ML13151A029
| ML13151A029 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/28/2013 |
| From: | James Shea Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAC ME6615, TAC ME6616, TAC ME6617 | |
| Download: ML13151A029 (4) | |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 May 28, 2013 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
Correction and Clarification of Proprietary Information Determination Regarding Response to Request for Additional Information Regarding BWRVIP-25 Core Plate Bolt Stress Analysis for BFN Units 1, 2, and 3 (TAC Nos. ME6615, ME6616, and ME6617)
References:
- 1. Letter from TVA to NRC, "BWRVIP-25 Core Plate Bolt Stress Analysis," dated June 15, 2011 (ADAMS No. ML11171A037)
- 2. NUREG-1843, "Safety Evaluation Report Related to the License Renewal of the Browns Ferry Nuclear Plant, Units 1, 2, and 3,"
April 2006
- 3. Letter from TVA to NRC, "Response to Request for Additional Information Regarding BWRVIP-25 Core Plate Bolt Stress Analysis for BFN Units 1, 2, and 3," dated October 25, 2012 (ADAMS No. ML12307A224)
- 4. NRC Letter to TVA, "Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request for Additional Information Related to Core Plate Bolt Stress Analysis (TAC Nos. ME6615, ME6616, and ME6617),"
dated June 28, 2012 (ADAMS No. ML12108A088)
T~y3 ~
Pnnted on recycled paper
U.S. Nuclear Regulatory Commission Page 2 May 28, 2013 On June 15, 2011, Tennessee Valley Authority (TVA) submitted the "BWRVIP-25 Core Plate Bolt Stress Analysis" (Reference 1) for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3, to complete a License Renewal Commitment. Enclosure 1 to that submittal was the General Electric - Hitachi (GEH) document, "Browns Ferry (Units 1-3) Core Plate Bolt Analysis Stress Analysis Report," NEDC-33632P (GEH Proprietary). In section 5.8 on page 7 of NEDC-33632P, the statement "Based on a fluence of 5x1 011 n/cm 2 for a 60 year plant life (54 effective full power years (EFPY))" was marked as GEH proprietary information. During the NRC review, the staff questioned the proprietary determination of the above statement based on information contained in NUREG-1 843 (Reference 2). After further review, GEH has determined the statement referenced above was incorrectly marked as proprietary and can be considered non-proprietary. The corrected page 7 of NEDO-33632 (GEH Non-Proprietary Version of NEDC-33632P) is provided in the enclosure to this letter.
Additionally, the NRC requested clarification regarding the proprietary information provided in the letter from TVA to NRC, "Response to Request for Additional Information Regarding BWRVIP-25 Core Plate Bolt Stress Analysis for BFN Units 1, 2, and 3," dated October 25, 2012 (Reference 3). of Reference 3 provided the TVA response to the NRC Request for Additional Information (RAI) transmitted by Reference 4. The proprietary information contained in of Reference 3 was extracted from Enclosure 3 of Reference 3 and marked as GEH proprietary information. Enclosure 3 of Reference 3 provided the GEH response to the NRC RAI in the form of a GEH proprietary report. The affidavit that requested the withholding of the GEH proprietary information contained in Enclosure 3 of Reference 3 was included as Enclosure 5 of Reference 3. Therefore, please consider the proprietary information so marked in Enclosure 1 of Reference 3 to be GEH proprietary.
This letter does not include any new regulatory commitments. Please direct any questions concerning this matter to Tom Hess at (423) 751-3487.
Respectfully, Vice President, Nuclear Licensing Enclosure Corrected Page from NEDO-33632 Revision 0 cc (Enclosure):
NRC Regional Administrator-Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant Alabama State Department of Public Health
ENCLOSURE Correction and Clarification of Proprietary Information Determination Regarding Response to Request for Additional Information Regarding BWRVIP-25 Core Plate Bolt Stress Analysis for BFN Units 1, 2, and 3 (TAC NOS. ME6615, ME6616, and ME6617)
Corrected Page from NEDO-33632 Revision 0
NEDO-33632 Revision 0 - CORRECTED PAGE 5.6 Preload Preload on the core plate bolts is accounted for after the FEA analysis run
))
5.7 Friction For this analysis, 304 SS is interacting with 304 SS on a wetted interface. ((
1]
A friction factor 0.2 is suggested in Section 5.5 of BWRVIP-5 1A (Reference 5) for modeling the friction restraint for the evaluation of retained flaws unless a higher value can be technically justified.
Typical jet pump material is also SS, and the recommended friction factor of 0.2 should be applicable for the SS core plate and core plate bolts. ((
5.8 Fluence The core plate bolt preload relaxes with fluence. Based on a fluence of 5x1019 n/cm2 for a 60 year plant life (54 effective full power years (EFPY)), ((
5.9 Thermal Relaxation No thermal gradients act across the core plate. However, thermal reduction in the core plate preload is included in the analysis. ((
7