ML101470013
| ML101470013 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/03/2010 |
| From: | James Kim Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| kim J, NRR/ADRO/DORL, 415-4125 | |
| References | |
| TAC ME2909, VY-ISI-014 | |
| Download: ML101470013 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 3, 2010 Vice President, Operations Entergy Nuclear Operations, Inc.
Vermont Yankee Nuclear Power Station P.O. Box 250 Governor Hunt Road Vernon, VT 05354
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION TO SUPPORT THE REVIEW OF THE VERMONT YANKEE NUCLEAR POWER STATION RELIEF REQUEST VY-ISI-014 (TAC NO. ME2909)
Dear Sir or Madam:
By letter dated December 14, 2009, Entergy Nuclear Operations, Inc. (the licensee) submitted Request for Alternative VY-ISI-014, for the fourth 10-year interval inservice inspection (lSI) program at Vermont Yankee Nuclear Power Station (Vermont Yankee), pursuant to paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations (10 CFR).
The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). A response to this RAI is requested to be provided within 30 days.
Sincerely, James Kim, Project Manager Plant l.lcenslnq Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-271
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ALTERNATIVE VY-ISI-014 FOR VERMONT YANKEE NUCLEAR POWER STATION Request VY-ISI-014 proposes an alternative to the lSI requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, in order to implement the alternative examination requirements of ASME Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds,Section XI, Division 1," for several ASME Code Class 1, Examination Category B-D components.
The NRC staff requests that the licensee provide the following additional information concerning this request:
- 1. Please describe the weld materials from which the subject nozzle welds in VY-ISI-014 were fabricated, including any weld repair materials. The staff notes that nickel alloy weld materials, including weld repairs, are highly susceptible to stress-corrosion cracking in a BWR environment and are, therefore, unacceptable for application of the proposed alternative criteria of ASME Code Case N-702.
- 2. Please state whether any relevant indications (e.g., flaws that were evaluated under the ASME Code,Section XI, Article IWB-3000, "Acceptance Standards") were found during previous ultrasonic examinations of ASME Code,Section XI, Examination Category B-D components during the current (fourth) 1O-year lSI Interval or previous lSI intervals.
Describe the nature of any such flaws (e.g., whether the flaws are fabrication flaws or service-induced) and any welds repairs that were implemented for any Examination Category B-D welds.
- 3. Please state whether the provisions of the ASME Code,Section XI, Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems" have been and will continue to be used for volumetric examinations of the subject components.
Enclosure
'.. ML101470013 OFFICE LPL1-1/PM LPL1-1/LA LPL1-1/BC NAME JKim SLittie NSalgado (JBoska for)
DATE 6/2/10 6/1/10 6/3/10