ML20212Q221

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Requests Addl Info Re full-scale Mark II Containment Test Facility.Detailed Info from Two Test Identified Requested to Help Determine Scope & Applicability of Other Detailed Info That Will Be Requested in Future
ML20212Q221
Person / Time
Issue date: 11/30/1979
From: Tong L
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To: Nozawa M
JAPAN
Shared Package
ML20209A640 List: ... further results
References
FOIA-85-782 NUDOCS 8702020187
Download: ML20212Q221 (4)


Text

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e D , j W ASHINGTON, D. C. 20555 NOV 3 01979

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Dr. M. Nozawa Head, Division of Reactor Safety Japan Atomic Energy Research Institute Tokyo, Japan

Dear Dr. Nozawa:

Thank you for the opportunity afforded by you for the recent meeting between you, Dr. Shiba and certain members of the Nuclear Regulatory Commission staff.

The Containment Systems staff of the U. S. Nuclear Regulatory Ccmmission is ex-tremely interested in the data being obtained by JAERI from the full-scale MARK II containment test facility. These JAERI data will help provide additional confir- f mation of the conservative hydrodynamic loads that are reported in NUREG-0487, L dated October,1978. Based on our preliminary review of the available JAERI full-scale multivent test data, we would find your continued cooperation especially i

helpful in the following amas:

First, we would like permission to release the facility description, i.e., JAERI y Memo 8110, and the associated facility drawings (Figs. 4.3, 5.1, 5.4, 5.5, 6.6, 6.7) to the General Electric Company as well as to the MARK II owners and their contractors. Release of these documents would allow them to initiate certain fluid structure interaction studies (FSI) by means of mathematical models of the JAERI facility.

Second, we would like to have certain additional data as identified below for two of the tests conducted so far.

A) From Test 2101 (1) All data acquired at 455.6 datapoints per second, Pulse Code Modu-lation (PCM) recorded. (indicated by an F in the D location of the channel code), i.e., from channels shown on Attachments 1 and 2. We would want these data for each transducer for the entire blowdown, i.e., from 0.0 to 350.0 seconds, expanded to a scale of 10 seconds per page. (Approx. 2,400 pages total.)

(2) Sane data as in (1) above but expanded to a scale such that only 2 complete condensation events (either C/0 or chug) fit on 1 page, i.e., a time scale expanded similar to that example from the GKSS tests (Attachment 3). Similar figures for all the other PCM data, for the transducers listed in Attachments 1 and 2, on expanded time scale corresponding to the duration of the 2 condensation events.

We want these data for only 2 chugs, but 2 which fall in the 92.0 to 98.0 second tire interval. (Approx. 120 pages.) /

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Dr. M. Nozawa NOV 3 01979

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B) From Test 3102 (1) All available JAERI data analysis done for this test including Power Spectral density (PSD), Cross Power Spectral density (CPSD),

Phase Difference, Coherence, Blowdown Calculations, Containment Response Calculations, and Complementary Cumulative Probability Density (CCPD).

(2) All PCM recorded data for this test, i.e., same data as identified in (A)(1) above for Test 2101. We want these data for each trans-ducer from 0.0 to 60.0 seconds expanded again on a scale of 10 sec-onds per page. (Approx.410pagestotal.)

(3) Same data as in (2) above but expanded to the scale requested in

( A)(2) above for Test 2101. We want these expanded data for 3 pairs of chugs:

(a) 1 pair occurring in the 4.496 to 8.991 second interval; (b) 1 pair occurring in the 17.982 to 22.478 second interval; and (c) 1 pair occurring in the 49.954 to 53.917 second interval.

(Approx. 210 pages.)

We would like expanded data for the above tests for the following reasons: Test 2101 is of interest because of the long duration of the blowdown. The long dura-tion yielded a relatively large number of condensation events, which is desirable for statistical purposes. Test 3102, on the other hand, represents a large break (200 mm) thereby giving results at the opposite extreme from Test 2101 (74 mm).

We understand also that Test 3102 has been singled out by JAERI for the in-depth data analysis we identified in (B)(1) above.

The detailed information from the two tests identified above should help us deter-mine the scope and applicability of other detailed infomation we will be request-ing in the future.

We would appreciate your early reply to this request for infomation. We are look-ing fomard to continuing our good working relationships with you and your staff.

Sincerely, V

Long S. Tong, Assistan Director of Water Reactor Saf ty Research Office of Nuclear Reg latory Research Attachments:

As stated

Attachrent 1 Table 2-2 Measurement Channels -- PCM Tr-1 a

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Channel No. Channel Code Measurement Location 1 RPPF-001 F.UPTURE DISC BREAK SIGNAL 2 BPMF-332 *AIN DISCHARGE VALVE CLOSE SIGNSL 3

4 CwrF-C01 DRYwSLL 5 VPPF-101 vF1 ( 0.5M AGCVE Oult.)

6 VPPF-?C1 VP2 ( O.5w ABCVE OUTL.) ,

7 vopF-3C1 VP3 ( 0.5w ABCVE OUTL.)

E VPPF-3v2 VP3 ( 6.0H ABOVE OUTL.)

9 VDPF-303 VP3 (11.$H ABOVE OUTL.)

10 VAPF-401 VP4 ( 0.5M ABOVE OUTL.)

11 VPPF-501 VP5 ( 0.3M AeOVE OUTL.)

12 VPPF-502 VP5 ( 6.0M ABOVE OUTL.)

13 VPPF-Sc3 VF5 (11.5M AMOVE OUTL.)

14 dePF-101 POCL SOTT.. UNDER VP1 15 =WPC-10? POOL 80TT.. UNDER VP2 1h WaPF-tv3 POOL BOTT.. UNDER VP3 17 h*PF-104 JOOL BOTI.. UNDEP Vpa le wwPf-235 PCOL BOTT.. UNDER VP5 _ , _

16 W5Pf-106 POOL 60TT.. BETW. VPl. VP6 6 PFDESTAL 20 haPF-10T FOOL ROTT.. BETW. VP2 6 VP3

?) WVPF-101 HALL SESIDE VP2 (P1 1.8M ABOVE FOT .)

22 WV FF-?C2 WALL RFS;ILE VA? (Pl. 3.69 AROVE 601T.)

. 23 wwPF-?C3 :ALL BESIDE VP2 (G1 6.0M ABG/E BOTT.)

76 Wn'PF-301 WALL BES!DE VP3 (P2 1.9M ABOVE BOTT.)

25 kWFF-iC? WALL BEsinE VD3 (P2 3.6M AROVE bOTT.)

20 hwfF-J03 =ALL bESIDE VPS (p2 6.0.d ABOVE BOTT.)

27 w w p F '. 0 1 3" ELL RFSIDE VP3 (o3 1.Rw ABOVE 60TT.)

28 VaFF-4C2 dHELL BESI')E vp3 (P3 3.ett ABOVE SOTT.)

29 kWFF-501 SHELL BESIDE VP* (P4. 1. Mt ASOVE BUTT.)

3n WWPF-$02 SHELL DE510E VP4 (P'. 3.eM ABOVE BUTT.)

31 kWPF-802 UALL SESIDE VP4 (FS. 3.6M AROVE ROTT.)

32 wwPF-70*J CALL 8EstDE VP7 (P6. 3.6M ASOVE BOTT.;

33 rwlF-001 *ETwtLL AIRSFACE (15.0M ABOVE PCTT.)

34 35 VPSF-101 LCWER PRACE 8ETh. VP1 6 *ALL 36 VPSF-102 LOWER RRACE BETW. VP1 6 VP2 1 37 VPSF-103 LOWER PR,6CE BETW. VP1 6 VP6 , l 32 VPSF-201 UPPER BH/CE 6ETW. VP1 6 PE0ESTAL 30 9

Attachment 2 Table 2-3 Measurement Channels -- PCM Tr-2

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Channel No. Channel Code Measurement Location '

1 apsp.CL1 h0P10RE DISC BRFAs SIGNAL.

? RPMF-CG2 PAIN DISCHARGE VALVF CLOSE SIGNAL 3

4 VPAF-1(.1 VP2 OUTL. ( CDEGJ 5 VPAF-2G? VP2 CUTL. (90DEG) 6 VPAF-201 VPS OUTL. ( CDEG) 7 VPAF-202 VP5 OUTL. (90DEG) 8 wwAF-001 POOL ROT 1. . UNDER VP5 9 W'.4AF-CG2 FOOL BOTT.. BETW. VP2. VP3. \PA L VP7 10 VAAF-033 WALL BESIDE VP2 (3.0:d ABOVE BOTT.)

11 WWAF-004 .ALL BEstat vp7 (3.0M ABOVE BOTT.)

12 wwsF-q09 SnELL RES!DE VP3 (3.0M ABOVE BOTT . ) .

13 ewAF-000 GHELL BE51DE VP3 (6.uM AB0VE BOTT .)

14 WVAF-UU7 bHELL BESIDE VP4 (3.0M ABOVE BOTT . )

3S wWAF-00F dHELL BEi!DE VP4 (6.0M ABOVE BOTT . )

16 ww A r -(.(39 DE0ESTAL (3.cM ABOVE BOTT.)

17 wwAr-010 PEDESTAL (6.0M ASOVE bOTT.)

16 kWAF-011 SHFLL AT DF LEVEL ( ODEG) 14 kWAF-012 dhFLL AT DF LEVEL (900EG) 20 1 21 WWLF-101 PilASE EDRY. (0.9M BELOW OUTL., CENTER) 11 u.LF-1Li

. FhASE FORV. (C.7M RELOW GUTL.. ODEG)

90CEG)

( .3 VWLF-2v4 FHASL BDPY. (C.CM BELCW OUTL..

' 24 WLLF-iCf PHA5L RDRY. (0.9M BELOW OUTL., 180DFG) ^

25 WWLF-106 PHASE FDRY. (0.9t' BELOW OUTL. 270DEG) 26 wkLF-20.9 FHASE PDPY. (0.6F BELOw OUTL..'CENTEP) 27 Wa'LF-203 FHASE BDhY. CO.6M DELLW OUTL.. 45DE3) 28 kWLF-?.Ut PFASE RDRY. (0.AM BELOW OUTL., 13.5DEG) 29 WWLF-207 PHASE RDRY. (0.6M BELOW OUTL., 225DEG) 30 WWLF-204 PHASE ADRY. (0.6M RELOW OUTL.. 3150EG) 31 hWLF-301 PWAsi BDRY. (C.3h BELOW OUTL.. CENTER) _

37 WW . F-332 PHASE BDRY. (0.3M BELOW OUTL.. ODE 3) 33 wwLF-304 FHASE SDdY. (0.3M BELOW OUTL.. 90DFG) 34 kwtF-306 PHASE RD9Y. (0.3M BELOW_OUTL.. 1800EG) 35 WdLF-3 'J e PHASE BDRY. (0.3M RELCW OUTL.. 2790EG).

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p ,o INSTITUT FOR ANLAGENTECHNIK DER GESELLSCHAFT FOR KERNENERGIEVERWERTUNG T IN SCHIFFBAU UND SCHIFFAHRT MBH.'  %.

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r GKSS Institut far Anlagenteenik ~l Postfam 1160, 2054 Geesthaet.Tesperhude Dr. E.W. McCauley Nuclear Containment Safety Research

- Nuclear Test Engineering Division Lawrence Livermore Laboratory University of California P.O. Box 808 t Livermore, ca. 94550, U.S.A.  ;

ine zei$en mre Na&riet Bearboner Hausapparat Geestnset. 3.12.1979 Herr Aust i2 m 549 AR/Au/Ha

Dear Dr. McCauley,

enclosed please find the following information material about our pressure suppression test program:

preprint of the test report No. 23 11 AR E 03 for test VM 3, plots of test M2 for time correlation (time signal of high speed camera and pressure signal of W-PA 42),

plots of test MI,

- channel table of the PCM channels for test VM i recorded on mag. tapes LLL VI A and LLL VI B,

- mag. tapes LLL VI A and LLL VI B; the tapes are produced by BAND PS and they are not transformed by TRABCD.

~ We hope, you will be successful in reading the PCM-data.

We told you about our difficulties in getting the pressure transducers and cables from the Dutch producer. You kindly offered to ask the manufactures in California about the possibility and terms of delivery such transducers. Here are the type of transducers we need: STATHAM PA 856-100 with plug DC 13 and integrated PTFE-cable of about 10 meters.

The results of the KWU-research on pressure suppression system in small scaled concret cells, you are interested in, are published in the report:

AbschluBbericht: F6rderungsvorhaben BMFT RS 78 E Kennwort: Kondensation V, Teil II

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Betonzellenversuche e RE 23/016/78, Juli 78 [-Q We hope you will get this report via U.S.NRC - GRS/FB.

4 Encl.

,\ Sincerely, cc: Mr. Cudlin, NRC

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t Dr. Baumgurtel,GRS (Dr. Schulth iB) (Seeliger)'

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