ML043580395
| ML043580395 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Crystal River, PROJ0693, Crane  |
| Issue date: | 12/21/2004 |
| From: | Mallay J AmerGen Energy Co, B & W Owners Group, Duke Energy Corp, Entergy Operations, FirstEnergy Nuclear Operating Co, Florida Power Corp, Framatome ANP |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BAW-2308(NP), Rev 1, NRC:04:074, OG:04:1858 | |
| Download: ML043580395 (3) | |
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Duke Energy Company Oconee 1, 2, 3 ArnerGen Energy Company, LLC TMI-1 Entergy Operations, Inc.
ANO-1 The B&W FirstEnergy Nuclear Operating Company D-B Florida Power Corporation Crystal River 3 Owners Group Framatome ANP Working Together to Economically Provide Reliable and Safe Electrical Power December 21, 2004 OG :04:1858 NRC:04:074 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Response to Request for Usage Summary on BAW-2308(NP), Revision 1, "Initial RTNDT of Linde 80 Weld Materials."
Ref.: 1. Letter, James F. Mallay (Framatome ANP), to Document Control Desk (NRC), UB&W Owners Group Reactor Vessel Working Group Submittal of Topical Report BAW-2308, 'Initial RTNDT of Linde 80 Weld Material'," NRC:02:039, July 26, 2002.
In a conference call with the NRC on December 9, 2004, the NRC requested a summary of the B&WOG member plants planning to use BAW-2308 (Reference 1) for licensing and operating applications. On behalf of the B&W Owners Group, Framatome ANP is providing a listing of those licensees who intend to use this topical report with a brief description of their specific needs.
The timely completion of the review of this topical report is appreciated.
Very truly yours, James F. Mallay, Director Regulatory Affairs cc:
D. G. Holland B&WOG Reactor Vessel Working Group Risk Informed Action Committee Project 693
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Document Control Desk NRC:04:074/OG:04:1858 Decembgr 21, 2004 Page A-1 Attachment I Plants that intend to use BAW-2308 "Initial RTNDT of Linde 80 Weld Materials" This summarizes the intent of the operators of 12 of the 13 B&WOG RVWG member plants to use BAW-2308 for licensing and operating applications as described below:
Dominion Surry Unit 1 hafnium flux suppression inserts are nearing the end of their design life. New ones will need to be purchased and inserted. A better option is justification of continued operation without their use. The flux suppression assemblies reduce output by about 8 EFPD per cycle. BAW-2308 provides the necessary justification. Dominion would also like to implement integral fuel burnable absorbers which would reduce power peaking evening out the power distribution (BAW-2308 is also needed for this core change). BAW-2308 could also be used to improve the PTS position and possibly the P-T limits of Surry Unit 2.
Florida Power & Light FP&L would like to remove the flux suppression assemblies from Turkey Point Units 3 and 4. Both units are close to the PTS screening criteria at 60 years. BAW-2308 would enable the removal of the flux suppression assemblies.
Exelon Exelon is currently evaluating uprate and license renewal for TMI Unit 1. At 40 years of operation with the current power level, the longitudinal weld is close to the PTS screening criteria. BAW-2308 approval would allow the PTS issue to be dealt with cleanly in the license renewal application.
Duke Power Duke continues to evaluate how best to optimize plant operations by studying the benefits of two year fuel cycles, uprating and updating P-T curves to improve their operating window. Also, further license extension possibilities need to be studied. Oconee Unit 2 is close to the PTS screening criteria at the end of 60 years of operation. BAW-2308 resolves reactor vessel integrity issues that need to be addressed when pursuing these options.
Nuclear Management Company NMC has applied for license renewal for Point Beach Units 1 and 2. The application uses the current IOCFR50.61 methodology with Unit 2 exceeding the screening criteria at 60 years with a planned uprate and removal of the hafnium suppression rods. Approval of BAW-2308 will enable the PTS issue to be resolved.
The RTpTs of the lower shell circumferential SA-1484 weld at Point Beach Unit 2 is close to the PTS screening criteria with a projected fluence of 4.8e19 n/cm2 (E>IMeV) at 60 years. NMC is also considering calculating new P-T curves incorporating the BAW-2308 initial RTTO. The common P-T curves of the two units are limited by the lower shell longitudinal SA-847 weld in Unit 1. NMC is considering using the lowered RTNDT values to improve the P-T curves for the units.
Document Control Desk NRC:04:074/OG:04:1858 December 20, 2004 Page A-2 FirstEnergy Nuclear Operating Company FENOC intends to submit P-T curves for Davis-Besse using BAW-2308 and other updated methodologies to improve operating margin.
Entermy Operations ANO Unit 1 has relatively restrictive P-T curves. Entergy has contracted Framatome ANP to calculate new P-T curves. Use of BAW-2308 will provide a wider operating window improving operator margins. Entergy intends to submit new P-T curves in the summer of 2005. In addition, Entergy is considering a power uprate for ANO-1.
Florida Power The Crystal River Unit 3 limiting weld (WF-70) initial RTNDT has already been reduced based on master curve data in 1993. Therefore, no improvement is anticipated for CR-3 with the use of BAW-2308.