ML062150553
| ML062150553 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 08/01/2006 |
| From: | Rowley J NRC/NRR/ADRO/DLR/RLRB |
| To: | Kansler M Entergy Nuclear Operations |
| Rowley J, NRR/DRIP/RLEP, 415-4053 | |
| References | |
| %dam200611 | |
| Download: ML062150553 (7) | |
Text
August 1, 2006 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601-1839
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION
Dear Mr. Kansler:
By letter dated January 25, 2006, as supplemented by letter dated March 15, 2006, the U.S. Nuclear Regulatory Commission (NRC) received the Entergy Nuclear Operations, Inc.
application for renewal of Operating License No. DPR-28 for the Vermont Yankee Nuclear Power Station (VYNPS). The NRC staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Specifically, the enclosed requests for additional information are from the NRC Project Team that performed the Aging Management Program, Aging Management Review, and Time-limited Aging Analysis audits at VYNPS.
Based on discussions with Mr. Jim DeVincentis of your staff, a mutually agreeable date for your response is within 30 days of the date of this letter. If you have any questions regarding this letter or if circumstances result in your need to revise the response date, please contact me at 301-415-4053 or by e-mail at jgr@nrc.gov.
Sincerely,
/RA/
Jonathan Rowley, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-271
Enclosure:
Requests for Additional Information cc w/encl: See next page
ML062151553 Document Name: E:\\Filenet\\ML062150553.wpd OFFICE PM:RLRB:DLR LA:DLR BC:RLRB;DLR NAME JRowley Iking JZimmerman DATE 07/ 14 /06 07/ 14 /06 08/ 1 /06
Letter to Michael Kansler from Jonathan Rowley dated August 1, 2006
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION HARD COPY DLR R/F E-MAIL:
JFair RWeisman AMurphy RPettis GGalletti DShum GBagchi SSmith (srs3)
SDuraiswamy YL (Renee) Li RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDe RidsNrrDci RidsNrreEemb RidsNrrDeEeeb RidsNrrDeEqva RidsNrrDss RidsNrrDnrl RidsOgcMailCenter RidsNrrAdes DLR Staff JEads JRowley RLaufer JShea CAnderson, RI MSykes, RI DScrenci, RI MModes, RI DPelton, Sr. Resident MLemoncelli RidsOpaMail
Vermont Yankee Nuclear Power Station cc:
Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. David R. Lewis Pillsbury, Winthrop, Shaw, Pittman, LLP 2300 N Street, N.W.
Washington, DC 20037-1128 Mr. David OBrien, Commissioner Vermont Department of Public Service 112 State Street Montpelier, VT 05620-2601 Mr. James Volz, Chairman Public Service Board State of Vermont 112 State Street Montpelier, VT 05620-2701 Chairman, Board of Selectmen Town of Vernon P.O. Box 116 Vernon, VT 05354-0116 Operating Experience Coordinator Vermont Yankee Nuclear Power Station 320 Governor Hunt Road Vernon, VT 05354 G. Dana Bisbee, Esq.
Deputy Attorney General 33 Capitol Street Concord, NH 03301-6937 Chief, Safety Unit Office of the Attorney General One Ashburton Place, 19th Floor Boston, MA 02108 Ms. Deborah B. Katz Box 83 Shelburne Falls, MA 01370 Ms. Carla A. White, RRPT, CHP Radiological Health Vermont Department of Health P.O. Box 70, Drawer #43 108 Cherry Street Burlington, VT 05402-0070 Mr. James M. DeVincentis Manager, Licensing Vermont Yankee Nuclear Power Station P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302-0500 Resident Inspector Vermont Yankee Nuclear Power Station U. S. Nuclear Regulatory Commission P.O. Box 176 Vernon, VT 05354 Director, Massachusetts Emergency Management Agency ATTN: James Muckerheide 400 Worcester Rd.
Framingham, MA 01702-5399 Jonathan M. Block, Esq.
Main Street P.O. Box 566 Putney, VT 05346-0566 Mr. John F. McCann Director, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Gary J. Taylor Chief Executive Officer Entergy Operations 1340 Echelon Parkway Jackson, MS 39213
Vermont Yankee Nuclear Power Station cc:
Mr. John T. Herron Sr. VP and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Oscar Limpias Vice President, Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Christopher Schwartz Vice President, Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Michael J. Colomb Director of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Travis C. McCullough Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Ted Sullivan Site Vice President Entergy Nuclear Operations, Inc.
Vermont Yankee Nuclear Power Station P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302-0500 Mr. James H. Sniezek 5486 Nithsdale Drive Salisbury, MD 21801 Ms. Stacey M. Lousteau Treasury Department Entergy Services, Inc.
639 Loyola Avenue New Orleans, LA 70113 Mr. Raymond Shadis New England Coalition Post Office Box 98 Edgecomb, ME 04556 Mr. James P. Matteau Executive Director Windham Regional Commission 139 Main Street, Suite 505 Brattleboro, VT 05301 Mr. William K. Sherman Vermont Department of Public Service 112 State Street Drawer 20 Montpelier, VT 05620-2601 Mr. Michael D. Lyster 5931 Barclay Lane Naples, FL 34110-7306 Ms. Charlene D. Faison Manager, Licensing 440 Hamilton Avenue White Plains, NY 10601 Mr. James Ross Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708
Enclosure VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION (RAIs)
RAI 3.5.1-53-W-1 In Table 3.5.2-1 (Primary Containment, page 3.5-54) of the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application (LRA), it states that the vent header support component, made of carbon steel material in an exposed fluid environment, has an aging effect of loss of material. The Generic Aging Lessons Learned (GALL) Report line item shown is III.B1.1-13 and the Table 1 reference is 3.5.1-53. The aging management program (AMP) shown for this line item is Inservice Inspection-IWF. GALL Report line Item III.B1.1-13 is for an indoor uncontrolled air or outdoor air environment. Please explain why GALL Report line Item III.B1.1-11 (treated water environment) and Table 1 Reference 3.5.1-49 are not associated with this aging management review (AMR) line item and the VYNPS Water Chemistry Control -
BWR Program also shown with the Inservice Inspection-IWF AMP.
RAI 3.3.1-22-K-01 Please confirm that no auxiliary components have elastomer linings or stainless steel cladding.
If there are such components, please provide a list of these componenets. Also, provide additional justification for the determination that pitting and crevice corrosion do not require aging management.
RAI 3.3.1-68-K-03 Beginning on Page 3.3-206 of the VYNPS LRA, loss of material from carbon steel components is managed using One-Time Inspection (OTI). Please justify the use of OTI for carbon steel exposed to raw water as opposed to a periodic inspection.
RAI 4.3-H-01 Table 4.3-2 on Page 4.3-4 of the VYNPS LRA indicates that the design transient of reactor startup/shutdown cycles has bounded all other transients for the reactor coolant system (RCS).
Please describe all the transients bounded and demonstrate this bounding transient encompasses all other RCS transients (e.g. transient curves for pressure and temperature cycles). Please demonstrate that the cumulative usage factors (CUFs) are still within the limit of this revised bounding transient.
RAI 4.3-H-02 Does the revised feedwater nozzle analysis (Table 4.3-3) include the unanticipated leakage bypass transient which was described in NUREG-0619? If this actual transient was not considered in the CUF evaluation, please provide justification for excluding it.
RAI 4.3-H-03 In the basis document of the Fatigue Monitoring Program, 100EF/hour heatup/cooldown rate was identified for the normal transient conditions. The actual operating condition for heatup and cooldown rate is 100EF when averaged over any one hour period. Therefore, the actual operating condition may indicate much higher rate than 100EF/hour. For example, a 60EF temperature change for the 0.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period represents a 600EF/hour rate. Physically, thermal stress is a function of rate of temperature difference. The higher the rate, the higher the stress.
Please provide a description to ensure that VYNPSs automatic cycle counting program will adequately define the transients and cycle numbers. Please provide a description to ensure the fatigue cumulative usage factor and thermal stresses are evaluated in accordance with the actual transients or encompassed by the actual transients.
RAI 3.1.1-17-P-01 According to USNRC Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, analytic uncertainty (Section 1.4.1) is to be considered in the calculation of fluence. As noted by the staff, in GE-NE-000-0007-2342-R1-NP (dated July 2003), Entergy Northeast Vermont Yankee Neutron Flux Evaluation, flux variations of up to but less than 19% was considered. In response to staff AMR audit question
- 202, the applicant provided extrapolated data to determine if the top of the recirculation inlet nozzles (located at a 104R940 height of 202 inches) might experience an extended power uprate fluence of >1XE17.
Was a maximum flux variation of ~19%, considered in this extrapolated data? If not, what calculated fluence level would be experienced by the top of the recirculation inlet nozzles when the applicant considers a maximum flux variation of just less than 19%?