ML20029C373
| ML20029C373 | |
| Person / Time | |
|---|---|
| Issue date: | 03/13/1991 |
| From: | Donatell L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| PROJECT-676A NUDOCS 9103270234 | |
| Download: ML20029C373 (6) | |
Text
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NUCLEAR REGULATOFiY COMMISSION
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March 13, 1991 g
Project No. 616 FACILITY:
AP-600 APPLICANT:
WESTINCHOUSE ELECTRIC CORPORATION SUBJLCT:
SUMMARY
OF MEETING WITH WESTINGHOUSE ELECTRIC CORPORATION On March 5 and 6 representatives of the Office of Nuclear Regulatory Pesearch and the Office of Nuclear Reactor Regulation were at the Westinghouse Electric Corporation offices in Monroeville, Pa. to discuss the current status of systems analysis and testing used for the AP-600 design.
Enclosed is a list of atten-dees.
The main focus of the neeting was for Westinghouse to update the staff on their testing program in support of the AP-600 design. Some of the test facilities have been designed and built, on others construction is uncerway at this time.
The following tests were highlighted during the meeting:
1.
Automatic Depressurization System (ADS) test to simulate operation of the ADS in a steam / water test loop to confirm valve and sparger operability and deti.rmine the dynamic effects on the In-containment RefuelingWaterStorageTonk(IRWST). The test loop has been designed and a test matrix has been developed.
2.
Core Makeup Tank (Ci1T) test to verify the gray 1ty drain behavior of the CMT and the operation of the tank level instrumentation.
The test loop has been designed and a test matrix has been developed.
3.
Check valve testing to denionstrate the capability of the passive safety injection check valves to open under low differential pressure conditions. The test loop has been designed and is under construction.
4.
A long term cooling test will result in a scale model to provide demon-stration and data for this mode of cperation.
The facility is being designed and scaled at tiiis time with construction completion expected in mid-1992. The podel will include the RV, SGs, loop piping, CMTs, accumulators, IRWST and the pressurizer. Additionally, some thought may be given to including the PRHR heat exchanger to further expand this test facility.
5.
A Departure from Nucleate Boiling (DNB) test may be performed to extend the lower flow limit of the DNB correlation if necessary 9
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. March 13, 1991 6.
A reactor titernals test will include the construction of a 1/7 height scale reactor vessel to verify the hydraulic cnd vibration charactetis-tics of the vessel and internals.
The testing would include specific design features that differ from previous designs.
The test loop and RV model are under construction with testing expected in the first half of 1991.
7.
The reactor coo 16nt pumps are being tested for flow performance and mechanical performance. Air tests for flow perf ormance are in progress with water tests to sto t in 1993. Mechanical performance has been tested, the analysis of the results is being performed. Design changes and retests will be planned when the data analysis is complete.
8.
The Passive Residual Heat Removal heat exchangtr testing that has been conducted thus for has identified the mixing patterns expected in the IRWST, the dominant heat tronsfer iegimes and has led to the develop-mcot of a design heat transfer correlation.
The tests noted above are in addition to containr:ent perfornece tests which were the subject of a previous meeting.
The r4eeting handouts are held as proprietary to Westinghouse and, as such, Westinghouse has requested that the staf f treat the handouts appropriutt.ly.
Recuests for copies of the n,aterial provided should be dirteted to me at (301)492-1141.
A 4'
Loren F. Donatell, Project Manager Standardization Projtct Directorate Division of Advanced Reactors and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next pge
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March 13, 1991 6.
A reactor internals test will include the construction of a 1/7 height scale reactor vessel to verify the hydraulic and vibr6 tion chorecteris.
tics of the vessel and internals.
The testing would include specific design features that dif fer from previous designs.
The test loop and RV model are under construction with testing cxpected in the first half of 1991.
7.
The reactor coolant puraps are being tested for flow perforhance and mechanicel performance. Air tests for flow performance are in progress with water tests to start in 1993. Mechanical performance hos been tested, the analysis of the results is being performeo. Design thenges and rett.sts will te planned when the data analysis is co!tplete.
8.
The Passive Residual licot Eersiovel heat exchanger testing that has been conducted thus far hat, icientified the mixing patterns expected in the IRW51, the dominant heat transfer regimes and has led to the develop.
meht of a design teot transf er corre16ticn.
The tests noted above ere in addition to containment perf ormance tests which were the subject of a previous meeting.
The roeeting hondouts are held as propriethry to Westinghouse and, as such, Westinghouse has requested that the staff treat the hendouts appropriately.
Requests for copies of the material provided should be directed to me at (301) 492 1141.
original signed by Lo:en F. Donatell, Froject Manager Standardization Project Directorate Division of Advanced Reactors and SKcial Projects Office of Huclear Reactor Regulction
Enclosure:
As stated cc w/ enclosure:
See next page UTC
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NAME:PShea[ :LDona 4: r:CMiller 4
DATE :03/\\ /91
- 03/13 /91
- 03/g/91 0FFICIAL RECORD COPY Docurent Name: MTG
SUMMARY
ANiTG3
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Project No. 676 Westinghouse Electric Corporation AP-600 cc: Mr. S. Tritch Nuclear Safety Departr.ent Westinghouse Electric Corporation Water Reactor Division Box 355 Pittsburgh, Pennsylvania 1E230 Mr. B. A. McIntyre Advanced Plant Safety and Licensing Vestinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania 15230 Hs, R. K. Beck Advanced Plant Safety and Licensir.g Westinghou3e Electric Corporation Energy Systems Busit: css Unit Boy 355 Pittsburgh, Pennsylvania 15230 Mr. M. D. Beaumont Nuclear Technology Systems Division Westinghouse Electric Corporation One Montrose Metro 11921 Rnckville Pike Suite 350 Rockville, Marylend 20852 Mr. Daniel F. Giessing U.5, Department of Energy Nf-42 Washington, D.C.
20585 Mr. S. M. Hodro EG&G Idahc Inc.
P. O. Box 16?S Idaho Falls, Idaho 83415
Et!CEOSURE WESTINtHOUSE/MRC AP600.$Y5TEMS MEETING MARCH 5. 1991 HMI ORGANIZATION l
I Brian A. McIntyre AP600 Licensing Alan Levin NRC/NRR/OST/SRXB John Miller EG&G Idaho S. Michael Modro INEL EG&G Idaho Louis Shotkin NRC/RES Brian Sheron NRC/RES Ralph Caruso-NRC/NRR/ DST Mark Rubin NRC/NRR/ DST Bob Youngblood Brookhaven National Lab Heryudo Kusumo AP600 Support Augustine Cheung W N.S. Transient Robert Kemper-W N.S. LOCA L'. E. Hochreiter W Nuc' lear Safety T. L. Schulz W AP600 Design M. M. Corletti W AP600 Design R. K. Beck W AP600 Licensing Eugene J. Piplica W AP600 Test Engineering Jorge Alba W Mgr., AP600 Test Eng.
Susan V. Fanto W AP600 Test Engineering Larry Conway W AP600 Test Engineering Chuck Brockhoff W AP600 Design l
Terry Schulz W AP600 Design Ron Vijuk W AP600 Engineering Loren F. Donate 11 NRC/NRR/DAR/PDST 1
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