ML071570611

From kanterella
Jump to navigation Jump to search
Summary of Category 2 Public Meeting with Expert Panel for the Wolf Creek Advanced Finite Element Analyses (Fea) Regarding the NRC Staff'S Questions About the Likelihood That Rupture May Occur Without Prior Evidence of Leakage in Pressurize
ML071570611
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 06/12/2007
From: Mauricio Gutierrez
NRC/RES/DFERR/DDME/CIB
To: Uhle J
NRC/RES/DFERR/DDME
Gutierrez, Maricio R, DORL, 415-2788
References
Download: ML071570611 (13)


Text

June 12, 2007 MEMORANDUM TO: Jennifer L. Uhle, Deputy Director Materials Engineering Division of Fuel, Engineering, and Radiological Research Office of Nuclear Regulatory Research THRU: Robert Hardies, Chief /RA/

Component Integrity Branch Division of Fuel, Engineering, and Radiological Research FROM: Mauricio Gutierrez, General Engineer /RA/

Component Integrity Branch Division of Fuel, Engineering, and Radiological Research

SUBJECT:

SUMMARY

OF THE MAY 31 - JUNE 01, 2007, CATEGORY 2 PUBLIC MEETING BETWEEN THE NUCLEAR REGULATORY COMMISSION STAFF AND THE EXPERT PANEL FOR THE WOLF CREEK ADVANCED FINITE ELEMENT ANALYSES (FEA)

On May 31 and June 1, 2007, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a Category 2 public meeting with industry representatives at Dominion Engineering, Incorporated in Reston, VA. A list of attendees, industry presentations, the NRC contractor presentation, and NRC staff presentation are enclosed. The meeting was a continuation of ongoing discussions between industry representatives and NRC staff regarding the NRC staffs questions about the likelihood that rupture may occur without prior evidence of leakage in pressurizer nozzle dissimilar metal welds susceptible to primary water stress corrosion cracking.

The meeting specifically addressed several key technical issues such as: weld residual stress (WRS) modeling, elastic-plastic fracture mechanics (EPFM) vs. limit load analysis, the role of secondary stresses, K-solution verification, finite element modeling convergence, and the industry proposed sensitivity matrix, acceptance criteria, and safety factors. Consensus was reached on K-solution verification, the inclusion of secondary stresses, and finite element model convergence. Discussions are ongoing with regards to EPFM vs. limit load to calculate critical crack size. The NRC staff provided comments on industrys proposals regarding acceptance criteria and safety factors and indicated that it would be developing acceptance criteria and safety factors that it plans to use to evaluate the industry results.

J. Uhle No members of the public were present at the meeting. The information discussed was non-proprietary. Please direct any inquiries to me at 301-415-1122 or mrg3@nrc.gov.

Enclosures:

1. List of Attendees
2. Dominion Engineering Presentation
3. Westinghouse and Combustion Engineering Repairs History Presentation
4. Quest Reliability Presentation
5. Structural Integrity Presentation
6. EMC2 (NRC Contractor Presentation)
7. NRC Staff Presentation
8. Westinghouse Presentation on Plants C and F Repair History

J. Uhle No members of the public were present at the meeting. The information discussed was non-proprietary. Please direct any inquiries to me at 301-415-1122 or mrg3@nrc.gov.

Enclosures:

1. List of Attendees
2. Dominion Engineering Presentation
3. Westinghouse and Combustion Engineering Repairs History Presentation
4. Quest Reliability Presentation
5. Structural Integrity Presentation
6. EMC2 (NRC Contractor Presentation)
7. NRC Staff Presentation
8. Westinghouse Presentation on Plants C and F Repair History DISTRIBUTION:

DFERR r/f ME r/f MEvans RidsNrrDprPspb RidsOpaMail RidsNrrAdro RidsNrrDpr TLupold RidsOgcMailCenter RidsNrrDciCpnb RidsNrrDe JGrobe TMensah WBateman RidsAcrsAcnwMailCenter RHardies ESullivan TChan Chai-Fu Sheng Memo:ML071570611 Enclosure ML071620388 DOCUMENT NAME:C:\Documents and Settings\nxi1\My Documents\Concur box old\Concc. SUNSI.wpd OAR in ADAMS? (Y or N) Y ADAMS ACCESSION NO.:Pkg.ML071620384 TEMPLATE NO. RES- 006 Publicly Available? (Y or N) N DATE OF RELEASE TO PUBLIC 06/12/07 SENSITIVE? N To receive a copy of this document, indicate in the box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy OFFICE RES/DFERR/CIB RES/DFERR/CIB BC:RES/DFERR/CIB SUNSI Review Complete SUNSI Review Complete NAME M. Gutierrez /RA/ A. Csontos /RA/ R. Hardies for R. Hardies /RA/ M. Gutierrez /RA/ R. Hardies /RA/

DATE 06/12/07 06/12/07 06/12/07 06/12/07 06/12/07 OFFICIAL RECORD COPY

Nuclear Regulatory Commission Meeting with the Expert Panel for Wolf Creek Finite Element Analysis May 31, 2007 and June 1, 2007 U.S. NUCLEAR REGULATORY COMMISSION Edmund Sullivan Aladar Csontos Simon Sheng Tim Lupold Dave Rudland (NRC Contractor)

Mauricio Gutierrez INDUSTRY Craig Harrington, EPRI Glenn White, DEI Jean Collin, DEI John Broussard, DEI Guy DeBoo, Exelon Mike Melton, NEI Tim Gilman, Structural Integrity Pete Riccardella, Structural Integrity Doug Killian, AREVA Cameron Martin, Westinghouse Warren Bamford, Westinghouse Dom Sutton, SNC William Sims, Entergy Ramiz Gilada TXU (On Phone)

Ted Anderson, Quest Reliability Jim Riley, NEI Enclosure 1

cc:

Mr. Anthony Pietrangelo, Vice President Mr. Alexander Marion, Executive Director Regulatory Affairs Nuclear Operations & Engineering Nuclear Energy Institute Nuclear Energy Institute 1776 I Street, NW, Suite 400 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Washington, DC 20006-3708 arp@nei.org am@nei.org Mr. Jack Roe, Director Mr. Jay Thayer, Vice President Operations Support Nuclear Operations Nuclear Energy Institute Nuclear Energy Institute 1776 I Street, NW, Suite 400 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Washington, DC 20006-3708 jwr@nei.org jkt@nei.org Mr. Charles B. Brinkman Mr. John Butler, Director Washington Operations Safety-Focused Regulation ABB-Combustion Engineering, Inc. Nuclear Energy Institute 12300 Twinbrook Parkway, Suite 330 1776 I Street, NW, Suite 400 Rockville, MD 20852 Washington, DC 20006-3708 brinkmcb@westinghouse.com jcb@nei.org Mr. Gary L. Vine, Executive Director Mr. James H. Riley, Director Federal and Industry Activities, Nuclear Engineering Sector Nuclear Energy Institute EPRI 1776 I Street, NW 2000 L Street, NW, Suite 805 Washington, DC 20006-3708 Washington, DC 20036 jhr@nei.org gvine@epri.com Mr. David J. Modeen Mr. James Gresham, Manager Vice President and Chief Nuclear Officer Regulatory Compliance and Plant Licensing EPRI Westinghouse Electric Company 1300 W. T. Harris Boulevard P.O. Box 355 Charlotte, NC 28262-8550 Pittsburgh, PA 15230-0355 dmodeen@epri.com greshaja@westinghouse.com Mr. John Gaertner Ms. Barbara Lewis EPRI Assistant Editor 1300 W.T. Harris Boulevard Platts, Principal Editorial Office Charlotte, NC 28262-8550 1200 G St., N.W., Suite 1100 jgaertner@epri.com Washington, DC 20005 Barbara_lewis@platts.com Ms. Rosa Yang EPRI Mr. Gary Welsh 3412 Hillview Avenue Institute of Nuclear Power Operations Palo Alto, CA 94304-1338 Suite 100 ryang@epri.com 700 Galleria Parkway, SE Atlanta, GA 30339-5957 welshgc@inpo.org

Mr. Kenneth Huffman EPRI 1300 W. T. Harris Boulevard Charlotte, NC 28262-8550 khuffman@epri.com