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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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(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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Exeltkn Exelon Generation Company, LLC Byron Station www.exeloncorp.com Nuclear 4450 North German Church Road Byron, IL 61010-9794 June 2, 2004 LTR: BYRON 2004-0061 File: 1.10.0101 United States Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Byron Station Unit 2 Facility Operating License No. NPF-66 NRC Docket No. STN 50-455
Subject:
Byron Station Unit 2 60-Day,-Response to First Revised NRC Order EA-03-009, "issuance 6f First Revised NRC Order (EA-03-009) Establishing Presurizd
- nterirni nspe6tion eq~er~ntsfor eac6'r Press Requirements 009)sse ssure Vessel Hestbihn Heads at' Pressurized Water Reacto.rs.
References:
- 1) Letter from NRC, "Issuance bf First Revised NRC Order (EA-03-009)
Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors," dated February 20, 2004.
- 2) Letter from R. P. Lopriore to NRC, 'Byron Station Unit 2 Response to NRC Bulletin 2002-01, uReactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity"," dated October 25, 2002.
In Reference 1, (i.e., First Revised NRC Order EA-03-009), the NRC modified interim inspection requirements for reactor pressure vessel (RPV) heads at pressurized water reactors. A bare metal visual inspection of the Byron Station Unit 2 RPV head surface, equivalent to that required by Section IV, paragraph C (5) (a) of Reference 1, was performed during Byron Station, Unit 2 refueling outage 10 (i.e., B2R10) in Fall 2002. The results of this inspection were provided to the NRC in Reference 2.
As'required by Reference 1,Section IV, paragraph D, a visual inspection'to identify potential boric acid leaks from pressure-retaining components above the RPV head was performed during Byron Station, Unitf2'refuelirig outage 11 (i.e., .B2R1 1) in March 2004. The visual inspection did not identify any boric acid leaks from pressure-retaining components above the RPV head or any boron deposits'on the mirror inusulation'above'the RPV head.
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June 2, 2004 U.S. Nuclear Regulatory Commission Page 2 Since no leakage or boron deposits were identified during this inspection, a report in accordance with Reference 1,Section IV, paragraph E, is not required to be submitted; however, the inspection results are being provided to assure thorough communications on First Revised NRC Order EA-03-009 actions.
Should you have any questions or desire additional information regarding 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