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| | number = ML16061A565 | | | number = ML16061A565 |
| | issue date = 03/09/2016 | | | issue date = 03/09/2016 |
| | title = Oconee Nuclear Station, Units 1, 2, and 3 - Request for Additional Information for Relief Request 14-ON-001, Letdown Cooler Nozzle Welds (CAC Nos. MF6290, MF6291 and MF6292) | | | title = Request for Additional Information for Relief Request 14-ON-001, Letdown Cooler Nozzle Welds |
| | author name = Hall J R | | | author name = Hall J |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Markley M T | | | addressee name = Markley M |
| | addressee affiliation = NRC/NRR/DORL/LPLII-1 | | | addressee affiliation = NRC/NRR/DORL/LPLII-1 |
| | docket = 05000269, 05000270, 05000287 | | | docket = 05000269, 05000270, 05000287 |
| | license number = DPR-038, DPR-047, DPR-055 | | | license number = DPR-038, DPR-047, DPR-055 |
| | contact person = Hall J R, NRR, DORL, 415-4032 | | | contact person = Hall J, NRR, DORL, 415-4032 |
| | case reference number = CAC MF6290, CAC MF6291, CAC MF6292 | | | case reference number = CAC MF6290, CAC MF6291, CAC MF6292 |
| | document type = Memoranda, Request for Additional Information (RAI) | | | document type = Memoranda, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:MEMORANDUM TO: FROM: | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 9, 2016 MEMORANDUM TO: Michael T. Markley, Chief Plant Licensing Branch 11-1 r |
| | Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1I () n FROM: James R. Hall, Senior Project Manager Plant Licensing Branch 11-1 f' 1~ |
| | Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation |
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| ==SUBJECT:== | | ==SUBJECT:== |
| UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 9, 2016 Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1 I () n James R. Hall, Senior Project Manager r f' Plant Licensing Branch 11-1 Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3-REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST 14-0N-001, LETDOWN COOLER NOZZLE WELDS (CAC NOS. MF6290, MF6291 AND MF6292) By letter dated May 4, 2015 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML15132A279), Duke Energy Carolinas, LLC, (the licensee) requested the Nuclear Regulatory Commission (NRC) to authorize relief from Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) related to inspection of the inside radius sections of the Letdown Cooler nozzles over the duration of the fifth (ten-year) in-service inspection (ISi) interval.
| | OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3- REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST 14-0N-001, LETDOWN COOLER NOZZLE WELDS (CAC NOS. MF6290, MF6291 AND MF6292) |
| On February 25, 2016, the NRC staff and the licensee held a clarifying discussion on the staff's draft request for additional information (RAI), transmitted via e-mail on January 7, 2016 (ADAMS Accession No. ML 16008A246). | | By letter dated May 4, 2015 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML15132A279), Duke Energy Carolinas, LLC, (the licensee) requested the Nuclear Regulatory Commission (NRC) to authorize relief from Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) related to inspection of the inside radius sections of the Letdown Cooler nozzles over the duration of the fifth (ten-year) in-service inspection (ISi) interval. |
| Based on that discussion, the NRC staff developed the attached final RAI, and requested that the licensee submit written responses to the revised questions, so that the staff can complete its review of the subject relief request. Docket Nos. 50-269, 50-270, and 50-287 | | On February 25, 2016, the NRC staff and the licensee held a clarifying discussion on the staff's draft request for additional information (RAI), transmitted via e-mail on January 7, 2016 (ADAMS Accession No. ML16008A246). Based on that discussion, the NRC staff developed the attached final RAI, and requested that the licensee submit written responses to the revised questions, so that the staff can complete its review of the subject relief request. |
| | Docket Nos. 50-269, 50-270, and 50-287 |
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| ==Attachment:== | | ==Attachment:== |
| | Final RAI cc w/attachment: Distribution via Listserv |
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| Final RAI cc w/attachment:
| | FINAL REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 14-0N-001 LETDOWN COOLER NOZZLE WELDS OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 DUKE ENERGY CAROLINAS, LLC DOCKET NOS. 50-269, 50-270 AND 50-287 By letter dated May 4, 2015 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML15132A279), Duke Energy Carolinas, LLC, (the licensee) requested the Nuclear Regulatory Commission (NRC) to authorize relief from Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) related to inspection of the inside radius sections of the Letdown Cooler nozzles over the duration of the fifth (ten-year) in-service inspection (ISi) interval. This relief request applies to the Oconee Nuclear Station, Units 1, 2 and 3. The licensee is requesting renewal of previously granted relief requests based on the impracticality of performing inspections in the specified areas. |
| Distribution via Listserv FINAL REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 14-0N-001 LETDOWN COOLER NOZZLE WELDS OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 DUKE ENERGY CAROLINAS, LLC DOCKET NOS. 50-269, 50-270 AND 50-287 By letter dated May 4, 2015 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML 15132A279), Duke Energy Carolinas, LLC, (the licensee) requested the Nuclear Regulatory Commission (NRC) to authorize relief from Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) related to inspection of the inside radius sections of the Letdown Cooler nozzles over the duration of the fifth (ten-year) in-service inspection (ISi) interval.
| | On February 25, 2016, the NRC staff and the licensee held a clarifying discussion on the staff's draft request for additional information (RAI), transmitted via e-mail on January 7, 2016 (ADAMS Accession No. ML16008A246). Based on that discussion, the NRC staff developed this final RAI, and requests that the licensee submit written responses to the following revised questions, so that the staff can complete its review of the subject relief request. |
| This relief request applies to the Oconee Nuclear Station, Units 1, 2 and 3. The licensee is requesting renewal of previously granted relief requests based on the impracticality of performing inspections in the specified areas. On February 25, 2016, the NRC staff and the licensee held a clarifying discussion on the staff's draft request for additional information (RAI), transmitted via e-mail on January 7, 2016 (ADAMS Accession No. ML 16008A246). | | : 1. Please provide a more detailed description of the nozzle inside radius sections that are required to be ultrasonically examined per the ASME Code, Section XI, by either referring to the drawings in the relief request as a guide or by providing additional sketches or drawings of the subject welds/nozzles. |
| Based on that discussion, the NRC staff developed this final RAI, and requests that the licensee submit written responses to the following revised questions, so that the staff can complete its review of the subject relief request. 1. Please provide a more detailed description of the nozzle inside radius sections that are required to be ultrasonically examined per the ASME Code, Section XI, by either referring to the drawings in the relief request as a guide or by providing additional sketches or drawings of the subject welds/nozzles. | | : 2. Section 1 of the relief request states that "... Oconee Unit 1 has two Letdown Coolers 1A and 1B. Each component has typically four B3.160 welds .... " Please confirm that the required examination is on the attachment welds of the nozzles, not the nozzles themselves, and that the required examination is on the inside radius of the welds. It appears that the nozzles are forged and are attached to the side of a pipe as a branch connection. The welds are deposited on the inside and outside circumference of the nozzles that are attaching to the pipe. Is the staff's understanding correct? If not, please clarify. |
| : 2. Section 1 of the relief request states that " ... Oconee Unit 1 has two Letdown Coolers 1 A and 1 B. Each component has typically four B3.160 welds .... " Please confirm that the required examination is on the attachment welds of the nozzles, not the nozzles themselves, and that the required examination is on the inside radius of the welds. It appears that the nozzles are forged and are attached to the side of a pipe as a branch connection. | | : 3. Section 1 of the relief request states that, "The coolers also have operational ready spares of similar design that are rotated from spare to installed components as required Attachment |
| The welds are deposited on the inside and outside circumference of the nozzles that are attaching to the pipe. Is the staff's understanding correct? If not, please clarify. 3. Section 1 of the relief request states that, "The coolers also have operational ready spares of similar design that are rotated from spare to installed components as required Attachment by maintenance | |
| ... " What is the relevance of this sentence with respect to the required examination of the subject nozzle weld inside radius sections?
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| : 4. Briefly describe the design and operation of the letdown coolers. Are the subject nozzles connected to the tube side or shell side of the letdown cooler? What fluids flow in the tube side and shell side of the coolers? What are the operating and design pressures and temperatures of the subject nozzles? If the fluid is not from the reactor coolant system, is the fluid being chemically treated to minimize corrosion?
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| : 5. Discuss how the letdown cooler and letdown system would be affected if the subject nozzles/welds fail completely (i.e., what are the consequences if the nozzle fails?). Section 4 of the relief request states that the nozzles are "set-on";
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| discuss the possibility of the nozzle ejecting from the pipe. Alternatively, discuss the bases for concluding that catastrophic failure of the nozzles/welds will not occur. 6. Confirm that the subject nozzles are made of 3-inch, stainless steel forging. What is the nozzle wall thickness?
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| What is the material of the pipe that the nozzle is attached to? What are the nominal pipe size and wall thickness of the pipe to which the nozzle is attached?
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| : 7. What is the weld filler material of the affected nozzles? Is the subject weld a full penetration weld, partial penetration weld, or fillet weld? 8. Has there been any leakage from or degradation of the subject nozzles/welds?
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| March 9, 2016 MEMORANDUM TO: Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: James R. Hall, Senior Project Manager IRA! Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
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| ==SUBJECT:==
| | by maintenance ... " What is the relevance of this sentence with respect to the required examination of the subject nozzle weld inside radius sections? |
| OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 -REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST 14-0N-001, LETDOWN COOLER NOZZLE WELDS (CAC NOS. MF6290, MF6291 AND MF6292) By letter dated May 4, 2015 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML 15132A279), Duke Energy Carolinas, LLC, (the licensee) requested the Nuclear Regulatory Commission (NRC) to authorize relief from Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) related to inspection of the inside radius sections of the Letdown Cooler nozzles over the duration of the fifth (ten-year) in-service inspection (ISi) interval.
| | : 4. Briefly describe the design and operation of the letdown coolers. Are the subject nozzles connected to the tube side or shell side of the letdown cooler? What fluids flow in the tube side and shell side of the coolers? What are the operating and design pressures and temperatures of the subject nozzles? If the fluid is not from the reactor coolant system, is the fluid being chemically treated to minimize corrosion? |
| On February 25, 2016, the NRC staff and the licensee held a clarifying discussion on the staff's draft request for additional information (RAI), transmitted via e-mail on January 7, 2016 (ADAMS Accession No. ML 16008A246).
| | : 5. Discuss how the letdown cooler and letdown system would be affected if the subject nozzles/welds fail completely (i.e., what are the consequences if the nozzle fails?). Section 4 of the relief request states that the nozzles are "set-on"; discuss the possibility of the nozzle ejecting from the pipe. Alternatively, discuss the bases for concluding that catastrophic failure of the nozzles/welds will not occur. |
| Based on that discussion, the NRC staff developed the attached final RAI, and requested that the licensee submit written responses to the revised questions, so that the staff can complete its review of the subject relief request. Docket Nos. 50-269, 50-270, and 50-287
| | : 6. Confirm that the subject nozzles are made of 3-inch, stainless steel forging. What is the nozzle wall thickness? What is the material of the pipe that the nozzle is attached to? What are the nominal pipe size and wall thickness of the pipe to which the nozzle is attached? |
| | | : 7. What is the weld filler material of the affected nozzles? Is the subject weld a full penetration weld, partial penetration weld, or fillet weld? |
| ==Attachment:==
| | : 8. Has there been any leakage from or degradation of the subject nozzles/welds? |
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| Final RAI cc w/attachment:
| | ML16061A565 OFFICE: N RR/DORL/LPL2-1 /PM NRR/DORL/LPL2-1/LA NAME: JRHall SFigueroa DATE: 3/09/2016 3/08/2016}} |
| Distribution via Listserv DISTRIBUTION PUBLIC RidsNrrDorlDpr Resource RidsNrrDorlLpl2-1 Resource J. Tsao, NRR/DE/EPNB ADAMS Accession No.: ML 16061A565 OFFICE: N RR/DORL/LPL2-1
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| /PM NAME: JRHall DATE: 3/09/2016 LPL2-1 R/F RidsNrrPMOconee Resource RidsNsirDprDdep Resource NRR/DORL/LPL2-1/LA SFigueroa 3/08/2016 OFFICIAL RECORD COPY}} | |
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Category:Memoranda
MONTHYEARML24122C6932024-05-0101 May 2024
Referral of Petition to Intervene and Request for Hearing Re Subsequent License Renewal Application from Duke Energy Carolinas, LLC for Oconee Units 1, 2 & 3
ML24124A0342024-05-0101 May 2024
Summary of Public Meeting Concerning Annual Assessment of Catawba Nuclear Station Units 1 and 2, McGuire Nuclear Station Units 1 and 2, Oconee Nuclear Station Units 1, 2, and 3, Brunswick Steam Electric Plant Units 1 and 2, Shearon Harris
ML24071A1692024-03-15015 March 2024
February 2024 Subsequent License Renewal Public Draft Environmental Impact Statement Meetings-Memo
ML24047A2092024-02-22022 February 2024
Calendar Year 2023 Baseline Inspection Completion
ML23118A2852023-05-0202 May 2023
Public Meeting Summary - 2022 Annual Assessment Meeting Regarding Catawba Nuclear Station, McGuire Nuclear and Oconee Nuclear Station
ML22299A0482023-01-11011 January 2023
Final Environmental Assessment and Finding of No Significant Impact for the Duke Energy’S Updated Decommissioning Funding Plans Submitted in Accordance with 10 CFR 72.30(C) for Oconee Nuclear Station Independent Spent Fuel Storage Installat
ML22349A1482022-12-19019 December 2022
Transmittal Letter for Oconee SE for SLRA Review
ML22193A2542022-08-0505 August 2022
SLRA - Audit Report
ML22111A3142022-05-0202 May 2022
Limited Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review
ML22084A6142022-04-0404 April 2022
SLRA - Summary of March 16, 2022 (Closed Public Meeting)
ML22024A1392022-03-11011 March 2022
SLRA - Request for Withholding Information
ML21347A0102021-12-20020 December 2021
Proposed Alternative to Implement ASME Code Case OMN-26
ML21279A1542021-11-0808 November 2021
August 25, 2021, Oconee Nuclear Station, Units 1, 2, and 3 Subsequent License Renewal Application Public Environmental Scoping Meeting Summary Memo
ML21064A3502021-07-26026 July 2021
OEDO-21-00048 - Oconee Nuclear Station, Units 1, 2, and 3 - Response Memorandum
ML21195A2692021-07-14014 July 2021
Meeting Summary: Pre-Submittal Meeting for the Oconee Subsequent License Renewal Application (EPID Number: L-2020-RNW-0028) (Docket Numbers: 50 269, 50-270, and 50-287) - Memo
ML21055A8672021-04-22022 April 2021
Memo to File: Final Ea/Fonsi of Independent Spent Fuel Storage Facilities Decommissioning Funding Plans Related to Oconee
ML21099A0932021-04-0909 April 2021
Public Meeting Summary - 2020 Annual Assessment Meeting Regarding Catawba, McGuire, and Oconee Nuclear Stations
ML20357B1332020-12-30030 December 2020
Transmittal Memo - Delivery of Partial Deliverable Associated with the Trace Code Maintenance, Plant Model Maintenance, and Plant Model Development to Support Licensing Actions and Emergent Technical Issues User Need
ML20141L4172020-05-20020 May 2020
EOC Public Meeting Summary
ML20036E3902020-02-11011 February 2020
Regulatory Audit in Support of Review of License Amendment Request to Revise the Licensing Basis for High Energy Line Breaks Outside of the Containment Building
ML19102A3352019-04-12012 April 2019
Public Meeting Summary - Oconee Nuclear Station Docket Nos. 50-269, 50-270, and 50-287
ML19037A0052019-02-0808 February 2019
Regulatory Audit in Support of Review of License Amendment Request No. 2018-02
ML18226A2152019-01-22022 January 2019
Response to Task Interface Agreement 2014-04, Adequacy of the Oconee Nuclear Station Design and Licensing Bases for Degraded Voltage Protection (TAC Nos. MF4622, MF4623, and MF4624; EPID L-2014-LRA-0003)
ML18082A0582018-03-23023 March 2018
Summary of Meeting with Oconee Nuclear Station to Discuss Annual Assessment of Oconee for the Period of January 01, 2017 - December 31, 2017
ML18032A4612018-03-0505 March 2018
Regulatory Audit in Support of Review of License Amendment Request No. 2017-03
ML18004A0122018-01-0404 January 2018
Regulatory Audit in Support of Review of Proposed Alternative (CAC Nos. MF7365, MF7366 and MF7367; EPID No. L-2016-LLR-001)
ML17264A0312017-09-29029 September 2017
Draft Response to Task Interface Agreement 2014-05 to Licensee Oconee Design Analysis for Single Failure/Integration of Class 1E Direct Current Control Cabling in Raceways with High Energy Power Cabling
ML17202U7312017-07-25025 July 2017
Regulatory Audit in Support of License Amendment Request No. 2015-03
ML17103A0292017-04-13013 April 2017
Summary of Meeting to Provide Opportunities to Discuss Annual Assessment of Oconee Nuclear Station Units 1, 2 and 3
ML16088A2042016-03-28028 March 2016
Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template)
ML16088A2052016-03-28028 March 2016
Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations
ML16061A5652016-03-0909 March 2016
Request for Additional Information for Relief Request 14-ON-001, Letdown Cooler Nozzle Welds
ML16056A5832016-02-26026 February 2016
and 3, Draft Request for Additional Information License Amendment Request to Adopt Emergency Action Level Scheme Based on NEI 99-01 Rev.6
ML16021A3452016-01-29029 January 2016
Draft Request for Additional Information License Amendment to Add High Flux Trip for 3 Reactor Coolant Pump Operation
ML15364A3802016-01-0808 January 2016
Draft Request for Additional Information Relief Request ON-GRR-01
ML15363A2962015-12-29029 December 2015
Special Inspection Charter to Evaluate the Power Cable Failures/Degradations on the Oconee Units 1 and 3 Startup Transformers
ML15345A3982015-12-15015 December 2015
Draft Request for Additional Information License Amendment Request to Adopt Emergency Action Level Scheme Based on NEI 99-01 Rev. 6
ML15265A1272015-09-17017 September 2015
Memoranda to C. Bladey Notice of Availability of Exemption for Duke Energy Carolinas, LLC, Oconee Nuclear Station Independent Spent Fuel Storage Installation
ML15231A1922015-08-19019 August 2015
NRC June 9 2009 Memo Revision
ML15233A4952015-08-14014 August 2015
Memo to C Bladey, Notice of Environmental Assessment and Finding of No Significant Impact - Duke Ene4rgy Carolinas LLC, Oconee Nuclear Station ISFSI - Admin EA Memo
ML15181A4332015-07-0707 July 2015
Closure of Licensee Responses to External Flooding Letters
ML15099A5612015-05-11011 May 2015
Safety Evaluation for Duke Submittal on Electronic Records (Nirma)
ML15089A1642015-04-27027 April 2015
Summary of February 25, 2015, Partially Closed Meeting with Industry Stakeholders Regarding the Babcock and Wilcox Loss of Coolant Accident Evaluation Model Analysis
ML15113A6262015-04-23023 April 2015
April 14, 2015 Summary of Public Meeting on Oconee Nuclear Station, Units 1, 2 and 3 to Discuss the Annual Assessment
ML14356A0052014-12-31031 December 2014
Summary of December 3, 2014, Category 1 Public Meeting with Duke Energy Carolinas, LLC to Discuss NTTF Recommendation 2.1, Flooding Response for Oconee Nuclear Station, Units 1, 2, and 3
ML14311A8622014-11-0707 November 2014
Request for Technical Assistance Regarding the Adequacy of the Oconee Station Design and Licensing Bases for the Degraded Voltage Relay Protection Design (TIA 2014-04) (Final)
ML14147A3652014-05-27027 May 2014
Annual Assessment Public Meeting Summary Memo
ML14055A4742014-02-0404 February 2014
Draft Memorandum from G. Cunningham, NRR to E. Leeds, NRR on Oconee Flood Protection and the Jocassee Dam Hazard Basis for Continued Operation
ML14058A0162014-02-0404 February 2014
Draft Memo from M. Cunningham, NRR Et Al to E. Leeds, NRR on Oconee Flood Protection and the Jocassee Dam Hazard Basis for NRC Allowing Continued Operation
ML14058A0172014-02-0404 February 2014
Draft Memo from M. Cunningham, NRR Et Al to E. Leeds, NRR on Oconee Flood Protection and the Jocassee Dam Hazard Basis for NRC Allowing Continued Operation
2024-05-01
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24197A2302024-07-15015 July 2024
Request for Additional Information - Oconee SLRA - Annual Update
ML24192A1312024-07-15015 July 2024
Licensed Operator Positive Fitness-For-Duty Test
ML24190A0462024-07-0505 July 2024
Notification of Inspection and Request for Information
ML24086A3772024-03-26026 March 2024
Request for Additional Information License Amendment Request to Revise Technical Specification 5.5.2
ML23284A3322023-10-11011 October 2023
Request for Additional Information Alternative Request (RA-22-0174) (L-2022-LLR-0060)
ML23178A0682023-07-0303 July 2023
Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1
ML23156A2452023-06-0505 June 2023
Audit Summary and RAI-RCI - Revised Enclosure
ML23151A3482023-05-30030 May 2023
Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)
ML23142A2732023-05-22022 May 2023
Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)
ML23095A0052023-04-0404 April 2023
002 Radiation Safety Baseline Inspection Information Request
ML23086C0362023-03-27027 March 2023
Request for Additional Information Steam Generator Tube Inspection Report (03R31)
ML23039A1632023-02-0808 February 2023
Requalification Program Inspection
ML23038A1832023-02-0707 February 2023
Request for Additional Information Alternative Request (RA-22-0174) to Use ASME Code Case N-752
ML23037A0772023-02-0606 February 2023
402 Cyber Notification and RFI Letter Final
ML22251A2902022-09-0808 September 2022
Request for Additional Information Additional Mode Change Limitations Applicable to the Adoption of Technical Specifications Tasks Force Traveler (TSTF) No. 359, Revision 9
ML22234A0052022-08-30030 August 2022
SLRA - Feedback for RAI B2.1.7-4a to Duke - August 16, 2022
ML22157A0042022-06-0606 June 2022
10 CFR 50.59 Inspection Initial Information Request
ML22157A0012022-06-0101 June 2022
Email from NRC (Angela Wu) to Duke (Paul Guill) - Oconee SLRA - Additional NRC Comments on RAI 4.6.1-1a
ML22154A2122022-06-0101 June 2022
SLRA - 2nd Round RAI B2.1.7-4b
ML22124A1632022-05-0303 May 2022
(Public) Oconee SLRA - 2nd Round RAI B2.1.7-4a
ML22124A1612022-05-0303 May 2022
Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B2.1.7-4a
ML22122A0182022-04-28028 April 2022
Attachment: Oconee SLRA - 2nd Round RAI B2.1.9-2a
ML22122A0192022-04-28028 April 2022
Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B2.1.9-2a
ML22122A1312022-04-27027 April 2022
(Public) Oconee SLRA - 2nd Round RAIs - Trp 76 (Irradiation Structural) - FE 3.5.2.2.2.6 Redacted
ML22115A1412022-04-25025 April 2022
NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information
ML22112A0072022-04-20020 April 2022
Email from Marieliz Johnson (NRC) to Steve Snider (Duke) - Oconee SLRA - Request for Confirmation of Information 3.5.2.2.2.6-L
ML22113A0092022-04-20020 April 2022
Attachment: Oconee SLRA - Final RAI 3.1.2-1
ML22081A0062022-03-21021 March 2022
Attachment: Oconee SLRA - 2nd Round RAI B4.1-3
ML22081A0052022-03-21021 March 2022
Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B4.1-3
ML22080A0772022-03-16016 March 2022
SLRA - RAI Set 4 (2nd Round Rais)
ML22069A0012022-03-0808 March 2022
Attachment: Oconee SLRA - Final Requests for Confirmation of Information - Set 4
ML22063A4502022-03-0404 March 2022
Request for Additional Information Application to Revise TS 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required Inoperable LPSW Pump
RA-22-0036, Responses to NRC Request for Additional Information Set 22022-02-14014 February 2022
Responses to NRC Request for Additional Information Set 2
ML22019A1032022-01-18018 January 2022
Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Requests for Additional Information - Set 3
ML22019A2442022-01-18018 January 2022
Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000269/2022010, 05000270/2022010, 05000287/2022010) and Request for Information (RFI)
ML22019A1042022-01-18018 January 2022
Attachment: Oconee SLRA - Final Requests for Additional Information - Set 3
ML22012A0422022-01-11011 January 2022
SLRA - Final Requests for Additional Information - Set 2
ML22010A1132022-01-0505 January 2022
SLRA - RCIs - Set 3
ML21333A0392021-11-29029 November 2021
RP Inspection Document Request
ML21327A2782021-11-23023 November 2021
Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Final RAIs (Set 1 and 2nd Round RAI B2.1.27-1a)
ML21327A2792021-11-23023 November 2021
SLRA - Final Requests for Additional Information - Set 1
ML21327A2802021-11-23023 November 2021
SLRA - Final 2nd Round RAI - RAI B2.1.27-1a
ML21330A0192021-11-23023 November 2021
Attachment: Oconee SLRA - Final Requests for Confirmation of Information - Set 2
ML21313A2342021-11-0404 November 2021
Attachment: Oconee SLRA - Final Requests for Confirmation of Information - Set 1
ML21274A0682021-10-0101 October 2021
Request for Additional Information Alternative Request (RA-20-0334) Regarding Use of an Alternative to the ASME Code Case N-853 Acceptance Criteria
ML21273A0492021-09-30030 September 2021
Request for Additional Information Alternative Request (ON-RPI-OMN-28) to Use Code Case OMN-28
ML21271A5892021-09-28028 September 2021
SLRA - RAI B2.1.27-1 (Draft)
ML21271A5902021-09-28028 September 2021
SLRA - RAI B2.1.27-1 (Final)
ML21271A5882021-09-22022 September 2021
SLRA - Request for Additional Information B2.1.27-1 - Email from Angela Wu (NRC) to Steve Snider (Duke)
ML21217A1912021-08-0505 August 2021
Request for Additional Information Alternative Request (RA-20-0334) Regarding Use of an Alternative to the ASME Code Case N-853 Acceptance Criteria
2024-07-05
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 9, 2016 MEMORANDUM TO: Michael T. Markley, Chief Plant Licensing Branch 11-1 r
Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1I () n FROM: James R. Hall, Senior Project Manager Plant Licensing Branch 11-1 f' 1~
Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3- REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST 14-0N-001, LETDOWN COOLER NOZZLE WELDS (CAC NOS. MF6290, MF6291 AND MF6292)
By letter dated May 4, 2015 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML15132A279), Duke Energy Carolinas, LLC, (the licensee) requested the Nuclear Regulatory Commission (NRC) to authorize relief from Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) related to inspection of the inside radius sections of the Letdown Cooler nozzles over the duration of the fifth (ten-year) in-service inspection (ISi) interval.
On February 25, 2016, the NRC staff and the licensee held a clarifying discussion on the staff's draft request for additional information (RAI), transmitted via e-mail on January 7, 2016 (ADAMS Accession No. ML16008A246). Based on that discussion, the NRC staff developed the attached final RAI, and requested that the licensee submit written responses to the revised questions, so that the staff can complete its review of the subject relief request.
Docket Nos. 50-269, 50-270, and 50-287
Attachment:
Final RAI cc w/attachment: Distribution via Listserv
FINAL REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 14-0N-001 LETDOWN COOLER NOZZLE WELDS OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 DUKE ENERGY CAROLINAS, LLC DOCKET NOS. 50-269, 50-270 AND 50-287 By letter dated May 4, 2015 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML15132A279), Duke Energy Carolinas, LLC, (the licensee) requested the Nuclear Regulatory Commission (NRC) to authorize relief from Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) related to inspection of the inside radius sections of the Letdown Cooler nozzles over the duration of the fifth (ten-year) in-service inspection (ISi) interval. This relief request applies to the Oconee Nuclear Station, Units 1, 2 and 3. The licensee is requesting renewal of previously granted relief requests based on the impracticality of performing inspections in the specified areas.
On February 25, 2016, the NRC staff and the licensee held a clarifying discussion on the staff's draft request for additional information (RAI), transmitted via e-mail on January 7, 2016 (ADAMS Accession No. ML16008A246). Based on that discussion, the NRC staff developed this final RAI, and requests that the licensee submit written responses to the following revised questions, so that the staff can complete its review of the subject relief request.
- 1. Please provide a more detailed description of the nozzle inside radius sections that are required to be ultrasonically examined per the ASME Code,Section XI, by either referring to the drawings in the relief request as a guide or by providing additional sketches or drawings of the subject welds/nozzles.
- 2. Section 1 of the relief request states that "... Oconee Unit 1 has two Letdown Coolers 1A and 1B. Each component has typically four B3.160 welds .... " Please confirm that the required examination is on the attachment welds of the nozzles, not the nozzles themselves, and that the required examination is on the inside radius of the welds. It appears that the nozzles are forged and are attached to the side of a pipe as a branch connection. The welds are deposited on the inside and outside circumference of the nozzles that are attaching to the pipe. Is the staff's understanding correct? If not, please clarify.
- 3. Section 1 of the relief request states that, "The coolers also have operational ready spares of similar design that are rotated from spare to installed components as required Attachment
by maintenance ... " What is the relevance of this sentence with respect to the required examination of the subject nozzle weld inside radius sections?
- 4. Briefly describe the design and operation of the letdown coolers. Are the subject nozzles connected to the tube side or shell side of the letdown cooler? What fluids flow in the tube side and shell side of the coolers? What are the operating and design pressures and temperatures of the subject nozzles? If the fluid is not from the reactor coolant system, is the fluid being chemically treated to minimize corrosion?
- 5. Discuss how the letdown cooler and letdown system would be affected if the subject nozzles/welds fail completely (i.e., what are the consequences if the nozzle fails?). Section 4 of the relief request states that the nozzles are "set-on"; discuss the possibility of the nozzle ejecting from the pipe. Alternatively, discuss the bases for concluding that catastrophic failure of the nozzles/welds will not occur.
- 6. Confirm that the subject nozzles are made of 3-inch, stainless steel forging. What is the nozzle wall thickness? What is the material of the pipe that the nozzle is attached to? What are the nominal pipe size and wall thickness of the pipe to which the nozzle is attached?
- 7. What is the weld filler material of the affected nozzles? Is the subject weld a full penetration weld, partial penetration weld, or fillet weld?
- 8. Has there been any leakage from or degradation of the subject nozzles/welds?
ML16061A565 OFFICE: N RR/DORL/LPL2-1 /PM NRR/DORL/LPL2-1/LA NAME: JRHall SFigueroa DATE: 3/09/2016 3/08/2016
