ML20197A663

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Notification of 980211 Meeting W/W in Rockville,Maryland to Discuss Classification of AP600 Containment Coatings
ML20197A663
Person / Time
Site: 05200003
Issue date: 02/09/1998
From: Joseph Sebrosky
NRC (Affiliation Not Assigned)
To: Quay T
NRC (Affiliation Not Assigned)
References
NUDOCS 9803090343
Download: ML20197A663 (4)


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February 9. 1998 MEMORANDUM TO: Theodore R. Quay, Director Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:

Joseph M. Sobrosky, Project Manager original signed by:

Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation

SUBJECT:

NOTICE OF MEETING WITH WESTINGHOUSE TO DISCUSS AP600 l

CONTAINMENT COATINGS DATE AND TIME:

February 11,1998 1 p.m. - 3 p.m.

LOCATION:

U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Room 0-4 B6 PURPOSE:

To discuss the classification of the AP600 containment coatings. The issues to be discussed are attached.

PARTICIPANTS *:

NBQ WESTINGHOUSE G. Holahan R. Vijuk J. Strosrdder T. Schulz G. Georglev D. Lindgren J. Davis B. McIntyre, et al.

R.Lobel E. Throm J. Peralta T. Quay J. Sobrosky, et al.

Docket No. 52 003

Attachment:

As stated cc w/atts: See next page j

' Meetings between the 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 " Commission Policy Statement on Staff Meeting Open to the Public," 59 Federal Reaister 48344,9/20/94. However, portions of this meeting may be closed to protect Westinghouse g

proprietaryinformation. Members of the public who wish to attend should contact me at (301) 415-1132.

DISTRIBUTION: See next page DOCUMENT NAME: A: COATINGS.NOT To receive a copy of this document, indicate in the box: 'C" = Copy without ll l lllllllllll ll attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy OFFICE PM:PDST:DRPM - l D:PDST:DRPM l l

NAME JSebrosky:sg M TQuay-4Yw DATE 02/ rd98

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02/ 1/98 9803090343 980209 CICIAL RECORD COPY PDR ADOCK 0520 3

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Westinghouse Electric Corporation Docket No. 52 003 cc:

Mr. Nicholas J. Liparulo, Manager Mr. Frank A. Ross Nuclear Safety and Megulatory Analysis U.S. Department of Energy, NE 42 Nuclear and Advanced Technology Division Office of LWR Safety and Technology Westinghouse riectric Corporat6on 19901 Germantown Road P.O. Box 355 Germantown, MD 20874 Pittsburgh, PA 15230 Mr. Russ Bell Mr. B. A. McIntyre Senior Project Managar, Programs Advanood Plant safety & Lloonsing Nuclear Energy institute Westinghouse Electric Corporation.

1776 l Street, NW Energy Systems Business Unit Suite 300 Box 355 Washington, DC 20006 3706 Pittsburgh, PA 15230 Ms. Lynn Connor Ms. Cindy L. Haag Doc Search Associates Advanced Plant Safety & Licensing Post Omco Box 34 Westinghouse Electric Corporation Cabin John, MD 20818 Energy Systems Business Unit Box 355 Dr. Craig D. Sawyer, Manager Pittsburgh, PA 15230 Advanced Reactor Programs GE Nuclear Energy Mr. M. D. Beaumont 175 Curiner Avenue, MC 754 Nuclear and Advanced Technology Division _

San Jose, CA 95125 Westinghouse Electric Corporation one Montrose Metro Mr. Rober1 H. Buchholz 11921 Rockville Pike GE Nuclear Energy Suite 350 175 Curtner Avenue, MC-781 P.ockville, MD 20852 San Jose, CA 95125 Mr. Storting Franks Barton Z. Cowan, Esq.

U.S. Department of Energy Eckert Seamans Cherin & Mellott NE 50 600 Grant Street 42nd Floor 19901 Germantown Road Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed Rodwell, Manager Mr. Chartes Thompson, Nuclear Engineer PWR Design Certification AP600 Certification Electric Power Research Instituto NE 50 3412 Hillview Avenue 19901 Germantown Road Palo Alto, CA 94303 i

Germantown, MD 20874

. Mr. Robert Malers, P.E.

Pennsylvania Department of Environmental Protection Bureau of Radiation Protection Rachel Corson State Office Building P.O. Box 8469 Harrisburg, PA' 17105 8469

4 AP600 Containment Coatings lesues to be Addressed Westinghouse has not provided a quantitative or experimental bases which demonstrate e

why failure of the containment coatings will not prevent functioning of the engineering safety features. Calculations are required to determine if failure of the coatings will result in 1

blockage of stralners. The analysis must be reviewed by the NRC staff since there is j

uncertainty in the calculations. Even if Westinghouse were to perform a transport analysis, I

the staff is not likely to accept it without additional experimental validation.

Westinghouse provides some qualitative discussions on what it believes will occur upon e

failure of containment coatings (e.g., assumes only localized failure of coatings, assumes coating material will settle on the bottom of various compartments and will not get transported in sufficient quantities which are undefined to the intake screens) but has not provided any evidence of this mechanism besides engineering judgment.

in addition to the staffs concems on debris transport to the containment sumps, the e

i performance characteristics of the passive containment cooling system (PCS) are based on an experimental test program with the coating. No testing is known to exist with either l

degraded coatings or without coatings. The justification for the mass and heat transfer correlations, the PCS film model and the water coverage model are all based on testing with the coating. In the Large Scale Test (LST), the coating exists on both the exterior and the interior surface of the vessel. Failure of the coating willimpact heat transfer, film formation and water coverage. Westinghouse has not provided any data or experimental evidence as to why deterioration of the containment coatings will not affect the design basis properties of the containment shell and the PCS performance.

r The evolutionary designs have effectively agreed to a safety-related coating program by e

committing to implement RG 1.54 to satisfy the requirements of Appendix B to 10 CFR Part 50. Westinghouse needs to demonstrate that protective coatings used in the AP600 are non safety-related, and clearly substantiate the basis for its current exception (in SSAR Appendix 1A) to RG 1.54 and the endorsed ANSI standards (i.e., explain why the provisions of Appendix B to 10 CFR Part 50 and 10 CFR Part 21 do not apply to protective coatings in the AP600).

Attachment

.n s DISTRIBUTION: Memorandum to Theodore R. Quav. Dated: February 4.

199R Docket File PUBLIC PDST R/F SCollins/FMiraglia,0-12 G18 BSheron,012 G18 BBoger,012 G10 JRoe DMatthews TJKenyon WCHuMman JMSebrosky JNWilson DScaletti GHolahan,0-8 E2 JStrosnider,0 7 D4 GGeorgiev,0-7 H15 JDavis,0 7 Di RLobel,0-8 H7 EThrom,0 8 H7 JPeralta,0 9 A1 CBerlinger,0 8 H7 JKudrick,0-8 H7 l-BRothman,0-7 H15 JBrammer,0 7 H15 WDean,016 E15 JMoore,015 B18 ACRS (11)

RBalley,0 2 B2 PMNS (e mail)

OPA (e-mail)