ML20137F245

Notification of 970416-18 Meeting W/W in Monroeville,Pa to Review Design Calculations & Supporting Documents for Application of LBB Methodology to AP600 Standard Plant. W/Draft Agenda

ML20137F245
Person / Time
Site:	05200003
Issue date:	03/27/1997
From:	Diane Jackson NRC (Affiliation Not Assigned)
To:	Quay T NRC (Affiliation Not Assigned)
References
NUDOCS 9704010020
Download: ML20137F245 (5)

Text

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March 27,1997 l

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MEMORANDUM T0: Theodore R. Quay, Director Standardization Project Directorate  !

Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM: Diane T. Jackson, Project Manager original signed by: l Standardization Project Directorate Division of Reactor Program Management )

Office of Nuclear Reactor Regulation

SUBJECT:

NOTICE OF MEETING WITH WESTINGHOUSE TO DISCUSS THE APPLICATION OF LEAK-BEFORE-BREAK (LBB) TO THE AP600 PLANT l

DATE AND TIME: April 16 through 18, 1997 - 8 a.m. - 5 p.m.  !

I LOCATION: Westinghouse Electric Corporation "

Westinghouse Energy Center  !

4350 Northern Pike Monroeville, PA 15146-2808 ,

1 PURPOSE: The purpose of this meeting is to review the design calcula-tions and supporting documents for the application of the LBB methodology to the AP600 standard plant. l PARTICIPANTS *: EG WESTINGHOUSE G. Bagchi R. Mandava S. Hou E. Johnson D. Jackson D. Bhowmick )

G. DeGrassi (Consultant) S. Swamy I R. Gamble (Consultant), et al. D. Lindgren, et al.  !

Docket No.52-003 j

Attachment:

Draft Agenda l l

cc w/ attachment:

See next page

• Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to the " Commission Policy Statement on Staff Meetings Open to the Public," 59 Federal Reaister 48344,9/20/94. However, portions of this staff meeting may be closed to protect Westinghouse propri-  !

etary information. Members of the public who wish to attend should contact Diane Jackson (NRC) at (301) 415-8548, or Don Lindgren (Westinghouse) at (412) 374-4856.

DISTRIBUTION:

l See next page i

l DOCUMENT NAME: A:ECG4 16.NOT Tm secehe e copy of this docuenent. InsEste in the bom *C* = Copy without ettechment/ enclosure "E" = Copy with attachment / enclosure *N' = No copy j OFFICE PM:PDST:DRPM _ , D:PDST:DRPM l l l NAME DTJackson:sg t/)( TRQuay 4 W DATE 5 /a?/97 () 3/rt/97 9704010020 970327 ^^lAL RECORD COPY PDR ADOCK 0520 3 f

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l l' Westinghouse Electric Corporation Docket No.52-003 a [

i cc: Mr. Nicholas J. Liparulo, Manager Mr. Frank A. Ross l

Nuclear Safety and Regulatory Analysis U.S. Department of Energy, NE-42 '

Nuclear and Advanced Technology Division Office of LWR Safety and Technology ,

i Westinghouse Electric Corporation 19901 Germantown Road P.O. Box 355 Germantown, MD 20874

Pittsburgh, PA 15230 ,

. Mr. Ronald Simard, Director Mr. B. A. McIntyre Advanced Reactor Program .l l Advanced Plant Safety & Licensing Nuclear Energy Institute  ;

Westinghouse Electric Corporation 1776 Eye Street, N.W.

Energy Systems Business Unit Suite 300 Box 355 Washington, DC 20006-3706 l Pittsburgh, PA 15230 ~

j Ms. Lynn Connor .

Ms. Cindy L. Haag Doc-Search Associates Advanced Plant Safety & Licensing Post Office Box 34 Westinghouse Electric Corporation Cabin John, MD 20818 -

Energy Systems Business Unit Box 355 Mr. James E. Quinn, Projects Manager Pittsburgh, PA 15230 LMR and SBWR Programs GE Nuclear Energy Mr. M. D. Beaumont 175 Curtner Avenue, M/C 165 i Nuclear and Advanced Technology Division San Jose, CA 95125 Westinghouse Electric Corporation s One Montrcse Metro Mr. Robert H. Buchholz i 11921 Rockville Pike GE Nuclear Energy 1 Suite 350 175 Curtner Avenue, MC-781  !

Rockville, MD 20852 San Jose, CA 95125 Mr. Sterling Franks Barton Z. Cowan, Esq.  !

U.S. Department of Energy Eckert Seamans Cherin & Mellott i NE-50 600 Grant Street 42nd Floor  :

19901 Germantown Road Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed Rodwell, Manager Mr. S. M. Modro PWR Design Certification Nuclear Systems Analysis Technologies Electric Power Research Institute Lockheed Idaho Technologies Company 3412 Hillview Avenue Post Office Box 1625 Palo Alto, CA 94303 Idaho Falls, ID 83415 Mr. Charles Thompson, Nuclear Engineer AP600 Certification NE-50 19901 Germantown Road Germantown, MD 20874 4

e. ,,-

t AP600 LEAK-BEFORE-BREAK AND RELATED ISSUES APRIL 16 THROUGH 18, 1997 DRAFT AGENDA i

I. Introduction II. Westinghouse presentation Bounding analysis procedures (OITS# 608) e W describes procedures used for bounding analyses and bounding curves, and explain why they will meet LBB acceptance criteria if COL applicant follows the SSAR specified verification process.

e Discuss SSAR revision to ensure clarity of description, o Discuss relationship with DAC approach in overall piping design and SSAR revision to clarify DAC approach.

III. Discuss weld inspection requirements and welder performance demonstra-tion during construction for ASME Class 2 and 3 piping with LBB applica-tion (OITS# 611) l i

e Accumulator discharge line circumferential welds (Class 3) i i

IV. Verification of computer codes used in calculation of leak rate, crack  ;

length, and crack stability (0ITS# 608, 618) e W describes verification process used and shows documentation,  ;

including benchmarked test data (indicated in W 1etter dated i February 25, 1997).

e Discuss correction factors developed by W for PICEP code.

V. Discuss water hammer loads in all piping with LBB application '(OITS#

620) e Implication of screening criteria presented by Prof. P. Griffith of MIT.

e Implication of rapid condensation loads found in Oregon State j University tests.

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Attachment I

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s VI. Audit of LBB calculations e Sample of LBB calculations (OITS# 608)

Following five lines are selected:

1. Main steam A (32")

2. Surge line (18")

3. PRHR return (10")

4. CMT-B (8")

5. Direct Vessel Injection A (6")

Verify conformance with bounding analysis procedures Verify meeting LBB acceptance criteria e Verify that SSE loads have considered all applicable soil condi-tions (0ITS# 615) e Verify that pipe break at branch line connection is postulated unless LBB is also applicable to the branch line (0ITS# 616)

VII. Discuss ITAAC provisions to verify that low point vents and adequate slope of piping near stagnant regions for minimizing water hammer.

VIII. Discuss uncertainties (basis) in applying LBB to smaller lines (See NUREG/CR-6443, Section 3.5 on restrained pressure-induced bending effect to maximum stress and crack length) (OITS# 608)

IX. Conclusion

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DISTRIBUTION: Memorandum to Theodore R Quay. Dated: March 27. 1997 l Docket file l PUBLIC PDST R/F Scollins/FMiraglia, 0-12 G18 AThadant, 0-12 G18 i RZimmerman, 0-12 G18 I TMartin MLSlosson TJKenyon DTJackson WCHuffman j JMSebrosky l WDean, 0-17 G21 l JMoore, 0-15 B18 ACRS (11)

GBagchi, 0-7 H15 Shou, 0-7 HIS RBailey/BGray, 0-2 82 l 1

PMNS (e-mail)

OPA (e-mail) l I

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