ML040300088

Draft Request for Additional Information

ML040300088
Person / Time
Site:	Vermont Yankee
Issue date:	01/30/2004
From:	Richard Ennis NRC/NRR/DLPM/LPD1
To:	Darrell Roberts NRC/NRR/DLPM/LPD1
Ennis R, NRR/DLPM, 415-1420
References
TAC MC0253
Download: ML040300088 (3)

Text

January 30, 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. MC0253)

The attached draft request for information (RAI) was transmitted on January 29, 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 amendment request for Vermont Yankee Nuclear Power Station (VYNPS) dated July 31, 2003, as supplemented on October 10, November 7 (2 letters), December 11 (2 letters), and December 30, 2003. The proposed amendment would revise the VYNPS licensing basis by incorporating full scope application of an Alternative Source Term methodology.

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 30, 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. MC0253)

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 amendment request for Vermont Yankee Nuclear Power Station (VYNPS) dated July 31, 2003, as supplemented on October 10, November 7 (2 letters), December 11 (2 letters), and December 30, 2003. The proposed amendment would revise the VYNPS licensing basis by incorporating full scope application of an Alternative Source Term methodology.

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 RHernandez PDI-2 Reading REnnis DSolorio ACCESSION NO.: ML040300088 OFFICE PDI-2/PM NAME REnnis DATE 1/29/04 OFFICIAL RECORD COPY

DRAFT REQUEST FOR ADDITIONAL INFORMATION RELATED TO ALTERNATIVE SOURCE TERM AMENDMENT REQUEST VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 By letter dated July 31, 2003, as supplemented on October 10, November 7 (2 letters),

December 11 (2 letters), and December 30, 2003, Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (Entergy or the licensee) submitted an amendment request for Vermont Yankee Nuclear Power Station (VYNPS). The proposed amendment would revise the VYNPS licensing basis by incorporating full scope application of an Alternative Source Term methodology.

The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittals:

1) While reviewing the system boundary, the staff found that valve OG-786 (located in grid E-2 of SUNTAC drawing A217) was not identified on the simplified diagram provided in Appendix A of Attachment 5 of the submittal dated July 31, 2003, nor was it identified on the system boundary description provided in Appendix A of Attachment 5 of the submittal. Provide the basis for concluding that valve OG-786 should not be included within the Alternate Leakage Treatment Seismic Boundary and provide a copy of the latest version of the drawing.

2) Attachment 5, page 54, of the licensees submittal dated July 31, 2003, states that:

"Since the radiological analysis accounts for leakage through the turbine stop valves (0.5% of total MSIV leakage), it is not necessary to meet the flow area fraction ratio described in Section 4.0 to Appendix C of NEDC-31858P Rev. 2."

a. Provide the basis for the assumption that leakage through the turbine stop valves will not exceed 0.5% of total MSIV leakage.

b. Provide the flow area fraction as described in Section 4.0 to Appendix C of EDC-31858P Rev. 2, including an explanation of how it was determined.

ATTACHMENT