ML20217L897

Informs That Proposal in W Ltr NSD-NRC-97-5780 Re AP600 Core Makeup Tank Level Instrumentation,Does Not Meet Requirements of 10CFR52.47(a)(2) & Therefore,Unacceptable

ML20217L897
Person / Time
Site:	05200003
Issue date:	08/15/1997
From:	Slosson M NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9708190219
Download: ML20217L897 (3)

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"% August 15, 1997 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230

SUBJECT:

AP600 CORE MAKEUP TANK (CMT) LEVEL INSTRUMENTATION

Dear Mr. Liparulo:

Westinghouse letter NSD-NRC-97-5180 dated June 12, 1997, submitted information on the AP600 CMT level instrumentation. Westinghouse proposed a "roadmap" of the process to determine the type of instrumentation to be used to detect water level in the CMT for AP600 design certification and stated that the combined license (COL) applicant will evaluate and select the type of CMT level instrument to be used with the AP600 design. The Westinghouse submittal also provided some information on qualification and testing of the CMT level instrument which would be required of the COL applicant. '

The CMT level instrumentation is a very import feature of the AP600 design and is used to automatically actuate the automatic depressurization system (ADS).

Because the CMT level instrument is part of the AP600 design scope, it cannot be a COL action item. The proposal in NSD-NRC-97-5180 does not meet 10 CFR 52.47(a)(2), which requires sufficient design information to make a safety finding and is, therefore, unacceptable. Westinghouse must provide sufficient design information on the CMT level instrumentation for the NRC staff to make its safety finding. The staff notes that there are AP600 design features which require reactor coolant system level measurement capability (similar to what would be needed for the CMT) that incorporate a specified design - such 4 as the pressurizer level instrumentation and the hot leg level instrumen-tation.

As an alternative approach, Westinghouse could propose design acceptance criteria (DAC) as part of its inspections, tests, analyses, and acceptance criteria (ITAAC), in lieu of detailed design information on the CMT level instrumentation. However, if Westinghouse adopts this approach, it must provide justification for the use'of DAC rather than a specific design and the NRC staff will request Commission approval as a matter of policy.

Regardless of what is ultimately placed into the AP600 certified design material for the CMT level instrument, the COL applicant will still have the option to request a change pursuant to the design certification change process if it wishes to use a new CMT level instrument design based on future techno-logical developments in level sensing devices.

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Mr. Nicholas J. Liparulo- August 15, 1997 If you have any questions regarding this matter, please contact the responsi-ble project manager, Mr. William Huffman, at (301) 415-1141.

Sincerely, original signed by: Seymour H. Weiss Marylee M. Slosson, Acting Director Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003 cc: See next page DISTRIBUTION:

Docket File PDST R/F MSlosson PUBLIC SWeiss TQuay-TKenyon BHuffman JSebroksy DJackson JMoore, 0-15 B18 WDean, 0-5 E23 ACRS (11) JNWilson GHolahan, 0-8 E2 GMizuno, 0-15 B18 HLi, 0-8 H3 MChiramal, 0-8 H3 JWermiel, 0-8 H3 Alevin, 0-8 E23 JLyons, 0-8 E23

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s O Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP610 cc: Mr. B. A. McIntyre Mr. Ronald Simard, Director Advanced Plant Safety & Licensing Advanced Reactor Programs-Westinghouse Electric Corporation Nuc' lear 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 Pr. 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

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