ML051040242

Draft Request for Additional Information

ML051040242
Person / Time
Site:	Vermont Yankee
Issue date:	04/14/2005
From:	Richard Ennis NRC/NRR/DLPM/LPD1
To:	Darrell Roberts NRC/NRR/DLPM/LPD1
Ennis R, NRR/DLPM, 415-1420
References
TAC MC5243
Download: ML051040242 (4)

Text

April 14, 2005 MEMORANDUM TO: Darrell J. Roberts, 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. MC5243)

The attached draft request for information (RAI) was transmitted on April 14, 2005, to Mr. James DeVincentis 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 dated December 6, 2004. The proposed amendment would make administrative changes to the Technical Specifications (TSs) including correction of references and deleting obsolete or redundant TS requirements and surveillances.

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

April 14, 2005 MEMORANDUM TO: Darrell J. Roberts, 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. MC5243)

The attached draft request for information (RAI) was transmitted on April 14, 2005, to Mr. James DeVincentis 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 dated December 6, 2004. The proposed amendment would make administrative changes to the Technical Specifications (TSs) including correction of references and deleting obsolete or redundant TS requirements and surveillances.

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 PHearn VBucci, OIG PDI-2 Reading REnnis TBoyce ACCESSION NO.: ML051040242 OFFICE PDI-2/PM NAME REnnis DATE 4/14/05 OFFICIAL RECORD COPY

DRAFT REQUEST FOR ADDITIONAL INFORMATION AMENDMENT REQUEST FOR ADMINISTRATIVE CHANGES VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 By letter dated December 6, 2004, 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 make administrative changes to the Technical Specifications (TSs) including correction of references and deleting obsolete or redundant TS requirements and surveillances.

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 submittal:

1. On page 6 of 8 of Attachment 1 to the submittal, the licensee proposed relocating TS 3.7.C.5 and Surveillance Requirement 4.7.C.5 to the Final Safety Analysis Report.

This relocation involves moving requirements for maintaining the Core Spray and low pressure coolant injection (LPCI) lower compartment doors closed in order to provide flood protection. Please provide additional information regarding the design and licensing basis for this flood protection function.

2. Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36(c)(2)(ii) requires that a TS limiting condition for operation (LCO) be established for each item meeting one or more of the following criteria:

Criterion 1: Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.

Criterion 2: A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

Criterion 3: A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

Criterion 4: A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.

Provide justification, using the above criteria, for the proposed relocation of TS LCO 3.7.C.5.

ATTACHMENT