACILITY *MAY BE SOPDHAT S&NARIO LIMITED ,
LOW COST I e
- PROVIDES POST EXPERT ,,
CONTRACTOR STAFF i
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STUDY CRITERIA ~
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- CAPABLE OF TESTING A WIDE RANGh 0F CHAPTER 15, D0ii]NANT RISK AND OPERATIONAL EVENTS THAT HAVE OCCURED CAPABLE OF TESTING A WIDE VARIATION OF SYSTEM GE0ME
- PROVIDE SUFFICIENTLY CREDIBLE RESULTS FOR CODE ASSESSME ACTION AND MAINTENANCE OF STAFF EXPERTISE l
ADEQUATE INSTRUMENTATION AND DATA ACQUISITION AUTOMATED CONTROL AS FEASIBLE TO MINIMIZE OP WITH MULTIPLE TEST FACILITIES PROVIDE A DOCUMENTED DEFENDABLE SCALING BASIS CAPABLE OF PROVIDING BOTH LOOP THERMAL HY RESULTS QUICK TURNAROUND TIME (2-4 WEEKS)
LOW ACQUISITION COST (LESS THAN $5 MILLION PER FA LOW OPERATING COSTS (3-5 MILLION/YR FOR MULTIP x
ADVANCED FACILITY SCALING STUDY - ~
l
- 1. EVALUATE PLAUSIBLE SCALING RATIONALS UP TO 4 SCALING RATIONALS SCALING RELATIONSHIPS AND ASSUMPTIONS EVENT CONTROLLING PHENOMENA ABILITY TO MODEL CONTROLLING PilEN0MENA I
WORKSHOP 0F EXPERTS
- 2. SELECTION OF DATA BASE SELECT B.E. TRANSIENT ANALYSES FOR LWRS
- 3. CONCEPT EVALUATION DEVELOP SCALED CONCEPTS l
ASSESS CONCEPT ABILITY TO PROVIDE PROTOTY t
- 4. COMPUTER CODE ANALYSIS OF PROPOSED FACILITIE
/ 5. FACILITY COST ESTIMATES '
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KNOWN NEEDED IMPROVEMENTS (TRAC-PWR)
DESCRIPTION IMPACT ON SAFETY CALC. SOURCE
- STEADY STATE AUTOMATIC CALCULATIONS RUN T00 LONG WITil00T NRR INITIALi/ATION Auf0MATIC INITIAllZATION
- CONDENSATION MODEL ERRORS IN CALCULATIONS AT ECC INJECTION ICAP, CODE DEVELOPERS POINTS IF VAPOR FRACTION IS lilGil (NRR)
T00 MUCil STEAM CARRY 0VER IN STEAM CODE DEVELOPERS,
- SEPARATOR MODEL LINE BREAK ACCIDENTS WORKSHOP MTGS, ICAP (100% SEPARATION) ,
EXCESSIVE WATER CARRY 0VER TO Il0T 2D&3D, LANL
- DEENTRAINMENT MODEL FOR UPPER PLENUM LEGS - ERR 0NE0US STEAM BINDING EARLY REWET (SUCil AS IN LOFT) IS NOT RES, ICAP, LANL
- POST CilF HEAT TRANSFER (INTERFACIAL DRAG) PREDICTED ACCURATELY. UNCERTAINTY CAN BE AS LARGE AS 400K.
STRATIFIED FLOW NOT ALWAYS PREDICTED ICAP, LANL
- FLOW REGIME MAP WELL, IMPACT REFLUX COOLING AND ECCS ,i INJECTION x -
KNOWN NEEDED IMPROVEMENTS (TRAC-PWR) (CON'D)
DESCRIPTION IMPACT ON SAFETY CALC, SOURCE
- VARIABLE GAS GAP REACTIVITY CALCULATIONS IN TRANSIENTS ICAP, USER WORKSHOP LANL ARE IN ERROR, FU[.L R0D TEMP,ERATURE PROFILE IS IN ERROR, 4
- MULTI-SOURCE VESSEL CELL MINIMAL IMPACT, USER CONVEN!ENCE .
ICAP, USER WORKSHOP, LANL
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' KNOWN NEEDED IMPROVEMENTS (RELAPS) ,,
DESCRIPTION IMPACT ON SAFETY CALCllLATIONS S0llRCE
- STEADY STATE CALCULATIONS RUN T00 LONG WITil0llT NRR AUTOMATIC INITIALIZATION AUTOMATIC INITIALIZATION
- OUTPUT TAPE RESTRUCTURE WASTE ON I/O AND TAPE STORAGE INEL
- VECTORIZATION SLOWINCOMPUTATIONSPEEDllENCElbNG INEL 8 NRR RUNNING TIME
- DOCUMENTATION LESS EFFICIENT OR WRONG USE OF THE ICAP IMPROVEMENT CODE
- PORTABILITY LESS EFFICIENT 8 LIMITED llSE AND INEL 8 ICAP -
IMPROVEMENT APPLICATION OF THE CODE ,
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KNOW NEEDED IMPROVEMENTS (RELAPS)(CONTINUED) ,
DESCRIPTION IMPACT ON SAFETY cal.CULATI'ONS SOURCE
- TIME STEP CONTROL LESSIFICIENCYINUSING DOMESTIC ASSESS IMPROVEMENT THE CODE
- POST-CllF llEAT QUENCHES IN LOBI NOT ICAP, DOMESTIC ASSESS TRANSFER MODELS CALCULATED CORRECTLY
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(FILM / TRANSITION ,
BOILING a TMIN)
- CONDENSATION' OCCASSIONALLY GIVES ERR 0NE0US MODEL RESULTS DURING ECC INJECTION ICAP, DOMESTIC ASSESS SOMETIMES GREATLY INCREASES RUNNING TIME BY REQUIRING SMALL TIME STEPS
- N0 FORMAL CCFL MODEL LARGE BREAKS, SMALL BREAKS, DOMESTIC ASSESS PARTICULARLY WITH UPI ,
INTERACTS WITH POST'CHF HEAT ICAP, DOMESTIC yINTERFACIALDRAG TRANSFER MODEL . ASSESS .
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KNOWN NEEDED IMPROVEMENTS (RELAPS)(CONTINilED)
DESCRIPTION IMPACT ON SAFETY CALCULATIONS SOURCE
- 100% SEPARATOR MODEL MAKES MODELING SOME EXPERIMENTS a INEL TRANSIENTS DIFFICULT, PARTICULARLY INSTEAM GENERATORS, ERR 0NE0US CALCULATION OF CARRYOVER IN STEAM LINE BREAK ACCIDENT
- CHOKING MODEL IN SMALL BREAK LOCA CALCULATIONS IN ERROR
- RES, DOMESTIC ASSESS.,
STRATIFIED FLOW .' ICAP, NRR ACCIDENTS WITil LONG DRYOUT PERIODS
- ICAP
- RADIATION MODEL
- METAL / WATER REACTION ERR 0NE0US CLAD TEMPERATURE CALCULATION RES UNDER SEVERE ACCIDENT CONDITION STEAM GENERATOR HEAT TRANSFER, RES, DOMESTIC
- NATURAL CIRCULATION ASSESSMENT WITil NONCONDENSIBLES AND REFLUX COOLING
- o
_7 KNOWN NEEDED IMPROVEMENTS (TRAC-BWR)
DESCRIPTint! IMPACT ON SAFETY CALCULATIONS S0llRCE
~
- CONDENSATION MODEL OCCASIONALLY GIVES ERR 0NE0US ICAP, DOMESTIC RESULTS DURING ECC INJECTION. ASSESSMENT, INEL SOMETIMES GREATLY INCREASES RUNNING
^
TIME BY REQUIRING SMALL TIME STEPS
- POST-CliF HEAT OllENCH TEMPERATURE AND TIME DOMESTIC ASSESS ,
TRANSFER MODELS- WILL NOT BE CALCULATED (FILM / TRANSITION CORRECTLY BOILING & TMIN)
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- INTERFACIAL DRAG INTERACTS WITH POST-CHF HEAT DOMESTIC ASSESS ,
MODEL TRANSFER MODEL ,
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KNOWN NEEDED IMPROVEMENTS (TRAC-BWR)(CONTINUED)- ,
DESCRIPTION IMPACT ON SAFETY IMPROVEMENTS S0llRCE
- CORE SPRAY MODEL ERR 0NE0US CALCllLATION IN UPPER RES, INEL .
PLEhuM FLOW AND TEMPERATURE DISTRIBUTIONS, CCFL PHENOMENA AND CORE COOLING
- -EM VERSION PRESENT APPENDIX K TYPE CALCULATION NRR CANNOT BE PERFORMED
- BRITISH UNIS FOR USER CONVENIENCE UTILITIES INPUT /0UTPUT 9 .
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n S
W N O
/
DETERMINING CODE UNCERTAINTY 0 SELECT KEY PARAMETERS FOR EACH CLASS OF PLANT AND TRANSIENT PWR KEY PARAMETERS LARGE BREAK LOCA SMALL BREAK LOCA TRANSIENT PRIMARY CLAD TEMPERATURE CLAD TEMPERATURE PRIMARY SYSTEM SUBC00 LING CORE COOLANT INVENTORY COOLANT INVENTORY AND PRIMARY SYSTEM INVENTORY SECONDARY DISTRIBUTION STEAM GENERATOR STEAM GENERATOR INVENTORY TERTIARY INVENTORY BWR LOCA TRANSIENT -
CLAD TEMPERATURE COOLANT INVENTORY ,
PRIMARY ,
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TABLE 1 PARTICIPATING COUNTRIES AND CODES COUNTRY ORGANIZATION RELAPS TRAC-PWii TRAC-BWR COBRA j
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a
!, AUSTRIA AUSTRIAN RESEARCH CENTER SIEBERSDORF X l BELGIUM TRACTIONAL X CANADA ATOMIC ENERGY OF CANADA LTD. (I) X FINLAND TECilNICAL RESEARCil CENTER OF FINLAND X IMATRAM VOIMA OY POWER COMPANY i F.R. GERMANY FEDERAL MINISTRY FOR RESEARCH & TECHNOLOGY f KRAFTWERK UNION AKTIENGESELLSCHAFT X X X
,b GESELLSCHAFT FUR REAKTORSICHERHEIT
- X X X KERNFORSCllVNGSZENTRUM KARLSRUHE X
- PROJECT llDR X
! ITALY ENEA X X (2)
JAPAN JAPAN ATOMIC ENERGY RESEARCH INSTITUTE X X KOREA KOREA ADVANCED ENERGY RESEARCll INSTITUTE X ,
NETHERLANDS NETHERLANDS ENERGY RESEARCH FOUNDATION X '
1 SPAIN CONSEJO DE SEGURIDAD NUCLEAR X X , ,
SWEDEN SWEDISil NUCLEAR POWER INSPECTORATE (3)X X J w S1UDSvix eNeRGirexNix AG m ,
TABLE I (CONT'D)
COUNTRY ORGANIZATION RELAPS TRAC-PWR TRAC-BWR COBRA SWITZERLAND SWISS FEDERAL INSTITUTE FOR X X X REACTOR RESEARCil TAIWAN TAIWAN POWER COMPANY (3) X X X UNITED KINGDOM UNITED KINGDOM ATOMIC ENERGY X X AUTHORITY-CEGB, NII, NCC, BNFL UNITED STATES NUCLEAR REGULATORY COMMISSION X X X X CEC JOINT RESEARCH CENTER ISPRA X X ESTABLISHMENT (1) LIMITED ONLY TO USE OF CODE TO SUPPORT NRU TESTS (2) OPTION (3) RELAPS AND/0R TRAC-PWR a
' 4 k
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/ , = ,
NUCLEAR PLANT DATA BANK 1
FY 85 o COMPLETED WORK AT PROFESSIONAL SOFTWARE (TDC) f .
o TRANSFER SOFTWARE TO ENGINEERING t'0DELLER (LANL) o INDEPENDENT DATA ENTRY CONTRACTORS IDENTIFY ERRORS IN SOFTWARE AND DOCUMENTATION FY 86 o ERRORS TO BE CORRECTED AT/BY LANL DATA ENTRY AND MINIMUM SET OF DATA DOCUMENTATION INTERFACE SOFTWARE TO TRAC E.G. BYPASS o DEMONSTRATION BY LANL OF RESAR-3S DATA ENTRY AND DECK CREATIONS AND REN0DALIZATIONS FY 87 o EXTEND NPDB TO WE.2L, WE.36, BaW, CE -
q-o CONTROLS AND SECONDARY I
%I b
i h1 NilCLEAR PLANT DATA BANK (CONT'D.) . .
o FY 88 o EXTEND NPDB TO BWR o FY 89 o COMPLETE NPDB TO BWR COSTS FY 1986 $ 450 (It!CLUDES $250K FY 85 CARPYOVER) + $50K TDC FY 1987 400 FY 1988 100 FY 1989 300 TOTAL $1250K ti
%' NPA L
t b
hj INEL LANL
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iA FY86
- 3 MORE PLANTS' NASKS
- IMPROVE TRAC-NPA g
lrj
- INTERACTIVE X-Y PLOTS M
- TRAC-BWR SELF-INITIALIZE
- DATA BASE MOD
- COMPLETE SECONDARY
- GENERIC 1-D COMPONENT
+ CONTROL SYSTEMS MASKS
- PARALLELIZATION p
- DEM0 ON CRAY XMP-48 f
h H
- IMPLEMENT TRAC-NPA ON R FY87
- BWR-4 MASK + 1 NPA-BWR DECK h
- TWO STEP NUMERICS ON 3-D A PARALLEL PROCESSOR h
r:
COMPONENTS OF TRAC-BWR
- CONSULTATION TO USERS
- CONSULTATION TO USERS V
- MAINTENANCE + CONSULTATION
$l j; FY88 .
- COMPLETE TRAC-BWR 2-STEP NUMERICS i
- IMPLEMENT NPA EXEC AND TRAC-BWR N ON PARALLEL PROCESSOR
- CONSULTATION i k -
b a
Q.
w I, < 4
r .
l / . .
5 NPA (CONT'D.) i .
5 f
INEL LANL FY89
- MAINTENANCE
- MAINTENANCE NPA FY86 $ 750K = 400 + 350 87 $1000K = 700 + 300 88 $ 500K = 400 + 100 89 $ 200K
$2450K i
M