ML11171A037

BWRVIP-25 Core Plate Bolt Stress Analysis

ML11171A037
Person / Time
Site:	Browns Ferry
Issue date:	06/15/2011
From:	Krich R Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MC1704, TAC MC1705, TAC ME1706
Download: ML11171A037 (2)

Text

Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing June 15, 2011 10 CFR 54.7 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

BWRVIP-25 Core Plate Bolt Stress Analysis

References:

1) Letter from TVA to NRC, "Browns Ferry Nuclear Plant (BFN) -

Units 1, 2, and 3 - License Renewal Application (LRA) - Revised Commitment List (TAC Nos. MC1704, MC1705, and MC1706),"

dated April 21, 2006

2) NRC Letter to TVA, "Issuance of Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (TAC Nos. MC1704, MC1705, and MC1706)," dated May 4, 2006

3) NUREG-1843, "Safety Evaluation Report Related to the License Renewal of the Browns Ferry Nuclear Plant, Units 1, 2, and 3,"

dated April 2006 On May 4, 2006, the Nuclear Regulatory Commission (NRC) issued Renewed Facility Operating Licenses to the Tennessee Valley Authority (TVA) for Browns Ferry Nuclear Plant, Units 1, 2, and 3. Per NUREG-1843 (Reference 3), TVA committed to perform a plant specific stress analysis of the Core Plate Hold Down Bolts as described in the Boiling Water Reactor Vessel Internals Program (BWRVIP)-25. Additionally, TVA committed to provide this analysis to the NRC two years prior to the start of the period of extended operation.

printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 June 15, 2011 In accordance with NUREG-1 843, Browns Ferry (Units 1-3) Core Plate Bolt Analysis Stress Analysis Report, NEDC-33632P (GE Proprietary) is provided in Enclosure 1. to this letter contains information that GE Hitachi considers to be proprietary in nature, and subsequently, pursuant to 10 CFR 2.390, "Public inspections, exemptions, requests for withholding," paragraph (a)(4), it is requested that this information be withheld from public disclosure. contains the redacted version of Enclosure 1 with the proprietary material removed, suitable for public disclosure. provides the affidavit supporting the request for withholding from public disclosure.

This letter does not include any new regulatory commitments. Please direct any questions concerning this matter to Tom Matthews at (423) 751-2687.

Respectfuly R. M. Krich

Enclosures:

1) Browns Ferry (Units 1-3) Core Plate Bolt Analysis Stress Analysis Report, NEDC-33632P (GE Proprietary)

2) Browns Ferry (Units 1-3) Core Plate Bolt Analysis Stress Analysis Report, NEDO-33632 (GE Non-Proprietary)

3) Affidavit cc (Enclosures):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant