ML20197F906
| ML20197F906 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 12/18/1997 |
| From: | Huffman W NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9712300321 | |
| Download: ML20197F906 (4) | |
Text
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December 18, 1997 e
Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghoust Electric Corporation
' P.O. Box 355 Pittsburgh, PA 15230
SUBJECT:
ADDITIONAL CPEN ITEMS ASSOCIATED WITH THE AP600 SAFETY EVALUA.
TlON REPORT (SER) ON THE REACTOR SYSTEMS TEST PROGRAM
Dear Mr. Liparulo:
)
On December g and 10,1997,it U.S. Nuclear Regulatory Commission (NRC) Advisory CommK:ee on Reactor Safeguards (ACRS) Subcommittee on Thermal Hydraulic Phenomena r,:st with Westinghouse and NRC staff reviewing the AP600 reactor systems test program and analyses. Based on discussions and concems raised dur'.ng the meeting, the staff has revised its draft SER on the AP600 reactor systems test program to include several additional open items which were not previously addressed. These open items are designated as FSER open items and have been enclosed with this letter, if you have any questions regarding this matter, you may contact me at (301) 4151141.
Sincerely, original signed by:
/
William C. Huffman. Project Manager j</
Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation
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Docket No. 52 003 HQp rg[ 951f?p?? gg
Enclosure:
As stated MN IE!
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12/li/97 OFFICIAL RECORD COPY 9712300321 971218 PDR ADOCK 05200003 E
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l Mr. Nicholas J. Uparulo Docket No. 52 003 Westinghouse Electric Corporation AP600 i
cc:
Mr. B. A. McIntyre Mr. Russ Bell Advanced Plant Safety & Lloonsing Senior Project Manager, Programs i
Westinghouse Electric Corporation Nuclear Energy instnute Energy Systems Business Unit 1776 l Street, NW P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006 3700 Ms. Cindy L Haag Ms. Lynn Connor Advanced Plant Safety & Ucensing Doc-Search Associates Westinghouse Electric Corporation Post Office Box 34 Energy Systems Business Unit Cabin John, MD 20818 Box 355 Pittsburgh, PA 15230 Dr. Craig D. Sawyer, Manager Advanced Reactor Programs Mr. Storiing Franks GE Nuclear Energy U.S. Department of Energy 175 Curtner Avenue, MC-754 NE 50 San Jose, CA 95125 19901 Germantown Road Germantown, MD 20874 Mr. Robert H. Buchholz GE Nuclear Energy Mr. Frank A. Ross 175 Curtner Avenue, MC 781 U.S. Department of Energy, NE-42 San Jose, CA 95125 Office of LWR Safety and Technology 19901 Germantown Road Barton Z. Cowan, Esq.
Germantown, MD 20874 Eckeri Seamans Cherin & Mellott 600 Grant Street 42nd Floor Mr. Charles Thompson, Nuclear Engineer Pittsburgh, PA 15219 AP600 Certification NE 50 Mr Ed Rodwell, Manager 19901 Germantown Road PWR Design Certification Germantown, MD 20874 Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94303
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ADDITIONAL CHAPTER 21 S2R OPEN ITEMS ASSOCIATED WITH THE AP600 REACTOR SYSTEMS TESTING PROGRANI BASED ON ACRS CONCERNS E
440.788F -
The staff recognizes the importance of establishing a process for ensuring that me performance of the actual ADS valves in an AP600 plant meets functional muirements consistent with those determined from the design certification test program and reflected in design-basis analyses performed for the plant. Accordingly, the staff has determined that the ADS " road map" documented in Westinghouse letter NSD NRC-976-5100, dated April 30,1997, should be incorporated into the AP600 SSAR. In addition, the steps in the " road map" leading from the design certification test program to the qualif^ation of the actual AP600 valves should be l
incorporated into the inspections, tests, analyses, and acceptance criteria (ITAAC) for the AP600, and cross referencing between the ITAAC, SSAR, and other appropriate documentation i.
should be included, to ensure that the process is properly and consistently implemented.- This is j
sn Opm item.
440.789F -
t The ADS test program was discussed in a meeting between Westinghouse, the staff, and the l
- ACRS subcommittee on Thermal-Hydraulic Phenomena on December 9-10,1997. In that -
meeting, questions were raised regarding Westinghouse's evaluation of the data from the test program, particu!srly the calculation of key thermal-hydraulic parameters. To respond to the ACRS concems, Westinghouse must revise the Test Analysis Report (TAR) for the ADS test
~,
p.ogram to more completely discuss how the data were evaluated, including assumptions made with respect to thermal-hydraulic conditions in the test facility (e.g., assumed negligible or unimportant effects), and how these assumptions affect the inferred Mrformance characteristics i
of 6e ADS valves in the AP600 plant. These revisions should also provide complete justification as to why the range of thermal-hydraulic conditions covered by the ADS test program, and the data acquired therefrom, compriso an adequate basis for validation of code models for ADS performance analysis. Revision of the ADS TAR is an Opeu item.
440.790F The scope, organization, and content of the "AP600 Scaling and PiRT Closure Report," WCAP-17727 was also discussed at the December 910,1997, meeting between the staff, Westing-house, arid the ACRS Subcommittee on Thermal-Hydraulic Phenomena. Westinghouse should revise the report to address ACRS comments, including:
(a)- correction of errors in equations; (b) correction (if necessary), complete discussion, and justification of assumptions and/or specific models used in data assessment, determination of scaling parameters, and "pi" group evaluations, Enclosure t
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(c) in the specific case of OSU/ APEX scaling, performance of a multi-loop scaling analysis, or an attemative quantitative assessment, to demonstrate that the facility is appropriately scaled for the thermal-hydraulic phenomena and system behavior occurring during the transition from the snd of the ADS blowdown period to the inception of IRWST injection
- (e.g., flow split between ADS-1/2/3 and ADS-4 valves, pressurizer draining behavior, CCFL in the pressurizer surgo line, overall system depressurization behavior), to provide confidence that these data can be used to assess design-basis accident analysis com-puter codes used for the AP600 plant.
Revision of WCAP-14727 to address these issues is an Open item.
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