ML20148S654
| ML20148S654 | |
| Person / Time | |
|---|---|
| Issue date: | 10/05/1978 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1574, NUDOCS 7812040019 | |
| Download: ML20148S654 (134) | |
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ll. DATE ISSUED: 10/5/78
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Q lo/Sl18 MINUTES OF THE FLUID DYNAMICS 1 SUBCOMMITTEE MEETING AUGUST 15, 1978 C M ~ U /7L! l IDAHO FALLS, ID ND M "/ # M ) l The Fluid Dynamics Subcommittee of the ACRS held a meeting on August 15, 1978, at the Westbank Hotel, Idaho Falls, Id. The main purpose of the meeting was to review NRC Research Programs related to analysis development on the Relap and Beacon Codes and several technical support programs. Notice of this meeting was published in the Federal Register on Monday, July 31, 1978. Copies of the notice, meeting attendees and the schedule are included as Attachments A, B, and C, respectively. No requests for time to make oral statements were received from the public and no written statements were received. The Designated Federal Employee for the meeting was Dr. Andrew Bates. . INTRODUCTORY STATEMENT BY THE SUBCOMMITTEE CHAIRMAN Dr. Plesset, Subcommittee Chairman, convened the meeting at 8:30 a.m., introduced the ACRS members and consultants who were present and indicated that the meeting was being conducted under the provision of the Federal Advisory Committee Act and the Government in the Sunshine Act. Dr. Isbin indicated that the INEL had an unique blend of experience and talent with a variety of integral facilities and code development efforts ongoing. He indicated that several questions that might be asked of INEL include: How well is the goal of putting these programs together into an integrated program being achieved?, How well is the task of optimizing the talents, experience, and facilities being done?, How does one distinguish what are essential features and what effects are 7 812 0 4 0 0 K'
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. fluid Dynamics -e- 8/15/78 just secondary?, and hok much sophistication does one really need in the code development? He stated that the Subcommittee consultants an'd members might want to comment on these questions during and after the meeting.
MEETING WITH THE NRC STAFF AND THEIR CONTRACTORS Dr. P. North, EG&G, presented the Subcommittee with an overview of the Code Development and Analysis Program at INEL (Attachment D). A variety of codes dealing with containments (BEACON and CONTEMPT), Reactor vessel and loops (R'ELAP-4 and 5), and fuel rods (FRAP-S, FRAP-T, and MATPit0) are under contin'uing development. Relap-4 Mod-6 has now been released tu the Argorle Code Center. This code extends the PWR LOCA calculational capabilicy into the reflood phase of the LOCA. The reflood portion of the code includes entrainment, upper plenum deentrainment, fallback, core superheat, local mass flux and moving mesh models. Mod-7 is under development and will provide an integral PWR LOCA calculation and improved models. Relap-4 Mod-7 will incorporate the ability to use FRAP-S and FRAP-T for coupling the fuel with the fluid. A renodalization will be built into the code to switch the nodalization between the blowdown and refill /reflood. Release of the Mod-7 version of the code should occur in August 1979. Improvements will be made in the blowdown fuel models and in the reflood fluid properties with subcooled, two phase and superheated core regions. Checkout and data comparisons will be made both for the blowdown portion of the code and the integral code. The Relap-5 code which is being developed should provide an economic advanced BE and EM code. The intent is to make the code user convenient, include physically based two phase models, utilize a Relap-4 modeling base, and make the code faster than Relap-4. At the present time a pilot Relap-5 code has been developed and is being tested; a complete systems code is under development. 3...- . . . - . . . . . .
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' Fluid Dynamics 8/15/78 Containment Code work is progressing in order to advance the current capabilities in calculations. New models will include non-equilibrium flashing flow, wall pressure distribution, local air / steam concentration and impact deentrainment. The BEACON code has features which include 2 phase, 2 component, unequal velocity unequal temperature (UVUT) flows, 2-D,1-D and lumped parameter multiregion coupling, obstacle cells, and mass energy and momentum sources.
Dr. Siess asked Dr. Iorth to give consideration to answering the questions of when does one step with the improved mathematical modeling. Dr. H. Sullivan, EG4G, reviewed the Relap-4 Mod-6/ Mod-7 developmental efforts (Attachment E). EG&G went through 3 developmental versions of the Mod-6 code before releasing the fourth version to ANL. In responr,e to questions, Dr. North and Dr. Sellivan indicated that the Relap codes have rigid wall boundies and that only the Relap-4 Mod-7 version 1 code had any BWR reflood capability. The BWR models have not been checked out and work has been discontinued in this area. In response to questions the NRC Staff indicated that the codes go through two checkout (development & assessment) stages. The first has been called developmental verification and is intended to check that the mathematical models and coding contained in the code are correct and that the code runs properly. The second stage is independent verification where an independent group attempts to compare the code against experiment to see if the mathematical models actually represent physical phenomena. The NRC Staff are now using the terms
" checkout" or " assessment" rather than " verification" to avoid the implication that a verified code will calculate the " truth" in a large PWR LOCA. Dr. Sullivan reported that the Version-2 developmental work was aimed at incorporating a BE fuel model into Relap-4 Mod-6. AW_
four-loop plant was modeled with the Version-2 program during blowdown
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Fluid Dynamics '8/15/78' . and the results w ere presented. A Refill /Reflood calculation is then done starting with the output of the blowdown calculation. The Relap-4 Mod-6 code must be stopped at the Blowdown-Refill transition point in order to renodalize the system and input additional data. During reflood there are three mesh regions in the core (course, medium and fine). The fine mesh advances with the quench front to provide better accuracy in the region of large temperature gradients. The reflood portions of the code have been modified to allow superheated vapor and saturated liquid to exist in the same cells in order to account for superheating steam in the core. Conclusions drawn from this test run include the need for a new energy balance in the heat transfer with the secondary system during blowdown, peak clad temperature occurs during reflood, and automatic coupling of the blowdown UU6od[.portioris_of_ the code,is"cTesirable. The running time for the blowdown portion of the code was about 30% larger than the Mod-5 version. In response to a question, Dr. Sullivan indicated that once the models of a reactor system are setup it requires about 2 weeks to get t brough a complete analysis of blowdown, refill and reflood with the Mod-6 code system. The need for a complete integral calculation , with the Mod-7 code is evident. Dr. Sullivan indicated that an extended checkout of the Mod-6 code had been done and that guidelines for users had been drawn up on time step and nodalization sensitivity. Guidelines for entrainment and heat transfer parameters established. The Mod-7 deveiopment program is ongoing in 4 distinct parts; 1-blowdown, 2-reflood, 3-integral, and 4-verification development. The Mod-7 Version-2 code has been linked to the FRAP-T code, has self-initialization, a new decay heat model, an automa' tic time step advancement, a new CHF model, and a two phase form loss model. The link to the FRAP-T code will eliminate the need to do further work on Relap fuel models and will allow incorporafi5n of the late.st FRAP models immediately. The self-initialization routine saves a cons.iderable amount of time in l
i Fluid Dynamics -F 8/15/78 P' setting up the program to run. The new decay heat is based on the latest ANS information and accounts for operating history and a mixture {
.of fissile nuclides. Other improvements in the water properties, metal-I water reaction rate, and mass flow rate calculations have been made. The blowdown portion of the liod-7 code is ready for release as of August 1973.
The reflood model d evelopt,. ant program .is also underway. The work involves hot pin modeling, a core hydraulic model, a reflood heat transfer model, mixture level crossing, and a reflood fuel model. The hot pin model will include a primary rod and four secondary rods with the moving mesh follow-ing the quench front on the primary rod. The core;. hydraulic model will contain three regions; subcooled, two-phase suturated, and a superheated ( l vapor region... - Entrained liquid can.be.in_ ths superheated vapor.. .Co a rs e _ ._____._~ ~ Gedium an'd fine mesh grids [are _us'ed td_foll.oit t'he q'uench front. Radiation
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heat transfer has b'ecn included in the core inodel. The reflood portion of the code should be completed in December 1978. The integral code development effort requires a refill model development with an ECC mixing model, slip model improvements, the renodalization l task, inclusion of 'S1 units, and overall code integati,on and citeckout. The present Relap models have problems during refill due to the homogenous equilibrium models contained in the code which cause water packing, pressure oscillations, and depressurization near the cold ECCS injection water. There are also problems with nodalization and slip models in the downcomer. The new code will have a non-equilibrium t$ixing model and an analytically based slip velocity calculation.. The models have been developed and some preliminary calculations have been performed. The code will also '..icorporate the capability of renodalizing the system between blowdown and refill /reflood. 4 9
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N Tluid Dynamics 8/15/78' . The blowdown, reflood, and integral code models wiii be checked out and go through a developmental verification process using data from tests on Semiscale, LOFT, THTF, and PBF. Studies will be made on code sensi-tivity to nodalization, time steps, and various model options. The checkout and documentation should be completed by January 1980. They hope to include user guidelines on how the program should be used for various calculations and what models should be selected in particular types of calculation. Dr. T. Murley indicated that the NRC was going to be making a decision on the development of a fast running advanced EM code. The THOR, Relap-5, and a fast version of TRAC are under consideration. Thor and Relap-5 are 1-D codes, TRAC may be 1-D or 3-D. INEL is developing the Relap-5 code. A decision will be made in September or October 1978 as to which code to develop fully. The request was made to keep the ACRS informed in a timely manner of the NRC decision regarding the choice of code. Mr. V. Ransom, EG&G, reviewed the INEL Relap-5 development effort (AttachmentF). The Relap-5 code is intended to be an economic advanced EM & BE code that is user convenient, with physically based two-phase models. It will utilize the Relap-4 modeling base and should be faster. The code will have component oriented input in 51 or British units. Fluid models will include non-homogenous and homogenous models with 4 equilibrium and non-equilibrium thermodyanmics. The structure of the code is improved and full dynamic storage is used in the computer. Problems with 260 fluid volume have been resolved (Relap-4 had a maximum of 75). Various Relap-4 routines are being converted to the Relap-5 code. Certain capabilities are being built into the present Mod-0 version of the code, later versions would include ATWS, core neutronics, and RIA calculations. At the present time they have completed a pilot code which has been tested. Computation time is about 0.5 millisecond per node per time step. The code also has an automatic time step control feature. There is also an operational system code which has
. Fluid Dynamies -i- d/15/78 been applied to pipe blowdowns, and Moby Dick and Semiscale tests.
Results of the comparison were good in some areas, poor in others. Certain phenomenon have been identified as important and modeling improvements are being made. In response to a question from Dr. Catton, Mr. Ransom indicated they had not found it necessary to include two-dimensional ef fects in the choked flow models, provided that tho' abrupt area change is not too great. The Los Alamos work was with a vena contracta before the breal; exit and this introduces 2-D effects whic' must be accounted f or. 11r. Ransom indicated that they did not see a need to account for the 2-D effects in an expansion type geometry. The
- choking model used does not require an accommodation coefficient under !
these condit'io.ns. The Relap-5 code also has an abrupt area change model incorporated into it with a mass weighted area flow split. This branching model is then applied to various piping nodes to produce pipe tees and downcomer nodes. Proper connection of the nodes allows th'e momentum vectors to be properly represented in space. A^ test run with a Semiscale
, downcomer calculation shows counter current flows, fluid holdup and j dumping and appears to be considerably' better then previous Relap models.
The Relap-5 Mod-0 code should be released by the end of 1978. The Mod-1 version of the code would probably involve adding reactor kinetics, reflood heat transfer, and BWR components. In response to questions, Mr. Ransom indicated that they hope to be able to keep the computer time i required for a calculation to under 1 hour. (Dr. Catton did not participate in the following portion of the meeting.) Dr.'. P. North reviewed the status of the DEACON code (Attachment G).. The c' ode is a short and intermediate term containment code. It contains mixed dimensioning with 1-D, 2-D and lumped parameter regions. The Beacon Mod-2 code has been released to the Argonne Code Center and INEL has performad check out work on the code to assess the validity of the various calculational models for containment applications and to determine reasonable values for phase coupling parameters for drag and mass transfer. Calculations were performed for a KWU Small Jet experiment and w---.w--. , , , _ . . - . . _ . . _ _ _ - . - . _ __ _ ---.--v4 -_ , _. esseurw - 1 l .
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Fluid Dynamics 8/15/78' - a Battelle-Frankfurt Experiment with a large jet. A drag coefficient and a mass transfer coefficient were determined by fitting calculations to the data from the two experiments. (The first was highly drag sensitive, the second highly mass transfer sensitive. With proper selection of coefficients both experiments could be accurately cal-culated.) Calculations were also performed for one of the Battelle-Frankfurt Containment experiments using 1-D, 2-D, and lumped parameter regions. Results of these calculations (pressures and temperature are too high) ; show that wall condensation effects need to be taken into account. The BEACON Mod-2A code incorporates this improvement. This will involve a coupled conduction code for the wall and liquid film, a 2-phase, 2-component film coefficient, a wall film and pool formation model, and droplet deentrainment. l The Mod-2A version should be released at the end of 1978. Future plans call for including a BWR vent model, an ice condenser model, and correlation improvements. In response to a question from Dr. Siess, Mr. Tiedler (NRC/NRR) indicated that Contempt-LT and Compare were the codes being used by NRR in evaluating containment system at the present time. The vendors j use various codes. The BEACON code is a Best Estimate Advanced Containment Code. Mr. T. Charlton, EL&G, reviewed the program of INEL Technical Support for the NRC/ Industry Cooperative Program (Attachment H). This program provides advice to t he ;4RC and ensures that the data from the NRC/ industry cooperative programs are adequate for assessment of LOCA analysis models. In 1978 the program tasks included audits of the BWR-BD/ECC Program and the Flecht-Seaset Program as well as some
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. -i Fluid Dynamics 8/15/78 testing of a BWP, Jet pump. The BWR-BD/ECC program involves obtaining and evaluating test data to determine the degree to which the models used in calculations describe observed phenomena and needed improvement.
If necessary they help develop improved models. The INEL personnel essentially serve as NRC consultants in the program to help insure that the program meets the NRC needs for data (The BWR-BD/ECC Program will be reviewed at an ACRS meeting on August 28-30, 1978). Con-clusions drawn from the analysis of test data thus far indicates that a better dryout criteria is needed, there may be a need to calculate flooding du' ring blowdown, break flow needs to be measured, and liquid level probes should be included in the BWR core for future tests. The INFL program on Jet pumps invcives setting up and carrying out a test program to evaluate the capability of present code models for jet pump performance. Steady-State tests have been performed and transient testing is ongoing. Data reduction should be completed in September 1978. The INEL work on the Flecht-Seaset program involves similiar audit and consulting activities for the NRC. Meetings are attended, test documents reviewed, test predictions are made and tests will be observed. These programs will be continued in FY 1979. Mr. Stan Bankert, EG&G, reviewed the NRR/RSR Data Bank Program at INEL. This program began in 1977 with software development for a computerized data bank. Experimental data was first entered into the system in March 1978. The intent of the program is to have an easily accessable storage system available for the large amount of experimental data being gathered in the various LOCA-ECCS programs. The data bank system is setup with main files and subfiles so that a particular test facility, then a test number, test system component, and type of data can be obtained in an easy-manner. Data s<tored includes raw test data, corrected test data in engineering units, and calculated data. All data entered into the system is reviewed
4 Fluid Dynamics 8/15/78 1 i and approved by the NRC. Users of the system can obtain access to the data, manipulate it, and use it for calculations, get plots, and obtain printed or taped outputs. Topical data banks for heat transfer l data, pump performance, and steam water mixing have also been setup. 1 Mr. K. Condie, EG&G, reviewed the heat transfer topical data base contained in the data bank (Attachment J). This portion of the program provides single effects heat transfer data, provides local ' conditions from integral tests, verifies correlations, develops new correlations, and develops heat transfer surface logic. The program invo,1ves data collection, calculation of local conditions in tests, evaluation of data uncertainties, and analysis of data distributions. Using data from fluid and heater rod temperatures and uncertainty bounds, calculations of the heat transfer coefficients can be performed and error bounds placed on the results. As a result of this program it is hoped that it will be possible to define the maximum variable uncertainty which will provide clad temperature predictions within 50 F, delineate ranges of acceptable data from local conditions calculations, and define instrumentation requirements. Mr. T. Knight, EG&G, reviewed the efforts in code verification on the Relap-4/ Mod-6 code (Attachment K). The work is just getting started and the results are preliminary. An independent group at INEL is preforming the code assessment program. The assessment procedure involves developing a matrix of calculations which test each of the sections of the code. One compares data from various tests with each of the calculations to determine the ability of the code to perform its function. The group is also developing a statistical method for extending the results of calculations on one facility to another facility. Summary documentation will be released at the end of FY 1978. . 4
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Fluid Dynamics 8/15/78 The procedure is reviewing blowdown and reflood tests in Semiscale, Flecht, LOFT, THTF, PBF, PKL and Marviken. Calculations are made on individual blowdown and reflood tests as well as integral tests. Pre-test predictions will be made for LOFT L1-5 and Semiscale S-07 tests. Results of the calculations are compared with data in order to determine where there are systemmatic differences that might be due to code problems. A number of data and calculational comparisons were reviewed for the subcomittee. Areas where problems appear are reviewed with the code developers and the Mod-7 version of the code will incorporate improve-ments. One problem area is in predicting the gravity reflood in Semiscale and Flecht. In response to a question from Dr. Siess, Mr. Knight indicated that in order to be considered an acceptable BE code, calculations would have to be accurate for the pressure, fluid flow, and other parameters as well as being accurate on the PCT values. A new area where INEL js just beginning to do work is in comparing the amount of error between experiment and calculation for different facilities. They hope that these comparisons will help to identify systematic biases in calculations of different experimental facilities. For example when .resu'lts of calculated error in the Semiscale Mod-1 facility are compared with tests in the Mod-3 facility there is an indication that the code is not properly treating both sets of data. They believe that this is due to the lack of a radiation heat transfer model which becomes more important in the longer Mod-3 core. Dr. Murley indicated that Research was pleased with the results of this assessment work. There is a lot of data being acquired and programs like the one above are needed to assess the experimental data and learn #~
Fluid Dynamics '8/15/73 Dr. L. Ybarrondo, EG&G, addressed some questions asked by Dr. Isbin on how all of the small scale work applies to %rge PWR's, and how much i data and analysis are enough. He indicated that he was answering the questions from the point of view of a knowledgable contributor to the NRC program rather then as a person responsible for licensing power plants. He noted that the experimental program has looked at tests which have hiiEome'na which are representative of what is beli.cyed to occur in LWR's. They believe that the codes do a creditable job of, dal.culating the phenomena observed. Some of the tests car'ried out in PBF have abused fuel rods to an extent not expected in reactors and failures were delayed for periods of upwords of 6 or 7 minutes. The have seen nothing in their work that would indicate that the present licensing basis is not conservative. They do however have some questions relating to how one assesses the codes; one can obtain agreement on the small scale tests but then has to extrapolate to large PWR's. .The methodology for doing this does not exist. That process is beginning to be developed. EG&G indicated to the NRC that they thought that large
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scale testing vioulTbe needed; pEovided that an accurate confirmation of
- codes is required.. Subsequently the NRC indicated that it was rethinking tiIe objective of the research programs and the goals of the best estimate code program. The NRC needs to assess the objectives of the ECCS-LOCA programs. At that point one may be able to determine how much is enough. ,
If the objective of the NRC program is to quantify the margin of conservatism on safety in the BE codes, than in EG&G's opinion full scale refill-bypass l experiments could be required. If that objective is modified, as Dr. Murley indicated it migh.t be, then those experiments may not be required. l. Dr.Murley ; indicated that NRC Research believes they are entering a new phase of the LOCA-ECCS research program. The program was largely developed over the past 5 or 6 years and now is producing a great deal l 1 l _- .
f Fl'uid Dynamic; 8/15/78 - l of information. The last pieces of large scale tests in the 2-D/3-D program are being put in place. The remainder _o.f_the problem is to reassess the ultimate goals of a best estimate code by defining the meaning of best,e' stimate, Research expects to be addressing this furtherinthe'w'eissahead. Dr. Plesset thanked the participants and adjourned the meeting at 5:55 p.m. A complete transcript of the meeting is available in the NRC Public Document Rdom at 1717 H St, NW, Washington, DC, or from Ace-Federal Reporters 444 North Capital St., NW, Washington, DC, for those who desire a more complete accounting of the neeting. A complete set of slides used at the meeting is on file in the ACRS with the record copy of the minutes.
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EST. -A. NUCLEAR REGULATORY ST 50-592-A and STN 50-3 Dateuuly 26,1978 Th Environmental Erpor was ten. COMMISSION dered ut initially rejected d is eX-Jonn C. HoYI.E. ADvlSORY COMMtTTEE ON REACTOR Adtisory Committee pected o be resubmitted o or before
$AFE!UARDS $UsCOMMITTEE ON f tUID Management O//icer. Septem er 1,1978. A sep. ate notice
##03 IFR Doc. 78-21137 FLled 7-28-18; 8:45 aml of recei and availability or this ro-Meet;ng maining ortion will be ublished at that tim A deadline r filing of Tha ACRS Subcommittee on Fluid [7590-01] other con ntions relat to matters Dynamics will hold an open meeting t covered in e omitted m rial will be en August 15, 1978 at the Westbank IDocket Nos. STN 50-592 and STN 50-5931/ established y the Bo subsequent Motal Coffee Shop. 475 River Park- AR ONA PUSUC SERVICE CO., ET AL. (PAto to acceptan of the vironmental wsy. Idaho Falls. Idaho 83401, to dis- RDE HUCLEAR GENERATING STATION, Report for a talled re ew.
cuss the RELAP 4 and 5 Codes and U FT5 4 AND 5) / After the *ironmerntal Report has their coplications to reactor calcula- a been received d analyzed by the tions. The BEACON Code also wC1 be Real t of Antitrust inferrastion and APpjica- Commission's D ecto of Nuclear Re. revi:wed. Notice of this meeting was ti*a or Coastrucil.n Penaits and operating actor Regulatforg or is designee, a pubushed at 43 FR 25162 and 30631. Ucen es: Time for $vbminion of vie s en draft environmen al tem'ent wC1 be Jun21G and July 17,1978, respective- Antit et Motters prepared by the Co mMion's staff. ly. Arizo. a Public Service Co. on half Upon preparation the draft envi. In accordance with the procedures of itsel and 10 joint applicints- ronmental stateme the Commission outlined in the FEDrnAI. EscIsTra on Southe California Edison .. E1 will cause to be pu Ished in the Frn-October 31,1977 (42 FR 56972). oral or Paso Ele ric Co., San Diego as & IRAr. Rrcistra a n lee of avanability written statements may be presented Electric C .. Nevada Power .. De- ct the draft sta ent, requesting by mImbers of the public, recordings partment o Water and Powe of the comments from try ested persons on will b3 permitted only during those city of Los geles. city of elm. the draft statemen Upon considera-portions of t.he meeting when a tran- city of Burb city of Glendale, city tion of commen su mitted with re- . script is being kept, and que.stions maY of Pasadena and city of Itiverside. spect to the d environmental state-
. be askal only by members of the Sub. . Calif. (the plicants), pttrsuant to ment, the staff ill pdppare a final en-committee, its consultants, and Staff. section 103 of he Atomic Energy Act vironmental st ment. the availabil.
Persons desiring to make oral state- of*1954, as am ded, filed / portions of ity of which will# be noticed in the Pro-ments should notify the ' Designated their applicati These arts which IRAI, RrcIsT 1 Federal Employee as far in advance as consist of the S ety Anr ysis Report, Copics of t individual portions of practicable so that appropriate ar- general and f. ancial information the applicat! , as nf}ted above are rangements can be mado to allow the were accepted for ng on March available for'public examination and necessary time during the meeting for 31,1978, and are ocke)d igne docket Nos. copying for fee at th Commission'- such statements. STN 50-592 and STU -593. Public Docu ent Room 1717 H Street In addition a porno of the applica. NW., Wash gton. D.C. 0555, and at Th2 agenda for subject meeting shall be as fonows' tion fUed contains th information re . the Phoen Public L1 ary. Science quested by the Atto*ney General for and.. Indu ry Sectior), 12 East TUESDAT, AucesT 15.1978 the purpose of an rMitrust review of McDowell ond, Phoe s:ss A.u. trwru.Taz concz.cszow or nestatss the application as s t forthi in 10 CFR Dated a Bethesda,,q Mg this Ariz. 85004 20th 50, appendix L. an w also accepted I' The Subcommittee may meet in Executive for docketing an is igned docket day of Ap il 1978. } l . ' . Session, with any of its consultants who and 4TN 50-593-A. For th Nuclear Regu3 tory Com-l rary be present, to explore and exchange Nos.STN 50-592 is for uthorization mission, The applicatio
- their preliminary opinions regarding ma*< Joict STot.z.
ters which shoud be considered during the to Construct an operate two pressur. mieting and to formulate a report and ree- ized water reacfors designated as the Chi , Light Water Recciors l cmmincations to the full Committee. Palo Verde Npelear Genbrating Sta. anch No.1, Dittisfo. of Prof-(, At the conclusion of the Executive tion, Units 4 d 5 on thelapplicants' e iManagement. ! Session, the Subcommittee will hear site in Mari a County, Ahiz. The re* IFR Dbc. 78-16334 Filed 6-13-is 8:45 aml
, presentations by and hold discussions actor is desi ed for operhtion at a / (
. with representatives of the NRC Staff, core power evel of 3,800 rperawatts
, ~ the Idaho National Engineering Labo- thermal, wi an equivalent net elec- [801 1] l! ratory ' (INEL).
~ pertinent toand their consultants, the above trical outp t of approximat y 1,307 topics. The megawatts ECURmES AND EXCHANGE J
- Subcommittee may then caucus to de- A noticejof hearing setting i h the COMMISSION \ !
termine whether the matters ident!. radiological issues to be co ' idered . 1
% fled in the initial session have been during t)'e review is being pu ished ,, (Release No.103341 peti-adequately covered and whether the separately. A date for submittin ,diolo- MF MANAGED MUNICIPAL BOND F D AND project is ready for review by the full tions fof leave to intervene on ra gical issues is set forth in the not ce of r;i; {SSACHUSETTS FINANCI Committee. -
J Further information regarding hearink. of Application Purnent to Sect n 6(c) An ' person who wishes to hav his . ,he Ace for en order Granting Ex7ption j -:* topics to be discussed, whether the view on the antitrust matters of r, ,, ,s. p,,,; ; . ., s.ct;on 22(d) of the e.. meeting has been cancelled or resche-J.T dulld, the Chairman's ruling on re- app cation presented to the Attor$he rJey ge, , W quests for the opportunity to present Ge eral for consideration shoQId Jm.Y 21,19,4, .
, e- oral statements and the time allotted su mit such views to the U.S. Nucle,ar Notice is hereby given that IFS
.' therefore can be obtained by a prepaid R 'gulatory Commission. Washington,
- 1. telephone call to the Designated Fed. C. 20555, Attention: Chief Antitru!!t Mdnaged Municipal Bond Trust the eral Employee for this meeting Dr. d Indemnity Group, Office of Nug Trust"), an open-end. diversilied.
3
. ~ Andrew L. Dates, telephone 202-634- ear Reactor Regulation, on or before management investment company heg-h FEDERAL REGl5TER, VOL. 43, NO.147-MONDAY, JULY 31, 1978 cL x f-o. i Y A ihh c -- 1 l%4~
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V . l j l FLUIDDYNAMICSSUBCOMMITTEEMEETING
. AUGUST 15, 1978 -
IDAHO FALLS, ID l I
. i ATTENDEES LIST i
ACRS NRC ] M. Plesset, Chairman T. Murley H. Isbin,' Member P. Strom C. Siess, Member L. S. Tong W. Mathis , Member- W. A. Paulson 4 H. Etherington, Member C. Tinkler ' F. Zaloudek, onsultant - K. Garlid, Consultant DOE ' T. Wu, Consdltant - L. S. Yao, Consultant - A. J. Pressesky Z. Zudans, Consultant P. E. Litteneker i I. Catton, Consultant W. W. Bixby A. Bates, Staff
- T. McCreless, Staff INTERMOUNTAIN J. Austin, Staff TECHNOLOGIES INC. .
EG&G G. Brockett l
- C. E. Slater 1 L. Winter R. T. Jensen I G. Sonneck .
P. North JAPAN UNIVAC ! H. Sullivan ' J. R. White K. Saito l R. J. Wagner J. D. Burtt ENERGY INCORPORATED ! Y. S. Chen S. R. Fischer G. R. Sawtelle ; G. L. Litteer - t ATTACHMENT B
)
s... . > - - . . . . . . .
- j. , . . - .
l p . . . . f .. .... . . AGENDA FLUID D A S UBC V41 MEETING 1- . . WESTBANK BANQUET ROOM
-- - IDAHO FALLS, IDAHO
.. . :. u:- - . - - "
TUESDAY, AUGUST 15, 1978 . . . . . . . . . . . . M[Df gs w--
.-u 8:30 am Executive Session, ; -.-
Overview of Code Development at INEL P. North 8:45 am H. Sullivan
~
_..9:15 am RELAP4/M006 - Accomplishments
~
RELAP4/M007 - Current Status and Plans H. Sullivan
~9:45 am
" "~
~~. J ..
[10:45am BREArs . RELAP5/M000 - Capabilities and Current Status V. Ransom
~
i1:00am V. Ransom 11:45 am _RELAP5/ MOD 1 Future Plans
- 712:15'pm~ LUNCH c: ..a .
1:15 pm . BEACON IIdD 2A Current Status and Futu Plans R. Wells Tech. Support for Industry Cooperative Programs T. Charlton
] 2:15 pm .
- . . :3:00 .
pm BREAK - LOCA Analysis Verification Results and Status T. Knight r_ .-3:15 pm
~
G. Schultz [.~4:00pm NRC/RSR Data Bank .
.. . e.. .
~ f 4:30 pm ADJOURN - . .
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Safety Analysis GOdeS} ., Containment ~4
. BEACON CONTEMPT
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I g~ . ( 6_ O j . { <O _ %_. / u d C- V '
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s__, U -- Loop, Vessel and Internals Fuel rods ? FRAP-S "
~
l RELAP4 RELAPS FRAP-T
~
MATPRO . m a....r
o . HELAP4 MUU6 PWR Reflood ~
~
Models .
. ~
- Entrainment models '
- Upper plenum deentrainment model
- Fallback model . .
~
- Core superheat model
- Local mass flux model
- Moving mesh model i s-S-12 026 l
h
' ~
Of 6 R
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2 W 1 S P L E s a d N I . 7 e r n o a - Di v t f n e c Oce n o i t e Mj l a i n
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ope
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a s c cs l e Al l A rl ea d o La r C sn uo m Ee O i L dt a d - Rv l a et vu e v - O r g op r o r pm e p t I n I moc ! m 4
~
~
S
Analysis Scheme FRAP-S I RELAP4 initialization I l l ' I RELAP4/ MOD 7 x i l FRAP-T I Renodalization I ' I I ~RELAP4/ MOD 7 5 Initialization Blowdown Refill Reflood ' Accident End Bottom Core initialization of of quenching bypass core recovery o INEL-S-12 029 8
"\ -
n . .: . .
RELAP4/ MOD 7 ll Schedule
~
Blowdown code ,, s development , P
- :: O Assembly and 8-21-78 -
checkout 0 *---- ' Internal release l Reflood model development 12-8 78 l - 79 integral code development 1-9-78l 7' renodalization/ refill 77 8-20-79 1-9-74 -- O Release to . Checkout, data A.C.C. comparisons and 3 documentation i
. INEL-S-12 037 *I
. q ,
g . . l l _
.g RELAP5 Program Objective 1
- Economic advanced BE & EM licensing code .
Goals
~
User convenient code Physically based two-phase models .
~
Faster than RELAP4 Utilize RELAP4 modeling base INEL-S-9166 .
= g
~
b .
~
Significant Problems Beyond
~
the Capabilities of Current . Containment Analysis Codes
- Nonequilibrium flashing flow _
l ' ' l.
- Wall pressure distribution
- Local air / steam concentrations e impact deentrainment .
INEL-S-9787 v' C1
6 . [
~
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- n!, BEACON !;.
Code Features
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- 2 phase, 2-component, U.V.U.T.' "#
' e 2-D,'1-D, lumped parameter with mixed
~ ~~ ~
, , dimension multiregion coupling. '
o'
~
Obstacle cells
- Mass, energy, momentum sources INEL-S-9788 5 D
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- o Special over4y of large probierns. . - o Stored energy matched FRAP-S analysis .
A D i o Performed new heat balance Base case analysis o INEL-S-12 307 1 (-
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ConCOLDS00r!S l; I .- e E x uu a w "=- n .c.,unx.w. w .u. w o =. x a .sr n .a. 1 3 s o ~ Blowdown analysis o New energy balance required -
~
~
o MOD 6 heat transfer surface ~ predicted - result similar to been .
.- BEEM study ,
l
- MOD 6. run time' about 30% slower ' '
than MOD 5 ~:
- Refill /reflood analysis o Refill tirne calculated explicitly o Peak clad temperature occurred in -
reflood (~1250 F) o Automatic coupling desirable t'
~
INEL-S-12 304
~
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! Extended RELAP4/ MOD 6 !s i Developmental Verification i
~
a j ,1 a w.m.m. .
. -..m _ m. -. _. . m. _ . m.m -
o Establishmeni of preliminary guidelines for users. . . lime step sens.t. i ivi.ty. o . e Nodalization sensitivity e Guidelines for entrainment and heat transfer parameters INEL-S-12 '303 l i l ii\ l \ V g.
L_i * .
!t Extended Deve00pmental lp 4 -
i Verafa. cata. on e . 4 e i 3 . Data B&se j. b s m.2&cs: . ., -:n : s =c.:&u . me : a - s='e.u m @ c- o_ a N
.t r . c s.: ' , a o FLECHT low flooding rate reflood series o Baseline FLECHT experiment 4831 o Analyzed seven FL! CHT experiments -
o
~
FLECHT-SET 3105B. o Semiscale forced feed S-03-2 o Semiscale Gravity S-03-6 ' INEL-S-12 312 i Q*
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. }, FRAP-T L. ink Advantages [
ts m ,=.m , . .
. _ . = m m :. m ._ . m . m x s . m . m. . m m. m i
a o Future RELAP4 fuel model development , ,. unnecessary . o~ Existing link to FRAP-S core
~
o Verification of FR E~i~ shared by linked
.1 code o Consistent material properties INEL-S-12 317 I
~
s
, e e
FRAP
~
Link implementation. ! l FRAP-T RELAP4 l e Surface heat transfer Radial temperature a Diametral expansion a Conduction solution ;"- --
>I i profile e Pin pressure .
Thermal / mechanical ? Clad integrity 4.. - --- w ' prope'r ties e Gap conductance INEL-S-12 331
%M
~
1. t'
e _ __ "A._* =%
- a = _* -- * *a . r A*_ . %"2 _f*_
m _' L ' e _ *_{_,', L *_ t syh' q \ h _5 ' ,e\m ' f m ( _,* ' " 'Q '
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b
- p -
J g - [ New ANS Decay Heat Model (;
. R_.s e e . s # . ..4u-.s.
_c. .. cm . __- 4.. m m. : _. x r : # . .m i .- - -- - - - - .+ = 2.m.,
. m ; .. m. ;. ,.: :- . =j t
i i. Rationale: . i
- - e Accounts for operating history .
e Lower power than 1971 standard
~
i
. 1 f!
o Has statisticat basis -
. INEL-S-12 309
-{ .
O e r ! L . - ! v 1 .
,, _. -_ _=
g 3..
; e -
s n; i New RELAP4 Decay Heat ! . 3 Model Options
- i. ,
l} - 2 - : i uxta .w .+-s . . :.a..e 2ax2 1- .,i s , .. w ; 5. a. _w . ~ _. .u a _ ,. . .;c .=. us.g,,cc.,n u $o l o infinite operating time,2asU only o Power history specified,3 nuclides -
~
o Decay heat multiplier ~
, , INEL-S-12 308 -
e 4 a
\
k~
7 Blowdown Code Dsveloprnent l Status .
~
l Task - Status Complete t i o Model develoment . o Checkout / debug Complete
~
o integration Complete _
~
o Config. control problems Complete o Developmental verificatio'n Complete o Documentation Complete o Release August 1978 : INEL-S-12 299
. 'Y '* " a- -" "= '- ^' ' E I E. .YS= en A ' ' nu- $" '- E, *--- s- -
' ' 6f, 'Y Ed ha ? _
.s, ,.
~
j Reflood Model Developrnent j 1 uk . . -- x .w ~ . . . n - ,gn m n.~. s e Reflood core model development . I o Hot pin modeling t o Core hydraulic model , t o Reflood heat transfer.
~
l . Mixture level crossing e o Reflood fuel model development INEL-S-12 293
. =
s M . L e
RELAP4/ MOD 7 .
, Motivation for Reflood PJiodel Development o Two region model o Collapsed liquid a Superheated regio'n .
- Entrainment, Steen-Wallis o Terminated on flow reversai
~
'o Coefficients not universal
- o. Subcooling t' racking
~
"^3'C6re channel subcooling .,.
during reflood oscillations~ 1 o Homogeneous mixture in lower plenum . o Liquid fallback a ignores fallback heat < transfer _ INEL-S-12 301
?' ..
4
~
~ ~ RELdP4/M OD' 7 . . Reflood Model Development :. s o ihree region model o Subcooled two-phase saturated superheated . region o Entrainment a Not flow reversal , l
.. dependent ',
e Based on critical velocity
~
and void fraction'
- o Subcooling tracking
~~
~"^~u Tfacking of subcooled .,.
liquid in core. channel
. 1 o interface with ECC miking model .
- Hot pin model e Moving mesh extended to cover parallel slab stacks INEL-S-12 302 g
- .- g 11
. .)
Core Hydraulic Modei . Hydraulic mesh . I t I
- 1 Super ;
1 heated +0 WALL 7 ! vapor
-- I region.
o { Entrainment
- l .
;"~~~~~~2 SAT m s m -- ,
e @ s E E -[ Saturat'ed K-QWALL lo
~
* =- ' region ;
y ._ - E 7 , a e# O m o g . c_ _- _ - ,\.
' L. __
kzSUB
' Subcooled) region "O WALL
.~ . , ,- i .__
.h. INEL-S-12 330 W9 hp 9
% % $ _jJ g g m I, n.b M
# k my - ' a -'M.-a __ S9S_.a .h ae d mA
*d_E* a "IA A-m 1 I _ _
j Refill Model Development j .;:
~
}c ... _ . = - m .x Approach ~.m._ .m.. _ 2 j
.. =._ .m
- Develop a nonequilibriurn mixing model o Separate explicit liquid energy balance .
o Flow regime map i.e Interface heat transfer and area - . o . implement an analytically-based slip .
~
velocity calculation .
.t
! o Flow regime map o Regime dependent slip velocity i , correlation package o Perform data comparisons ,,m.s.,, 2,, 9 .. g
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! RELAP4 Siip Modifications !.t -
y bu . . ;;m w. _a -
._a :+ n = .
. . = c.m: n. ..a:.w ..- ca .v. -:~t - = $
include flow regime map (Bennett, Dukler, etc.) consistent with mixing model Include a drift ve.locity correlation package o ' Bubbly-Churn Turbulent Flow (Zuber-Findlay) o Annular flow (ISHil? . Investigate flooding characteristics ~ of o RELAP Slip Model. o Rework BCL Downcomer Model ma.s.u ms M
;i;
#dOD7 Renodalization
~
l t
- 4 .
- - u a c
- c ._.s - ~=-n _
a- _ u..: _ : .- - - av
- m;- . : r2: ::= 1:_x _, ~ = w o- Integrate phases of LOCA transient o Change nodalization emphasis during transient e Add flexibility to problem restart
~
o Associated development. tasks - o Generalized input - , o Generalized restart o input into LCM o Segment loader l o Restructure plot restart tape INEL-S-12 310
~P .
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o Blowdown code prelirninary verification o Data comparisons e Checkout problent_. Integral code developmental verification a o . o Preliminary verification . o MOD 7 code defined o Developrnental verification INEL-S-12 283 4 t
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- I E E System components E beg 2 .
E g g g $ g I g Nodalization Model/ options y
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I 5 $ g separate Effects Nodalization I .g 5 E ' Model/ options a Scaling studies g ! g j l Nodalization Model/ options l Time steps D I 9 5 Documentation -g I ggg g I I ' E i 5 J/21/80 8/20/79 A 4 integrat Systems Preliminary D.V. System Components separate Effects Pump Semiscale Semiscale ., Semiscale LOFT Pressurizer LOFT LOFT TLTA Steam generator THTF . THTF Accumulator PBF PBF , FLECHT, SET,CSET FLECHT Break flow Core model TLTA INEL-S-12 297 PKL PKL > N . h
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RELAPS Program Objective . l.- l . . . i l,
- Economic advanced BE & EM licensing code Goals . .
l - User conve';sient code i i - Physically based two-phase models
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REl_APS Program Status .
. s
- Completed pilot code phase
* -Developed hydrodynamic model -
- Tested constitutive models 1 interphase drdg, vapor generation, wall friction -
,
- Developed process models area chanDe, branching, choldng -
- Demonstrated fast execution , ,
0.5 msec cycle time, automatic time step
~
- Operational system code -
1
- Developed user convenient input .
, pipes, branches, pump, boundaries, heat transfer. .
- Continuing model development .
- CODEAPPLIEDTOPIPEBLOWDOWNS,MOBYDICKANDSEMISCAL5
~
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- o Modeling concepts .
~ -
- Hydrodynamics
- Constitutive models .
Flow regime, interphase drag, wall friction, vapor generation, heat transfer .
- Process models ~
Abrupt area changh,'Idanching, -. I
. breakflow, pump, accumulator, .
downcomer . INEL-S-9169 i l - i
' L .
.O l
r . RELAP5/ MOD"O"~ i , . l
- Solution strategy
'
- Limited implicitness j
- Lumped models for " FAST" processes - '
Area change, break flow, pump, l accumulator
- Direct time step solution ,
- Automatic time ~ step, control .~
f i Mass conservation, Courant limit, , g j edits - I
- Dynamic storage
- Standard CDC 7600 INEL-S-9220 l . . .
~ ~
RELAP5/lillOD1 -
- Reactor kinetics
~
~
- Reflood heat transfer .
- More general downcomer BWR components Steam separator. - - -
Jet pump ; Upper head injection Entrainment/deentrainment . !
-1 s INEL-S-9213 2
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0FFICIAL USE ONLY WORKING COPY DATE ISSUED: 10/2/78 . MINUTES OF THE FLUID DYNAMICS SUBCOMMITTEE MEETING AUGUST 15, 1978 IDAHO FALLS, ID The Fluid Dynamics Subcommittee of the ACRS held a meeting on August 15, 1978, at the Westbank Hotel, Idaho Falls, Id. The main purpose of the meeting was to review NRC Research Programs related to analysis ievelopment Notice on the Rel,ap and Beacon Codes and severa? technical support programs. of this W nig was published in the Federal Register on Mordsy, July 31, 1978 M ; of the notice, meeting attendees and the schedule are intn . ' Attachments A, B, and C, respective 1;' No requests for time to make oral statements were received trom the public and no rritten statements were received. The Designated Federal Employee for the meeting was D1. Andrew Bates. .
. INTRODUCTORY STATEMENT BY THE SUBCOMMITTEE CHAIRMAN Dr. Plesset, Subcomittee Chairman, convened the meeting at 8:30 a.m. ,
introduced the ACRS members and consultants who were procent and indicated that the meeting was being conducted under the provision of the Federal Advisory Committee Act and the Government in the Sunshine Act. Dr. Isbin indicated that the INEL had an unique blend of experience and talent with a variety of integral facilities and code development efforts ongoing. He indicated that several questions that might be asked of INEL include: How well is the goal of putting these programs together into an integrated program being achieved?, How well is :.he task of optimizing the talents, experience, and facilities being done?, How - does one distinguish what are essential features and what ef fects are 0FEICIAL USE ONLY
1 O
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. Pe= 0.001 1 Ko = 104 1.0 *-
Pe = 0.015 Pe = 0.100 _ 0.5 -
^ .m 0
0 100 200 300 Radial distance from jet centerline (mm) INEL S-12 367
., 1
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" '=
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b7 iffect of Interface Drag on Calculated Flat Plate Pressure Distribution
- 1.5 i -
, Battelle-Frankfurt C-12 Calculated results KD = 104 Pe = 0.015 l
KD = 2.2x108 .
- 0.5 -
e 0- 1 1 0 100 20 300_ R'adial distance from jet centerline (mm) INEL-S-12365 ~
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G.-ib , BATTELLE-FRANKFURT CONTAINMENT N. -
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! , 1 I ' i INEL-S-2063 REVISIO..N 1
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l 1
1 . P Battelle-Frankfurt D-1 Test Room 9 N BEACON Model
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- p 0 0.5 ' 1.0 1.5 2.0 2.5 " 1 Time after flow initiation (s) INEL-S-8996
l i l - Pressure - Room 9 ! 0.18 , i i i 0.16 - n - m - s O. , E
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i
.i BEACON / MOD 2A l
- Wall heat transfer .
. - Coupled conduction code phase,2-component film coefficienti
~
- Wall filrn and pool formation
- Droplet deentrainment
- Time. history plot capability
- Coupling improvements INEL-S-9004 c p 2
*- - c. __m--_.__ - _ _ _ _ _ _ _ _ _ _ -
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- Steady-state velo. city profile
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~ .
Forces on film: gravity, interface drag and pressure gradient
- No slip at wall
- Integrated average veloce.y INEL-S-12 357
. D ,
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t, BEACON
~
Future Plans .
- Correlation improvements
- BWR vent model
- Ice condenser model .
l INEL-S-12 356 1
,- D L
N
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~
TECHNICAL SURVEILLANCE FOR - NRC/ INDUSTRY COOPERATIVE - PROGRAMS T. R. CHARLTON whrJ7y i l l \ 4 1 -
~
/ 1 I G
l l
~
s BWR-BD/ECC PROGRAM OBJECTIVES - T
-r.
O TO OBTAIN AND EVALUATE ~B7\SICBD/ECC DATA FROM TEST SYSTEM CON-FIGURATION WHICH llAVE CALCULATED PERFORMANCE CHARACTERIST.ICS - SIMILAR TO A BWR WITH 8 X 8' FUEL BUNDLES DURING A-HYP0TilETICAL LOCA. ,,.
~
~^
O DETERMINE Tile DEGREE TO WHICil MODELS-FOR BWR SYSTEM AND FUEL BUNDLES DESCRIBE THE OBSERVED PHENOMENA AND AS NECESSARY, . DEVELOP IMPROVED MODELS WilICil ARE GENERALLY USEFUL IN IMPROVED LOCA ANALYSIS METHODS. O n J x
- l. -
(
~
n.a r 1978 INEL ACTIVITIES FOR BWR-BD/ECC AUDIT o ATTEND PMG MEETINGS AS NRC CONSULTANT O REVIEW PROGRAM DOCUMENTS
- BD/ECC 1A TEST PLAN
- BD/ECC.1A FACILITY DESCRIPTION OTEST PREDICTIONS
- COMPLETED 8 X 8 BDHT TEST PREDICTIONS FOR TEST 6006 AND 6007
~
GP DATA COMPARISONS
- COMPARED RELAP4 WITH BDHT DATA FROM TEST 6004 AND 6005 GPWITNESS 8 X 8 BD/ECC EXPERIMENTS
-OBSERVEDTESTPROCEDUREFORTEST60b7 ,
(p ANALYSES OF FACILITY DESIGN
- CONDUCTED ANALYSES OF ALTERNATE REFLOOD ,
PATH PRELIMINARY FACILITY DESIGN.
-H ,
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I m g CONCLUSIONS FROM TESTS 6D04 AND 6005 , O A BETTER DRYOUT CRITERIA IS.NEEDED FOR. BWR TYPE SYSTEM CALCULATIONS O THE ABILITY TO CALCULATE FLOODING MAY BE REQUIRED DURING BLOWDOWN AS HELL AS DURING~ CORE SPRAY OPERATION eBREAK FLOW SHOULD BE MEASURED IN FUTURE EXPERIMENTS FOR ASSESSMENT
, OF CRITICAL FLOW MODELS
~
O LIQUID LEVEL PROBES SHOULD BE INCLUDED IN THE CORE FOR FUTURE TLTA .
. ., TESTS 3:
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~
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1978 INEL ACTIVIflES FOR JET PUMP TEST PROGRAM ' O COMPLETED PROGRM1 REQUIREtlENTS AND PLAN DOCUMENT _ O DESIGNED TEST APPARATUS
- COMPLETED PRELIMINARY DESIGN REVIEW (FEB) -
- COMPLETED FINAL DESIGN REVIEW (MAY) t O FABRICATED TEST APPARATUS
' ~
~
- COMPLETED PROCOREMENT OF PARTS AND' INSTRUMENTATION
- COMPLETED FABRICATION (JULY)
- INSTALL'ED APPARATUS IN LOFT SUPPORT TEST FACILITY -
'(AUG)
OTESTING
- COMPLETED STEADY STATE TESTS (AUG)
- PERFORMING TRANSIENT TESTS
- DATA REDUCTION WILL BE COMPLETED IN SEPT .
, Y
~
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FLECHT-SEASET REFLOOD PROGRAM 0.BJECTIVES AND STATUS
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s 9 STEAM GENERATOR SEPARATE EFFECTS TASK
~
- OBJECTIVE - TO OIARACTERIZE FLECHT NET LARGE STEAM GENERA RELEASE PERFORMANCE ,.
- STATUS - SHAKEDOWN TESTING TO START 9/11/78 G UNBLOCKED BUNDLE SEPARATE EFFECTS TASK
-OBJECTIVES-TOPROVIIjENEWR0DDESIGNDATNBASEFORCOMPARIS0N c
- WITil OLD ROD DESIGN
' - TO PROVIDE BASELINE DATA BASE FOR COMPARISON WITH -
BLOCKED BUNDLE
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$ - STATUS - SHAKEDOWN TESTING'TO START MID FEBRUARY 1979 - -
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SEPARATE EFFECTS UPPER PLENUM
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e SYSTEM EFFECTS TASK ,
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t I-{ - t 0 1 1978 INEL ACTIVITIES FOR THE FLECHT-SEASET AUDIT O ATTEND PMG MEETINGS AS NRC CONSULTANT O REVIEW PROGRAM DOCUMENTS -
. i
, - PROGRAM PLAN- '
UNBLOCKED BUNDLE TASK PLAN '
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1
- COMPLETED TEST PREDICTION FOR FIRST STEAM GENERATOR ,
TEST
- MAKING TEST PREDICTION FOR FIRST UNBLOCKED BUNDLE TEST 0 WITNESS TESTS
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- COMPLETED SORVEY OF BLOCKAGE EXPERIMENTS AND FORWARDED PROMISING PAPERS
. - PROVIDED INFORMATION AND RESULTS FROM INEL REFLOOD TESTS AND ANALYSES 4
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i L l l 1 l EY 1979 PROJECTED ACTIVITIES t . l g o AUDIT BWR-BD/ECC PROGRAM i
.., - REVIEW PROGRAM DOCUMENTS (4 ESTIMATED) -
~
- CONSUL-TATION't4 ~PMG MEETINGS)
~
- TEST PREDICTI0tlS AND DATA COMPARISONS -
(2 EACH) , 0 JET PUMP TESTING
- MODIFY RELAP4 JET PUMP MIXING MODEL
- VERIFY.NEW MODEL -
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O AUDIT FLECHT-SEASET PROGRAM -
- REVIEW PROGRAn DOCUMENTS (6 ESTIMATED)
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DESCRIPTION EXAMPLE rOELD DATA SOURCE SEMISCALE (( 1. 2 TEST SERIES TEST NUMBER
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