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MONTHYEARML0633202222006-11-30030 November 2006 Forthcoming Meeting with Duke Power Company LLC, to Discuss the Use of Fiber-Reinforced Polymer Project stage: Meeting ML0700804162006-12-12012 December 2006 Licensee Handouts for Oconee, Summary of December 12, 2006 Meeting Project stage: Meeting ML0700400512007-01-0909 January 2007 Onconee Nuclear Station, Summary of December 12, 2006, to Discuss the Use of Fiber-Reinforced Polymer (TAC Nos. MD22129, MD2130, MD2131) Project stage: Other ML0712303292007-05-0303 May 2007 5/14/07, Meeting Notice to Discuss the Use of Fiber-Reinforced Polymer at Oconee Nuclear Station, Units 1, 2, and 3 Project stage: Meeting ML0803200652008-02-21021 February 2008 Issuance of Amendments Regarding Use of Fiber-Reinforced Polymer (FRP) Project stage: Approval ML0803200712008-02-21021 February 2008 Technical Specifications, Issuance of Amendments Regarding Use of Fiber-Reinforced Polymer (FRP) Project stage: Approval ML0807204142008-03-26026 March 2008 Correction to Amendment Nos. 360, 362, and 361 for Oconee Nuclear Station, Units 1, 2, and 3 Project stage: Other ML0807204332008-03-26026 March 2008 Correction Pages for Correction to Amendment Nos. 360, 362, and 361 for Oconee Nuclear Station, Units 1, 2, and 3 Project stage: Other 2007-01-09
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Category:Safety Evaluation
MONTHYEARML24145A1782024-08-26026 August 2024 Issuance of Amendment Nos. 430, 432, and 431, to TS 5.5.2, Containment Leakage Rate Testing Program for a one-time Extension of the Type a Leak Rate Test Frequency ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML22349A1452022-12-19019 December 2022 Non-Proprietary Safety Evaluation Related to the SLRA of Oconee Nuclear Station, Units 1, 2, and 3 ML22321A0492022-12-0808 December 2022 Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22096A1872022-07-15015 July 2022 Issuance of Amendment Nos. 424, 426, and 425 Revise TS 3.7.7, Low Pressure Service Water (LPSW) System to Extend the Completion Time for One Required Inoperable LPSW Pump ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22068A0252022-03-15015 March 2022 Code Case OMN-28 - Alternative Valve Position Verification Approach to Satisfy ISTC-3700 for Valves Not Susceptible to Stem-Disk Separation ML22046A2802022-02-23023 February 2022 Relief from ASME Code Paragraph ISTP-3540(b) Related to High Pressure Injection Pumps Vibration Measurements ML22046A2452022-02-18018 February 2022 Regarding Alternative to Implement Code Case OMN-22, Smooth Running Pumps ML22019A1352022-01-21021 January 2022 Proposed Alternative to Implement ASME Code Case OMN-24 ML21347A0102021-12-20020 December 2021 Proposed Alternative to Implement ASME Code Case OMN-26 ML21335A1062021-12-0707 December 2021 Proposed Alternative to ASME Code W, Section XI, Subsection Iwl Regarding Containment Post-Tensioning System Inservice Inspection Requirements ML21281A1412021-11-19019 November 2021 Authorization and Safety Evaluation for Alternative Reactor Pressure Vessel Inservice Inspection Intervals ML21155A2132021-08-26026 August 2021 Plant ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21006A0982021-03-15015 March 2021 Issuance of Amendment Nos. 421, 423, and 422 Revision of Licensing Basis for High Energy Line Breaks Outside of Containment (EPID L-2019-LLA-0184) (Public Version) ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20335A0012021-01-26026 January 2021 Issuance of Amendment Nos. 420, 422, and 421 Measurement Uncertainty Recapture Power Uprate ML20303A0242020-12-0909 December 2020 Issuance of Amendments 419, 421, 420 TSTF-272, Refueling Boron Concentration Clarification ML20296A2812020-11-25025 November 2020 Issuance of Amendment Nos. 418, 420 and 419 TSTF-421, Revision to RCP Flywheel Inspection Program ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20237F4352020-09-0404 September 2020 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML20055F5712020-02-26026 February 2020 Proposed Alternative Request 19-ON-001 to Use Modified American Society of Mechanical Engineer'S Boiler and Pressure Vessel Code Case N-853 ML20042D7142020-02-13013 February 2020 Relief Request 19-ON-002 for Proposed Alternative to Reactor Vessel Nozzle Weld Examination Frequency Requirements in ASME Code Case N-770-2 ML19260E0842019-10-31031 October 2019 Issuance of Amendments 415, 417, and 416, Regarding the Updated Final Safety Analysis Report Description of Tornado Mitigation ML19056A0862019-09-30030 September 2019 Issuance of Amendments Nos. 414, 416 and 415 Regarding the Physical Security Plan ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19183A3172019-07-17017 July 2019 Issuance of Amendments Regarding the Updated Final Safety Analysis Report Section for Fission Gas Gap Release Rates ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML18311A1342018-12-17017 December 2018 Non Proprietary - Issuance of Amendments Regarding the Updated Final Safety Analysis Report Section for the Standby Shutdown Facility ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18040A1942018-04-12012 April 2018 Issuance of Amendments Regarding the Technical Specifications for Control Room Habitability (CAC Nos. MF9555, MF9556, and MF9557; EPID L-2017-LLA-0219) ML18051B2572018-02-28028 February 2018 Safety Evaluation for Alternative to Codes and Standards Requirements Associated with Bronze Tape Wrapped Emergency Power Cables (CAC Nos. MF7365, MF7366, and MF7367; EPID L-2016-LLR-0001) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17335A0252017-12-0505 December 2017 Correction to Safety Evaluation for Amendment Nos. 406, 408, and 407 (CAC Nos. MF7417, MF7418, and MF7419; EPID L-2016-LLA-0002) ML17124A6082017-11-20020 November 2017 Issuance of Amendments Regarding the Technical Specifications for Electrical Power Systems (CAC Nos. MF7417, MF7418, and MF7419; EPID L-2016-LLA-0002) ML17202U7912017-08-30030 August 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17167A2652017-07-12012 July 2017 Issuance of Amendments Regarding the Technical Specifications for Dry Spent Fuel Storage Cask Loading and Unloading (CAC Nos. MF8161, MF8162, and MF8163) ML17103A5092017-05-11011 May 2017 Issuance of Amendments Allowing the Use of the Copernic Fuel Performance Code 2024-08-26
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-2-3.0 TECHNICAL EVALUATION The masonry walls discussed in the license amendment request (LAR) are non-structural elements, and are single and multiple wythe in-fill panels constructed of hollow or grouted concrete blocks or constructed of solid concrete bricks. The typical FRP application will consist of a matrix of fiber bonded directly to existing masonry walls with a polymer. The LAR stated that future use of FRP, as proposed, will be predicated on the satisfactory completion of qualification testing and commercial grade dedication of the selected FRP system and the incorporation of subsequent periodic surveillance requirements into existing plant programs.The detailed design, qualification, installation and inspection, and inservice surveillance methods for the FRP system are contained in the LAR. The Nuclear Regulatory Commission (NRC) staff reviewed the licensee's proposed methods and data provided by the licensee that had been acquired from a number of industry performance tests that are relevant to the masonry walls located within the Oconee 1/2/3 auxiliary buildings.
The acceptability and applicability of the licensee's methods for design, qualification, installation and inspection, and inservice surveillance are discussed below.3.1 Applicability of the FRP System Design Method The licensee's FRP design method is only applicable to the non-structural concrete block masonry walls located in the Oconee 1/2/3 auxiliary buildings.
It is not applicable to the non-structural solid brick masonry walls located in these auxiliary buildings.
3.2 The FRP System Design Method The design is based on a working stress method and assumes a one-way span behavior for masonry walls to resist the flexural stress generated by a tornado. In its October 30, 2007, response to the NRC staff's request for additional information (RAI), the licensee stated that it will limit the masonry allowable flexural compressive stress to 70 percent of the masonry compressive strength, which is intended to preclude the brittle failure mode of masonry walls.The licensee also stated in its response to the RAI that it will comply with the NRC staff's request and limit the reinforcement index to 70 percent, which is intended to preclude the shear failure of the FRP-strengthened masonry walls. The licensee stated that the masonry allowable shear stress will be limited to 50 psi. The licensee stated that both ACI 531-79 and ACI 530-05,"Building Code Requirements for Masonry Structures," indicate an upper limit of 50 psi for masonry allowable shear stress for flexural members without shear reinforcement.
The NRC staff concludes that the licensee's compliance with these limits on masonry allowable flexural compressive stress, reinforcement index, and masonry allowable shear stress will provide additional assurance that the FRP-reinforced masonry walls will withstand the uniform pressure loads resulting from a tornado. Therefore, the NRC staff concludes that the FRP System design method is acceptable.
In addition, the design procedure includes a provision to evaluate the flexural stress generated due to the corner effect of masonry wall panels, and to reinforce them, if warranted.
3.3 The FRP System Qualification Method The licensee has committed that qualification tests and reporting for the selected FRP system will be performed in accordance with "Interim Criteria for Concrete and Reinforced and Unreinforced Masonry Strengthening Using Fiber-Reinforced Polymer (FRP) Composite Systems," International Code Council (ICC) AC125, June 2003. The licensee has committed to perform and document a technical evaluation of the selected FRP system (fibers and polymeric resin) to demonstrate the following:
(1) The selected FRP system qualifies as commercial grade in accordance with Duke's Supply Chain Directive (SCD) 230, "Commercial Grade Items";(2) The supplier is capable of supplying a quality product in accordance with SCD 230; and (3) The quality of the selected FRP system has been evaluated in accordance with ICC AC125; and, therefore, its quality can be reasonably assured.The NRC staff concludes that the FRP system qualification method is acceptable because it complies with ICC AC125 and Duke's SCD 230.3.4 The FRP System Installation and Inspection Method The licensee commits to use technical procedures to test the concrete masonry substrate, and to control the installation and inspection of the FRP system onto existing nasonry walls, in accordance with ICC AC125; "Guide for the Design and Construction of Externally Bonded FRP Systems for Strengthening Concrete Structures," ACI 440.2R-02; and "Interim Criteria for Inspection and Verification of Concrete and Reinforced and Unreinforced iMasonry Strengthing Using Fiber-Reinforced Polymer (FRP) Composite Systems," ICC AC 178, July 2003.The NRC staff concludes that the FRP system installation and inspection method is acceptable because it complies with these three standards.
3.5 The FRP System Inservice Surveillance Method The licensee's inservice inspection of the FRP system will be performed on a nominal 5-year interval, which is the standard interval defined in Duke's Engineering Directive Manual EDM-410 for monitoring and assessing the condition of civil engineering structures and components.
This inspection frequency may be reduced to a nominal 10-year interval with appropriate justification based on the structure, environment, and previous inservice inspection results. The inspection includes visual inspections for changes in color, debonding, peeling, blistering, cracking, deflection and other anomalies.
The inspection also includes tension adhesion testing of cored samples using methods specified in "Standard Test Method for Pull-Off Strength of Coatings Using Portable Adhesion Testers," American Society for Testing Materials (ASTM)D4541, or "Building Code Requirements for Masonry Structures," ACI 530R-02. Records of the inservice inspection reports will be considered Quality Assurance Records in accordance withTitile 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix B,Section XVII,"Quality Assurance Records." All inspection reports will be maintained for the life of the plant.The NRC staff concludes that the FRP system inservice surveillance method is acceptable because it complies with Duke's EDM-41 0, ASTM D4541, ACI 530R-02, and 10 CFR, Part 50, Appendix B,Section XVII.