ML040050187
| ML040050187 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/05/2004 |
| From: | Richard Ennis NRC/NRR/DLPM/LPD1 |
| To: | Darrell Roberts NRC/NRR/DLPM/LPD1 |
| Ennis R, NRR/DLPM, 415-1420 | |
| References | |
| TAC MC0848 | |
| Download: ML040050187 (3) | |
Text
January 5, 2004 MEMORANDUM TO:
Darrell J. Roberts, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM:
Richard B. Ennis, Senior Project Manager, Section 2
/RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MC0848)
The attached draft request for information (RAI) was transmitted on January 5, 2004, to Ms. Ronda Daflucas of Entergy (the licensee). This information was transmitted to facilitate a upcoming conference call in order to clarify the licensees relief request ISI-06 for Vermont Yankee Nuclear Power Station dated September 25, 2003. The licensee's submittal proposes alternative examination requirements for Reactor Pressure Vessel (RPV) circumferential shell welds in lieu of certain requirements in Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code).
This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.
Docket No. 50-271
Attachment:
Draft RAI
January 5, 2004 MEMORANDUM TO:
Darrell J. Roberts, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM:
Richard B. Ennis, Senior Project Manager, Section 2
/RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MC0848)
The attached draft request for information (RAI) was transmitted on January 5, 2004, to Ms. Ronda Daflucas of Entergy (the licensee). This information was transmitted to facilitate a upcoming conference call in order to clarify the licensees relief request ISI-06 for Vermont Yankee Nuclear Power Station dated September 25, 2003. The licensee's submittal proposes alternative examination requirements for Reactor Pressure Vessel (RPV) circumferential shell welds in lieu of certain requirements in Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code).
This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.
Docket No. 50-271
Attachment:
Draft RAI DISTRIBUTION PUBLIC DRoberts NRay MKhanna PDI-2 Reading REnnis SCoffin ACCESSION NO.: ML040050187 OFFICE PDI-2/PM NAME REnnis DATE 01/05/04 OFFICIAL RECORD COPY
ATTACHMENT DRAFT REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUEST ISI-06 VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 By letter dated dated September 25, 2003, Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (Entergy or the licensee) submitted relief request ISI-06 for Vermont Yankee Nuclear Power Station (VYNPS). The licensees submittal proposes alternative examination requirements for Reactor Pressure Vessel (RPV) circumferential shell welds in lieu of certain requirements in Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code).
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed relief request and would like to discuss the following issues to clarify the submittal:
1)
As discussed in the submittal dated September 25, 2003, during VYNPS refueling outage 19 (in 1996), the licensee performed augmented examination of essentially all of the accessible RPV circumferential and axial shell welds. During the inspection, seven indications in the RPV were found and one of them exceeded the Section XI acceptance criteria. The flaw was accepted in an NRC Safety Evaluation dated October 11, 1996.
Subsequently, the licensee sought relief from successive inspection of that particular flaw. Entergy letter dated January 28, 1999, stated "for this flaw VY will continue to examine the required vessel volumetric inspection according to the schedule stipulated by ASME Section XI, IWB-2412." Based on that commitment, the NRC approved the alternate inspection (Safety Evaluation dated April 7, 1999).
The licensee is now requesting relief from the requirements of examination of circumferential welds based on BWRVIP-05. The NRC staff would like to discuss the basis for the requested relief.