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Category:Letter type:L
MONTHYEARL-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023 Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023 Readiness for Resumption of NRC Supplemental Inspection L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022 L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023 Occupational Radiation Exposure Report for Year 2022 L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023 and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage L-23-059, Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-0022023-03-0909 March 2023 Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-002 L-22-212, CFR 50.55a Request RP-5 Regarding Inservice Pump Testing2023-03-0606 March 2023 CFR 50.55a Request RP-5 Regarding Inservice Pump Testing L-23-048, Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2023-03-0101 March 2023 Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023 Energy Harbor Nuclear Corp Retrospective Premium Guarantee L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023 Submittal of Pressure and Temperature Limits Report, Revision 5 L-22-284, Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS)2022-12-28028 December 2022 Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS) L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022 Submittal of Pressure and Temperature Limits Report. Revision 4 L-22-213, Occupational Radiation Exposure Report for Year 2021 - Correction2022-09-23023 September 2022 Occupational Radiation Exposure Report for Year 2021 - Correction L-22-129, Submittal of the Updated Final Safety Analysis Report, Revision 342022-09-20020 September 2022 Submittal of the Updated Final Safety Analysis Report, Revision 34 L-22-194, Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events2022-09-19019 September 2022 Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events L-22-203, Submittal of Evacuation Time Estimates2022-09-12012 September 2022 Submittal of Evacuation Time Estimates L-22-050, Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual2022-08-0909 August 2022 Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual L-22-152, Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan2022-07-0505 July 2022 Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan L-22-068, Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report2022-06-30030 June 2022 Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report L-22-037, 2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2022-06-30030 June 2022 2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022 Post Accident Monitoring Report L-22-153, Readiness for NRC Supplemental Inspection Required for a White Finding2022-06-22022 June 2022 Readiness for NRC Supplemental Inspection Required for a White Finding L-22-098, Withdrawal of Proposed Inservice Inspection Alternative RR-A22022-06-22022 June 2022 Withdrawal of Proposed Inservice Inspection Alternative RR-A2 L-22-136, Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage2022-06-0707 June 2022 Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage L-22-102, Report of Facility Changes, Tests, and Experiments2022-05-16016 May 2022 Report of Facility Changes, Tests, and Experiments L-22-092, Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 20212022-05-16016 May 2022 Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 2021 L-22-124, Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building2022-05-12012 May 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building L-22-047, Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 12022-05-10010 May 2022 Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 1 L-22-127, Readiness for NRC Supplemental Inspection Required for a Greater than Green Finding2022-05-0606 May 2022 Readiness for NRC Supplemental Inspection Required for a Greater than Green Finding L-22-089, Occupational Radiation Exposure Report for Year 20212022-04-12012 April 2022 Occupational Radiation Exposure Report for Year 2021 L-22-056, Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage2022-03-22022 March 2022 Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage L-22-059, Response to Request for Additional Information on Proposed Inservice Test Alternative RP-32022-03-21021 March 2022 Response to Request for Additional Information on Proposed Inservice Test Alternative RP-3 L-22-074, Response to Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-15015 March 2022 Response to Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations L-22-061, Ile Post Exam Letter L-22-0612022-02-24024 February 2022 Ile Post Exam Letter L-22-061 L-22-023, Retrospective Premium Guarantee2022-02-17017 February 2022 Retrospective Premium Guarantee L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A22022-01-27027 January 2022 Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 L-20-289, Emergency Plan Amendment Request2022-01-19019 January 2022 Emergency Plan Amendment Request L-21-290, Response to NRC Inspection Report 05000346/2021091, EA-21-1762021-12-21021 December 2021 Response to NRC Inspection Report 05000346/2021091, EA-21-176 2023-09-12
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TM 5501 North State Route 2 Oak Harbor, Ohio 43449 FirstEnergy Nuclear Operating Company Brian D. Boles 419-321-7676 Vice President, Fax: 419-321-7582 Nuclear August 12, 2015 L-15-250 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License No. NPF-3 Deviation from MRP-227A. "Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines" In accordance with Nuclear Energy Institute (NEI) 03-08, "Guideline for the Management of Materials Issues," FirstEnergy Nuclear Operating Company (FENOC) is informing the Nuclear Regulatory Commission (NRC) of a deviation from MRP-227A.
The following is a ~ummary of the technical justification for the deviation from MRP-227A inspection requirements for primary and expansion reactor internals components listed in Table 4-1, "B&W Plants Primary Components," and Table 4-4, "B&W Plants Expansion Components." This information is being provided by FE NOC for the Davis-Besse Nuclear Power Station (DBNPS), Unit. No. 1 and is for information only. FENOC is not requesting any action from the NRC staff.
Specifically, the deviation addresses an MPR-227A "needed" requirement because MRP-227A Tables 4-1 and 4-4 cannot be implemented as written. MRP-227A, Table 4-1, for primary component, Lower Grid Assembly, Alloy X-750 dowel-to-guide block welds is no longer applicable to DBNPS because the block was modified after hot functional testing and the X-750 material and associated nickel based weld were removed and replaced with stainless steel materials. The expansion link for the Alloy X-750 dowel-to-guide block welds is the Alloy X-750 dowel locking welds to the upper and lower grid fuel assembly support pads. Table 4-4 states that the upper grid assembly, X-750 dowel-to-upper-grid fuel assembly support pad welds applies to all plants with the exception of DBNPS. However, after review of the fabrication records, Alloy X-750 dowel-to-upper grid fuel assembly support pads were transferred to the DBNPS contract and installed in the plant.
Davis-Besse Nuclear Power Station, Unit No. 1 L-15-250 Page 2 of 3 The deviation replaces the MRP-227A, Table 4-1, Primary Component, Lower Grid Assembly, Alloy X-750 dowel-to-guide block welds with the current MRP-227A, Table 4-4, Expansion Component, Lower Grid Assembly, lower grid fuel assembly Alloy X-750 dowel-to-lower grid fuel assembly support pad welds. The Alloy X-750 dowel-to-upper grid fuel assembly support pads will become the linked expansion component for the Lower Grid Assembly, lower grid fuel assembly support.
The deviation will add two new table rows applicable to DBNPS as follows.
T a bl e 4- 1 B&W Pl ~n t s Pnmary
. componen ts Item Applicability Effect Expansion Examination Examination (Mechanism) Link Method/Frequency Coverage (Note 2) (Note 2)
Lower Grid Davis- Cracking Alloy X-750 Initial visual (VT-3) Accessible Assembly Besse (SCC), dowel-to- examination no later surfaces of Alloy X-750 including the upper than two 100% of the dowel-to- detection of grid fuel refueling outages dowel lockin~
lower grid separated or assembly from the welds.
fuel missing support pad beginning of the assembly locking welds license support welds, or renewal period.
pad welds missing Subsequent dowels. examinations on the 10-year ISi interval.
t Expans1on c omponen ts T a bl e 4 -4 B&W Pl ans Item Applicability Effect Primary Examination Examination (Mechanism) Link Method/Frequency Coverage (Note 1) (Note 1)
Upper Grid Davis- Cracking Alloy X-750 Visual (VT-3) Accessible Assembly Besse (SCC), dowel-to- examination. surfaces of Alloy X-750 including the lower Subsequent 100% of the dowel-to- detection of grid fuel examinations on dowel lockin~
upper grid separated or assembly the 10-year IS I welds fuel missing support pad interval unless assembly locking welds an applicanUlicensee support welds, or provides pad welds missing an evaluation for dowels NRC staff approval that justifies a longer interval between inspections.
Davis-Besse Nuclear Power Station, Unit No. 1 L-15-250 Page 3 of 3 By letter dated July 20, 2015 the Electric Power Research Institute Materials Reliability Program has been notified of the aforementioned needed revision to MRP-227 to address the DBNPS as-built configuration.
The duration of this deviation is from April 22, 2015 until MRP-227 is revised to include the as-built configuration for DBNPS.
Because the alternate actions meet the objective and level of conservatism of MRP-227A, there is no postulated impact to safety.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager-Fleet Licensing at (330) 315-6810.
Sincerely,
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Brian D. Boles cc: NRC Region Ill Administrator NRR Project Manager NRC DLR Project Manager NRC Resident Inspector NRR Division of Component Integrity Utility Radiological Safety Board