ML20136E006
| ML20136E006 | |
| Person / Time | |
|---|---|
| Issue date: | 12/03/1985 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2377, NUDOCS 8601060368 | |
| Download: ML20136E006 (44) | |
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, g, DATE ISSUED: 12/3/85
[ ACRS ECCS SUBCOMMITTEE MEETING MINUTES NOVEMBER 22, 1985 WASHINGTON, DC PURPOSE: The purpose of the meeting was to review selected portions of the NRC Research Program on reactor thermal hydraulics (T/H) for the ACRS Report to Congress on the FY 1987 budget. ATTENDEES: Principal meeting attendees included: ACRS NRC D. Ward, Chairman L. Shotkin, RES J. Ebersole, Member W. Beckner, RES C. Michelson, Member F. Odar, RES I. Catton, Consultant D. Bessett, RES V. Schrock, Consultant C. Troutman, RES H. Sullivan, Consultant G. Rhee, RES T. Theofanous, Consultant Y. Chen, RES C. Tien Consultant D. Solberg, RES P. Boehnert, Staff B. Sheron, NRR MEETING HIGHLIGHTS, AGREEMENTS, AND REQUESTS:
- 1. Regarding the NRC (T/H) Research Program, Mr. Ward asked the Consultants to advise whether:
(a) The Program goals and directions are appropriate. (b) These goals will support improvements in safety? (c) The goals will strengthen NRC in protecting public health and safety? (d) There are any thermal hydraulic issues that are not being addressed in RES Thermal Hydraulic Program? (e) The resources being devoted to thermal hydraulic research are appropriate? B601060368 851203 UEJICSAIEU C =Ih# b PDR ACRS l i 2377 PDR Coctified Ey O' ob __ b
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. ECCS Meeting Minutes November 22, 1985 Mr. Ward also noted that he wants the Subcommittee to discuss the nature of the role the ECCS Subcommittee and the ACRS should play in this area.
- 2. Dr. L. Shotkin reviewed the FY 87 T/H budget in closed session. He noted that there is no word, as of yet, from OMB as to the accept-ability of the NRC FY 87 budget proposal.
For FY 86, the T/H budget is $20.1 million. The FY 87 budget proposal is $23.4 million. Figure 1 shows the breakdown by l Subelement. Figures 2-4 detail the spending projections for individual Programs in each Subelement. Key points noted include: Dr. Catton asked for a response from RES as to how the 2D/3D data will "close the loop" vis-a-vis code verification; i.e., exercising.the codes against small scale. test results, up to a full-scale facility _ (e.g. , UPTF). In response to Dr. Sullivan, Dr. Shotkin said that RES is assuming that in FY 87, a decision will be made to have some sort of continuing experimental capability (CEC), and that a facility or facilities will be built or relocated for future use.
- Code development has essentially ceased. Codes will be
- maintained or " improved" in the context of model corrections L or enhancements.
.RES also discussed future (FY 87-89) spending projections (Figure 5). Two new directions in T/H research would be a Technical Integration Center (TIC) at INEL, and the CEC Program (see below).
e -* ECCS Meeting Minutes November 22, 1985' A long-term management plan is proposed for the 1985-95 time frame. Key elements of this Plan include: (1) INEL becomes Technical Integration Center for thermal hydraulic research needed to resolve safety and licensing issues including specialized support from other DOE laboratories through 1990; (2) Continue cooperative research with domestic industry and international partners; (3) Continuing experimental capability beyond 1990 for safety issue resolution, as required, and maintenance of expert staff support; and, (4) support for thermal hydraulic issues raised in severe accident studies. Dr. Theofanous encouraged the technical inte-gration effort noting this has historically been the Achillies Heel of the RES research effort. He also suggested, however, that an element cf competition be maintained to help dispel complacency and assure top quality effort is given.
- 3. In open session,.there was follow-on discussion of the above point vis-a-vis the TIC concept. Dr. Shotkin said the RES Staff will have to rely on Contractors to integrate the research results due to funding constraints. Drs. Theofanous and Catton suggested .that the Contractors need to be doing more analyses of their results.
Dr. Shotkin disagreed that Contractors are not doing this type of analyses. Further, RES envisions that the TIC will act as an Agent to the NRC in integrating research results. In response to Mr. Michelson, Dr. Shotkin said the TIC concept was designed to main-tain a " critical mass" in the thermal hydraulic area in the face of contracting budgets. Dr. Tien expressed concern that the TIC responsibilities may overlap and interfere with NRC's responsibil- < ity to assure integration of research. D. Ward agreed. Dr. Theofanous indicated that NRC Contractor reports he has seen lack the sophistication he expects from these Organizations. After further discussion, Mr. Beckner (RES) committeed to provide w __
ECCS Meeting Minutes November 22, 1985 documentation showing examples of how research results were suc-cessfully integrated by RES. Referring to the RES long-term plan vis-a-vis the TIC concept (Fig. 6), D. Ward said it is imperative that the Subcommittee understand NRC's approach and goals. Mr. Michelson said he needs more details before commenting on this approach. Dr. Schrock said one needs to see the overall TIC plan in order to be able to comment. Mr. Michelson agreed. Mr. Ward sees the TIC role as a center of research expertise not as an overall integrator of research. He feels the TIC approach is a reasonable one. Dr. Tien said the integration role of the TIC needs to be clarified, vis-a-vis RES's overall integration role. Dr. Shotkin said in response that: (1) RES cannot legally abandon its role as "the integrator"; (2) W of TIC's are envisioned one in each main' area of NRC research to assure a " critical mass"; and, (3) Congress earmarked some FY 86 money to establish TIC's in four major areas-one of which_ is thermal hydraulics. Mr. Ward asked if NRC has considered joint NRC/ Industry TIC's. Dr. Shotkin said there has not been any proposal in that direction, but urged ACRS to pursue this idea with NRC management (EDO, etc.).
- 4. W. Beckner (RES) overviewed the status of the joint IST Program.
Key points noted included:
' MIST facility is complete - debug testing has begun.
- For the analysis effort, a 3-D TRAC calculation has shown that the downcomer exhibits a 1-D thermal hydraulic behavior.
Also, it was found necessary to use detailed noding of the MIST upper plenum region to capture significant thermal hydraulic behavior. Mr. Michelson asked if the effect of Nr .
ECCS Meeting Minutes November 22, 1985 bypass leakage from the upper head to the core region is modeled in TRAC. RES said they would check on this and respond at the next ECCS Subcommittee meeting. In response to Mr. Ward, RES said they are' planning to conduct a sensitivity study of the AFW spray distribution as modeled in TRAC.
- The UCMP test loop is undergoing shakedown tests. Tests will be run during FY-86 and FY-87.
- The EPRI SRI-2 status is given in Figure 7.
ANL two-phase flow study results supporting the IST have shown that flow separation at the U-bends is not an important concern vis-a-vis core heat removal.
- 5. F. Odar provided an overview of the code development, assessment and NPA work. Basically, the thermal hydraulic codes will be in a maintenance status. Figure 8 provides details. From now on, only the TRAC-BWR & -PWR versions will be improved, but RELAP-5 will be slightly improved under the ICAP.
In response to Dr. Theofanous, RES said very few changes (3 so far) have been made in the frozen code versions. There are a number of , proposed changes for the next code versions to be frozen. There was extensive discussion of how and whether cod'e changes are to be made given a finding of some problem (s) with the frozen code version. NRC indicated that the only changes allowed are those necessary to assure its proper, or correct, functioning. However, the discussion indicated there is a " gray area" in this activity. Further discussion resulted in a recommendation that the code ! Newsletter, periodically published by INEL/LANL, more carefully specify which corrections have been made to the frozen codes. p-- > -
e ECCS Meeting Minutes November 22, 1985 In further discussion of incorporation of errors into the frozen versions of the codes, it was acknowledged by RES that some of the changes are in a " gray area", i.e., borders on a model change (Fig. 12). Quarterly Newsletters are being published to assure effective communication among all participants vis-a-vis code errors, re-sults', model changes, etc. Figure 9 details the status of the NPA/NPDB Program.
- 6. The international code assessment and application program (ICAP) was reviewed by D. Bessette. Details of the Program's purpose is given on Figure 10. The list of foreign users is given in Figure
- 11. The ICAP will run N5 years. Results of benefits to date have largely centered on the discovery of code errors. In response to Dr. Sullivan, RES said there will be no assessment of COBRA, primarily due to a lack of interest.
Dr. Tien asked if RES is looking to use the new supercomputers vis-a-vis the thermal hydraulic codes. RES indicated they are indeed looking into this.
- 7. C. Troutman (RES) detailed the status of the NPA and NPDB programs.
Figure 12A lists the current NPA users and Figure 13 details the different NPA decks that will be available during the 1986-89 time frame. 1 For the NPDB, Figure 14 provide the present status and work planned for FY 86-87.
- 8. The separate effects (SE) Program was overviewed by W. Beckner.
l Figures 15-18 detail the individual studies under this Program l element. Dr. Theofanous questioned the usefulness of the steam 2'-w
ECCS Meeting Minutes November 22, 1985 explosion work (Figure.17). He indicated that the results of this work will not have any applicability' to reactor safety. Mr. Ward questioned RES regarding their position that no further action is needed on water hammer (WH). The Subcomittee noted that recently there have been a number of WHs and the question of what would be the impact on a plant if a WH occurred during the course of a severe thermal hydraulic transient has not been addressed by NRC. Dr. Catton said one needs to be able to bound the outcome of such an event. Dr. Theofanous agreed. Mr. Michelson cited the potential for hydraulic disturbance in the case of BWR vessel overfill and subsequent flooding of the steamline.
- 9. D. Solberg discussed the RES plans for continuing experimental capability (CEC). RES cautioned that no definite plans on this item have been made as of this date.
RES sees four main needs in the CEC area. These are: (1) provide integral test data to rapidly respond to new designs and safety issues (e.g. NRR user requests); (2) continue the dual analytical-experimental approach used in the past; (3) provide a continuing team of technical experts; and (4) provide integral test data to assess.the need for best-estimate code improvement and to quantify uncertainty. The current major (RES) test facilities will be shutdown by FY 88-89. Five alternatives for CEC have been explored (Figs. 19-20). Annual costs for the various alternatives range from N $1 million to
*W $10-15 million. The desirable criteria RES has been evaluating for the various alternatives are listed in Figure 21.
RES has inaugurated a scaling study to aid in selection of the ! "best" CEC alternative. A Workshop was held at INEL to obtain ~ ,
s ECCS Meeting Minutes November 22, 1985 expert advice in this area. -Key coments resulting from the Workshop included:
- 1. The basic approach to evaluate the scaling alternatives were not questioned, but the scope of investigation should be expanded.
- 2. Perhaps the single greatest remaining uncertainty in pre-dictions of comercial plant behavior is multidimensional effects in complex transients because they have never been simulated well in integral facilities.
- 3. New future facilities should be of a different design approach than past designs to improve understanding of transient response, and provide the best tests of code capabilities.
- 4. Input from code assessment work is important to establish future facility capability requirements.
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- 5. Investigate capabilities for the "best" linear scaled facility and estimate facility costs.
- 6. Perform a cost estimate for a small visual facility operating with freon.
Preliminary comparisons of design features and costs for B&W and W_ facilities are shown in Figures 22-23. RES invisions completion of preliminary and final design of a new facility in the FY 87-88 time frame - assuming a new facility is built.
- 10. D. Ward solicited the coments of the Subcomittee Consultants.
e ECCS Meeting Minutes November 22, 1985 I. Catton: (1) Funding for separate effects work is too low; much of this work is subsumed in the B&W IST Program; (2) The INEL experimental data bank should be strongly supported - careful and complete documentation of experimental data should be emphasized; (3) the TIC concept is sound but the CEC facility should support issues of current concern; (4) believes that the ICAP is "giving away the store "vis-a-vis the advanced codes; (5) for the NPA/NPDB i work, RES should emphas'ze the state of the art in small computers; RES should look at the work EPRI is supporting in this area; and (6) the water hammer issue should be reopened given the recent events seen in this area. V. Schrock: (1) Support I. Catton's comments; (2) the TIC concept needs much more definition and critical review - historically, the weakest part of the RES Program has been a lack of critical analy-ses of test data. It is essential to assure that there is strong overall integration of tie set of TICS established by RES; (3) ACRS needs to assure that RES programs focus on pursuit of an under-standi_ng of physical phenomena to assure code modelling is done correctly; (4) agree that the water hammer issue deserves a re-look. T. Theofanous: (1) Agree with above coments; (2) the overall approach of the TIC is acceptable but he would prefer to see an element of competition among the TICS to assure a good product and dispel complacency. Peer review of the final products from the TIC is essential; (2) RES need to revise their procedures for closing out technical issues. Complete documentation and analysis of data is needed to assure the work is correctly integrated into the j overall RES Program Plan; (3) the water hammer issue should be i reopened; and, (4) the various scaling approaches being considered as part of the CEC work deserve careful thought. i
. ECCS Meeting Minutes November 22, 1985 C. Tien: (1) separate effects funding should be increased; (2) the CEC facility will be a waste of resources if it is dedicated to the old issues; the focus must be on issues of current concern; (3) enthusiastically supports the efforts to increase the processing time of the thermal hydraulic codes-believe this will pay great dividends in the future; and (4) the TIC concept requires more study and characterization before a decision is made to move ahead on this.
- 11. B. Sheron (NRR) described NRR's User Needs for the RES Thermal Hydraulic Program. Key points of his presentation included:
In general, RES has been responsive to NRR's Users need requests. NRR's most recent user need letter requests RES simulate the Davis Besse event in a test facility (University of Maryland facility was suggested) and analyze it via the thermal hydraulic codes. NRR endorsed a continued experimental capability but could not identify any analytical deficiencies which warrant specific test needs.
,
- The ICAP may be more extensive than necessary for providing verified codes, but the program keeps the U.S. in the fore-front of international thermal hydraulic code efforts. The program is part of an effort which maintains a cadre of expert code users at labs. This cadre of experts is necessary for the Staff to have rapid response capability.
- NRR is taking a " wait and see" attitude for the NPA and NPDB.
In the past 4 years, no useful product has yet been produced. NRR will use the NPA when plant data has been inputted, i
- h. ._-
. ECCS Meeting Minutes November 22, 1985
- In response to Mr. Michelson, Dr. Sheron said regarding the TIC concept that the main benefit is a central location of technical experts.
- In the new NRR organization, the Division of Reactor Safety and Oversight (DSR0) will have oversight function for ECCS-related activities. DSR0 will report regularly to the ACRS on the status of ECCS-related issues of on-going concern. ACRS comments on the functioning of the new organization were solicited by Dr. Sheron.
- 12. The status of the 2D/3D Program was given by G. Rhee. Figures 24-25 delineate the Program status and workscope. Key LB LOCA test data results from the Japanese CCTF and SCTF facilities show:
- 1. Significant liquid fraction (about 10%) is established through-out the core shortly after (about 20 seconds) water enters the core inlet. Clad temperatures turnaround very quickly because of this liquid.
- 2. The uppermost core region (top 10%) quenches faster than the middle region because of deentrained liquid at the core / upper plenum interface.
- 3. High broken loop pressure drop improves the flooding rate.
- 4. The entire core quenches when the core collapsed liquid level reaches approximately mid-plane.
- 5. Sixty percent coplanar flow blockage in 2 out of 8 bundles has l no significant effect on core cooling.
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o ECCS Meeting Minutes November 22, 1985
- 6. Upper plenum injection (UPI) tests show that core cooling and que.nching are nearly as effective as the cold-leg injection tests even though the hydrodynamics are completely different.
- 7. Best estimate tests show a wide margin for PCT (380*C versus 1204 C in Appendix'K). There were slow core flow oscillations with a period of 50-100 seconds caused by the steam binding effect.
Referring to item 7 above - it was noted that severe fluid oscil-lations were seen for test cases with high ECCS flow rates. In response to Mr. Michelson, RES said it does not believe that these oscillations result in significant impact loads. Mr. Michelson urged that NRC review this item on an expedited basis to confirm their belief. Items requiring attention for the 2D/3D program include: (1)UPTF test schedule delay may cause cost increase ~ in later years; and, (2) timely coupling of UPTF/SCTF tests results need to be assured.
- 13. Y. Chen discussed the status of the ROSA-IV cooperative NRC/JAERI test Program. Key points noted were:
- A 5% CL.SB LOCA tests in ROSA-IV showed the same phenomena as was seen in Semiscale, i.e., core liquid level depression due to liquid holdup in the SG U-tubes. Core quench occurred after loop seal clearing without any significant heatup.
- Figures 26-28 show the tests planned for FY 85 and proposed tes't for FY 86, respectively.
l l
. ECCS Meeting Minutes November 22, 1985
- Figure 29 shows the status of the associated analysis work at LANL (TRAC) and INEL (RELAP-5). As decision as to whether to t use either TRAC or RELAP has not yet been made. [
The ROSA-IV workscope for FY 87 is detailed on Figure 30. i The meeting was adjourned at 5:00 p.m. i i
********************** f NOTE: Additional meeting details can be obtained from a transcript' ,
of this meeting available in the NRC Public Document Room, I 1717 H Street, NW, Washington, DC, or can be purchased from : ACE-Federal Reporters, 444 North Capital Street, Washington, i DC 20001 (202) 347-3700. F i 7 ( { i l 1
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FY 1986-1987 TilERMAL HYDRAllLIC BUDGET ($M) u PROJECT J FY 1986 FY 1987 COMMENT h INTEGRAL FACILITIES 11.4 14.3 i .
$ MIST 3.2
, 4.4 FOLLOW-0N PROGRAM REQUESTED BY NRR.
It 2D/3D 3.2 3.6 INCREASE IN COMMITTED ANALYSES.
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ROSA-IV 1.4 1.6 ). , REPORT ON LIQUID HOLDUP TEST p ANALYSES.
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... FIST 0.3 0.2 i FACILITY MOTHBALLED.
SEMISCALE/ CEC 3.3 4.5 SEMISCALE MOTHBALLED; START
$ (CONTINilING EXPERIMENTAL CONSTRllCTION OF NEW-SCALE l CAPABILITY) o FACILITY.
SEPARATE EFFECTS 3.1 3.3 INITIATE VISUAL LOOPS AND ANALYSIS g CENTERS AT UNIVERSITIES i TRANSIENT MODELS AND 5.6 5.8 COST-EFFECTIVE NPA/DB ' CODES TOTAL 20.1 23.4 I jD ' [
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' FY 1987 DETAILS : INTEGRAL FACILITIES MIST 4.4 _
SUPPORT AT INEL AND LANL 0.9 PHASE-III LLOSE0VT AND REPORTING 0.5 PHASE-IV FOLLOW-ON MODS AND TESTING 3.0 2D/3D 3.6 ANALYSIS AND
SUMMARY
REPORTS 2.3 INSTRUMENT AND DAS SUPPORT; RESIDENT ENGINEER 0.9 TECHNICAL SUPPORT AND RILS 0.4 ROSA-IV 1.6 INSTRllMENT SUPPORT AND RESIDEt!T ENGINEER 0.4 ANALYSIS (INEL AND LANL) 1.2 SEMISCALE/ CEC 4.5 . SEMISCALE MOTHBALLED 0.7 CEC DESIGN AND CONSTRUCTION 3.8 lx 2.
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hl ' 1 FY 1987 DETAILS : SEPARATE EFFECTS 3,3 UNIVERSITY OF MARYLAND LOOP 0.3-i EXPERIMENTAL DATA BANK (INEL) 0,4
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0,2 UNIVERSITY GRANTS 1.1 FLUID MIXING STEAM GENERATOR MODELING VISUAL LOOPS ANALYSIS CENTERS TESTING AND MODELING AT DOE LABS 1,3 10 DINE TRANSPORT AFTER SGTR FACILITY SCALING STUDIES CONDENSATION MODELING FLOW REGIME MODELING
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'A FY 1987 : TRANSIENT MODELS AND CODES 5,8 INTERNATIONAL CODE ASSESSMENT PROGRAM (ICAP) 1.5 NUCLEAR PLANT ANALYZER / DATA BANK (NPA/DB) 1.6 CODE IMPROVEMENT AND MAINTENANCE 1,7 DOMESTIC ASSESSMENT AND APPLICATION 1.0 6
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O f I . r . a 1 LONG-TERM (2-3 YEARS) SPENDING PROJECTION I a FY 1987 FY 1988 FY 1989 INTEGRAL FACILITIES 14.3 y
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14.5 -14.0 . SEMISCALE/ CEC ?.-. . !; 4.5 5.0 MIST ' 5.0(+5.2CEbi6PGRADE) 4.4 5.0 1.8 2D/3D l 3.6 3.5 1.4 FIST 0.2 0.2 0.2 ROSA-IV 1.6 0.8 0.4 . SEPARATE EFFECTS 3.3 3.3 2.9 ' _ TRANSIENT MODELS AND CODES 5.8 5.3 4.6 ' TOTAL : 23.4 23.1 21.5
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THERMAL HYDRAULIC RESEARCH : MANAGEMENT PLAN 1985-1995 INEL BECOMES TECHNICAL INTEGRATION CENTER FOR THERMAL HYDRAULIC RESEARCH NEEDED TO RESOLVE SAFETY AND LICENSING ISSUES. SUPPORT FROM OTHER DOE LABORATORIES THROUGH 1990 IN SPECIALIZED AREAS.
. CONTINUE SUPPORT FROM UNIVERSITIES AND SMALL BUSINESS, CONTINUED INVOLVEMENT IN 00 PERATIVE RESEARCH WITH DOMESTIC INDUSTRY AND INTERNATIONAL PARTNERS.
USER SUPPORT AND MAINTENANCE FOR NPA/DB AND COMPUTER CODES BEYOND 1990, CONTINUING EXPERIMENTAL CAPABILITY BEYOf!D 1990 FOR SAFETY ISSUE RESOLUTION, AS REQUIRED, AND MAINTENANCE OF EXPERT STAFF SUPPORT, SUPPORT FOR THERMAL HYDRAULIC ISSUES RAISED IN SEVERE ACCIDENT STUDIES, i N I 3; 9 i f t
EPRI/ SRI-2 STATUS - BASE ON INFORMATION PROVIDED BY J-P SURSOCK/EPRI AT PfiG MTG, THE FOLL0lilNG REFLECTS DIFFERENT TASKS PERFORMED B
- MODEL ASSEMBLY AND INSTRUMENTATION (EXCEPT PAR AND BREAK FLOW MEASUREMENT DEVICE)
- PRIMARY SYSTEN LEAK TEST
- FILTERING SYSTEN FOR PRIMARY COOLANT WATER !
- FILLIliG AND-DRAINING '0F THE LOOP I
- PRIMARY SYSTEM VOLUME f1EASUREMENT
- LOOP RESISTANCE TEST
- IN-SITU LEVEL GAUGE CALIERATION
- PRESSURIlER HEATER TESTING DEBUG WILL CONTINUE ON TO END OF 1985 AND TESTING C IN 1986
7.- OVERVIEW 0F FUTURE THERMAL AND HYDRAULIC ISSUES (CONTINUE MAINTENANCE OF THE CODES.
.. TRAC-PWR '
.. TRAC-BWR
,, RELAP5/ MOD 2
.. . COBRA-TRAC
,. COBRA-TF
,, RAMONA-IIIB
' MAINTENANCE MEANS PERFORMING THE FOLLOWING TASKS:
- 1. OPERATIONAL SOFTWARE IN THE COMPUTER ENVIRONMENT,
- 2. . ERROR CORRECTIONS,
- 3. IMPROVE USER CONVENIENCE ITEMS, AND
- 4. USER SUPPORT.
ONLY TRAC-PWR AND TRAC-BWR CODES WILL BE IMPROVED IN FUTURE LIMITED IMPROVEMENT OF RELAPS-UNDER ICAP). t t ys l . 2SJ ,, ;
NPA-NPDB
. INTEGRATED MANAGEMENT PLAN I,' ' PROJECT
' FY 1985 ~~FY'T986 FY 1987 FY 1988 FY 1989 A '
l FY 1990-199 BNL-NPA Comple :ed BWR/4 l l SBLOCA BWR/6 BWR/3 K-I RRAM NPA Operati onal at Asses ment INEL and NRC of M,\RK-I User Su 3 port . MARK-I HYDRO-NPl! A Operational at A Assessmer t .Us er Support - LANL and NRC of MARK-I Compl ete 3D Two-Step Numerics MARK-I TRAC-B NPA JL k Jk Test Case Demo on BWR 4 at Ass assment User Support Compl eted of.iARK-I INEL an'd NRC
; Complete 30 Two-Step Numerics for BWRs MARK-II HYDRO-NPA Jk n A n Develop Al gorithms Demo on Decision on fer for al1el Implement on User Suppori I CRA"-XMP MARK-II Compu ters Parallel Selection of Ml croprocessor Hardware MARK-II-TRAC-B-NPA
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Start User Support Imp lement on F arellel l Micr oprocessor 4 NPDB Tra ns f er Project Opera tional I Exten d to WE Extend to BWR E to L \NL for WI 4-Loop 2, 3 Loops, B&W-T ransfer to k to IN EL
PURPOSE ASSESS: TRAC-PF1/fl001 RELAPS/ MOD 2 TRAC-BD1/ MODI : TRAC-BFI BROADEN THE INPUT OF USER EXPERIENCE AND Pf7, VIDE PEER REVIEW. QUANTIFY THE CODE UNCERTAINTY, CORRECT ERRORS. ESTABLISH AND IMPROVE USER GUIDELINES. USER GUIDELINES PUBLISHED THIS FALL FOR ALL THREE CODE DETERMINE CODE IMPROVEMENT NEEDS. IMPROVE INPUT /0UTPUT AND USER CONVENIENCES. MEANS OF GENERAL C00PEPAT10N AND INFORMATION EXCllANGE . COUNTRIES IN THE AREA 0F TilERMAL HYDRAULICS. )w$T r, kE' , .'ss , [ .
FOREIGN USERS TRAC-PWR RELAP5 TRAC-BWR FRANCE AIJSTRIA i F.R. GERMANY F.R. GERMANY BELGIUM SWITZERLAND JAPAN FINLAND SWEDEN F.R. GERMANY UNITED KINGDOM ITALY JAPAN KOREA 1 NETHERLANDS SWEDEN SWITZERLAND TAlWAN i
- J.R.C. ISPRA -
EXAMPLES OF ERROR CORRECTIONS IN TRAC TWO-PilASE PIPE FLOWS SLUG FLOW INTERFACIAL HEAT TRANSFER IS CALCULATED DURING 0F STRATIFIED FLOW. DISCONTINUITY.IN INTERFACIAL HEAT TRANSFER COEFFICIENT DURING CONDITIONS OF STRATIFIED FLOW. SUPPRESSION OF WALL CONDENSATION Ifl PORIZONTAL PIPES. FORM _ LOSSES OVERPREDICTED FOR SMOOTH AREA REDUCTIONS.
. CORE HEAT TRANSFER DETERMINATION OF INVERTED ANNULAR FLOW NADF BASED ON SATURA TEMPERATURE INSTEAD OF CRITICAL llEAT FLUX TEMPERATURE.
CODING ERROR CAUSED EXCESSIVE HEAT TRANSFER FROM VAPOR TO D AT HIGH VOID FRACTIONS. INTERFACIAL SHEAR PACKAGE INCONSISTENT WITH ENTRAINMENT - I CORRELATION.
.. T CHF SOMETIMES GREATER THAN T p MIN FOR CONDITIONS WITH HIGH QUALITY.
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!s : '.'i CURRENT USERS '
I: NRR GAIN TECHNICAL BASIS FOR RAPID LICENSING RESPONSE TO EVEN DAVIS-BESSE. ' RES STAFF PERFORMING IN-HOUSE WORK (MIST). 18E OPERATIONS CENTER TRAINING DRILLS. DOE CONTRACTOR STAFF PERFORMING LWR ANALYSES FOR NRC. DOE CONTRACTOR STAFF ANALYZING TEST DATA AND PERFORMING CODE A
.NRC.
HUMAN FACTORS, AND OTHER EXPERTS, EVALUATING OPERATOR GUIDELINES. I 1 k g i
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!!UCLEAR PLANT ANALYZER DECKS / MASKS -
MODELS 1986 1987 1988 FINE NODED, RELAPS O'CONEE-1 (B8W 177) (150) ROBINSON (W, 3-LOOP) DAVID-BESSE (B8W 177, RAISED LOOP BELLEFONTE (B&W 205) BROWNS FERRY (BWR/4) (BATCH) ANO-2 (CE) RESAR-414 (W, 4-L, 14' CORE) C0 ARSE..N0DED, RELAPS ROBINSON. K 30) . BELLEFONTE ANO-2 OCONEE FINE N0DED, TRAC-BF1 BROWNS FERRY (150) GRAND GULF DRESDEN-3 FINE N0DED, TRAC-PF1 OCONEE (150) CE, WE, EX'S \ NPA-HYDRO . J., w .. , BNL/HIPA BWR/4 BWR/6 BWR/3
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, NUCLEAR PLANT DATA BANK
. FY 1985 COMPLETED WORK AT PROFESSIONAL SOFTWARE (TDC),
t TRANSFER SOFTWARE TO ENGINEERING MODELER (LANL). INDEPENDENT DATA ENTRY CONTRACTORS IDENTIFY ERRORS IN SOFTWARE DOCUMENTATION.
. FY 1986 ERRORS TO BE CORRECTED AT/BY LANL.
DATA ENTRY AND MINIMUM SET OF DATA.
... DOCUMENTATION.
... INTERFACE SOFTWARE TO TRAC, E.G., BYPASS.
. FY 1987 DEMONSTRATION BY LANL OF WE-4L DATA ENTRY AND DECK CREATIONS AND' REN0DALIZATIONS.
.. USER-FRIENDLY DATA ENTRY (SCIENTECH, SBIR).
. .. EXTEND NPDB TO HE-2L, B&W, CE. .
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l SEPAPATE EFFECTS PROGRAF 1 i EXPERIMENTAL. DATA BANK AT INEL LARGE DATA BASE TO BE ENTERED IN FY 1986 AS DATA FROM PTS PROGRAM, ROSA-IV, MIST, AND 2D/3D BECOME AVAILABLE. DATA ENTRY WILL REMAIN HEAVY TilROUGH FY 1987 TO CLEAR BACKLOG FROM FY 1986. -
. IODINE PARTITION C0 EFFICIENT MEASURE IODINE PARTITION COEFFICIENT AS'A FUNCTION OF PH, BORIC ACID CONCENTRATION, AND OTHER VARIABLES FOR USE IN ANALYZING IODINE RELEASE DURING STEAM GENERATOR TUBE RUPTilRES. MAKE PLANT MEASUREMENTS DURING VARYING CONDITIONS.
) .. WORK IS IN PROGRESS AND WILL BE COMPLETED IN FY 1987.
. IINIVERSITY OF MARYLAND 2 X Li LOOP )
TESTS OF NATURAL CIRCULATION, FEED AND BLEED, SBLOCA, MIST SCALING ' COMPARISONS, ETC. TESTING STARTING IN FY 1986 AND CONTINUING AT LEAST THROUGH FY 1987. s% x...... I 4 ,
SEPARATE EFFECTS PROGRAM (CONTINUED) FLUID MIXING HDR AND IVO PTS DATA EVALUATION / PREDICTIONS. i
.. FINAL PTS REPORT.
8 BORON MIXING EXPERIMENTS AND MODELING FOR BWR ATWS
. . . PTS REPORT / PRELIMINARY BORON WORK FY 1986.
FINAL WORK COMPLETED FY 1988. SCALING STllDIES t CONTINilED SCALING SUPPORT FROM ANL FOR MIST AND CEC. POSSIBLE NEW SCALING ANALYSIS / EXPERIMENTS (SEE VISUAL LOOPS / ANALYSIS CENTERS). TWO-P11ASE MODELING i! INVER.TED ANNULAR FLOW STUDIES COMPLETED FY 1986. ~
.. HOT-LEG U-BEND WORK COMPLETED FY 1987, s
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SEPARATE EFFECTS PROGRAM (CONTINUED)
. STEAM EXPLOSION ANALYSIS OF LARGE-SCALE STEAM EXPLOSIONS IN PAPER INDUSTRY COMPLETED FY 1986
. . -SMALL-SCALE WORK TO LOOK AT SCALING AND APPLICABILITY OF PAPER INDUSTRY DATA STARTING IN FY 1986.
POST-CHF HEAT TRANSFER /REWET CURRENTLY PLANNING ADDITIONAL WORK TO CORRECT CODE DEFICIENCIES IN , THIS AREA.
. STEAM GENERATOR MODELING ENTRAINMENT/ CARRYOVER IN 0-TURE STEAM GENERATOR WORK COMPl.ETED IN FY 1986.
.. EXTENSION TO OTSG IN FY 1987. .
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, SEPARATF EFFECTS PROGRAM (CONTINUED)
VISUAL LOOPS / ANAL.YSIS CENTERS - UNIVERSITY WORK TO EXPERIMENTALLY INVESTIGATE SCALING 0F FACILITIES AND SEPARATE EFFECT STUDIES OF COMPONENTS.
.. USE OF COMPUTER CODES.
.. COMPLEMENT CEC PROGRAM.
. SBIR PROGRAM - '
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CONDENSATION (PHASE-I START IN FY 1986). PC ANALYZER (COMPLETE PHASE-II IN FY 1986). PLANT DATA BANK (PHASE-II START IN FY 1986). PLANT ANALYZER BOUNDARY CONDITION CONTROLLER (PHASE-II START IN , FY 1986). FY 1987 AWARDS NOT YET DETERMINED. -
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e ALTERNATIVE APPROACHES _ COST $M ALTERNATIVE INITIAL ANNilAL PR0 CON
- 1. EXISTING FACILITIES AT PRESENT LOCATION, SEMISCALE 0] CONTINUE KNOWN TECHNOLOGY, MAXIMllM OPERATIllG COST.
MIST 0p10-15 FilLL CAPABILITY FROM EACll RELATIVELY INFELXIBLE, FACILITY,
/ 1 FIST,. J0) MOSI EXPERT OPEPATING STAFF,
- 2. ONE OR MORE ' EXISTING '
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FACILITIES AT INEL, i: l' ji SEMISCALE 0 MINIMllM OPERATIflG EXPENSES, ' NEED FOR GE, BP.W, AND EPPI CONCURRENCE, MIST UNK f ~3-5 PPOVIDES MOST EXPERT SOME LOSS OF TEST CAPABILITY CONTRACT 0P STAFF, PD^SIBLE, FIST- 5,7) UNKN0UN COST TO MOVE, INSTALL, N h AND CHECK 0UT MIST, k ' RELATIVELY INFLEXIBLE,
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ALTERNATIVE APPROACHES (CONTINUED)
. COST $M ALTERNATIVE INITIAL ANNUAL PRO CON
- 3. VISUAL LOOP (+ SEPARATE <1 <1 RAPID RESPONSE.
Lif1ITED APPLICABILITY TO EFFECTS TESTING AS SELECTIVELY IMPROVES UNDER- STATED NEEDS. NEEDED). STANDING.
- 4. NEW CEC Il-24 13-5 BEST SCALING APPROACH. INITIALLY LIMITED TO ONE MULTIPLE FACILITIES AT LOW VENDOR DESIGN.
COST. PROVIDES MOST EXPERT CONTRACTOR STAFF.
- 5. CONSTRUCTION OF MIST- 10-15 <3-5 MINIMUM OPERATING EXPENSE. P0TENTIAL OPERATOR CONFLICT OF TYPE FACILITY AT B8W CONTINUE KNOWN TECHNOLOGY, INTEREST.
ALLIANCE, OHIO. REQUIRES EXPERT CONSULTANTS TO NRC, S0 DIVIDED EXPERTISE AND INCREASE ANNUAL COST. INFLEXIBILITY. h 9 L **
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STUDY CRITERIA CAPABLE OF TESTING A WIDE RANGE OF CHAPTER 15, DOMINANT RISK EVENTS AND OPERATIONAL EVENTS THAT llAVE OCCURRED. - CAPABLE OF TESTING A WIDE VARIATION OF SYSTEM GE0METRIES. PROVIDE SUFFICIENTLY CREDIBLE RESULTS FOR CODE ASSESSMENT, NRC STAFF, AND MAINTENANCE OF STAFF EXPERTISE. ADEQUATE INSTRUMENTATION AND DATA ACQUISITION FOR INTENDED USES.
". AUTOMATED CONTROL AS FEASIBLE TO MINIMIZE OPERATING STAFF AND FOR USE WITH MULTIPLE TEST FACILITIES.
. PPOVIDE A DOCUMENTED DEFENDABLE SCALING BASIS.
. CAPABLE OF PROVIDING BOTH LOOP THERMAL HYDPAULIC DATA AND OPERATOR INTERACTION RESULTS.
. QUICK TURNAROUND TIME (2-4 WEEKS). -
I LOW ACQUISITION COST (LESS THEN $5 MILLION PER FACILITY TYPE) AND LOW OPERATING COSTS (3-5 MILLION/ YEAR FOR MULTIPLE FACILITY COMPLEX).
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i . . e i FACILITY DESIGN FEATURES AND COSTS s.. 1 BaW WESTINGHOUSE i FEATURES RHFPF RHRPW. RHFPW Rl1FPF RHRPW RHFPW TYPE OF LOOP 2Xi1 2Xf1 2X4 flX4 4X4 4X4 D WORKING FLUID FREON 11 WATER WATER" FREON 11 WATER WATER fl PRESSURE, PSIA 432 435 2170 449 435 Il 2250 {j HEIGHT SCALE .375 .375 .342 .375 .375 .375 HOT-LEG 1.D., IN. 1.8 3.6 2.4 1.7 2.5 2.1 NO. RODS IN CORE 100 400 169- 196 1 110 0 289 NO.TUBESIN[S.G. 39 155 66 20 40 29 - NO. PUMPS ?- 11 4 g 4 4 4 4 CORE POWER, MWT 1.17 4.8 ' 2.k8 l.82 i 10.82 .
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EACILITY DESIGN FEATURES AND COSTS (CONTINUED) B:& W WESTINGHOUSE t0STS, $103 RHFPF RHRPW RilFPW RHFPF RHRPW RHFPW '
' LOOP DESIGN 8 CONST. 9400 12,500 12,600 '12,400 14,600 16,800 ~
BASE FACILITY MODS 1200 3700 4200 1200 3700 4600 CONTROL SYSTEM 1940 1940 1940 1940 1940 1940 DATA ACQUISITION 235 235 235 235 235 235 UPGRADE 7 BASE TOTAL 12,800 18,400 19,000 15,800 20,500 23,600 PEliUCED OPTION TOTAL 10,600 14,900 16,700 13,500 i 17,300 20,800 9 e b ts NI ..
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- 1. STATUS A.
2D/3D AGREEMENT EXTENDED.TilROUGli SEPTEMBER 30, 1988. B. JAERI CYLINDRICAL CORE TEST FACILITY (CCTF) CORE-II TEST SE MARCH 1985. C. JAERI SLAB CORE TEST FACILITY (SCTF) CORE-Il TEST SERIES COM JULY 1985. D. JAERI SCTF CORE-III MODIFICATION NEARLY COMPLETED. ALL U.S. INSTRUMENTS INSTALLED AND CllECKED OUT. MAIN TESTS TO START IN FEBRUARY 1986. E. GERMAN UPPER PLENUM TEST FACILITY (UPTF) UNDER COMMISSIO COMMISSIONING TEST COMPLETION DELAYED BY 8 MONTHS BECAU MODIFICATIONS NEEDED TO AVOID A POTENTIAL HATER MAIN TESTS11AMMER PRO TO START IN MAY 1986. i A . y
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?D/3D U.S. WORKSCOPE FISCAL YEAR: 198fi 1987 1988 1989 A. INSTRUMENTATION ON-SITE SUPPORT FOR UNUSilAL PROBLEMS l
B. TRAC ANALYSES (N0 0F ANALYSES) TOTAL CCTF ? 0 0 0 2 SCTF 7 3 1 o- ji l ' UPTF 2 8 8 2 20 PWR 1 2 2 0 __5 TOTAL 12 13 11 2 38 C. DATA ANALYSES AND RILS CCTF-I y UPI A SCTF-I . _ . a CCTF-!! , SCTF-1i SCTF-III
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llPTF
"____h D. TRAC MODEL IMPROVEMENTS TIE PLATE CCFL ~"
a { STFAM/ WATER SEPARATOR a 5 NULTI-SOURCE CONNECTION CAPABILITY c D r
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l b 9 9 3 STATUS OF Tile TESTING PROGRAM IN LSTF (CONTINUED)
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FOR CODE ASSESSMENT EFFORT ABOUT 6 TO 8 DATA TAPES - PER YEAR WILL BE MADE AVAILABLE TO Tile USNRC (I.E., LANL AND EG8G Tile REMAINING TESTS IN FY 1985 ARE: ST-NC-01 .- Natural circulation cooling Core power 4.28 W. SC pressure 7.63 HPa SC temperature 5641 ) K. Primary system
. 11/*/85 ST-NC-02 mass inventory chsnged stepwise.
Natural circulation cooling Core power 0.71 HW, SC pressure 7.63 HPa SC temperature 564.9 K. , 11/*/85 Primary system ST-SC-01 mass inventory changed stepwise 1 liest transfer in SC Core power 4.28 HL changed stepulse. SC water level 12/*/85 ST-SC-02 l Ilest transfer in SC ; Core power 0.71 HW. changed stepwise. SC water level 12/4/85 SB-CL-06 . Serstacale S-UT-8 related test 5% cold leg side-break I (Semiscale counterpart test) 0.3% DC-Ull, 0.6% DC-IIL bypass flow 2/*/86 SS-CL-07 I Semiscale S-UT-8 related test 51 cold leg side-break. ' O.3% DC-Ull, 0.2% DC-IIL bypass flow. Internal vent valves open. 3/*/86 i w -
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. STATUS OF LSTF TEST MATRIX IN FY 1986 1.
JAERI IIAS. PROPOSED Tile FOLLOWING TEST MATRIX, 3 Identification Objective i Description Date Su-c0L-01 Break location effect 5% crossover leg side-break TR-LF-01 Operational transient 4/*/86 Complete loss of feedwater. Recovery with PORV latched open and llPI. 5/*/86 TR-LL-01 Operational transient Loss of load. Progressing to hot standby conditon 6/*/86 . Sa-sc-01 Break location effect
.9C/U-tube rupture after main steam line break 6/*/86 SR-PV-01 Break location effect PV lower plenue break
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1 ,- ': 1f , STATllS OF LSTF TEST MATRIX IN FY Hj86 (CONTINUED) h h Identification Objective Description -
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, Date Sas L-09 h Break area effect 10% cold leg side-break h 9/*/86 0.3% DC-Ull, 0.2% DC-IIL bypass flow SB-CL-10 3 Break area effect 2.5% cold les side-break
, 0.3Z DC-Ult, 0.2% DC-ILL bypass flow 10/*/86 S8-CL-11 Break area effect 0.1% cold leg side-break 0.3% DC-Uli, 0.2% DC-IIL bypass flow 11/*/86 SB-IIL-02 Break location / area effect 5% hot leg side-break SB-IIL-01 12/*/86 Break location / area'effect 10% hot leg side-break SB-llL-03 1/*/87 Break location /. area effect 2.5% hot leg side-break [ SB-IIL-04 2/*/87 Break location / area effect 0.1% bot leg side-break . 3/*/87 11. llSHRC IS REVIEWING AND PREPARING COMMENTS ON JAE .. N. J P u\
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. STATilS OF ANALYSIS WORK AT l.ANI. AND INEL
. STATUS GEOMETRY INPUT OF TRAC LSTF MODEL COMPLETE.
STEADY-STATE RllN TO 1000 SECONDS. NEED MORE STEADY-STATE DATA TO VALIDATE Tile RESULTS. FY 1986 WORKSC0_PE P COMPLETE POST-TEST ANALYSIS OF 8 TO 10 LSTF TESTS. CREATE TRAC OR RELAPS REFERENCE PWR INPlJT DECK TO f EXPERINENTAL PROGRAM. PERFORM DATA ANALYSIS FOR Tile ROSA-IV TPTF SEPARAT !
-PROVIDE RECOMMENDATIONS ON TEST MATRIX TO ENSilRE THA SAFETY AND LICENSING ISSllES ARE ADDRESSED. '
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-- ~ e w-- ee vnRKSCOPE OF 'li!E ROSA-IV PROGRAM IN FY 1987
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CONTINUE TO PERFORN THE DATA ANALYSIS. . CONTINUE TO PROVIDE TECilNICAL AND FIELD SUP INCLUDING RECOMMENDATIONS ON TEST MATRIX AND TES
' PERFORM Tile TPTF DATA ANALYSIS, AS NEEDED.
t .i . PROVIDE RESOLUTION ON SAFETY AND LICENSING IS SBLOCAS. CONTINUE TO PROVIDE SPARE PARTS AND REFURBIS INSTRUMENTS TO JAERI. PROVIDE INSTR 1 MENT TRAINiflG SERVICE TO Tile JAERI EN 0 %w L ' _ _ . _. _. .}}