ML080720426
| ML080720426 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 03/06/2008 |
| From: | Travieso-Diaz M Entergy Nuclear Operations, Entergy Nuclear Vermont Yankee, Pillsbury, Winthrop, Shaw, Pittman, LLP |
| To: | Atomic Safety and Licensing Board Panel |
| SECY/RAS | |
| References | |
| 50-271-LR, ASLBP 06-849-03-LR, RAS-M-2 | |
| Download: ML080720426 (8) | |
Text
DOCKETED USNRC March 6, 2008 March 6, 2008 (1:57pm)
OFFICE OF SECRETARY UNITED STATES OF AMERICA RULEMAKINGS AND NUCLEAR REGULATORY COMMISSION ADJUDICATIONS STAFF Before the Atomic Safety and Licensing Board In the Matter of )
)
Entergy Nuclear Vermont Yankee, LLC ) Docket No. 50-271-LR and Entergy Nuclear Operations, Inc. ) ASLBP No. 06-849-03-LR
)
(Vermont Yankee Nuclear Power Station) )
ENTERGY'S FINAL LIST OF WITNESSES Pursuant to Section 11.1 .C of the Atomic Safety and Licensing Board's Board Initial Scheduling Order (Nov. 17, 2006), Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. ("Entergy") hereby provide their final list of witnesses, as follows.
,New England Coalition Contention 2A (adequacy of analytical methods employed in Entergy's calculations of environmentally assisted fatigue):
Lead Product Manager for BWR Fatigue Gary L. Stevens. P.E.
Management Program Development Structural Integrity Associates 6855 South Havana Street, Suite 350 Centennial, CO 80112 303-792-0077 James C. Fitzpatrick Former (as of March 10, 2008) Senior Lead Engineer, Design Engineering Vermont Yankee Nuclear Power Station AREVA NP 400 Donald Lynch Blvd.
Marlborough, MA 01752 978-568-2805
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i, Mr. Stevens is an expert in the application of finite element analysis, fracture mechanics, and structural and fatigue analyses for nuclear components. He has extensive experience in the application of American Society of Mechanical Engineers ("ASME") Code Sections III and XI methodology to fatigue analyses of reactor vessels and internals components. He was the Chairman of former ASME Section XI Task Group on Operating Plant Fatigue Assessments, is the Secretary of the ASME Section XI Working Group on Operating Plant Criteria, is the Secretary of the ASME Section XI Subgroup on Evaluation Standards, and is a member of the ASME Section XI Subcommittee on Nuclear Inservice Inspection. In his testimony, Mr. Stevens will describe the methodology and results of the calculations and analyses of environmentally assisted fatigue of components at VY performed under his supervision. He will testify that the results of these calculations and analyses demonstrate that the fatigue usage factors, including environmental effects, for all critical components and locations analyzed, remain within the allowable value of 1.0 established by Section III of the ASME Code the for the entire twenty years of VY extended operation.
Mr. Fitzpatrick has thirty years of experience in the design, construction, and modification of nuclear power plant structures, piping systems, pressure vessels, and in the seismic evaluation of mechanical and electrical equipment. At VY, he has been responsible for the development and implementation of plant design changes, inspection programs, equipment specifications, installation support, outage support, and operability evaluations of degraded components. Mr. Fitzpatrick will testify on Entergy's plan to predict and manage the effects of fatigue on critical reactor components during the twenty-year period following renewal of the VY operating license and will describe how the VY's operating history, its current operating 2
conditions, and other relevant painiteter's were duly ih0*oiý6ated as inputs to the environmentally assisted fatigue calculations.
New England Coalition Contention 3 (steam dryer):
John R. Hoffman Former Project Manager for the VY License Renewal Project P.O. Box 377 24 Christine Overlook Conway, NH 03818 408-978-8200 Larry D. Lukens Former Supervisor, Code Programs Vermont Yankee Nuclear Power Station 119 Flint Ct.
Bellefonte, PA 16823 814-353-0186 Mr. Hoffman has over 37 years of nuclear power engineering experience and was associated with the Vermont Yankee Nuclear Power Station from 1971 until his retirement in September 2006. He had, among other responsibilities, that of Project Manager for the License Renewal Project at VY. In that capacity, Mr. Hoffman was responsible for overseeing the development of the proposed program to manage the aging of the VY steam dryer during the extended license operating period. Mr. Hoffman's testimony will summarize the dryer monitoring and inspection program that has been implemented at VY since the plant uprate was accomplished and describe Entergy's proposed steam dryer aging management program for the period of extended plant operations, including continuous monitoring of plant parameters indicative of significant steam dryer cracking, assessment of the monitoring data and evaluation of the significance of the data by several levels of qualified personnel. Mr. Hoffman will also demonstrate that there is no need to provide a means to estimate and predict stress loads on the 3
dryer during operation for comparison to establishe'd-fatigu& limits because the monitoring program, supplemented by the periodic dryer inspections during refueling outages, is sufficient to diagnose whether significant dryer cracking has occurred before such cracking results in dryer failure.
Mr. Lukens has over 38 years of nuclear power experience and was associated with the Vermont Yankee Nuclear Power Station from 2002 until his retirement in July 2007. At VY he had, among other responsibilities, that of Supervisor, Code Programs and in that capacity he was responsible for ensuring the completion and evaluation of the steam dryer inspections, as well as other Code-required tests and inspections. Mr. Lukens will summarize the steam dryer inspections that have been conducted to date at VY and their results, and will describe the dryer inspections to be performed during the period of plant operations after renewal of the VY license. He will describe how the most recent steam dryer inspections show that the strengthening modifications made to the dryer in 2004 in anticipation of uprate operations are performing as expected and will explain how the fact that the VY steam dryer showed no evidence of fatigue induced cracks after one year of EPU operation indicates that continued routine inspection of the steam dryer during the period of extended operation will provide reasonable assurance of continued steam dryer integrity.
New England Coalition Contention 4 (flow accelerated corrosion):
Jeffrey S. Horowitz Independent Consultant 3331 Avenida Sierra Escondido, CA 92029 760-747-8714 James C. Fitzpatrick Fortner (as of March 10, 2008) Senior Lead Engineer, Design Engineering Vermont Yankee Nuclear Power Station 4
AREVA"NP 400 Donald Lynch Blvd.
Marlborough, MA 01752 978-568-2805 Dr. Horowitz has over 35 years of experience in the field of nuclear energy and related disciplines and has specialized for the last 22 years in flow-accelerated corrosion ("FAC") and nuclear safety analysis. An internationally recognized expert on FAC issues, he is the author of several computer code widely used to predict the most likely locations for FAC damage to occur in nuclear reactors. Among the codes he has authored is CHECWORKS, currently used in facilities around the world (including VY) as an aid in identifying plant locations where FAC inspections should be conducted. Dr. Horowitz will testify on the methodology, assumptions and data used in performing CHECWORKS evaluations, describe the industry experience with FAC and the use of CHECWORKS, and will explain why the data accumulated on VY's operations at uprate levels by the time the period of extended operation begins will be sufficient to permit accurate FAC predictions. He will also describe the audit he performed in April 2007 of the FAC program at VY and the bases for his conclusions that the program appropriately implements the recommendations of the Electric Power Research Institute and provides reasonable assurance that effects of aging will be managed such that applicable components will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.
Mr. Fitzpatrick, whose experience and credentials are described above, has been involved with FAC issues since 1987 and was responsible for the development of the FAC program for VY in 1990 and its implementation since that time. In his testimony, Mr. Fitzpatrick will describe the program that VY proposes to implement to control FAC during the period following 5
license renewal, including the criteria used for selecting the components and locations to be inspected for FAC during refueling outages. He will also summarize the most important actions taken at VY to minimize potential effects of FAC and explain why the FAC program to be implemented at VY after license renewal will be adequate to assure the physical integrity of plant components.
Respectfully Submitted, David R. Lewis Matias F. Travieso-Diaz PILLSBURY WINTHROP SHAW PITTMAN LLP 2300 N Street, N.W.
Washington, DC 20037-1128 Tel. (202) 663-8000 Counsel for Entergy Nuclear Vermont Yankee, LLC, and Entergy Nuclear Operations, Inc.
Dated: March 6, 2008 6
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensina Board In the Matter of ))
Entergy Nuclear Vermont Yankee, LLC ) Docket No. 50-271-LR and Entergy Nuclear Operations, Inc. ) ASLBP No. 06-849-03-LR
)
(Vermont Yankee Nuclear Power Station) )
CERTIFICATE OF SERVICE I hereby certify that copies of"Entergy's Final List of Witnesses" dated March 6, 2008, were served on the persons listed below by deposit in the U.S. Mail, first class, postage prepaid, and where indicated by an asterisk by electronic mail, this 6 th day of March, 2008.
- Administrative Judge *Administrative Judge Alex S. Karlin, Esq., Chairman Dr. Richard E. Wardwell Atomic Safety and Licensing Board Atomic Safety and Licensing Board Mail Stop T-3 F23 Mail Stop T-3 F23 U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Washington, D.C. 20555-0001 ask2(@nrc.gov rewmnrc.gov
- Administrative Judge *Secretary Dr. Thomas S. Elleman Att'n: Rulemakings and Adjudications Staff Atomic Safety and Licensing Board Mail Stop 0-16 C1 5207 Creedmoor Road, #101, U.S. Nuclear Regulatory Commission Raleigh, NC 27612. Washington, D.C. 20555-0001 tse@nrc. gov; ellemana),eos .ncsu. edu secy@nrc.gov, hearingdocket@nrc. gov Office of Commission Appellate Adjudication Atomic Safety and Licensing Board Mail Stop 0-16 C I Mail Stop T-3 F23 U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Washington, D.C. 20555-0001
- Lloyd Subin, Esq. *Sarah Hofmann, Esq.
- Mary Baty, Esq. Director of Public Advocacy Office of the General Counsel Department of Public Service Mail Stop 0- 15 D21 112 State Street - Drawer 20 U.S. Nuclear Regulatory Commission Montpelier, VT 05620-2601 Washington, D.C. 20555-0001 Sarah.hofmann(dstate.vt.us LBS3 0anrc. gov; mcb 1@onrc. gov
- Anthony Z. Roisman, Esq. *Ronald A. Shems, Esq.
National Legal Scholars Law Firm *Karen Tyler, Esq.
84 East Thetford Road Shems, Dunkiel, Kassel & Saunders, PLLC Lyme, NH 03768 9 College Street aroisman(cination allegalscholars.com Burlington, VT 05401 rshems(a),sdkslaw.com ktyler@sdkslaw.com
- Peter L. Roth, Esq. *Marcia Carpenter, Esq.
Office of the New Hampshire Attorney General Atomic Safety and Licensing Board Panel 33 Capitol Street Mail Stop T-3 F23 Concord, NH 03301 U.S. Nuclear Regulatory Commission Peter.roth doi.nh.gov Washington, D.C. 20555-0001 mxc7@nrc.gov Matias F. Travieso-Diaz 2