Letter Sequence Other |
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MONTHYEARML0209203502002-04-0808 April 2002
Telephone Conversation with Duke Energy Regarding the Inspection of the Reactor Vessel Head at Oconee Nuclear Station
Project stage: Other
ML0211506812002-04-24024 April 2002
Summary of April 3, 2002, Conference Call Regarding Duke Energy'S Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity for Oconee Unit 1
Project stage: Other
ML0232405872002-11-22022 November 2002
RAI, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-Day Response
Project stage: RAI
2002-04-24
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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] |
Text
April 8, 2002 MEMORANDUM TO: John A. Nakoski, Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Leonard N. Olshan, Project Manager, Section 1 /RA/
Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
TELEPHONE CONVERSATION WITH DUKE ENERGY REGARDING THE INSPECTION OF THE REACTOR VESSEL HEAD AT OCONEE NUCLEAR STATION, UNIT 1 (TAC NO. MB4559)
On March 26, 2002, the Nuclear Regulatory Commission (NRC) staff and the staff of Duke Energy (the licensee) held a telephone conference call to discuss the reactor vessel head inspection being conducted at Oconee Nuclear Station, Unit 1 (Oconee 1). Oconee 1 is classified as a high-susceptibility plant using the guidance of EPRI MRP-44, Part 2, and NRC Inspection Manual TI 2515/145, Appendix A. Oconee 1 shut down on March 23, 2002, for a scheduled refueling outage.
At the time of the call, the licensee had already completed a 100-percent bare-metal inspection of the top of the head. This qualified inspection (as discussed in NRC Bulletin 2001-01) was done with the head on the vessel. The inspection identified evidence of boric acid deposits around two nozzles. The licensee indicated that the most likely sources of these deposits were from leaks coming from above the vessel head rather than from cracks in the nozzles.
Nonetheless, the licensee is planning additional ultrasonic inspection of these two nozzles and will make all necessary repairs prior to restart.
The last inspection of the Oconee 1 reactor vessel head was conducted in November 2000.
There were some small localized areas of boric acid deposits identified during this inspection which were left on the top of the head. The 100-percent bare-metal inspection performed at this time identified one leaking control rod drive mechanism nozzle and five leaking thermocouple nozzles. All the nozzles were repaired by grinding out the defects. There were no signs of degradation of the reactor vessel head base material during the repairs of these nozzles (i.e., in the region near the J-groove weld where the entire thickness of the nozzle was removed by grinding). During the 2002 inspection, all of the nozzles repaired during the November 2000 outage were reexamined. There were no signs of wastage near these nozzles (based on visual examination on the top surface of the head) nor were there signs of leakage from these nozzles.
The 2002 nozzle inspections will be performed using a Framatome Aramis tool. The examinations will start at the bottom of the nozzle and end about two inches above the J-groove weld. The NRC staff asked the licensee to consider performing an ultrasonic examination
through the entire thickness of the head for the two nozzles with evidence of boric acid deposits and for the nozzles previously repaired with through-wall/through-weld defects. The NRC stated that it might be possible that a cavity could be present within the thickness of the head that might not be detected unless the entire thickness of the head is inspected (this assumes that the cavity initiates from within the reactor vessel head rather than on the surface).
The licensee is planning to replace the reactor vessel head during the next outage, which is planned for the fall of 2003. Startup from the current outage is scheduled for April 23, 2002.
Docket Nos. 50-269
through the entire thickness of the head for the two nozzles with evidence of boric acid deposits and for the nozzles previously repaired with through-wall/through-weld defects. The NRC stated that it might be possible that a cavity could be present within the thickness of the head that might not be detected unless the entire thickness of the head is inspected (this assumes that the cavity initiates from within the reactor vessel head rather than on the surface).
The licensee is planning to replace the reactor vessel head during the next outage, which is planned for the fall of 2003. Startup from the current outage is scheduled for April 23, 2002.
Docket Nos. 50-269 DISTRIBUTION:
Public SCoffin PDII-1 R/F KKarwoski LOlshan SBloom CHawes Accession Number: ML020920350 *See previous concurrence OFC PDII-1/PM PDII-1/LA EMCB* PDII-1/SC NAME LOlshan CHawes SBloom JNakoski DATE 4/8/02 4/8/02 4/4/02 4/8/02 OFFICIAL RECORD COPY
