ML20127B277
| ML20127B277 | |
| Person / Time | |
|---|---|
| Site: | 05200004 |
| Issue date: | 01/11/1993 |
| From: | Stancavage P GENERAL ELECTRIC CO. |
| To: | Pierson R NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| MFN-005-93, MFN-5-93, NUDOCS 9301120225 | |
| Download: ML20127B277 (7) | |
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January 11,1993 MFN No,005 93 Docket STN 52 004 Document Control Desk
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U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attentior.:
Robert C. Pierson, Director Standardization and Non Power alcactor Project Directorate
Subject:
Intnrmation Requested during the December 17,1992 Meeting on the SilWR Testing Program
Dear Mr. Pierson:
During the subject meeting, the Staff asked GE to provide additionalinformation concerning the GIRAFFE, PANTilERS, PANDA, and MIT/UCl3 testing programs. The encloseJ information follows the format suggesed by the Staff during the meeting. This information wi!! clarify the on going and completed tests that have been discussed over the past months. GE suggests that a meeting be held in San Jose on January 28,1993, to discuss the content of the enclosure.
Sincerel r > h",
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P.P. Stancavage, eting Manager Safety & Licensing M/C 444, (408) 925-6948 Enclosure 120011.
1TRBK9M4 040 9301120225 '730111 g)
SBWR Test Programs University Condensation Tests 1.
Purpose:
The MIT and UCB test programs were initiated in order to develop a heat transfer correlation for steam condensation that can be used in the TRACG analysis of the SBWR IC and PCCS condensers. The effective heat transfer in the condensors is dependent on both shear enhancement and noncondensable gas effects. Previously published studies in this area have considered the effects of noncondensable gases, but they have mainly dealt with external surfaces and report only average heat transfer coefficients. The present studies provide the local heat transfer coefficient for steam condensation inside of tubes. The noncondensables considered are air and helium representing, respectively, nitrogen and hydrogen in the SBWR contalnment.
A correlation based on the completed test data has been incorporated in TRACG. Additional tests to be conducted this year will provide confirmation of previous results.
2.
Scaling Analysis:
All tests used essentially full length tubes. The Reference 1 experiments used a 1" diameter tube. All others have used 2" diameter tubes, which are prototypical of SBWR condenser tubes. Additional details are given in Reference 2.
3.
Test instrumentation:
This is discussed in References 1 through 4.
4.
Test Matrix:
Details are given in References 2 through 5.
5.
Test Schedule:
Testing in support of the SSAR are complete. Additional confirmatory testing is scheduled for completion by September 1993.
6.
Post-test Analysis:
References 1 through 6 provide the post test analysis of data used in the SSAR analysis. An additional test report documenting the ongoing testing will be prmided in November 1993.
7.
NRC Site Visit:
It is recommended that the NRC staff visit to the two test sites be the week of March 22,1993 for the University of Calif, at Berkeley and the week of April 19,.
1993 for MIT.
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SBWR Test Programs University Condensation Tests (cont.)
References:
1.
Karen Vierow and Virgil Schrock,
- Condensation in a Natural Circulation Loop with Noncondensable Ganes, Parts I and 11", Proceedings of the International Conference on 1/uttiphase Flows, Tsukuba, Japan, September 1991.
2.
Karen Vierow," Behavior of Steam Air Systems Condensing in Cocurrent Vertical Downflow", M.S. Thesis, U.C. Berkeley Dept. of Nuclear Engineering, August 1990.
3.
Mansoor Siddique, "The Effects of Noncondensable Gases on Steam Condensation under Forced Convection Conditions", Doctor of Philosophy Dissertation, Massachutietts Institute of Technology, January 1992.
4.
Daniel Ogg, " Vertical Downflow Condensation Heat Transfer in Gas-Steam Mixtures", M.S. Thesis, U.C. Berkeley Dept. of Nuclear Engineering, December 1991.
5.
M. Golay, " Steam Condensation Measurements at MIT", provided by J.
Baechler to the U.S. NRC.
6.
J. Kuhn, V.E. Schrock, P.F. Pr,erson, " Status of UCB Condensation Experiment", provided by J. Daechter to the U.S. NRC.
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l SBWR Test Programs GIRAFFE 1.
Purpose:
The objectives of the GIRAFFE testing program are to provide separate effects and integral test data for qualification of TRACG, the computer code which will be used for analysis of the SBWR containment. The separate effects tests address the issues of steam condensation heat transfer rates from a steam-nitrogen mixture under steady state. conditions, and of venting of noncondensable gases from scaled down passive containment heat exchangers (PCC's) to the suppression pool. The integral tests demonstrate the concept of the PCC System and provide data for a variety of LOCA simulations, against which analytical models for the containment may be qualified.
2.
Scaling Analysis:
Details are provided in References 1,2 and 3.
3.
Test Instrumentation:
A description is given in References 1,2 and 3.
4.
Test Matrix:
Data from the separate effects condensation tests were obtained at a total pressure of 0.3 MPa, for steam flow rates of 0.01 to 0.04 kg/s and nitrogen partial pressures of 0.0 to 0.03 MPa The initial conditions for the noncondensable venting and long term integral tests corresponded to those at.
one hour after LOCA occurrence. For the venting study, the nitrogen vent line of the scaled down heat exchanger was submerged by 0.40m,0.65m, and 0.90m.
The main steam line break, GDCS line break and bottom drain line break LOCAs were simulated during the long term system response tests.
Additional details are given in References 1,2 and 3.
S.
Test Schedule:
Testing has been completed.......
SBWR Test Programs GlRAFFE (cont) 6.
Post-test Analysis:
A complete qualification of the TRACG computer code is given in Reference 6.
Additional analyses are presented in References 1,4 and 5. In May,1993, a report presenting the results of testing completed in late 1992, specifically the Gravity-Driven Cooling System and Bottom Drain line break integral tests, will be supplied to the NRC.
7.
NRC Site Visit:
A recommendation regarding tN da',e for a site visit will be made by the end of this month. GE needs to cWn ciailability with Toshiba.
References:
1.
" Joint Study Report, Feature Technology of Simplified BWR (Phase-1)",
Final Report,1990.
2.
Nagasaka, H., K. Yamada, M. Katoh, S. Yokobori, " Heat Removal Tests of isolation Condenser Applied as a Passive Containment Cooling System", from transactions of International Conference on Nuclear Engineering - 1, Tokyo, Japan, Nov.,1992, pp. 257-263.
3.
Yokobori, S., H. Nagasaka, T. Tobimatsu, " System Response Test of Isolation Condenser Applied as a Passive Containment Cooling System", from transactions of International Conference on Nuclear Engineering - 1, Tokyo, Japan, Nov.,1992, pp. 265 271.
4.
Oikawa, P., K. Aral, H. Nagasaka," Optimization Study on SBWR lsolation Condenser Heat Removal Performance", from transactions of International Conference on Nuclear Engineering - 1 Tokyo, Japan, Nov.,1992, pp. 273 279.
5.
Arai, K., H. Nagasaka, " Analytical Study on Drywell Cooler Heat Removal Performance as a Passive Containment Cooling System", from transactions of International Conference on Nuclear Engineering - 1, Tokyo, Japan, Nov.,1992, pp. 281287.
6.
Andersen, J. G. M., et. al, "TRACG02 Oualification Licensing Topical Report", (scheduled publication in February,1993). '
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SBWR Test Programs PANTHERS TEST 1.
Purpose:
The major objective of these tests is to confirm, for the Passive Containment Cooling (PCC) condenser, the thermal hydraulic performance for the SBWR service conditions. See reference document Par. 3.2 for more details.
2.
Scaling Analysis:
This is a test of full scale prototype of the condenser, therefore no scaling analysis is necessary.
3.
Test Instrumentation:
See reference document, Par. 4.1.4.
4.
Test Matrix:
See reference document, Par. 5.2 and Appendix A.
5.
Test Schedule:
The test schedule is currently under revision, and the new schedule will be available by the end of this month. The PCC shakedown testing will occur during the second half of this year. Matrix testing will start approximately one month later.
6.
Post test Analysis:
A report describing PCC confirmatory test results will be completed during the first quarter of 1994.
7.
NRC Site Visit:
It is recommended that the NRC visits to the PANTHERS test site be:
(1) during the May/ June 1993 time frame for review of the test matrix and (2) approximately November / December 1993 to witness the PCC tests.
Reference:
" Isolation Condenser & Passive Containment Condenser Test Requirements",
GE NE Document No. 23A6999, Rev.1,11/12/91.
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SBWR Test Proarams PANDA TESTS 1
1.
Purpose:
The overall objectives of these tests are to demonstrate that the containment long term cooling performance is the same in a large scale system as previously demonstrated at a smaller scale (GIRAFFE) and that with non-uniform drywell conditions, no significant adverse effects are introduced on the performance of the Passive Containment Cooling System (PCCS).
2.
Scaling Analysis:
See reference document.
3.
Test instrumentation:
See attached material taken from Draft TM 4218, ALPHA 213.
4.
Test Matrix:
Two main steamline (MSL) break tests will be performed. The first test will duplicate the initial conditions of the GIRAFFE MSL bronk test with uniform drywell conditions and the second will be the same except with non uniform conditions in the drywell.
F.
Test Schedule:
The testing will be performed in the first half of 1994.
6.
Post-test Analysis:
A test report is expected to be available by mid 1994.
7.
NRC Site Visit:
It is recommended that the next NRC visit to the PANDA test site be during the May/ June 1993 period to review test procedures and planned data analysis.
Reference:
Coddington, P., " ALPHA - The Long Term Passive Decay heat Removal and Aerosol Retention Programme" (previously given to NRC).
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