ML080350166

(PA-LR) Draft January 8, 2008 NRC-VY/Entergy Meeting Summary

ML080350166
Person / Time
Site:	Vermont Yankee
Issue date:	01/15/2008
From:	Rowley J NRC/NRR/ADRO/DLR
To:	Devince J, Mannai D, Metell H Entergy Nuclear Operations
References
TAC MD2297
Download: ML080350166 (10)

Text

Page 1 of I Jonathan Rowley -January 8, 2008 NRC-VY/Entergy meeting summary From: Jonathan Rowley To: dmannai@entergy.com; hmetell@entergy.com; jdevinc@entergy.com Date: 01/15/2008 4:22 PM

Subject:

January 8, 2008 NRC-VY/Entergy meeting summary Please review the attached meeting summary and provide comment as soon as possible if there are any.file://C:\temp\GW}

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Creation Date From: Created By: January 8, 2008 NRC-VY/Entergy meeting summary 01/15/2008 4:22:05 PM Jonathan Rowley JGR(nrc.gov Recipients entergy.com PM dmannai (dmannai (ientergy.com) hmetell (htnetell(centergy.com) jdevinc (idevinc(&Dentergy.com)

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& Opened LICENSEE: Entergy Nuclear Operations, Inc.FACILITY:

Vermont Yankee Nuclear Power Station

SUMMARY

OF MEETING HELD ON JANUARY 8, 2008, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND ENTEFRGY NUCLEAR OPERATIONS, INC. REPRESENTATIVES TO DISCUSS THE RESPONSE TO A REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION On January 8, 2008, the Nuclear Regulatory Commission staff (the staff) met with members of Entergy Nuclear Operations, Inc. (the applicant) in a public meeting to discuss the response to a request for additional information (RAI) made by the staff pertaining to the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application.

The applicant had an opportunity to comment on this summary.A list of attendees is provided in Enclosure

1. The meeting agenda is provided in Enclosure 2.Comments made by the public during the meeting are provided in Enclosure

3. A copy of the slides presented by the applicant is provided as Enclosure

4. A summary of the discussion follows: Backqround In a letter dated November 27, 2007, the staff issued RAI 4.3.3-2 to the applicant.

The purpose ofthe request was to gather additional information on the calculations used at VYNPS to reanalyze their time-limited aging analysis (TLAA) that addresses environmentally-assisted fatigue. In a letter dated December 11, 2007, the applicant provided its response to RAI 4.3.3-2 to the staff. The staff reviewed the response and expressed concerns with the methodology described in the submittal and statements made that shear stresses are negligible during a conference call with the applicant on December 18, 2007. During the call, the applicant indicated that some terminology misunderstanding may exist between the staff and Entergy. The applicant requested a face-to-face meeting to ensure the understanding pertaining to this highly technical issue was properly and effectively communicated.

Discussion During the meeting, the applicant made a slide presentation of the reactor pressure vessel nozzle environmental fatigue analyses for license renewal at VYNPS. The applicant attempted to clarify the terminology used in the response to RAI 4.3.3-2 and explain the methodology used. The applicant also attempted to demonstrate that the shear stresses in the nozzles were negligible.

The applicant explained that nozzle corner, blend radius, and inner radius are interchangeable terms for locations with geometrical discontinuities; locations where stresses are a maximum. The applicant explained that their methodology incorporates the use of axisymmetric modeling rather than a 3-Dimensional (3-D) or 2-Dimensional (2-D) modeling.

They explained that axisymmetric modeling is virtually 3-D except that rather than being modeled as piping joined to a cylinder, it is modeled as piping joined to a sphere with a multiplier to account for stress effects. With the aid of colored graphs, the applicant demonstrated specific nozzles where stresses are negligible.

The applicant also discussed the various conservatisms used in their analysis.Conclusion The applicant did not demonstrate that the shear stresses were negligible for all nozzles.As such additional confirmatory work will be performed by the applicant and submitted to the staff for review and acceptance.

The applicant indicated that it will take the following actions: 1) Perform benchmarking calculations on the feedwater nozzle, which is the most limiting component, using the axisymmetric model; 2) attempt to prove that the Vermont Yankee specific benchmarking calculations bound the results for the other nozzles still in question;

3) calculate fatigue usage factors (CUFs) using NRC approved ASME Section III NB-3200 methods; and 4)compare the resulting CUFs to the previous environmental assisted fatigue calculations in an attempt to verify the previous calculations are adequate.Jonathan G. Rowley, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-271

Enclosures:

1. Attendance List 2. Agenda 3. Public Comments 4. Presentation slides cc w/encls: See next page stresses are a maximum. The applicant explained that their methodology incorporates the use of axisymmetric modeling rather than a 3-Dimensional (3-D) or 2-Dimensional (2-D) modeling.

They explained that axisymmetric modeling is virtually 3-D except that rather than being modeled as piping joined to a cylinder, it is modeled as piping joined to a sphere with a multiplier to account for stress effects. With the aid of colored graphs, the applicant demonstrated specific nozzles where stresses are negligible.

The applicant also discussed the various conservatisms used in their analysis.Conclusion The applicant did not demonstrate that the shear stresses were negligible for all nozzles.As such additional confirmatory work will be performed by the applicant and submitted to the staff for review and acceptance.

The applicant indicated that it will take the following actions: 1) Perform benchmarking calculations on the feedwater nozzle, which is the most limiting component, using the axisymmetric model; 2) attempt to prove that the Vermont Yankee specific benchmarking calculations bound the results for the other nozzles still in question;

3) calculate fatigue usage factors (CUFs) using NRC approved ASME Section III NB-3200 methods; and 4)compare the resulting CUFs to the previous environmental assisted fatigue calculations in an attempt to verify the previous calculations are adequate.Jonathan G. Rowley, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-271

Enclosures:

1. Attendance List 2. Agenda 3. Public Comments 4. Presentation slides cc w/encls: See next page DISTRIBUTION:

See next page ADAMS Accession No.: DOCUMENT NAME: G:\ADRO\DLR\RLRB\ROWLEY\Meeting with VY-Entergy Summary -January 8, 2008.doc OFFICE LA:DLR PM:RPB2:DLR BC:RPB2:DLR BC:RER1:DLR NAME JRowley RFranovich KChang DATEICIAL R COPY OFFICIAL RECORD COPY MEETING BETWEEN THE NRC STAFF AND ENTERGY NUCLEAR OPERATIONS, INC.VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION 6003 EXECUTIVE BOULEVARD ROOM EBB1B15 ROCKVILLE, MARYLAND MEETING ATTENDANCE LIST JANUARY 8, 2008 PARTICIPANTS Jonathan Rowley Samson Lee John Fair Kenneth Chang PT Kuo Rani Franovich Robert Sun Qi Gan Kaihwa Hsu Ricardo Rodriguez Mary Baty Perry Buckberg Evelyn Gettys Yeon-Ki Chung Peter Wen On Yee Gary Hammer David Mannai John McCann Jay Thayer Matias Travieso-Diaz Michael Metell Garry Young Norm Rademacher Alan Cox AFFILIATIONS U.S. Nuclear Regulatory Commission (NRC)NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC Entergy Nuclear Operations, Inc. (Entergy)Entergy Entergy Entergy Entergy Entergy Entergy Entergy Enclosure 1

PARTICIPANTS James Fitzpatrick Scott Goodwin John Dreyfuss Joe Hopenfeld David Lochbaum THE FOLLOWING PARTICAPATED Sarah Hoffman John Sipos Paul Eddy Joan Leary Matthews Blaise Constantakes Rudolf Hausler Raymond Shadis Claire Chang Ulrich Witte Ed Anthes Rich Schaller Chalmer Myer Bob Audette Susan Smallheer Sally Shaw Fred Mogolesko AFFILIATIONS Entergy Entergy Entergy New England Coalition (NEC)Union of concerned Scientist VIA TELEPHONE BRIDGELINE Vermont Department of Public Service New York Office of the Attorney General New York Office of the Attorney General New York Office of the Attorney General New York Office of the Attorney General New York Office of the Attorney General NEC NEC NEC Nuclear Free Vermont Strategic Teaming and Resource Sharing Southern Nuclear Operating Company The Brattleboro Reformer The Rutland Herald Entergy Enclosure 1

MEETING BETWEEN THE NRC STAFF AND ENTERGY NUCLEAR OPERATIONS, INC.VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION 6003 EXECUTIVE BOULEVARD ROOM EBB1 B15 ROCKVILLE, MARYLAND AGENDA JANUARY 8, 2008 I. Introduction and opening remarks II. Discussion of Response to Request for Additional Information (Response to RAI 4.3.3-2)10 minutes 80 minutes 30 minutes II1. Public Comments IV. Adjourn Enclosure 2

MEETING BETWEEN THE NRC STAFF AND ENTERGY NUCLEAR OPERATIONS, INC.VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION ROCKVILLE, MARYLAND ROOM EBB1 B15 MEETING MINUTES JANUARY 8, 2008 Background In a letter dated November 27, 2007, the staff issued RAI 4.3.3-2 to the applicant.

The purpose of the request was to gather additional information on the calculations used at VYNPS to reanalyze their time-limited aging analysis (TLAA) that address environmentally-assisted fatigue.In a letter dated December 11, 2007, the applicant provided its response to RAI 4.3.3-2 to the staff. The staff reviewed the response and had concerns about the methodology described in the submittal and statements made that shear stresses are negligible.

The staff raised its concern in a conference call with the applicant on December,18, 2007. During the call, the applicant indicated that there was a terminology misunderstanding between the sides. The applicant requested a face-to-face meeting to ensure communications pertaining to this highly technical issue were effective.

Discussion During the meeting, the applicant presented a slide presentation regarding the reactor pressure vessel nozzle environmental fatigue analyses for license renewal at VYNPS. The applicant attempted to clarify the terminology used in the response to RAI 4.3.3-2 and explain the methodology used. The applicant also attempted to demonstrate that the shear stresses in the nozzles are negligible.

The applicant explained that nozzle corner, blend radius, and inner radius are interchangeable terms for locations with geometrical discontinuities; locations were stresses are a maximum.The applicant explained that their methodology incorporates the use of axisymmetric modeling rather than a 3-Dimensional (3-D) or 2-Dimensional (2-D) modeling.

They explained that axisymmetric modeling is virtually 3-D except that rather than being modeled as piping joined to a cylinder, it is modeled as piping joined to a sphere with a multiplier to account for stress effects. With the aid of colored graphs, the applicant demonstrated specific nozzles where stresses are negligible.

Conclusion The applicant did not demonstrate that the shear stresses where negligible for all nozzles so additional confirmatory work will be done and submitted to the staff for review and acceptance.

The applicant has to perform benchmarking calculations on the feedwater nozzle, which is the most limiting component, using the axisymmetric model. The applicant will attempt to prove that the Vermont Yankee specific benchmarking calculations bound the results for the other nozzles Enclosure 3

still in question.

The applicant will calculate fatigue usage factors (CUFs) using NRC approved ASME Section III NB-3200 methods. The resulting CUFs are to be compared to the previous environmental assisted fatigue calculations in an attempt to verify the previous calculations are adequate.Enclosure 3