BYRON 2011-0018, Regulatory Commitment Change Summary Report
ML110320154 | |
Person / Time | |
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Site: | Byron |
Issue date: | 02/01/2011 |
From: | Enright D Exelon Generation Co, Exelon Nuclear |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
BYRON 2011-0018 | |
Download: ML110320154 (3) | |
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Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee RS-12-162, Company, Llc’S 180-Day Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 Company, Llc’S 180-Day Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12341A1652012-11-0707 November 2012 Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 3 of 3 ML12341A1662012-11-0707 November 2012 Enclosure 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Byron Station, Unit 2, Report No: 12Q0108.20-R-002, Revision 1 RS-12-161, Q0108.20-R-002, Rev. 1, Seismic Walkdown Checklist (Swc). Part 1 of 22012-11-0707 November 2012 Q0108.20-R-002, Rev. 1, Seismic Walkdown Checklist (Swc). Part 1 of 2 ML12341A1612012-11-0707 November 2012 Enclosure 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Byron Station, Unit 1, Report No. 12Q0108.20-R-001, Revision 1 ML12341A1642012-11-0707 November 2012 Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 2 of 3 ML12341A1632012-11-0707 November 2012 Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 1 of 3 RS-12-161, Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 3 of 32012-11-0707 November 2012 Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 3 of 3 RS-12-161, Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 2 of 32012-11-0707 November 2012 Byron Generating Station, Unit 1, 12Q0108.20-R-001, Rev. 1, Appendix C, Seismic Walkdown Checklist (Swc). Part 2 of 3 2024-05-28 |
Contents
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Exel n Nuclear February 1 2011 LTR; BYRON 2011-0018 File: 1.10.0101 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
2010 Regulatory Commitment Change Summary Report Enclosed please find the Regulatory Commitment Change Summary Report for Byron Station.
This report contains summary information from January 1 through December 31, 2010.
Revisions to docketed regulatory commitments were processed using the current revision of Nuclear Energy Institutes document NEI 99-04 Guidelines for Managing Nuclear Regulatory Commission (NRC) Commitment Changes.
If you have any questions concerning this report, please contact D. Gudger, Regulatory Assurance Manager at (815) 406-2800.
Respectfully, Daniel J. Enright Site Vice President Byron Station DJE /TLH! cy Enclosure
ATTACHMENT BYRON STATION REGULATORY COMMITMENT CHANGE
SUMMARY
REPORT FOR 2010 Original Document and Commitment:
Commitment AR 8405 The NRC required compliance to NUREG 0612 Control of Heavy Loads at Nuclear Power Plants. Byron Station Procedure BFP FH-30 was revised effective 06/19/96 to prohibit lifting a spent fuel shipping cask higher than 6 inches above the floor, except to change elevations or maneuver around obstacles.
Subiect of Deletion:
Commitment is being deleted. Implementation of EC 367123 (dry cask storage project) to replace the FHB overhead crane with a single failure proof design meets the intent of limiting the consequences of a dropped cask by restricting cask height.
Basis:
The actions taken meet LS-AA-1 10, Commitment Management, Rev 7, justification for making the commitment no longer valid. As a result of plant changes, they are no longer applicable.
Status:
The commitment was deleted under Commitment Change Number 10-010.
ATTACHMENT BYRON STATION REGULATORY COMMITMENT CHANGE
SUMMARY
REPORT FOR 2010 OriQinal Document and Commitment:
Commitment AR 91 9060-01 The NRC required compliance to NUREG 0612 Control of Heavy Loads at Nuclear Power Plants. NUREG 0612 essentially provided two approaches to achieve risk reduction of a load drop: (1) reduce the likelihood of failure of load handling systems (i.e. make them single-failure proof), or (2) demonstrate that the consequences of failure acceptable.
Because the Fuel Handling Building (FHB) crane originally was not single-failure proof, and because Byron was able to demonstrate that the consequences of a failure was acceptable (i.e.,
by limiting the loads carried and by implementing admin controls on the movement of heavy loads that would limit the consequences of a failure), option 2 was chosen for compliance to NUREG 0612 (Ref: Byron SSER 5 Section 9.1.5).
To maintain option 2 while implementing the lSFSl project, it would have been necessary to demonstrate acceptable consequences of a load drop of the casks involved in the transportation of spent fuel from the SFP to the storage casks. In lieu of that, Byron has elected to change its method of compliance with NUREG 0612 to option 1, single failure proof load handling system.
Subiect of Change:
Commitment is being revised. The Byron FHB crane has been designed and constructed and will be maintained as a single failure proof load handling system in accordance with the guidelines of NUREG 0554 and alternative methods described in Section 5.1.6 and Appendix C of NUREG 0612. Special lifting devices for SEP cask operations meet ANSI N.14.6-1993.
Basis:
As described In NRC RIS 2005-25, licensees may consider a change to a single failure proof load handling system that fully conforms to the guidelines of Section 5.1.6 of NUREG-061 2, an approved method of safely handing heavy loads. As described in NRC RIS 2005-25, Supplement 1, special lifting devices that satisfy ANSI N14.6-1993 are consistent with the NRC Standard Review Plan (NUREG-0800) Section 9.1.5, Rev 1, and are acceptable for use in single failure proof load handling systems.
Status:
The commitment was revised under Commitment Change Number 10-011.