ML20140G499
| ML20140G499 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 05/09/1997 |
| From: | Huffman W NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9706160305 | |
| Download: ML20140G499 (13) | |
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NUCLEAR REGULATORY COMMISSION k.....[2 WASHINGTON, D.C. 20666-0001 May 9, 1997 Mr. Nicholas J. Liparulo, Kanager Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230
SUBJECT:
DATA TO SUPPORT AP600 PASSIVE RESIDUAL HEAT REMOVAL (PRHR) HEAT EXCHANGER HEAT TRANSFER CORRELATIONS ANALYSES
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Dear Mr. Liparulo:
l In a Nuclear Regulatory Commission (NRC) letter to Westinghouse dated February 19, 1997, the staff requested that Westinghouse compare the AP600 PRHR heat exchanger heat transfer correlation with experimental data from a "C" tube heat exchanger design to confirm the validity of the analytical
)
models.
In our letter, the staff offered Westinghouse data from the ROSA test i
facility as a potential source of data which may contain sufficient informa-tion to permit confirmation of the PRHR heat transfer correlation.
Based on review of technical literati.re, Westinghouse states that data are not i
available in the public domain' for a "C" tube heat exchanger design at thernal conditions for comparison to the AP600 PRHR heat exchanger. Consequently, Westinghouse letter dated April 15, 1997, requests that the staff provide PRHR data from two ROSA tests (AP-BO-01 station blackout and AP-CL-041/2 inch cold leg break) to support the PRHR additional heat transfer analysis.
The staff has obtained data from the two ROSA tests cited above which it believes Westinghouse can use to predict the performance of the ROSA PRHR heat exchanger.
Specifically, the staff has extracted representative data for mass flow, primary pressure, inlet temperature, and in-containment refueling water storage tank temperatures during stable PRHR operational periods for the 80-01 and CL-04 ROSA tests (Enclosure 1). Westinghouse is requested to predict the PRHR outlet temperature and primary system temperature for various locations along the ROSA "C" tubes based on the heat transfer correlation it is using for the PRHR design basis (Enclosure 2). The results will be compared with actual data from the ROSA test (which will not be provided to Westinghouse) as part of the staff's safety evaluation of the PRHR performance modeling.
You have requested that portions of the information submitted in the June 1992 h) p application for design certification be exempt from mandatory public disclo-sure. While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.790, that portion of the submit-I ted information is being withheld from public disclosure 'pending the staff's g
final determination. The staff concludes that the enclosed information do not I
contain those portions of the information for which exemption is sought.
However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westinghouse the 9706160305 970509 ADOCK0520g3 gg hy PDR i
Mr. Nicholas J. Liparulo May 9, 1997 opportunity to verify the staff's conclusions.
17, after that time, you do not request that all or portions of the information in the enclosures be withheld from public disclosure in accordance with 10 CFR 2.790, this letter will be placed in the NRC Public Document Room.
If you have any questions regarding this matter, you can contact me at (301) 415-1141.
Sincerely, original signed by:
William C. Huffman, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003
Enclosures:
As stated cc w/ enclosures:
See next page I
DESTRIBUTION:
- Enclosure to be held for 30 days
(? Docket: File-PDST R/F MSlosson PUBl.IC SWeiss TRQuay TKenyon BHuffman JSebrosky DJackson JMoore, 0-15 B18 WDean, 0-17 G21 l
ACRS (11)
TMartin, 0-12 G18 JLyons, 0-8 E23 GHolahan, 0-8 E2 FEltawila, T-10 E46 WHodges, 0-10 E37 DHassell, 0-15 818 Alevin, 0-8 E23 i
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DOCUMENT NAME: A: DATA-ROS.A T3 shesive a copy of this document,inacate in the box: "C" = Copy without attachment / enclosure
- E' s Copy with attachment /ent,losure
'N' = No copy 0FFICE PM:PbST:DRPM SC:SRX,8;DSSA l D:PDST:DRPM l
NAME WCHuffman:(g b WAlev F M TRQuay112ty DATE 05/tr/97
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05/ 9/97 0FFICIAL RECORD COPY
Q Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600 cc: Mr. B. A. McIntyre Ms. Cindy L. Haag Advanced Plant Safety & Licensing Advanced Plant Safety & Licensing Westinghouse Electric Corporation Westinghouse Electric Corporation Energy Systems Business Unit Energy Systems Business Unit P.O. Box 355 Box 355 Pittsburgh, PA 15230 Pittsburgh, PA 15230 Mr. M. D. Beaumont Mr. S. M. Modro
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Nuclear and Advanced Technology Division Nuclear Systems Analysis Technologies Westinghouse Electric Corporation Lockheed Idaho Technologies Company One Montrose Metro Post Office Box 1625 11921 Rockville Pike Idaho Falls, ID 83415 Suite 350 Rockville, MD 20852 Enclosure to be distributed to the following addressees after the result of the proprietary evaluation is received from Westinghouse:
Mr. Ronald Simard, Director Ms. Lynn Connor Advanced Reactor Programs DOC-Search Associates Nuclear Energy Institute Post Office Box 34 1776 Eye Street, N.W.
Cabin John, MD 20818 Suite 300 Washington, DC 20006-3706 Mr. Robert H. Buchholz GE Nuclear Energy Mr. James E. Quinn, Projects Manager 175 Curtner Avenue, MC-781 LMR and'SBWR Programs San Jose, CA 95125 i
GE Nuclear Energy 175 Curtner Avenue, M/C 165 Mr. Sterling Franks San Jose, CA 95125 U.S. Department of Energy NE-50 Barton Z. Cowan, Esq.
19901 Germantown Road Eckert Seamans Cherin & Mellott Germantown, MD 20874 600 Grant Street 42nd Floor Pittsburgh, PA 15219 Mr. Charles Thompson, Nuclear Engineer AP600 Certification Mr. Frank A. Ross NE-50 U.S. Department of Energy, NE-42 19901 Germantown Road Office of LWR Safety and Technology Germantown, MD 20874 19901 Germantown Road Germantown, MD 20874 l
Mr. Ed Rodwell, Manager PWR Design Certification Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94303 l
i l
l Test BO-01 9 15,000 s
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348.7 K 8.533 m l
1 l
361.0 K 7.314 m i
359.9 K 6.095 m i
j 357.6 K 4.876 m 342.4 K 3.657 m I
326.5 K 2.438 m l
324.5 K 1.219 m l
Bottom of tank Inlet flow:
1.38 kg/s Inlet temperature: 444.9 K Pressure:
5.4 MPa l
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t Test B0-01 9 19,000 s 364.2 K 8.533 m i
370.5 K 7.314 m 3'70.7 K 6.095 m 369.9 K 4.876 m 364.7 K 3.657 m
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337.0 K_
2.438 m 335.2 K 1.219 m Bottom of tank l
Inlet flow:
1.34 kg/s l
Inlet temperature: 445.6 K Pressure:
4.8 MPa l
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k l
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Test 80-01 9 30,000 s 374.8 K 8.533 m j
376.0 K 7.314 m 376.6 K 6.095 m 376.6 K 4.876 m 375.4 K 3.657 m 360.4 K 2.438 m 358.4 K 1.219 m Bottom of tank Inlet flow:
1.27 kg/s Inlet temperature: 445.8 K Pressure: 3.2 MPa
.=..
I Test B0-01 9 45,000 s I
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374.8 K 8.533 m 375.1 K 7.314 m 375.9 K 6.095 m i
376.0 K 4.876 m 375.6 K 3.657 m 374.5 K 2.438 m 373.8 K 1.219 m Bottom of tank Inlet flow:
1.23 kg/s Inlet temperature: 447.5 K Pressure:
2.3 MPa 1
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Test 80-01 9 49,000 s i
374.3 K
! 8.533 m i
375.1 K 7.314 m 375.7 K 6.095 m 1
375.3 K 4.876 m 375.3 K 3.657 m 1
374.4 K 2.438 m 374.2 K l.219 m Bottom of tank Inlet flow:
1.23 kg/s Inlet temperature: 448.0 K Pressure: 2.1 MPa
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l Test CL-04 9 2,000 s i
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l 326.1 K 8.533 m s
361.0 K 7.314 m 4
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333.2 K 6.095 m l
311.9 K 4.876 m 306.2 K 3.657 m l
l 301.8 K 2.438 m 298.8 K 1.219 m Bottom of tank l
Inlet flow:
2.14 kg/s Inlet temperature:
537.9 K l
Pressure: 8.2 MPa i
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Test CL-04 9 8,000 s l
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374.3 K 8.533 m 374.5 K 7.314 m 374.7 K 6.095 m 373.4 K 4.876 m 330.3 K 3.567 m 326.9 K 2.438 m i
325.4 K 1.219 m Bottom of tank Inlet flow:
1.55 kg/s In1Et temperature: 459.; K Pressure:
3.6 MPa
... -... ~.
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l Test CL-04 9 14,000 s l
374.3 K 8.533 m l
374.9 K 7.314 m 374.8 K 6.095 m l
l 374.7 K 4.876 m 375.0 K 3.657 m 346.9 K 2.438 m i
1 344.4 K 1.219 m Bottom of tank l
Inlet flow:
1.41 kg/s Inlet temperature:
447.0 K Pressure:
2.4 MPa L
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l Additional Information on the Test conditions l
1)
System pressures are absolute.
l 2)
The flow represents the flow through all ROSA heat excha'nger tubes for both tests.
l 3)
The initial IRWST water level for AP-B0-01 was 8.20 m.
At 22,000 s i
seconds, the water level began to decrease to a final level of 8.00 m at 49,000 s due to boil-off.
The IRWST water level for AP-CL-04 was relatively constant at 7.48 m 4) throughout the data range provided.
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Westinghouse is requested to predict the follow:ng information based on the heat transfer correlation it is using for its AF600 design basis calculations.
l AP-BO-01 Time 15,000 s 19,000 s 30,000 s 45,000 s 49,000 s PRHR Outlet Temp Primary Temperature at 1.52 meters l
Primary Temperature l
at 3.52 meters Primary Temperature at 6.20 meters AP-CL-04 Time 2000 S 8000 S 14.000 S PRHR Outlet Temp Primary Temperature 4
i at 1.52 meters Primary Temperature at 3.52 meters Primary Temperature at 6.20 meters Westinghouse should predict the primary fluid temperatures for an average middle tube as measured along the length of the tube starting from the inside tank wall to points at 1.52 m, 3.52 m, and at 6.20 m along t.he length of the tube.
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