ML20235N223
| ML20235N223 | |
| Person / Time | |
|---|---|
| Issue date: | 05/07/1987 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2499, NUDOCS 8707170479 | |
| Download: ML20235N223 (74) | |
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/r7 Advisory Comittee on Reactor Safeguards T/H Phenomena Subcommittee Meeting Minutes l April 28-29,1987 Idaho Falls, ID i
1 PURPOSE: The purpose of the meeting was to: (1) review the status of !
the T/H research Program; (2) review the activities of the INEL Techni-cal Integration Center; (3) review the status of the proposed ISIF j (Improved Scale Integral Facility); (4) review the latest draft of the l Research Compendium supporting the proposed ECCS Rule revision; (5) review the results of the OECD LOFT Program; (6) discuss the status of the TRAC Code Modeling effort; (7) discuss the status of the work of the RES Expert's Group on Code Uncertainty; and (8) discuss, briefly, the issue of water hammer.
ATTENDEES: Principle treeting attendees included:
ACRS NRC C. Michelson, Chairman L. Shotkin J. Ebersole, Member W. Beckner D. Ward, Member D. Solberg I. Catton, Consultant N. Zuber V. Schrock, Consultant N. Lauben H. Sullivan, Consultant C. Tien, Consultant LANL P. Boehnert, Staff D. Liles B. Boyack INEL T. Charlton K. Condie J. Wolf J. Adams G. Johnson D. Hanson Ir7: "M";D CI!IGINAL B70717p987 g vw.
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T/H Phenomena Meeting Minutes April . 28-29,1987 j j
j MEETING HIGHLIGHTS, AGREEMENTS, AND REQUESTS U 1. C. Michelson proposed that the T/H Subcommittee prepare a letter on
% the status of T/H research for consideration at the July ACRS l Meeting. ' He said there will be further discussion of this' item i later in the Meeting.
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- 2. L. Shotkin (RES) provided an overview'of the T/H research program.
.He began by noting the details of the recent NRC reorganization as it impacts the research Office (Fig.1). In response to Mr.
Michelson, Dr. Shotkin noted that he plans to coordinate with his respective counterparts in NRR (Reactor System and Plant Systems Branches)andAE0D. In addition, Dr. Shotkins said RES also plans to coordinate with the Regional Offices vis-a-vis their T/H re-search needs.
RES discussed the important T/H management issues currently being addressed. These issues include: (1)currentNRCcodeimprovement plans thru FY 90 (TRAC-P, TRAC-B and RELAP-5), with final frozen codeversionsinFY90;(2)investigationofnewresearchareas including containment, balance of plant, advanced LWR designs and plant operational safety; (3) updated justification of the need for a continuing experimental capability and finalize the issues to be addressed, work scope and schedule; and, (3) Industry support for the OTSG testing program. .Dr. Catton asked how RES will determine when a given version of a code (ex: TRAC PF1/ MOD 1) is " finished" before one goes on to an improved code version. Dr. Shotkin agreed that each code version should be carefully documented (QA'ed) and the associated uncertainty needs to be determined. RES has been meeting with the Laboratories to address these very issues. Dr.
Shotkin indicated that they would be better able to discuss this item by June of this year.
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- T/H Phenomena Meeting Minutes April 28-29, 1987 4
Dr. Catton said RES needs to develop an integrated approach to addressing the problems associated with the assessment and uncer-tainty issues for the T/H codes. Dr. Shotkin cited a number of US and international programs that are designed to address these issues. These programs include both experiments and modeling efforts. In response to Dr. Catton, Dr. Shotkin agreed to provide documentation that tracks the resolution of these issues.
Mr. Ward asked if the codes can model the advanced LWR designs.
Dr. Shotkin said that for the W ALWR there doesn't appear to be any problems. Dr. Beckner echoed the same for the GE advanced ABWR efforts. RES said this area is to be investigated for new research (see above). Dr. Catton and Professor Schrock indicated they believe there will be some new issues requiring research to aid code modelling of these new reactor designs.
L. Shotkin noted that the new RES management has requested justi-fication for the need for a new integral test facility (the ISIF -
see discussion below).
In response to Mr. Ebersole, Dr. Shotkin indicated that RES, NRR and the B&W plant Owners will need test data to support design, operational, and maintenance changes expected to be made to B&W olants to improve their safety.
In response to Mr. Michelson, Dr. Shotkin noted that RES has initiatted two programs on the water hammer (WH) issue. One program is a cooperative effort between MIT (P. Griffith) and EPRI that is expected to develop a WH " guidebook" and the other is focused on developing " maps" for avoidance of WH during normal operation (Creare). These are funded at relatively low levels. Mr.
Michelson suggested RES investigate the T/H of containment isolation valves given their need to close against, for example, LOCA/SGTR loads.
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T/H Phenomena Meeting Minutes April 28-29, 1987 In response. to Professor Schrock, Dr. Shotkin sa'id RES (and the Laboratories) recognize that they need to pro'/ide vigorous ' ocumen- d tation for the codes. Dr. Tien said RES should focus the documen-tation on the codes' shortcomings and areas in need of improve-ments. Dr. Shotkin also noted that RES believes the US badly needs integral experimental capability in the future (beyond the MIST Program).
RES detailed the T/H programs underway and/or planned and their respective completion dates (Figs. 2-4). These programs are divided by vendor (ex: 3/CE, B&W and GE). Dr. Catton suggested that the issue of T/H code modelling of the condensation phenomenon be made a separate issue given-its importance. RES agreed to consider this.
In response to Mr. Michelson,' RES said a few submittals have been received from the Industry for NRC review vis-a-vis BE code uncer-
-tainty methodology. RES is thus developing a proposed scheme to review this methodology (see.below).
Dr. Shotkin reviewed the funding projections for FY 87-89 (Fig. 5).
RES is anticipating industry contributions for the B&W programs.
Dr. Sullivan questioned the heavy focus of funding on the B&W-related work to the exclusion of other issues.
T/H research planned for FY 90 and beyond are listed on Figures 6-7. Key points noted included:
- After FY 90, the only US integral test capability will exist at the proposed ISIF test rig.
- PES will support operational safety issues and maintain cognizance of other domestic and international research.
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1 T/H Phenomena Meeting Minutes April 28-29,1987 i I
- The RES T/H research branch will participate in the proposed development of an accident management plan.
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- 3. D. Solberg overviewed the activities of the INEL Technical Inte-grationCenter(TIC). Figure 8 details the current TIC structure.
Mr. Solberg noted that this TIC is the only one developed by RES to date, although development of others (ex: plant aging) has been l discussed. Dr. Solberg noted that a'synthe:,is report is under -
I development on the topic of feed-and-bleed core cocling and is due to be completed later this year (October- December 1987).
In response to Mr. Michelson, Dr. Solberg indicated that research
" integration" exists only to the extent directed by NRC-RES.
Further discussion focused on the fact that there seems to be a lack of integration of research by INEL. Dr. Tien suggested a formal review of the TIC by RES to assure its proper function. The Subcommittee strongly recommended that INEL assume the role of a true integrator for T/H research. The Subcommittee said this would result in a mode where RES can propose the work needed - INEL assures the work is done - whether at the TIC, a university, or wherever.
The details of the TIC programs and results to date were discussed by T. Charlton and D. Hanson. Mr. Charlton detailed the specific technical issues worked by the TIC (Figs. 9-12). Code assessment and code development work was also reviewed.
Referrino to the various code assessment studies conducted by the ICAP participants, the Subcommittee asked if these studies are being coordinated to assure all relevant concerns are being ad-dressed. Mr. Charlton said the TIC is attempting to do this.
Further discussion on this point indicated that a stronger, more direct, management function may be needed here.
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z T/H Phenomena Meeting Minutes April 28-29,1987 .
.I Discussing the' future plans for the T/H codes (Fig.13), the- !
. Subcommittee urged that the new code models by carefully documented for use in the various codes. q l'
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The code applicability' effort was described (this will be detailed j below). 'The initial focus of this effort will be on the B&W olant design. In response to Mr.. Michelson, Mr. Charlton.said the initial applicability studies will center on so-called classical accidentcases-(LOCA,etc.). Dr. Tien recommended additional synthesis reports on such. topics'as condensation phenomena. Mr.
Charlton said he would provide _a. list of topics under consideration for future synthesis reports.
- 4. D. Hanson (INEL) discussed the TIC effort supporting the B&W plant safety evaluation underway at NRC. The TIC approach is to inte-grate various methodologies (risk assessment, equipment perfor-I mance, human factors, etc.) to evaluate plant safety. The emphasis is on application of PRA to evaluate the impact of any potential modifications (equipment, procedures, etc.) on overall core melt
! risk.
C. Michelson questioned the above approach vis-a-vis use of PRA.
Dr. Shotkin said this approach is an attempt to make use of PRA to integrate it with thermal hydraulics. In response to Dr. Catton, Mr. Hanson indicated that this is one of the first attempts to integrate T/H considerations with PRA methodology.
l A trial application of this approach was made using a RELAP-5/ MOD-2 model of the Oconee plant. The results indicated that direct comparisons of PWR vendor thermal hydraulics is difficult due to the variances in assumptions, boundary conditions used, etc. It was also noted that overcooling scenarios dominated event tree l
paths, given loss of ICS function.
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Pe T/H Phenomena Meeting Minutes April 28-29,1987 INEL carried the orogram to a second stage which evaluated the
-:. tent to which plant systems and/or operator actions.are effective-in reducing the severity of transients in B&W plants; the study also compared the above results to a similar assessment of CE and W ,
plants and evaluated the significance of the findings in tenns of l risks currently identified in PRAs for the selected plants. . H. B.
Robinson (W) and Calvert Cliffs (CE) were the other PWRs con-l- sidered. Three transients (LOFW, SB LOCA and SG overfill) were evaluated. Results noted included:
B&W plants respond significantly faster to changes in secon-dary system conditions but when the secondary or the candy cane are not major influences, primary system responses are .
similar.
l Although the effectiveness of primary system feed and bleed is adequate at all three plants, the Oconee system can respond over a wider range of conditions or failures.
- For all plants, the core remains in a safe condition during the SB LOCA evaluated. However, the B&W plants could not use the steam generators to take the plant to RHR conditions without initiating forced circulation in the RCS.
Potential future work in this area would include en extension of j the Oconce results to other B&W plants (especially given the
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superior Oconee plant operating history). Mr. Ward expressed approval of this work and noted that this topic should be persued at a B&W Subcommittee meeting scheduled for July 7,1987.
K. Condie reviewed the B&W OTSG experimental program. The program objective is to obtain experimental data for improvement of code models during auxiliary feedwater injection in a B&W once-through
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T/H Phenomena Meeting Minutes April 28-29, 1987 steam generator. Details of the AFW spray header arrangement were noted (Fig. 14).
Four experimental apparatuses either have been used (Figs. 15-17) or are proposed for use (Fig.18) by INEL to evaluate this problem.
There was extensive discussion of the particulars of the above facilities. The fourth facility is the one labelled "0TSG-LPSF" that is designed to support the MIST follow-on effort.
C. Michelson asked if the above issue justifies an expense of
$12M for the LPSF. Dr. Shotkin indicated that this information is needed to get a sufficient understanding of the uncertainty associ-ated with this phenomenon. Dr. Beckner indicated that this infor-mation cannot be obtained in a full scale plant. He also said no specific safety concern exists, but the phenomena is the least understood of that associated with SG behavior. Dr. Shotkin said that if they could get the data from industry, RES would not build this facility. Further discussion left some doubt with the Subcom-mittee that the safety significance of this issue justifies the expense involved. In response to Mr. Ward, Dr. Beckner ir,dicated that sensitivity studies will be performed to help evaluate the importance of this phenomena.
D. Solberg addressed items identified as concerns to the Subcommit-tee vis-a-vis the TIC. Figures 19-23 detail the RES responses.
The Subcommittee asked if the TIC obtained independent review of their programs. W. Beckner indiccted that review is given to the TIC programs.
Dr. Tien said the TIC seems to lack a sharp focus. He said a real effort at integration of research is needed. Dr. Solberg indicated that RES will try to improve the TIC effert in this area.
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- T/H Phenomena' Meeting' Minutes ; April 28-29, 1987
- 5. Discussibn of.the ISIF was provided by K. Condie, beginning with review of the integral scaling' study conducted by INEL. 'The study's objectives and guidelines are noted on Figures 24-25. The final goal was to provide recommendations'to RES on a desirable scalingapproach(s).
Five facility concepts were evaluated:
Full heicht full pressure water.(FHFPW)
Reduced height reduced pressure water (RHRPW)
- Reduced height full pressure water (RHFPW)
- Linear height full pressure water (LHFPW)
- Reduced height' full (scaled) pressure Freon (RHFPF)
INEL ranked each of the above concepts against the. ability of the concepts to simulate a number of local scaling phenomena (Fig. 26).
Dr. Tien suggested that INEL evaluate the above scaling phenomena against experimental facility experience. Mr. Condie agreed that this is a good suggestion.
Ranking ~ of the above concepts for B&W plant's shows little differ-ence between them (Fig. 27). Mr. Ward noted that the ranking system did not address the synergism of phenomena seen in an integral facility. Mr. Condie agreed and noted that code analyses will be run to help determine if the synergistic effects are important vis-a-vis the local phenomena. Dr. Catton agreed that this is a good next step. Dr. Tien praised the study approach.
The study concluded that:
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T/H Phenomena Meeting Minutes - April 28-29, 1987 (1) -FHFPW.is the best representation of the largest number of phenomena.
(2) FHFPW is the.only concept to provide distortion free heat transfer mechanisms in both the heat source and heat sink.
(3) Scalability of phenomena is somewhat independent of. plant
. type. i
- 6. C. Michelson. requested documentation available to justify the proposed OTSG work. W. Beckner said he would provide a copy of the -
NUREG supporting the entire B&W research Program (NUREG-1236) to Mr. Boehnert for distribution to the ACRS. In response to Mr.
Michelson, K. Condie said the main feedwater flow can be diverted to the AFW sparger in B&W plan.ts.
- 7. J. Wolf discussed the INEL proposed working concept for the ISTF, as well as reviewed comments made by a scaling review Group formed by RES.
A number of parameters are specified to define the facility model.
These include:
- Working Fluid
- fluid type
- pressure length Ratio Diameter Ratio or Length Ratio / Diameter Ratio Core Power
- full
- decay
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T/H' Phenomena Meeting Minutes .
- Base. Plant to be'Modeled
- Available Funding J. Wolf showed a plot that can be used to determine. the facility, parameters given the constraints imposed by funding, the scaling approach selected, etc. (Fig. 28). By selecting system parameters-(Fig. 29), Mr. Wolf showed how one can walk through the chart to illustrate how much " plant space" is available (Figs. 30 open area - Fig. 32 - dark area). Using the-INEL proposed working concept (RHFPW - Fig. 33), the graph shows the working space.
l available(Fig.34). Figure 35 noted the bases'used for selecting the working concept parameters.
I Discussion on the reason for not selecting Freon over water as a working fluid brought out the fact that the codes are " tuned" too closely to the T/H properties of water. In response to Dr. Tien, Mr. Wolf said the major cost parameters for the ISIF are the core electrical power capability available, and the 'ize of the steam generators. Mr. Wolf also indicated. that there will be further analyses (TRAC, RELAP?), and review, before a final concept design l
is selected.
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Discussion of the various trade offs.that had to be considered, plus comments received from the INEL consultants (bigger is better, approach linear scaling, and give up full scale power for size),
led to the working concept parameters noted in Figure 36.
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Dr. Catton suggested INEL explore the trade offs associated with a reduced pressure facility. He also suggested NRC explore the impact of varying the downcomer gap width. Dr. Sullivan expressed I _ - _ _ _ _ -__- _ -
1 y-T/H Phenomena Meeting Minutes April 28-29 1987 concern with the distortion expected in the steam generator scale parameters. RES agreed and noted that they have separate effects tests planned to address this concern. K. Condie said there will indeed be distortion in this area, but the advantage gained with the ISIF is the ability to model multidimensional effects which cannot be modelled in other B&W facilities.
Mr. ' Wolf noted the comments received by the scaling review Group (Fig.37). The comments appear to support the working concept >
proposal. Mr. Wolf noted.that INEL is soliciting. critique of the working concepts from the ACRS and others.
Mr. Ward said he is persuaded that the trade offs being proposed for capture of multi-dimensional effects appears worthwhile. Mr.
Ward also indicated that going to a lower pressure system may also be worthwhile, given the emphasis on using the test date for code development. Mr. Wolf indicated that going to lower pressure (ex:
1000 psi) doesn't save much money or ease operationa? constraints.
Dr. Catton argued that the flexibility obtained with use of a lower pressure bolted system is worth a great deal. Using this approach avoids the problem of Board Notices as was seen with Semiscale:
1.e. , you rely on the code to interpret the results. Mr. Wolf indicated that the modular concept was deemed impracticable. Dr.
Sullivan asked how the question of modeling a raised vs lower loop plant was decided. Dr. Beckner said there has not been a decision on this as of yet, but noted all but one operating B&W plant is of lowered loop design.
I Further discussion noted the following points:
Dr. Sullivan asked: "why a B&W design?" (for the ISIF). Dr.
Beckner said no firm decision has been reached on this issue, but B&W plants are of concern today. Dr. Catton said this i
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.T/H Phenomena Meeting Minutes April 28-29,1987 indecision argues for facility' flexibility (as discussed above). Dr. Sullivan noted that there is no test data avail-eble that is directly applicable to CE plant designs.
- In response to Mr. Michelson, RES said they would build a four loop plant if a W design is selected: 1.e., geometrical-similitude would be maintained for the design chosen.
Dr. Sullivan again asked how test data not available until 1991'would be used here. RES said they are still wrestling with this point.
Don Solberg noted RES found the scaling study of good use. It is :l only one input to the decision process vis-a-vis fac.111ty design i selection. He said that if a reduced pressure facility meets their objectives, it will be considered.
RES noted that the needs (mission) of the new facility will be documented and should be available in June 1987. A SECY paper detailing the design chosen should be issued by the end of the year. In response to Mr. Ward, Dr. Solberg said, at the present time, NRR has not expressed support for this facility. Dr. Shotkin said the ED0 supports the need for a new facility, but the new NRR r:enagement has yet to evaluate this issue.
- 8. Dr. Catton made some comments on the issue of water hammer (WH).
He noted the following points based on information obtained at an EPRI information meeting:
(1) Thirty fluid systems in the four reactor designs have the potential for water hammer events; ten of the thirty fluid systems perform safety functions.
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.T/H Phenomena. Meeting Minutes April 28-29,1987 (2)' Some interesting observations-include:-
'* subsystems designed to. prevent water hamer may become an
. initiator
- severe accident management instructions may lead to circumstances favoring water hammer
- off-normal plant configurations can aggravate potential water hammer initiators He expressed an opinion that NRR's statement that WH is not a safety concern has lead to lack of. utility interest in the phenome-non.
Other points noted by Dr. Catton include:
(1) "Backroom wisdom" is that only 1 in 10 water hammer events is reported.
(2) If a water hammer yields its maximum pressure pulse, a (pipe, equipment) failure will occur.
(3) The statistics surrounding water hammer events are not well defined.
(4) It is not clear that water hammer is properly incorporated I into risk studies.
Dr. Catton also said that given the move to removing snubbers in plants, the risk of piping damage due to WH may be increasing. C.
Michelson said his understanding of the NRR LBB requirements is that if a piping system is subject to WH, snubbers are not to be '
removed; thus, consideration of WH is important here.
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I In response to Dr. Sullivan,~Dr. Catton indicated that some util-ities have looked into purchase ~of equipment for WH mitigation, but will not install it because they can't get the cost into the rate base, given NRR's position on the WH issue (i.e., its " resolved").
l 9. D.Liles(LANL)discussedthestatusoftheTRAC/PFIMODIandMOD2 code versions. (Note: H. Sullivan declared himself in conflict for this presentation). He noted that a version of TRAC PF1/ MODI is maintained in a frozen status for the ICAP effort. The unfrozen
- j. M001 version has been extensively updated to account for error
, correction, user convenience, new models, etc.
In response to Dr. Catton, Dr. Liles said RES will probably slow assessment of the M002 version in order to assure timely completion l of a QA document for the MODI code.
l LANL detailed recent improvements to the MODI and MOD 2 versions. f These improvements are:
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For MOD 1:
Self-Initialization Multiple Source Terms in the 3-D vessel CCFL Model
- Separator Model I For M002 - all the above plus:
3D-2-Step Numerics With Some Vectorization in 3-D
- Improved Core Void Model Comments by the Subcommittee included:
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- For the CCFL model, there was concern that the "B-value" is input to the model, thus leaving total discretion to the user.
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i T/H Phenomena Meeting Minutes April 28-29,1987 Dr..Tien suggested LANL issue guidelines for the " correct" value to be.used in a given calculation.
LANL noted that MOD 2 runs N 3 times faster than M001 with the above improvements.
- 10. W.'Beckner discussed the Compendium Report that supports the~
proposed ECCS Rule revision. Dr. Beckner noted that the Notice of Proposed Rulemaking was published in the Federal Register on March
- 3. 1987. The public.-comment period closes July 1, 1987. The draft regulatory guide, "Best-Estimate Calculations of Emergency Core Cooling Systems Performance," was published for public comment on April 2,1987. The nearly completed draft of the ECCS research report (Compendium) was placed in the Public Document Room on April 2, 1987. The completed Draft will be published as NUREG-1230.
RES made a number of major revisions to the Compendium since the last review by the Subcommittee /ACRS. These include:
(1) Previous Chapters 4 and 7 ("LOCA/ECCS Phenomena and Issues":
and " Experimental Test Programs and Results") have been combined in a new Chapter 6 per recommendations of the Subcom-mittee.
(2) Previous Chapter 6 on instrumentation has been made an Appen-dix and rewritten.
I (3) Chapter 4 "(USNRC Response - R&D Methodology") has been extensively edited and expanded to include code uncertainty and scaling methods. Chapter 5 ("Best Estimate Codes") has a section reserved for the results of the code uncertainty work, once completed.
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-T/H Phenomena Meeting Minutes April'28-29,'1987 (4) Many detailed.coments of the ACRS Consultants were con-sidered.
RES also addressed specific comments / concerns raised by the Subcom-mittee/ACRS (Fig. 38). Dr. Beckner noted that the Compendium will be peer reviewed by the ICAP participants. Mr. Michelson suggested a NRC/ Industry Workshop to provide pecr review. RES said they will consider this proposal.
In response to Mr. Miche' son, Dr. Beckner said the primary purpose of the Compendium is to serve as a historical document of the ECCS/LOCA research that has been conducted since 1975.
The code models deemed acceptable for use in BE codes are listed in the draft Regulatory Guide. Mr. Ward was puzzled as to the need for extensive peer review given the Compendium is a historical document. Dr. Beckner said the Report is linked to the Rule from the standpoint that it provides support for moving to a BE approach for the codes. Mr. Lauben said the Report serves as a description of ECCS/LOCA research for the public and will also act as an
" institutional memory" for the NRC as well.
Mr. Michelson indicated that Subcommittee and ACRS review of the Report should be separated from review of the Rule and Regulatory Guide.
The Subcommittee made a number of comments on the Compendium.
Highlights include:
- Dr. Tien suggested that the document be given a rigorous peer review to establish credibility in the technical community.
He also suggested that documents be referenced that reflect research that has itself been peer reviewed.
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T/H Phenomena Meeting Minutes April 28-29,'1987
- Professor Schrock comented on the Section on decay heat. He said a more indepth discussion on this topic is called for, l given its historic importance. He noted a few significant errorsinthewrite-up(Chapter 6.12)aswellasdescribedthe key components of the decay heat issue that should be ad-dressed in this Section.
Dr. Catton expressed disappointment at the limiting of the Compendium to historical use only.
Dr. Sullivan praised the effort RES has expended on this Document. He suggested RES include a statement, up front, as to the objective (mission) of the Report. He also suggested reference be made in the Report to the work of the HSST Program as it applies to LOCA (pipe / vessel rupture) probabil-ity. Reference also is missing to the issue of requiring coolable geometry per Appendix K. Other problems were noted which reflected a lack of consistency from Chapter to Chapter.
There was also a lack of code vs data comparisons in the Report.
- In response to Dr. Catton, Dr. Beckner said that while this Document carries no regulatory requirement, RES does consider it important to the Rulemaking effort.
- Dr. Tien noted a lack of discussion on the phenomena of condensation and radiative heat transfer.
- 11. N. Zuber detailed the RES effort to develop a code scaling, appli-cability and uncertainty (CSAU) evaluation. (Note: H. Sullivan declaired himself in conflict with this work.) Dr. Zuber noted that RES has held three meetings with a group of Experts. The last l meeting resulted in a proposed uncertainty methodology.
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- T/H Phenomena Meeting Minutes Apri1~28-29, 1987.
l Addressing-the background surrounding this issue and.the CSAU effort here, Dr. Zuber said three central questions must be ad-dressed vis-a-vis use of the T/H codes. These questions arei (1) Has the code the capability to scale up phenomena observed in small scale test facilities to a full size NPP?
(2)_ Has the code the capability to address a particular scenario or a set of scenarios for a given plant design?
(3) What is. the uncertainty with whici, the code calculates impor-tant parameters, say the peak cladding temperature (PCT), in a full scale NPP?
Discussing the problems of scale distortion and code complexity, Dr. Zuber noted the ultimate capability of a code rests on four elements:
(1) Field-(conservation) equations: which provide code capability to address global processes.
(2) Closure equations: which provide code capability to model and scale particular processes.
(3) Numerics: which provide code capability to perform efficient and reliable calculations.
(4) Structure and Nasalization: which address code capability to model plant geometry and perfom efficient and accurate plant calculations.
In order to assure the ability of the code to correctly perform a calculation, NRR will insist on rigorous documentation consisting
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-T/H Phenomena Neeting Minutes April 28-29,1987 of a code user manual, a QA report, a user. guide, an assessment report and an applicability document.
'Dr. Zuber noted that LANL will-be directed to provide a QA. document on' TRAC PF1/ MOD 1 to NRC by December 1987. He also noted that NRC will henceforth hold the code developers (Laboratories) to a set of. ;
requirements vis-a-vis code QA documents and assessment reports.
Dr. Zuber also cited an instance involving the TRAC. code that illustrated the need for a good QA document to assure proper l applications of the codes. !
i The'CSAU methodology developed by RES was described. The main I
-features of the method and an illustrative flow chart are shown on Figures 39-41. Figure 42 shows a flow chart illustrating how one would make use of the CSAU methodology for determination of the q total code uncertainty for calculation of LB LOCA PCT. !
In response to Mr. Ward, Dr. Zuber said whether or not CSAU method-ology is used by a licensee for a BE ECCS EM calculation will be up to NRR. In response to another- question from Mr. Ward, Dr. Zuber 1
indicated that RES is currently negotiating with the Laboratories (and others) for exercising the CSAU methodology. The RES goal is to complete this work by the end of the year. !
Details of the CSAU methodology are given in Figures 43-53.
l Dr. Zuber said the CSAU methodology remains to be tested, but he believes the process will be a success. In response to another
. question, Dr. Zuber noted that RES will henceforth require complete L documentation on all codes sponsored by NRC - prior to their l
. release from the Laboratories.
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T/H Phenomena Meeting. Minutes April 28-29, 1987.'
C. Michelson asked if the CSAU methodology will be referred to in.
the Rule 'and/or Regulatory Guide. Dr. Shotkin indicated that the:
Rule, Regulatory Guide and Compendiuin are linked by reference to each other. .The vendors will be required to be aware of the Compendium when they submit their BE models. Mr. Lauben noted that' a number of vendor / licensee B2 uncertainty methodology submittals have already been received for review by NRC.
Dr. Tien expressed approval of the above approach.
- 12. C. Michelson requested a written report from the Consultants. giving -
their comment vis-a-vis the TIC (especially the B&W OTSG study),
the ISIF, and general comments on the Compendium and CSAU method -
ology. The Chairman detailed his intentior,s to inform the ACRS of the results of this meeting at its May meeting. He also asked the Subcommittee for guidance as to what issues should be brought to the Committee for its review. Mr. Ward said he believed the CSAU methodology should be reviewed by the Committee. The Subcommittee suggested a presentation be made at the July ACRS Meeting.
The meeting was adjourned at 3:55 p.m. April 29, 1987.
- 4************f********
NOTE: Additional meeting details can be obtained from a transcript of this meeting available in the NRC Public Document Room, 1717 H Street, N.W., Washington, D.C., or it can be purchased from ACE-Federal Reporters, 444 North Capitol Street, Wash-ington, DC 20001,(202)347-3700.
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