ML20236Y443

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Comments on Proposal for Multiple Vent Steam Tests in Gkss Facility,Per 770516 Memo.Steam Condensation Oscillation Studies Currently Being Conducted in Programs Sponsored by Owners Group.Nrc Recommendations for Tests Encl
ML20236Y443
Person / Time
Issue date: 06/14/1977
From: Buckley B, Charemagne Grimes
Office of Nuclear Reactor Regulation
To: Fabic S
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
Shared Package
ML20236X982 List:
References
FOIA-87-160 NUDOCS 8712110328
Download: ML20236Y443 (57)


Text

{{#Wiki_filter:~ A,. j,. g. urss e cu e s m e ss 9 e 4 WUCLEAR REGULATORY COMMISSION }- N'giM o WASHINoTON, D. C. 20$55 i g .l } \\ . MEMORANDUM FOR: S. Fabic, Chairman, Containment Code Review Group, RSR FROM: C.-Grimes, Plant Systems Branch, DOR -i B. C. Buckley, Section Leader, Plant Systems Branch, DDR

SUBJECT:

C05NENTS ON PROP 0FAL FOR MULTIPLE VENT STEAM TESTS IN GKSS FACIL7TY In accordance with. your memorandum, dated May 16, 1977, we have revie.ed L. Slegers' trip report and the revised draft.of "NRC Recomatendations for. Tests in GKSS Pressure Suppression Test Facility." The objectives of the GSKK test program as described in these l documents are:.(1)1toL provide confirmatory steam condensation load data for.the Mark II. containment design; and (2) to quantify pressure amplitude f dependence - cn the number of ~ vents by directly comparing the multiple vent' data from GKSS with the single vent data developed by General Electric -(GE). For both of the citernativef facility configurations described i in the report, it appears that the stated program objectives may be /, 'I difficult to achieve. l l Early results from the analytical investigations of the steam condensation phenomena that arc being conducted by GE and the consultants to the Owners Groups (Mark I and Mark II), indicate that acoustic coupling l between the vents may have a significant effect on the^ amplitude and- [ character of the steam. condensation pressure oscillations. The two alternative GKSS configurations are characterized by: (1) 'a drywell volume per vent that is three times smaller than that'for the Mark II containment; -(2) multiple vent lengths; and (3)' vent headers _ tha t are. not found in the Mark II design. These differences can be expected to have substantial effects on the acoustic coupling so that it would be difficult to relate any data from this facility to the Mark II configuration. '1hese effects would have to be thoroughly assessed before' the pressure amplitude dependence can be reliably quantified. As you are aware, application of the single veut condensation oscillation data has been inhibited by concerns relating to the degree of fluid-structure interaction and its influence on the true forcing function. l GE has subcontracted a. medal analysis of, the single vent test facility-in order to properly interpret the' data. In addition, the M2rk I Owners Group has devoted a considerable amount of attention to the structural. l 8712110328 770614I ~ PDR FDIA MENZ87-160 PDR d___-__ __i_._ _.

=___ o. . design of their full. scale steam condensation test facility.- The'GKSS-facility utilizes a much more. complex. structure. Moreover, it is not! ~ apparent that the selection of either the facility configurations or' the : instrumentation was based-on any. consideration.of potential. fluid. 3 structure interaction effects. We have a namber of' comments regarding the' conduct of. the; tests which' we will be providing when the' test plans are,to be finalir d. However,: l based on the comments outlined above, it is our view that consideration, should be given either to' alter. the objectives of the tests or' to selection 1 of an alternate facility..As.previously mentionedy steam condensation b . oscillation studies are currently being' conducted in programs; sponsor'ed! by the Owners Group. The results;of these. studies may resolve many j of these problems.in the!near future. -] l. j 'C.. Grimes ' Plant' Systems Branch ' Division of. Operating Reactors-6.c. hM 4 B. C. Buckley,.Sectibn Leader-Plant: Systems Branch. Division' of. Operatihg' Reactors - l

Contact:

C. Grimes 492-8077 l- -cc: D. Eisenhut W. Butler J.'Guibert L. Rubenstein W. Paulson l G. Lainas

2..

J. Kudrick l ^ L. Slegers k g j %h4 L e 4 l 1 _D

l l i i. i i i \\ NRC RECOMMENDATIONS FOR TESTS IN GKSS PRESSURE SUPPRESSION TEST FACILITY j 1 1 i I 1 1 I 1 I e 1

t l '. Introduction As. part of the combined Containment Review fleeting of 9 and'10 Dec, 1976, further plans-have been-worked ~out-for testing in the GKSS Pressuro Sucoression Test F This part of the planning accommodates the US NRC i acility., ' n their need for data on trultiple vente during steam condensations Specific measurements are desired for pressure oscill ti (and - pressure soikes) during the condensation a ons of rela-tively air free steam from~ multiple, large scale vents. In addition measurements on the lateral' vent load -multiple vent configuration n-a are-important. l l 1 1 f 1

I ,g : l 2. Obiective l ,i i The objective of these measurements is to provide con-l firmatory data for the MARK-II BNR containment. The MARK-II' i 1 design is based on full scale single vent exper'iment;that 'I l simulate a loca transient. Of primary interest.in the de-1 1 sign are the dynamic loads during steam conden.sation In 9 addition.the lateral loads on the structure between the vent: need confirmation for-multiple vents. 'j 1 i 5 With detailed measurement of thin type on a full-scale sinqlt-j l (unit cell) arrangement 'the need exists 'for. extension vent of these data to multiple vent: configurations. 1 Past experiments indicate pressure amplitudes ^for. multiple f vents which show a certain dependenc6 of pressure amplitudes on numner of. vents. The: objective of these tests is therefore a to quantify this amplitude dependence under comparible'experi ] mental conditio.ns, unit cell as-multiple vents (3 to 5). I'or reference, unit cell data of the General Electric Co. kill be used. The proposed measurements would' utilize the ,\\ 1 GKSS facility to approximate multiple unit-cells in the same i ] scale,up to the caoacity of the appara tu s (3.to.5). I q '1 l l l I Iy 1 l i i ~ ._..._m __-m

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Configuration 3.1 . Scaling considerations The proposed procedure for applying the test'results.to_ i .l l the full scale plant is,.that ;he relevant-plant parameters be maintained in the' experiment. Such plant parametershave ] been identified in the past and appear'in Table 1.-This table { also lists the: range:in important parameters for all !1 ARK-II' 1 -{ plants, and the valuesLfor La salle as plant reference.. { In addition, the values for the reference GE' tests _appearp in 1 colum (2) and (3). Comparible test conditions ~for;a multinle-4 1. vent arrangement are then obtained if1 the ' values in table -/- j for the proposed tests. column 4 and.5 are reasonably close a j to thone'in the other columns. I i a 3.2 Constructions -) Based on the pres nt configuration of the pressure ' suppression test facility (s. GKSS-Report No. 11 15 AR B O2) two multi- ] vent configuration have been designed, one with three vents,- I i and the second one with five vents-(Fig. 1 ' A/1 B and 2 ~ A / 2 ' R), i Alterative one (1 A/1 B) is a five vent configuration.where i two headers are connected to the1drywell via two pipes of' O.45 m 1.D. This configuration represents a section o.f.the vent.configura-tion of BWR-MARK-II-arrangement with O. 51 m -(20' in.- ) ~ i. D. vents. A possible disadvantage of this alternative could be-expected in non uniform flow distribution for all five vents. Alternative two is'a three vent' arrangement where the vents of 0.61 m (24' in) 1.D..are directly connected.to the drywell. This configuration represents a three vent arrangement of a

a. The advantage of this configuration.is to be seen in the uniform flow' Distribution. However it should be mentioned, that a plant representative spacing of the vents is not realized. Relevant parameters are'shown in Table 1. 3.3 Test Configuration Table'1 shows the degree of correspondence between the proposed tests and the reference test. Alternative 1 is to the reference test in the relationship of poo1~ area.to vent. Alternative 2 on the other hand 13 in this respect to the actual configut'ations. The applicability with respect to the other parameters is the same for'both alternatives. A containment respons'e prediciton for the GKSS facility with alternative 2 is untained in Fig. 3, 4 and 5. The input data for the calculation are listed in Table 2. The computation shows the design basis Loca as simulated'in the proposed tests. It is recognized that for the objectives of the proposed tests, the early phase of the Loca transient need not be simulated. Only the later phase with relatively air free sb&c1 condensation is of interest. The range of interest for the experimentation is therefore restricted as follows: - specific cess flux not to exceed 60. kg/m2 g - wetwell pressure ca. 3 bar pool temperature .40 - 70 C U - maximum pool. depth 5.50 m - clearence vent exit to pool bottom 2.44 m - vent submergence 3.06 m 1 l

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  • 4 Instrumentations The level of instrumentation' anticipated f experiments will_ correspond to,the scope of i or the proposed employed in the reference'GE tests,' and consist nstrumentatio:

measurements to evaluate the dynamic loads for th s of pressu:, vent tests. A comparibl9 level of instrumentati e multi-temperature is recommended. For the-dete on'for' pool lateral loads on - the vent exit, rmination1of the 2 vents independentlyfis recommended,aEloades11 measu ' l /. l l

.c 6-- ' 4 '. Anticipated Procram Scone-The nature of these confirmatory te t a limited riumber of multiple vent ' tests '~( s s is such that the. parameter.~ran'ge listed'in 5'3 3 a up to ten) over The preferred scheduling of:these test .. re planned. availability:Is planned'for. late 1978 s is<such thatLdata-l i l 1 f ) r

1 1 1 COMPARISON PLANT, PSTF, GKSS-PSS', Mark ilrange TABLE 1: (Data of Plant, PSTF and Mark 11 range acc. to Dr.L.51eegers) l UNIT PLANT PSTF GKSS Mark 11 range Parameter (1) (2) (3) -(4)- (5) (6).' j 1 i Number of gg 3 3 5' Vents 0,597. 0.61 0.51 0.61 0.51 In. ~23 3 .24. 0 20.0. 24.0. 20.0 20-24 q Diameter m i 3 64.01 53.6 53.6 19 33 11.6L vent ft3 2260. 1892. 1892. 683 0 410. '1800-2700-Orywell voi m 228.9' 195.7 -285 3 66.24 57 2. j l ft 750.9 642.0' 936.0' 217.3 187.8 575-914 Orywell vol m vent area 5.33 3 18 -3 27

57 3 4-1 vent ft2 57.4 34.2 35'2 61.

36.6-36,8-60,0-Pool area m 19 1 11.6 17.4 19.4 16.8' 12.- 20 l Pool area 1 vent area m 39 2.74

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N 7"A 3 4 g g. RECIRCULATION,'l LItlE BREAK FLOW RATE / AREA AT.THE EXIT OF DOWNCOMERS DOWMCOMER EXIT PRESSURE-32Psig Steam flow rage / area Liquid flow rate / area Time (Kg/sec-m ) (Kg/sec-m2) l - (sec)- 10.13 129;86 301.16 20.13 121.09 301.12 20.16 129.39 133.73 25.01 93.96 94.43-30.03 70.35 65.39 l 40.03 28.89 2/.45 i

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July 8, 1977-I CONTEMPT-LT/26 ANALYSES OF GKSS PRESSURE SUPPRESSION TESTING FACILITY' by: Fei Ken Chiang Introduction L Four containment pressure and temperature analyses were carried out l on the german GKSS pressure suppression testingLfacility through the use of the Contempt-LT/26. Discussion l m,..u. The german GKSS pressure suppression testing facility'is a full Q, @ e pu,., o scale multiple venticonfiguration Mark II BWR containment system. ft-n 6, .v.

a hass. at the present, two conceptual designs; each one corresponds to a

,o different vent, configuration., Design no.1 has five 20 inch I.D. Vents mw,' (two different vent" configurations) and design no. 2 has three 24 inch I.D.' Ventf(-two--different vent configurations.). They are shown on figure 1A 1B 3 l and figure 2A, 2B respectively. L l -I L Contempt-LT/26 code was used to predict the long-term thermal-j 1 hydraulic behavior of water-cooled nuclear reactor containment systems - ) under the postulated loss-of-coolant accident (LOCA) condition. Among other variables, it calculated the time variation of pressure and temperature i of different compartments modeled in ghe reactor containment system-(including the drywell and wetwell). Contempt-LT/26 will accept only i One type of vent configuration for its input. In other words, Contempt-LT/26 assTnued all vent configuration input to be identical for each run. To carry out containment pressure and. temperature analyses'on the'GKSS pressure suppression testing facility, the following method was used. For design no.1, one of the two vent configurations was assumed for all vents and a containment pressure and temperature analysis was performed on the containment s/ stem. Afterward, the second vent' configuration was assumed

for all vents and again, a containment pressure and temperature analysis was perfomed on the containment system. The same procedure applieh to design no. 2. Figure 3A shows one assumed vent configuration for design no. 1 and 3B shows the other. The same also applied to figure 4A and.4B for { l design no. 2. Summary l Four Contempt-LT/26 runs were made altogether. Runs no. 1, 2, 3, 4 used vent configuration of figure 3A, 3B, 4A, 4B respectively. For each I I l run, in addition to the pressure and-temperature histories in the drywell l and wetwell, the following parameters were computed:

1) air mass flow rate in the vents
2) water (droplet) mass flow rate-in the vents

] i

3) vapor mast, flow rate in the vents 1

The graphs of these parameters versus time for runs no.1 through 4 are i i shown on graphs no. 1 through 9. It was intuitively expected that the values of the above parameters for the actual design no.1 lie within the range of the experimental values obtained for configurations used in runs no. 1 and 2. Likewise, values of design no'. 2 lie within the range of values obtained through runs no. 3 and.4 1 1 \\ L____._____

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July 8, 1977-CONTEMPT-LT/26 ANALYSES OF GKSS PRESSURE SUPPRESSION TESTING FACILITY by: Fei Ken Chiang Introduction Four. containment pressure and temperature analyses were carried out on the german GKSS pressure suppression testing facility.through the use l cf the Contempt-LT/26. Discussion The german GKSS pressure suppression testing facility is a full scale multiple vent configuration Mark II BWR containment system. It j l has, at the present, two conceptual designs; each one corresponds to a d different vent configuration. Design no. 1 has five 20 inch I.D. vents (two different vent configurations) and design no. 2 has three' 24 inch I.D. Ventf(twodifferentventconfigurations). They are shown on figure 1A, 1B ] and figure 2A, 2B respectively. Contempt-LT/26 code was used to predict the long-term thennal-hydraulic behavior of water-cooled nuclear reactor containment systems under the postulated loss-of-coolant accident (LOCA) condition. Among other variables, it calculated the time variation of pressure and temperature of different compartments modeled in ghe reactor containment system (including the drywell and wetwell). Contempt-LT/26 will accept only one type of vent configuration for its input. In other words, Contempt-LT/26 assmued all vent configuration input to be identical for each run. To carry out containment pressure and temperature analyses on the GKSS pressere suppression testing facility, the following method was used. For design no.1, one of the two vent configurations was assumed for all vents and a containment pressure and temperature analysis was performed on the containment system. Afterward, the second vent configuration was assumed

r --..-.a.. for all vents and again, a containment pressure and temperature analysis was performed on the containment system. 'The same procedure applied.to design'no. 2. Figure 3A shows one assumed vent' configuration for. design no. l' ~ and 3B shows the.other. The'same also applied to figure 4A and 4B for. design no. 2.. Summary Four Contempt-LT/26 runs were made altogether. Runs no.L1, 2, 3, 4 used. vent configuration of figure' 3A, 38, 4A, 4B respectively. For each1 run, in addition to the pressure and. temperature histories in the drywell and wetwell, the following parameters were ' computed:

1) air mass flow rate-in the vents 2). water (droplet) mass flow rate in the vents
3) vapor mass flow rate in.the vents The nraphs of these parameters versus time for runs no.1 through 4 are f

shown on graphs no.1 through 9. It was intuitively expected that.the 3 Yalues of the above parameters for;the actual design no. 1 lie within. j the range of the experimental values obtained for configurations used I in runs no. 1 and 2. Likewise, values of design no. 2 lie within the range of values obtdined through runs no. 3 and 4. O e ~ - +, - -,,. _ ~,, ~.. -A --_-_-_n_____-.___ .s.._- u

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