ML040020063

Draft Request for Additional Information

ML040020063
Person / Time
Site:	Vermont Yankee
Issue date:	01/02/2004
From:	Richard Ennis NRC/NRR/DLPM/LPD1
To:	Darrell Roberts NRC/NRR/DLPM/LPD1
Ennis R, NRR/DLPM, 415-1420
References
TAC MC0960
Download: ML040020063 (3)

Text

January 2, 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. MC0960)

The attached draft request for information (RAI) was transmitted on December 31, 2003, 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 RI-01 for Vermont Yankee Nuclear Power Station dated October 1, 2003, as supplemented by letter dated December 23, 2003. The licensee's submittal proposes to use various Boiling Water Reactor Vessels Internal Program (BWRVIP) guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for Inservice Inspection of Reactor Pressure Vessel internal components.

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 2, 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. MC0960)

The attached draft request for information (RAI) was transmitted on December 31, 2003, 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 RI-01 for Vermont Yankee Nuclear Power Station dated October 1, 2003, as supplemented by letter dated December 23, 2003. The licensee's submittal proposes to use various Boiling Water Reactor Vessels Internal Program (BWRVIP) guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for Inservice Inspection of Reactor Pressure Vessel internal components.

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 ALee MKhanna PDI-2 Reading REnnis SCoffin ACCESSION NO.: ML040020063 OFFICE PDI-2/PM NAME REnnis DATE 12/31/03 OFFICIAL RECORD COPY

DRAFT REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUEST RI-01 VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 By letter dated dated October 1, 2003, as supplemented by letter dated December 23, 2003, Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (Entergy or the licensee) submitted relief request RI-01 for Vermont Yankee Nuclear Power Station (VYNPS).

The licensees submittal proposes to use various Boiling Water Reactor Vessels Internal Program (BWRVIP) guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for Inservice Inspection of Reactor Pressure Vessel (RPV) internal components.

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 submittals:

1) The Inspection Basis column in Table 1 of the submittal dated December 23, 2003, references the following General Electric (GE) Service Information Letters (SILs) as the basis for the inspection of various RPV internal components: SIL 462, Revision 1; SIL 409, Revision 2; and SIL 644, Supplement 1. The NRC staff needs a copy of these GE SILs as part of the review.

2) The Inspection Basis column in Table 1 of the submittal dated December 23, 2003, has the term Risk To Generation as the basis for the inspection of various RPV internal components. The licensee should provide an explanation for this term and how it serves as an inspection basis.

3) The Inspection Basis column in Table 1 of the submittal dated December 23, 2003, has the term NRC Commitment as the basis for inspection of the vessel cladding. The licensee should elaborate on the specifics of this commitment (i.e., provide a reference to explain the nature of the commitment etc.).

ATTACHMENT