ML20237K697
| ML20237K697 | |
| Person / Time | |
|---|---|
| Issue date: | 07/09/1987 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2510, NUDOCS 8708270260 | |
| Download: ML20237K697 (38) | |
Text
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()v a e - m qupr CERTIED DATE ISSUED: 7/9/87 ACRS THERMAL HYDRAULIC PHENOMENA SUBCOMMITTEE MEETING JUNE 18, 1987 WASHINGTON, DC PURPOSE: The purpose of the meeting was to review HIST Program Status including results of MIST Phase III tests, IST Scaling Coordination, and plans for a follow-on test Program.
ATTENDEES:
Principle meeting attendees included:
ACRS NRC D-~Rard, Chairman B. Sheron, RES J. Ebersole, Member R. Lee, RES W. Kerr, Member D. Solberg, RES
]
G. Reed, Member R. Jones, NRR i
C. Wylie, Member L. Shotkin, RES i
H. Etherington, Consultant V. Schrock, Consultant j
l H. Sullivan, Consultant GPU (B&W OG)
{
l L. Lanese i
EPRI D. Sursock UMCP
{
Y. Y. Hsu INEL J. Wolf B&W J. Klingenfus LANL J. Gloudemans l
D oyack T. Knight MEETING HIGHLIGHTS, AGREEMENTS AND REQUESTS 1.
Mr. Ward noted that the Committee is planning a comprehensive report to the Commission on the status of T/H Research. He asked i
the Subcommittee to keep this broader goal in mind as the day progresses. He said that another Subcommittee Meeting may be neceded, and some of the Consultants may be requested to present information to the ACRS.
DCIGNATED ORIGINAL B708270260 870709 hfO
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d T/H Phenomena Minutes June 22, 1987 Mr. Reed noted his concerns with B&W plants. He said that a lack of diversity in DHR requirements is troubling. He noted the vulnerabilities of:
the potential for CL thermal block, HL vapor block and core barrel vent valves disrupting core cooling. This I
results in a heavy burden on the operator. He prefers to see a hardware fix(es), not procedure fixes, to these problems. Mr. Ward indicated that Mr. Reed should be able to sharpen his general concerns as the Subcommittee review progresses.
2.
B. Sheron (RES) provided an overview of the RES T/H research program.
He said the information provided today is preliminary at this time. Key points noted were as follows:
Figure 1 provides details of the T/H research budget. This budget assumes a $1M DOE supplement for facility upgrades, and that $3.9M is obtained from Industry in FY 89 to fund separate effects (SE) work on the B&W OTSG, In response to Dr. Sullivan, Dr. Shotkin said CEC will be abandoned until at least FY 90 (see below) and that the Industry contribution for the OTSG SE work is less than originally identified.
- RES will take a new approach to development of new versions of T/H codes. This approach is that development of a new version of the code should await complete independent assessment of the previous version.
RES plans to establish a Group associated with ICAP to develop priorities for suggested code changes. Given the above, RES is delaying issuance of the MOD-2 version of TRAC PF1 until adequate documentation is
T/H Phenomena Minutes June 22, 1987 available. A M00-3 version will be delayed until RES has determined just what (any why) improvements are needed.
- RES has eliminated funding for a new integral test facility (CEC). This was done primarily because no clear user need can be identified at this time.
Foreign test facilities will be relied on as needed. Assurance of safety for new designs will be the Industry's responsibility. As noted above, RES will examine the need for a new integral facility in FY 90.
In response to Mr. Ward, Dr. Sheron said RES is exploring the idea of a joint NRC/ Industry effort for a new facility, or a Consortium agreement among Countries to build and operate a facility. RES has also actively solicited funding from DOE.
- RES noted a need for data on OTGS T/H performance, particularly given AFW injection. While there are no regulatory or safety concerns, a better understanding of the OISG performance is desirable for BE code modeling, life extension programs, PTS screening criterion, etc. RES has proposed SE OTSG tests. Running these tests requires Industry support (N $8.4M over 3 years).
If NRC/ Industry agreement cannot be obtained soon, RES will:
(1) terminate all MIST Phase 4 experimental work in FY 88; (2) negotiate moving the MIST OTSG to INEL for FP0 testing - this may preclude ever completing the MIST follow-on program; (3) consider other priority programs for expenditure of money - once committed, industry will lose the opportunity for a cooperative funded program; and (4) stupulate that any future requirements for steam generator performance data will be the sole responsi-bHity of industry.
3.
J. Gloudemans (B&W) provided highlights of the MIST Phase III tests.
Figure 2 shows the MIST test matrix. Thirty six transient l
(,.,.
- n T/H Phenomena Minutes June 22, 1987 tests have been run - 5 tests involving pump operation in two phase flow were postponed to the Phase IV Program.
I Highlights of the observations seen for the SB LOCA transients run were detailed.
Figure 3 lists the phenomena observed. Questions l
from Mr. Ward indicated that the codes (TRAC and RELAP) did not model (predict) unusual / unexpected phenomena seen in the tests.
In summary, Mr. Gloudemans noted that:
(1) the MIST system compen-sates for various HPI flow rates; (2) the data is acceptable for code benchmarking; and (3) the MIST testing address all the origi-nal TAG issues to some degree. Mr. Ward, suggested a future presentation should note just how each TAG issue would be addressed by the MIST-data.
L. Lanese (GPU/B&W OG) addressed plans for assessment of IST observations.
Figure 3A provides a flow chart of how the Owners Group will perform this function.
For each observation noted, the OG will evaluate and recommend action based on their judgement.
All actions will be reported and documented.
The Owners have begun to develop training films / lectures for plant operators to enhance their understanding of plant phenomena, based on the results obtained from the IST Program,. Mr. Reed noted that he feels the plant procedures are becoming too complex. Mr. Lanese said that once the structure and logic of the procedures are understood, the operators have indicated satisfaction with them.
R. Lee (RES) overviewed the status of the MIST Phase IV tests.
Figure 4 lists the test matrix and accompanying facility modifica-tions.
Figure 5 lists the NRR issues to be addressed in Phase IV.
Most of the issues can't be addressed because MIST cannot simulate full scaled power.
RES also detailed the on-going NRC/B&W OG i
T/H Phenomena Minutes June 22, 1987 negotiations on obtaining OG funding for the Phase IV and OTSG SE tests (seeabove).
4.
The status of the EPRI-sponsored MIST support Projects were re-viewed by J. P. Sursock. The-SRI-II integral facility work was first discussed.
Key points noted were as follows:
- For single phase natural circulation (NC) tests:
single-phase natural circulation exhibits RCS flow oscillations at low secondary levels; the oscillation frequencies become lower and the amplitudes become larger as secondary levels are lowered; and the oscillation frequencies coincide with AFW on-off frequencies.
- For two-phase NC tests:
the primary system underwent steady-state two-phase natural circulation, oscillatory two-phase natural circulation periods of insufficient cooling, and the boiler-condenser mode (BCM) of cooling; loop asymmetry was observed between 400 and 470 minutes; the the boiler-condenser cooling mode lowers the primary temperature and BCM was achieved only after the primary levels in the tubes were lowered to those of secondary levels. These tests were run with 5 distinct RCS levels ranging from 100% to 56%.
There was extensive discussion regarding means of core cooling i
in a B&W plant, sparked by questions from Mr. Reed. Mr.
Lanese said that B&W plants can adequately cool the core by feed and bleed if necessary.
In response to Dr. Sullivan, Dr.
Sursock said the cause of the loop asymmetry seen in SRI-II is not explainable at this time. Mr. Etherington asked if one can indefinitely operate in BCM cooling given buildup of hydrogen in the SG tubes.
B&W said that tests at MIST have l
,e T/H Phenomena Minutes June 22.-1987 1
shown you can - given large amounts of non-condensable gas in the RCS.
- Figure 6 lists the SRI-II test matrix. Seven tests are planned for 1987 - two of which are discussed above. The last test involves an attempt to develop a scale approach to allow scale up of the test results to a full size plant.
I 5.
The status of the University of Maryland College Park (UMCP) facility was reviewed by Y. Y. Hsu and K. Almenas.
Key points of the presentations included:
- K. Almenas reviewed the experimental repeatability of UMCP.
Repeatability is of concern because of stochastic and bifur-cation type deviations that can be seen during the experi-ments. Referring to a comparison of two tests results (Figures 6A and 7), Dr. Almenas noted that the results were time-shifted. Other results were shown to make the case that random bifurcations in the test scenarios will make test repeatability extremely difficult, if not impossible. He recommended that an " enveloping procedure" be used to model the phenomena of interest. Mr. Ward asked how this approach can be judiciously applied in BE analyses.
Dr. Almenas indicated that enveloping a class or set of results is the best one can hope for.
- Y. Y. Hsu reported on the results of some recent UMCP tests.
Aseriesofnaturalcirculation(NC)testswereruntostudy the effect on core cooling of biasing secondary SG feed flow.
The results showed that core cooling degradation does not become significant until secondary flow bias is extreme (N j
100%/10%).
.i' T/H Phenomena Minutes June 22, 1987
- Two phase. flow tests demonstrated that core cooling can be maintained without HPI if the'SG secondary side water level is kept above the primary side level. Dr. Hsu noted that this result may not be seen if HPI is used (UMCP will install-HPI capability in the near future)... Another key result is that j
the cold leg loop seal phenomenon is important vis-a-vis loop flow asymmetry.
- Figure 8 details the future test schedule for VMCP.
6.
J. Wolf (INEL) overviewed the IST scaling report results. The objective of the Report was to allow meaningful comparisons of the test results from the MIST, UMCP and SRI-Il facilities.
Figures 9-11 detail the reports conclusions.
INEL concluded that all the facilities are geometrically well scaled per the design criteria selected.
Counterpart experiments are suggested (Figure
- 11) and INEL noted that the individual experimenter must have a good understanding of the transient to be simulated in order to establish the correct pressure scale. True counterpart experiments will be difficult to perform in the low pressure facilities (UMCP, SRI-II).
In response to Dr. Sullivan, Mr. Wolf said that by judicious use of analyses one can have a true counterpart experi-ment. Dr. Sullivan indicated skepticism that useful results will be obtained.in this exercise. Dr. Kerr asked how one can properly scale the code (s) if one can't scale the tests.
R. Lee said that test results to date offer promise that meaningful comparisons can be made.
R. Lee reviewed the plans and schedule for the above planned counterpartexperiments(Figure 12). Mr. Schrock and Dr. Hsu debated the approaches available for proper scaling of break flow, i
,t T/H Phenomena Minutes June 22, 1987' l
I given subcooled versus saturated conditions in a low pressure facility.
7.
R. Lee discussed the coordination of the IST and IST support projects (NUREG-1163). The NUREG will be updated in early 1988 to include discussion of updated design'information on integral and separate effects experiments conducted, and sumarize key results (obtained to date) that address the issues'of: decay heat removal by single and two phase natural circulation, consequences of steam generator tube rupture, and loop-to-loop oscillation. The Report l
will also sumarize key results (obtained to date) that address MIST atypicalities. Results of the ANL hot leg U-bend study i
conducted by Ishii are detailed in Figures 13-16.
V. Schrock noted that the results show a type of 2-phase flow regime that is not recognized in the codes. Given this, it appears further study is warranted.
Addressing the issue of development of a final report to integrate key TAG issues, Dr. Lee said there will be a ten-volume Report on the MIST program and that the above noted revision to NUREG-1163 will address coordination of IST and IST support Projects.
D. Solberg discussed how the TIC B&W programs will be linked to the IST Programs. Coordination of the two efforts will be handled via:
' a draft plan in NUREG-1236 "T/H Research Plan for B&W Plants."
This plan may define additional IST program requirements. Mr.
Ward recomended that the Subcommittee review this Report.
L.
Shotkin said the final Report should be available in None month.
' the INEL B&W plants safety evaluation which compared B&W plant f
response against W and CE plants. The study is under review
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T/H Phenomena Minutes June 22, 1987 4
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1 by NRR. A draft comprehensive report is scheduled to be issued at the end of July 1987, j
t
' publication of synthesis Reports by INEL from time to time. A Report on feed and bleed is under preparation.
i
- the code applicability program which is underway vis-a-vis 1
RES.
For B&W plants, an. applicability study for loss of feed transients will be run. Other applicability studies for B&W l
transients are planned for FY 88. The program is an offshoot of the CSAU effort.
I S.
R. Jones (NRR) provided NRR comments on the B&W IST Program.
Key points noted included:
- MIST Phase III appears to provide adequate data to resolve the TAG issues.
- In October 1984, NRR issued a User Need Letter requesting a MIST follow-on Program. The primary concern is the ability of the codes to predict OTSG behavior.
In response to Mr. Ward, Mr. Jones said the concern over 0TSG behavior ranges from full power transients (SL break) down to post shutdown events.
i
- The MIST Phase IV tests are useful for evaluating the B&W ATOG.
full power tests, and tests of AFW flow penetration and spreading. Tests have been proposed to address these issues and they appear i
satisfactory.
In response to Mr. Reed, Mr. Jones indicated
)
that the margins of SG performance haven't been quantified -
thus the code calculations are suspect.
In response to Dr.
4 I
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_.._._._.._.._________d
T/H Phenomena Minutes June 22, 1987 Kerr, Mr. Jones indicated that licensees may be requested to i
providedatatosupportspecificlicensechanges(ex:
request l
from SMUD to reduce AFW flow rate).
In response to Dr.
Sullivan, Mr. Jones indicated that the full power MIST facility would be prohibitly expensive.
1 Mr. E. Davidson (FP&L) noted that the B&W OG is proposing to benchmark their RELAP/5 code version against actual plant transients. This approach avoids the issue of scale. Mr.
Davidson also said the NRC program is still a moving target.
Mr. Ward requested a technical presentation on the OG bench-marking Program at a future Subcommittee Meeting.
In response to Mr. Schrock, Mr. Davidson said they have fairly detailed measurements of the plant transients, however they must infer the SG T/H phenomena.
9.
Three MIST RELAP-5/ MOD-2 pretest analyses were reviewed by J.
Klingenfus (B&W). The three MIST tests calculated were:
(1) 2 nominal scaled 10 CM coldlegpumpdischarge(CLPD) break;(2) 2 10-tube SGTR with full HPI capacity; and (3) 50 CM scaled CLPD break.
Based on the above pretest predictions, B&W recommend four changes to the code input model and one change to the steam generator heat transfercoefficient(Figure 17). Mr. Schrock and Dr. Sullivan expressed concern with the change made to the SG heat transfer model, i.e., the change appear arbitrary. Mr. Lanese said the benchmark program should " prove" the OG SG model.
- 10. Thad Knight discussed the results of the TRAC-PF1/ MOD-1 pretest analyses.
Figure 18 lists the pretest calculations performed.
Summarizing the pretest results, Mr. Knight noted:
(1) calculated primary flow is low during steady state which results in the
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T/H' Phenomena Minutes June 22, 1987 h
hot-side temperatures being too high; (2) with the above problem, the code still calculated the trends of the tests correctly; and (3) a quirk in the OTSG secondary level was seen as the secondary dries out during feed-and-bleed tests. This is related to code logic concerning horizontal stratified flow.
LANL modified the code for posttest analyses.
These modifications included a change in the OTSG heat transfer model. Mr. Knight indicated that this change is arbitrary and he believes additional data is needed in this area.
LANL concluded that:
(1) given the error in steady-state con-ditions, the pretest results were reasonable, but MIST highlights the AFW effect in an atypical way; (2) code calculated all of the observed phenomena; and (3) the MIST facility has also demonstrated j
significant sensitivities to initial and boundary conditions.
- 11. The RELAP-5/M00-2 posttest analyses were reviewed by J. Klingenfus.
The methodology used to select tests for posttest analyses, and tests selected, are shown on Figures 19 and 20.
For this set of test calculations, no " tuning" of the code was allowed between each separate calculation. Mr. Klingenfus said that the comparisons shown indicated good agreement was obtained.
12.
B. Boyack reviewed the LANL TRAC pasttest analysis program. The goal is to provide " reasonable" cgreement between calculated or predicted results. As an aside, Mr. Boyack proposed a set of descriptors for characterizing code versus data agreement (Figure 21). Mr. Ward expressed support of this approach.
Figure 22 lists the MIST tests selected for the TRAC posttest calculations. The key observation from the initial posttest
f T/H Phenomena Minutes June 22, 1987 calculations noted was that:
the MIST facility is quite sensitive to changes in initial and boundary conditions; thus, it is very important to specify the correct initial and boundary conditions for the calculation.
Future analyses scheduled in support of the IST Program are listed on Figure 23.
- 13. Mr. Ward noted that the topics not covered today would be discussed at another Meeting in the future (i.e. use of B&W code analyses, and update of CSAU methodology development vis-a-vis B&W plant modeling).
l The Chairman said the Subcommittee wishes to comment on the RES T/H Programs based on the perceived technical research needs. He is aiming for an ACRS letter in the fall of this year. He sees a need for N 1-2 more Subcommittee Meetings in this area. Mr. Ward would prefer to provide general, not detailed advice. He framed the
. challenge as:
"Whatdowethink(technically)shouldbeaddressed in the NRC T/H research program?"
Is the program in focus, on track, appropriate? How should it be organized? etc. Do we need to get more detailed technical input to carry out this task?
Mr. Ward noted that RES would prefer 0G participation in a major i
OTSG SE experimental program. The question he asked the Subcommit-tee was:
"How do we go about informing ourselves so we can give good advice on this question?"
i The Chairman requested written reports from the Consultants and Members present on these items.
Mr. Reed said that he believes the Programs heard today are lack-ing. What is needed is a backup DHR (primary blowdown system).
(
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~ June 22, 1987 T/H Phenomena Minutes
- 14..The. meeting was adjourned at 4:50 p.m.
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-l ington, DC 20001, (202) 347-3700.
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REACTOR AND PLANT SYSTEMS BRANCH PROGRAM FY 88 FY 89 XIST 800 2,300 CONTINUING EXPERIMENTAL CAPABILITY-250 0
0lSG (FPO) 1,500 1,500 OTSG (LPSF) 1,000 100*
TECHNICAL INTEGRATION CENTER 1,500-2,343 CODE UNCERTAINTY 700-1,000 DEVELOPMENT 8 ASSESSMENT OF CODES 4,760 5,400 BASIC STUDIES 1,620 1,700 FOREIGN EXPERIMENT SUPPORT 1,300 1,400 2D/3D PROGRAM 3,350 1,700 TOTAL 16,780 21,343 LESS DOE LESS INDUSTRY SUPPLEMENT 1,000 SUPPLEMENT 3 900 TOTAL RPSB BUDGET 15,780 17,443
- (3.9 M INDUSTRY)
Y*
1 i
MIST TEST PATRIX AND STATUS e
4 TEST TYPES:
DEBUG CHARACTERIZATION MAPPING TRANSIENT 0
6 GROUPS OF TRANSIENT TESTS:
1.
BOUNDARY CONDITIONS 2.
LEAK AND HPi CONF 1GURATIONS 3.
HPI-PORV COOLING 4.
TUBE RUPTURE 5.
NONCONDENSIBLES AND VENTING 6.
PUMP OPERATION 0
COMPLETED 36 TRANSIENT TESTS.
REMAINING 5 TESTS INVOLVE PUMP OPERAT10N IN TWO-PHASE FLG4.
INITIAL CONDlT10NS AND CONTROL 8
OBSERVATIONS (IN APPROXIfoATE CHRONOLOGICAL OPLER):
1.
PRlfMRY SYSTEM DEPRESSURIZATION
/
2.
ASYMfETRIC INTERRUPT 10N OF LOOP FLOW SWgi3GP MN /M# W/M 3.
TEST REPEATABILITY Sv8S1 tunny R/vnt VsIS 4.
COLD LEG INTERACTIONS (COUNTERBLOW, INTER-COLD LEG FLOW)
REACT 0p,VESSELVEN{VALVEEFFECT)S 5.
(qEF cf/ v6 H T Kh%uvet pg,gygg 6.
BOILER-CONDENSER MODE (EFFECTIVENESS, ALTERNAT10N) 7.
EQUILIBRIUM AND SPILLOVER 8.
RESTART OF NATURAL CIRCULATION 9.
CORE COOLING W A5 A 4 "d f 5 *###f#/###
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L TENTATIVE TIME TABLE OF. TASKS 8 SUBTASKS HOT LEG PHASE SEPARATI0f1 e PHASE DISTRIBUTION PROFILES 12-86 e HOT LEG CARRY OVER LIMITATIONS 7-87 e FLOW INTERRUPTION & RESUMPTION 10-87 e PUMP EFFECT (INSTALLATION OF PuMe 11-12, 87)
STEAM GENERATOR INTERACTION e NC BEHAVIOR SCOPING 9-86 e NC BIASED LOAD EFFECT 3-87 e BCM BEHAVIOR SCOPING 7-87 e BCM TRANSITION POINT IDENTIFICATIONS 8-87 e INTEGRAL TESTS DELIVERED TO LASL 9-87 W/0 AUXFEED e INTEGRAL TESTS DELIVERED TO LASL I4-88 WITH AUXFEED e MULTI-LOOP INSTABILITY ANALYSIS 1-88 e AUXFEED EFFECT 3-88 DOWNCOMER BEHAVIOR e LOOP SEAL EFFECTS 10-87 e DOWNCOMER FLOW FIELD 10-87 h
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MIST PRETEST PREDICTION CONCLUSIONS AND RECOMMENDATIONS 9
THE PRETEST PREDICTION RESULTS FOR TESTS 3109AA AND 3406AA CORRECTLY EXHIBITED THE GOVERNING THERMAL HYDRAULIC PHENOMENA ALTHOUGH THE MAGNITUDES OF THE INTERACTIONS WERE SOMEWHAT SKEWED.
THE MAJOR DIFFERENCES CAN BE TRACED TO SLIGHT PRETEST PREDICTION MODEL BOUNDARY CONDITION DIFFERENCES SUCH AS 1.
AFW PROPORTIONAL / INTEGRAL FLOW CONTROLLER DIFFERENCES 2.
LACK OF STEAM LINE HEAT LOSSES IN THE MODEL 3.
UNDERPREDICTION OF THE FULL SECONDARY STEAM RELIEF CAPACITY DURING THE STEAM GENERATOR TUBE RUPTURE TEST.
9 BASED ON THE PRETEST PREDICTION RESULTS THE FOLLOWING MODIFICATIONS SHOULD BE MADE TO THE INPUT MODEL PRIOR TO PREFORMING POST-TEST CALCULATIONS:
1.
ADJUST THE INITIAL LOOP NATURAL CIRCULATION CONDITIONS TO BE CONSISTANT WITH FACILITY COMPUTED TEST PARAMETERS, 2.
ADD THE ESTIMATED SECONDARY STEAM LINE HEAT LOSSES TO THE INPUT MODEL, 3.
ADIUST THE MODEL AFW P/I FLOW CONTROLLER GAINS, 4.
PROVIDE ACCURATE SECONDARY STEAM RELIEF CAPACITY.
9 BASED ON THE PRETEST PREDICTIONS ONLY ONE CODE CHANGE IS SUGGESTED.
THE SECONDARY DRY STEAM HEAT TRANSFER COEFFICIENT SHOULD BE MODIFIED SUCH THAT ONLY THE STEAM REYNOLDS NUMBER IS USED WITH THE DITTUS-BOELTER CORRELATION.
THE NEED FOR THIS CHANGE WAS EVIDENCED BY THE DRY TUBE TEMPERATURE PROFILE CALCULATED DURING THE STEADY-STATE INITIALIZATION.
l lP/6.17]
PRETEST CALCULATIONS 1
310000 - MIST nominal case,10 cm2 SBLOCA with nominal HPI and AFW, symmetric SG ccoldown 310503 - same as nominal except for throttled AFW and asymmetric SG cooldown l
320604 - same as nominal except used evaluation model(EM) HPI capacity 330201 - feed-and bleed cooling with EM HPI-head flow characteristics 330302 - feed-and bleed cooling with full HPI delayed 20 minutes after first lifting of PORV i
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ASSESSMENT ANALYSES TO BE PERFORMED FOR IST EXPERIMENTS USING TRAC 1.
MIST EXPERIMENTS (1987)
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3109AA Nominal 3801 Core Uncovery 3404 Single-loop cooldown with 1 tube SGTR and isolated SG 320201 Increased leak size 2.
UMCP EXPERIMENTS (1987)
Nominal (3109AA counter One other (to be defined) part) 3.
SRI-2 EXPERIMENTS (1987)
Nominal (3109AA counterpart)
One other (to be defined)
Analysis schedule dependent on test schedule LOS ALAMOS 6/18/87 11 oSL