ML20148H138

Submits Comments on AP600 SG Tube Surveillance Program in Ts,To Be Incorporated Into Next Rev to AP600 TS

ML20148H138
Person / Time
Site:	05200003
Issue date:	06/05/1997
From:	Huffman W NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9706090244
Download: ML20148H138 (3)

Text

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g & UNITED STATES g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30e06 0001

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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:

COPMENT ON THE AP600 STEAM GENERATOR TUBE SURVEILLANCE PROGRAM IN TECHNICAL SPECIFICATIONS (TSs)

Dear Mr. Liparulo:

The U.S. Nuclear Regulatory Commission (NRC) is reviewing the AP600 TSs (08/96-Amendment 0) which were included with Revision 9 to the AP600 standard safety analysis report. Based on review by the Materials and Chemical Engineering Branch of the AP600 steam generator tube surveillance program described in the administrative controls of TSs, the staff has the following comment which needs to be incorporated into the next revision to the AP600 TS.

TS 5.5.5 states that "(t)he provisions of SR 3.0.2 are applicable to SG Tube Surveillance Program inspection frequencies except those established by Category C-3 inspection results." In the future, the bracketed reference to Regulatory Guide 1.83 will be replaced with a reference to a regulatory guide that is currently in draft, but which is scheduled to be finalized in 1998.

This regulatory guide contains guidance on, among other things, how to

- establish surveillance intervals. The maximum surveillance interval will be dictated on considerations of maintaining SG tube integrity for the entire period of operation between inspections. For example, because of the rate of degradation in certain areas of old SGs, some plants are not able to be  !

operated for a full refueling cycle between inspections. That is,-they l perform mid-cycle inspections. Once the maximum interval for a plant is '

determined, it would be technically unacceptable to apply a 25 percent extension. In the case of a plant with SG tubing in good condition, SG inspection intervals will not be. limiting and the 25 percent extension will not be an issue. Therefore, the wording in the TS should read instead as follows:

"The provisions of SR 3.0.2 are not applicable to SG Tube Surveillance Program inspection frequencies."

\ o 090022 NRCELECEMBEBPY 9706090244 970605 PDR ADOCK 05200003 A PDR

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Mr. Nicholas J. Liparulo June 5, 1997 i

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If you have any questions regarding this matter, you may contact me at l (301) 415-1141.

Sincerely, original signed by:

William C. Huffman, Project Manager l Standardization Project Directorate  !

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

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0FFICIAL RECORD COPY I

.e .c Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600 cc: Mr. B. A. McIntyre Mr. Ronald Simard,' Director j Advanced Plant Safety & Licensing Advanced Reactor Programs l Westinghouse Electric Corporation Nuclear Energy Institute '

Energy Systems Business Unit 1776 Eye Street, N.W.

P.O. Box 355 Suite 300 l Pittsburgh, PA 15230 Washington, DC 20006-3706 l l l l Ms. Cindy L. Haag Ms. Lynn Connor )

l Advanced Plant Safety & Licensing Doc-Search Associates j Westinghouse Electric Corporation Post Office Box 34 j Energy Systems Business Unit Cabin John, MD 20818 i 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 l

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 l 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 i 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 I I

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