ML20217K671
| ML20217K671 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 08/13/1997 |
| From: | Quay T NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9708180040 | |
| Download: ML20217K671 (3) | |
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l August 13,.1997 Mr. Nicholas 'J. Liparulo, Manager Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology _ Division Westinghouse Electric Corporation P.O. Box 355 l
Pittsburgh, PA 15230
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO VALIDATION OF THE NOTRUMP SMALL BREAK LOCA CODE FOR AP600
Dear Mr. Liparulo:
In support of the AP600-design certification review, the Nuclear Regulatory Commission (NRC) staff is evaluating the use of the NOTRUMP small break loss-of-coolant-accident (LOCA) analysis computer code for assessing the perfor-mance of the AP600. On July 29 and 30, 1997, Westinghouse presented an overview of the AP600 NOTRUMP code verification and validation effort before the Thermal-Hydraulic Subcommittee of the Advisory Committee on Reactor
. Safeguards (ACRS),
Based on discussicas and concerns rairs.d during the meeting, additional information is needed by the staff to complete its review.
The required information is included as an enclosure to this letter.
'If you have any questions regarding this matter, you can contact Bill Huffman at (301) 415-1141.
Sincerely, original signed by:
Theodore R. Quay, Director Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003
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Enclosure:
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Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600 cc: Mr. B. A. McIntyre Mr. Ronald Simard, Director Advanced Plant Safety & Licensing Advanced Reactor Programs Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit 1776 Eye Street, N.W.
P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006-3706 Ms. Cindy L. Haag Ms. Lynn Connor Advanced Plant Safety & Licensing Doc-Search Associates Westinghouse Electric Corporation Post Office Box 34 Energy Systems Business Unit Cabin John, MD 20818 Box 355 Pittsburgh, PA 15230 Mr. James E. Quinn, Projects Manager LMR and SBWR Programs Mr. M. D. Beaumont GE Nuclear Energy Nuclear and Advanced Technology Division 175 Curtner Avenue, M/C 165 Westinghouse Electric Corporation San Jose, CA 95125 One Montrose Metro 11921 Rockville Pike Mr. Robert H. Buchholz Suite 350 GE Nuclear Energy Rockville, MD 20852 175 Curtner Avenue, MC-781 San Jose, CA 95125 Mr. Sterling Franks U.S. Department of Energy Barton Z. Cowan, Esq.
NE-50 Eckert Seamans Cherin & Mellott 19901 Germantown Road 600 Grant Street 42nd Floor Germantown, MD 20874 Pittsburgh, PA 15219 Mr. S. M. Modro Mr. Ed Rodwell, Manager Nuclear-Systems Analysis Technologies PWR Design Certification Lockheed Idaho Technologies Company Electric Power Research Institute Post Office Box 1625 3412 Hillview Avenue Idaho Falls, ID 83415 Palo Alto, CA 94303 Mr. Frank A. Ross Mr. Charles Thompson, Nuclear Engineer U.S. Department of Energy, NE-42 AP600 Certification Office of LWR Safety and Technology NE-50 19901 Germantown Road 19901 Germantown Road Germantown, MD 20874 Germantown, MD 20874 v
REQUEST FOR AD0!TIONAL INFORMATION RELATED TO AP600
.NOTRUMP VERIFICATION AND VALIDATION l
440.721 Based on. issues raised during the July 29-30, 1997-ACRS Thermal-Hydraulic Subcommittee meeting with Westinghouse:and the staff on V&V of the; NOTRUMP computer code _ for_ AP600, the _NRC staff needs the following information clarified and documented-in the AP600 NOTRUMP Final Verifica-tion and Validation Report (WCAP-14807):
(a)-
Provide. additional explanation and significance of the consistent delay in NOTRUMP predicted commencement of CMT draining when compared to testing data.- What is the significance of NOTRUMP's lac ( of a flashing model in failing to accurately predict start of CMT drain-down.
(b)
Provide additional justification why adverse effects from non-condensable gases are not a concern for AP600 NOTRUMP small break LOCA calculations. Explain where the non-condensable gases end up and why assemptions made for NOTRUMP calculat41s are conservative. -
(c)
Provide a thorough explanation regarding NOTRUMP's misprediction of mass flow out of the ADS stage 1, 2, and 3 valves in the OSU experiments (and related pressurizer refill).
Improve the justifi-cation as to why this deficiency is-acceptable.
(d)
Provide an explanation for NOTRUMP's mispredictions when compared to the OSU test results of DVI line breaks.
(e)
Explain the significance and justify the bases for any differences in the Nodalization between the two integral test facilities (OSU and SPES) and the AP600.
(f)
Provide more details on NOTRUMP's misprediction of pressurizer drainage in the OSU tests.- Thoroughly explain the significance of this deficiency in the code,-such as-non-conservatively predicting IRWST flow, and how it will be treated in performing AP600 calcula-tions.
(g)
Related to (f) above, Westinghouse is proposing to apply a penalty in IRWST level.
Provide a detailed explanation of how the penalty is. determined via scaling from the OSU test data to the AP600.
Justify why this -is conservative.
(h)
Provide detailed justification-for not including momentum flux in the NOTRUMP models.
(i)-
Provide discussion on how NOTRUMP treats entrainment (waterspout)-
in branch lines.
(j)
- Justify and demonstrate why use' of. Henry.auske/ HEM rather than Moody is: conservative-for calculating break flow through the ADS stage 1,: 2, and 3 valves and why this is appropriate for an appen-dix K type calculation.
Enclosure
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