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Category:Letter type:BYRON
MONTHYEARBYRON 2023-0065, Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline2023-11-17017 November 2023 Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) BYRON 2023-0029, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-06-0101 June 2023 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements BYRON 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Plan, Training and Qualification Plan, and Independent Spent Fuel Storage Installation Plan, Revision 17 BYRON 2020-0008, 2019 Regulatory Commitment Change Summary Report2020-02-0707 February 2020 2019 Regulatory Commitment Change Summary Report BYRON 2019-0105, Post Examination Submittal Letter2019-11-26026 November 2019 Post Examination Submittal Letter BYRON 2019-0095, Registration of Use of Cask to Store Spent Fuel2019-10-10010 October 2019 Registration of Use of Cask to Store Spent Fuel BYRON 2019-0090, Registration of Use of Cask to Store Spent Fuel2019-09-18018 September 2019 Registration of Use of Cask to Store Spent Fuel BYRON 2019-0078, Registration of Use of Cask to Store Spent Fuel2019-08-22022 August 2019 Registration of Use of Cask to Store Spent Fuel BYRON 2019-0041, Revision to Site Security Plan, Safeguards Contingency Plan, Training and Qualification Plan, and Independent Spent Fuel Storage Installation Plan, Revision 162019-04-25025 April 2019 Revision to Site Security Plan, Safeguards Contingency Plan, Training and Qualification Plan, and Independent Spent Fuel Storage Installation Plan, Revision 16 BYRON 2019-0035, Submittal of 2018 Annual Radioactive Effluent Release Report2019-04-18018 April 2019 Submittal of 2018 Annual Radioactive Effluent Release Report BYRON 2019-0040, Cycle 22 Core Operating Limits Report2019-04-15015 April 2019 Cycle 22 Core Operating Limits Report BYRON 2019-0039, Annual Dose Report for 20182019-04-11011 April 2019 Annual Dose Report for 2018 BYRON 2019-0022, 2018 Regulatory Commitment Change Summary Report2019-03-13013 March 2019 2018 Regulatory Commitment Change Summary Report BYRON 2019-0015, Cycle 23 Core Operating Limits Report and Byron Station Unit 2 Cycle 21 Core Operating Limits Report2019-03-0707 March 2019 Cycle 23 Core Operating Limits Report and Byron Station Unit 2 Cycle 21 Core Operating Limits Report BYRON 2018-0130, Transmittal of 90-Day Lnservice Inspection Report for Interval 4, Period 1, (B1R22)2018-12-20020 December 2018 Transmittal of 90-Day Lnservice Inspection Report for Interval 4, Period 1, (B1R22) 2023-06-01
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Exelkrns.
Exelon Generation Company LLC www.exeloncorp.com Nuclear Byron StationNula 4450 North German Church Road Byron, IL 61010-9794 December 17, 2004 LTR: BYRON 2004-0131 File: 2.01.0700 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit 1 and Unit 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
Notification of Deferral of a Generic Letter (GL) 89-13 Component Cooling Heat Exchanger Inspection
References:
- 1) Generic Letter 89-13, "Service Water System Problems Affecting Safety Related Equipment,dated July 18, 1989"
- 2) Letter from M.H. Richter (Exelon) to NRC Document Control Desk, "Response to Generic Letter 89-13, dated January 29,1990"
- 3) Letter from S.E. Kuczynski (Exelon) to NRC Document Control Desk, "Regulatory Commitment Change Summary Report, dated April 1, 2004" Byron Station Unit 1 and 2 have a shared Component Cooling (CC) Water Heat Exchanger (i.e., OCC01A). Conducting a visual inspection of this heat exchanger on a frequency of once per 5 years is part of our commitment to GL 89-13. In Reference 3 we notified the NRC of a revision to this commitment to allow a 25% grace period to the 5-year frequency in order to facilitate scheduling.
OCCOlA was successfully inspected in the first four inspections since implementation of the GL 89-13 Program (i.e., June 1990, January 1992, July 1993, and June 1998.)
However, the fifth inspection scheduled for .Septmber2004 could not be accomplished due to the inability to obtain proper isolation of the heat exchanger due to degraded essential service water isolation valves. September 2004 was the end of the 5-year plus 25% interval.
An Engineering Evaluation concluded that it was acceptable to defer this inspection by 6 months until the Unit-1 refueling outage (i.e., B1 R1 3) scheduled for March 2005. This extension was based on historic inspection and Eddy Current Test results of OCC01A, comparison to the other CC heat exchangers and operational parameters of the OCCOlA during plant cooldowns for at least the last two refuel outages. During B1 R13 outage period, a preferred thermal performance test is planned for this heat exchanger versus a visual inspection. Subsequent to this performance test, a suitable periodic inspection of OCC01 A will be chosen but not to exceed a nominal 5-year frequency.
Should you have any questions concerning this letter, please contact William Grundmann, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, Stephen E. Kuczynski Site Vice President Byron Nuclear Generating Station cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Byron Station NRC Project Manager - NRR - Byron Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety
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Text
Exelkrns.
Exelon Generation Company LLC www.exeloncorp.com Nuclear Byron StationNula 4450 North German Church Road Byron, IL 61010-9794 December 17, 2004 LTR: BYRON 2004-0131 File: 2.01.0700 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit 1 and Unit 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
Notification of Deferral of a Generic Letter (GL) 89-13 Component Cooling Heat Exchanger Inspection
References:
- 1) Generic Letter 89-13, "Service Water System Problems Affecting Safety Related Equipment,dated July 18, 1989"
- 2) Letter from M.H. Richter (Exelon) to NRC Document Control Desk, "Response to Generic Letter 89-13, dated January 29,1990"
- 3) Letter from S.E. Kuczynski (Exelon) to NRC Document Control Desk, "Regulatory Commitment Change Summary Report, dated April 1, 2004" Byron Station Unit 1 and 2 have a shared Component Cooling (CC) Water Heat Exchanger (i.e., OCC01A). Conducting a visual inspection of this heat exchanger on a frequency of once per 5 years is part of our commitment to GL 89-13. In Reference 3 we notified the NRC of a revision to this commitment to allow a 25% grace period to the 5-year frequency in order to facilitate scheduling.
OCCOlA was successfully inspected in the first four inspections since implementation of the GL 89-13 Program (i.e., June 1990, January 1992, July 1993, and June 1998.)
However, the fifth inspection scheduled for .Septmber2004 could not be accomplished due to the inability to obtain proper isolation of the heat exchanger due to degraded essential service water isolation valves. September 2004 was the end of the 5-year plus 25% interval.
An Engineering Evaluation concluded that it was acceptable to defer this inspection by 6 months until the Unit-1 refueling outage (i.e., B1 R1 3) scheduled for March 2005. This extension was based on historic inspection and Eddy Current Test results of OCC01A, comparison to the other CC heat exchangers and operational parameters of the OCCOlA during plant cooldowns for at least the last two refuel outages. During B1 R13 outage period, a preferred thermal performance test is planned for this heat exchanger versus a visual inspection. Subsequent to this performance test, a suitable periodic inspection of OCC01 A will be chosen but not to exceed a nominal 5-year frequency.
Should you have any questions concerning this letter, please contact William Grundmann, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, Stephen E. Kuczynski Site Vice President Byron Nuclear Generating Station cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Byron Station NRC Project Manager - NRR - Byron Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety
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