|
---|
Category:Code Relief or Alternative
MONTHYEARML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds 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) 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 RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) 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 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 ML22028A3652022-02-0707 February 2022 Authorization and Safety Evaluation for Alternative Acceptance Criteria for Code Case N-853 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 RA-20-0036, Request for Alternative to Defect Removal Prior to Performing Repair/Replacement Activities on Low Pressure Service Water (LPSW) System Piping2020-03-0202 March 2020 Request for Alternative to Defect Removal Prior to Performing Repair/Replacement Activities on Low Pressure Service Water (LPSW) System Piping 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 RA-19-0028, Submittal of Relief Request (19-ON-001) to Utilize Code Case N-853, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress2019-03-21021 March 2019 Submittal of Relief Request (19-ON-001) to Utilize Code Case N-853, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)2019-02-11011 February 2019 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001) RA-18-0180, Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 22018-11-12012 November 2018 Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML16118A2302016-04-30030 April 2016 Relief Request 14-ON-022 Alternative Requirements for Class 2 Residual Heat Removal Heat Exchange Welds ML16053A5012016-03-0101 March 2016 Relief Request ON-GRR-01 Grace Period for OM Code Frequencies (CAC Nos. MF7130, MF7131, and MF7132) ML16004A1812016-01-0707 January 2016 Relief Request 14-ON-003 Alternative Requirements for Class 1 Category B-J Piping Welds ML16004A2622016-01-0707 January 2016 Relief Request 15-ON-004: Limited Visual Examinations of the Reactor Pressure Vessel Support Skirt for the Fourth 10-Year Inservice Inspection Interval Program ML15349A4532015-12-29029 December 2015 Relief Request 15-ON-001 Repair of Low Pressure Service Water System Piping ONS-2015-087, Fourth Ten-Year Inservice Inspection Plan, Relief Request No. 15-ON-003, Limited Volume Inspections from 3EOC27 Outage2015-07-15015 July 2015 Fourth Ten-Year Inservice Inspection Plan, Relief Request No. 15-ON-003, Limited Volume Inspections from 3EOC27 Outage ONS-2015-088, Fourth Ten-Year Inservice Inspection Plan, Relief Request No. 15-ON-004, Limited Visual Examinations from 1 EOC27, 2EOC26 and 3EOC27 Outages2015-07-15015 July 2015 Fourth Ten-Year Inservice Inspection Plan, Relief Request No. 15-ON-004, Limited Visual Examinations from 1 EOC27, 2EOC26 and 3EOC27 Outages ML13365A0232014-01-17017 January 2014 Relief from the Requirements of the ASME Code for Fourth 10-Year Interval Inspection Program Request for Relief ML13066A1002013-02-27027 February 2013 End of Cycle (EOC) 27 Refueling Outage Steam Generator Inservice Inspection Report ML13045A2902013-02-15015 February 2013 Relief from the Requirements of the ASME OM Code ML13038A1522013-01-31031 January 2013 Fourth Ten-Year Inservice Inspection Plan, Request for Relief No. 12-ON-001 ML13038A1502013-01-31031 January 2013 Fourth Ten-Year Inservice Inspection Plan Request for Relief No. 12-ON-002 ML12173A3122012-06-18018 June 2012 Approval Request for the Fifth Ten-Year Inservice Test Program Interval Pump Specific Code Relief Request No. ON-SRP-HPI-03 ML12030A0892012-01-23023 January 2012 Duke Energy Carolinas - Relief Request Serial #09-GO-001 Request for NRC Clarification ML11143A0592011-06-21021 June 2011 Relief Request 10-ON-001 for Reactor Vessel Core Flood Nozzle Weld Examinations ML1106605882011-03-28028 March 2011 Relief Request (RR) Proposed Alternative for Certain Vibration Measurement Requirements RR (ON-SRP-HPI-03)) (TAC Nos. Me 3840, ME3841, ME3842, ME5790, ME5791, ME5792, ME5793, ME5794 and ME5795) ML1016604732010-06-0909 June 2010 Relief Request No. 10-ON-001, Alternative to Volumetric Examination Requirements for the Residual Heat Removal (RHR) Heat Exchanger Class 2 Nozzle-to-Shell Welds ML1008802862010-03-31031 March 2010 Relief Request 09-ON-003 for the Use of Full Structural Weld Overlay & Alternative Examination Techniques, for the Letdown Line, Reactor Vessel Core Flood & Reactor Coolant Pump Inlet & Outlet Nozzle Butt Welds. ML1006006982010-03-0303 March 2010 Relief, Request 09 ON-005 for Reactor Vessel Core Flood Nozzle Weld Examinations (ME1846, ME1847, and ME1848) ML0927403122009-09-24024 September 2009 Relief Request from Immediate ASME Code Flaw Repair of Standby Shutdown Facility Auxiliary Service Water Piping ML0921500282009-07-28028 July 2009 Fourth Ten Year Inservice Inspection Interval Request for Relief No. 09-ON-005 ML0914702652009-05-20020 May 2009 Request for Extension of Duke Response Time to Referenced Letter ML0908307262009-03-20020 March 2009 Fourth Ten Year Inservice Inspection Interval, Request for Relief No. 09-ON-003 ML0833600322008-11-20020 November 2008 Summary Ultrasonic Examination Results of Completed ML0810200532008-04-0707 April 2008 Relief Request No. 08-ON-003, from Immediate ASME Code Flaw Repair of Low Pressure Service Water Piping ML0734600272008-01-17017 January 2008 Relief Request to Use Preemptive Weld Overlay and Alternative Examination Techniques on Decay Heat Removal Line to Hotleg Nozzle Welds ML0715605102007-05-29029 May 2007 Fourth Ten Year Inservice Inspection Interval Request for Relief No. 04-ON-007, Revision 1 ML0712300902007-04-27027 April 2007 Part 21 Interim Report, Dresser Investigation File No. 2007-02, Interim Reporting of a Potential Defect Involving Power Actuated Pressure Relief Valves Supplied to Calvert Cliffs, Fort Calhoun and Oconee Plants ML0626202342006-09-11011 September 2006 Relief Request 06-ON-004 Request for Additional Information ML0622902642006-08-0909 August 2006 Response to Request for Additional Information Request for Relief No. 05-ON-004 ML0619400162006-07-0606 July 2006 Replacement of Steam Generators Request for Relief No. 04-ON-007, Rev. 1 ML0609302482006-05-0404 May 2006 Relief Request 05-ON-003 ML0608302912006-04-17017 April 2006 Relief, Volumetric Examination of Essentially 100 Percent of the Volume as Required by the ASME, Boiler and Pressure Vessel Code, Section XI, for Class 1 and 2 Welds ML0608301052006-04-14014 April 2006 SE MC5483 and MC5483, Relief Request RR-04-ON-013 ML0536302312006-03-13013 March 2006 Relief Request MC8852, Repair of Steam Generator Tubes 2023-09-25
[Table view] Category:Letter type:ONS
MONTHYEARONS-2018-025, 2017 Annual Radiological Environmental Operating Report (AREOR)2018-05-15015 May 2018 2017 Annual Radiological Environmental Operating Report (AREOR) ONS-2018-024, 2017 Annual Radioactive Effluent Release Report (ARERR)2018-04-30030 April 2018 2017 Annual Radioactive Effluent Release Report (ARERR) ONS-2018-032, Ufsar/Selected Licensee Commitment Changes2018-04-17017 April 2018 Ufsar/Selected Licensee Commitment Changes ONS-2018-029, Technical Specifications Task Force (TSTF) - 448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 32018-04-0404 April 2018 Technical Specifications Task Force (TSTF) - 448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 3 ONS-2018-027, Oconee, Units 1, 2, and 3, Submittal of Emergency Plan Revision 2018-0022018-03-28028 March 2018 Oconee, Units 1, 2, and 3, Submittal of Emergency Plan Revision 2018-002 ONS-2018-023, Response to Nrc'S Request for Additional Information Regarding Relief Request 17-ON-001; Alternative to Extend the Code Case N-770, Inspection Item B, Examination Frequency2018-03-20020 March 2018 Response to Nrc'S Request for Additional Information Regarding Relief Request 17-ON-001; Alternative to Extend the Code Case N-770, Inspection Item B, Examination Frequency ONS-2018-017, Oconee, Units 1, 2, and 3, Submittal of Revised Evaluation to Emergency Plan2018-03-15015 March 2018 Oconee, Units 1, 2, and 3, Submittal of Revised Evaluation to Emergency Plan ONS-2018-021, ISFSI - Submittal of 2017 Annual Effluent Release Report2018-03-0101 March 2018 ISFSI - Submittal of 2017 Annual Effluent Release Report ONS-2018-020, Refuel 28 (O2R28) In-service Inspection (ISI) and Steam Generator In-service Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval2018-02-26026 February 2018 Refuel 28 (O2R28) In-service Inspection (ISI) and Steam Generator In-service Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval ONS-2018-013, Technical Specification Bases Changes2018-02-22022 February 2018 Technical Specification Bases Changes ONS-2018-015, Duke Energy Response to Request for Additional Information; Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2) Associated with Bronze Tape Wrapped Emergency Power Cabl2018-02-19019 February 2018 Duke Energy Response to Request for Additional Information; Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2) Associated with Bronze Tape Wrapped Emergency Power Cables i ONS-2018-014, License Amendment Request (LAR) for Changes to the Duke Energy Physical Security Plan - License Amendment Request No. 2018-012018-02-12012 February 2018 License Amendment Request (LAR) for Changes to the Duke Energy Physical Security Plan - License Amendment Request No. 2018-01 ONS-2018-019, Submittal of Emergency Plan, Section B2018-02-0505 February 2018 Submittal of Emergency Plan, Section B ONS-2018-011, Ufsar/Selected Licensee Commitment Changes2018-01-25025 January 2018 Ufsar/Selected Licensee Commitment Changes ONS-2017-087, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ...2017-12-0404 December 2017 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ... ONS-2017-083, Core Operating Limits Report (COLR) for Cycle 29 ONEl-0400-491, Revision 02017-11-21021 November 2017 Core Operating Limits Report (COLR) for Cycle 29 ONEl-0400-491, Revision 0 ONS-2017-041, Revision to Tornado/Helb Mitigation Strategies and Regulatory Commitments2017-11-15015 November 2017 Revision to Tornado/Helb Mitigation Strategies and Regulatory Commitments ONS-2017-085, Duke Energy Comments on the October 24, 2017, Public Meeting with NRC Committee to Review Generic Requirements (CRGR)2017-11-15015 November 2017 Duke Energy Comments on the October 24, 2017, Public Meeting with NRC Committee to Review Generic Requirements (CRGR) ONS-2017-079, Supplemental Information to Support NRC Review of Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency2017-11-13013 November 2017 Supplemental Information to Support NRC Review of Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency ONS-2017-078, Emergency Plan Revision 2017-0042017-11-0909 November 2017 Emergency Plan Revision 2017-004 ONS-2017-074, Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Section Associated with Tile Standby Shutdown Facility License Amendment Request No. 2017-032017-10-20020 October 2017 Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Section Associated with Tile Standby Shutdown Facility License Amendment Request No. 2017-03 ONS-2017-067, Response to Request for Additional Information Regarding License Amendment Request for TSTF-448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 22017-10-16016 October 2017 Response to Request for Additional Information Regarding License Amendment Request for TSTF-448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 2 ONS-2017-069, (ONS) - Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement2017-10-13013 October 2017 (ONS) - Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement ONS-2017-070, Transmittal of Oconee, Units 1, 2, and 3, Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-0022017-10-0505 October 2017 Transmittal of Oconee, Units 1, 2, and 3, Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-002 ONS-2017-072, Fifth Ten Year Lnservice Inspection Interval, Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency2017-10-0303 October 2017 Fifth Ten Year Lnservice Inspection Interval, Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency ONS-2017-066, Registration for Use of General License Spent Fuel Cask Numbers 147 and 1482017-09-20020 September 2017 Registration for Use of General License Spent Fuel Cask Numbers 147 and 148 ONS-2017-061, Revised Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator License Examinations2017-08-10010 August 2017 Revised Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator License Examinations ONS-2017-060, Registration for Use of General License Spent Fuel Cask Numbers 145 and 1462017-08-0303 August 2017 Registration for Use of General License Spent Fuel Cask Numbers 145 and 146 ONS-2017-059, Transmittal of Response to March 12, 2012 Request for Information, Recommendation 2.1 Flooding, Required Response 3, Flooding Focused Evaluation Summary2017-07-31031 July 2017 Transmittal of Response to March 12, 2012 Request for Information, Recommendation 2.1 Flooding, Required Response 3, Flooding Focused Evaluation Summary ONS-2017-050, Technical Specification Bases Change 2017-042017-07-21021 July 2017 Technical Specification Bases Change 2017-04 ONS-2017-052, Technical Specification Bases Change 2017-032017-07-20020 July 2017 Technical Specification Bases Change 2017-03 ONS-2017-043, Technical Specification Bases Change 2017-012017-07-20020 July 2017 Technical Specification Bases Change 2017-01 ONS-2017-047, Registration for Use of General License Spent Fuel Cask Numbers 142, 143, and 1442017-06-27027 June 2017 Registration for Use of General License Spent Fuel Cask Numbers 142, 143, and 144 ONS-2017-042, Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement, License Amendment Request No. 2015-08, Supplement 22017-06-0101 June 2017 Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement, License Amendment Request No. 2015-08, Supplement 2 ONS-2017-040, Transmittal of Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-0032017-05-22022 May 2017 Transmittal of Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-003 ONS-2017-037, 2016 Annual Radiological Environmental Operating Report2017-05-15015 May 2017 2016 Annual Radiological Environmental Operating Report ONS-2017-026, Submittal of Ufsar/Selected Licensee Commitment Change2017-04-11011 April 2017 Submittal of Ufsar/Selected Licensee Commitment Change ONS-2017-024, Revision 028 to ERTG-001, Emergency Response Organization and Emergency Services Training Program2017-03-16016 March 2017 Revision 028 to ERTG-001, Emergency Response Organization and Emergency Services Training Program ONS-2017-001, Submittal of Emergency Plan Program Procedure HP/O/B/1009/001 Rev 0452017-03-0202 March 2017 Submittal of Emergency Plan Program Procedure HP/O/B/1009/001 Rev 045 ONS-2017-017, Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-0012017-03-0202 March 2017 Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-001 ONS-2017-018, Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-0012017-03-0202 March 2017 Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-001 ONS-2017-015, End of Cycle 29 (1 EOC29) Refueling Outage Lnservice Inspection (ISI) and Steam Generator Lnservice Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval2017-02-24024 February 2017 End of Cycle 29 (1 EOC29) Refueling Outage Lnservice Inspection (ISI) and Steam Generator Lnservice Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval ONS-2017-019, Technical Specification Bases Change 2015-092017-02-23023 February 2017 Technical Specification Bases Change 2015-09 ONS-2017-011, Emergency Plan Revised Evaluation2017-02-0202 February 2017 Emergency Plan Revised Evaluation ONS-2017-009, Units 1, 2 & 3 - Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events.2017-02-0101 February 2017 Units 1, 2 & 3 - Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events. ONS-2017-004, Submittal of Core Operating Limits Report2017-01-12012 January 2017 Submittal of Core Operating Limits Report ONS-2017-006, Emergency Plan Revision 2016-0032017-01-12012 January 2017 Emergency Plan Revision 2016-003 ONS-2016-097, Emergency Plan/Emergency Plan Implementing Procedures Manual, Revised 10CFR 50.54(q) Evaluation(S)2016-11-17017 November 2016 Emergency Plan/Emergency Plan Implementing Procedures Manual, Revised 10CFR 50.54(q) Evaluation(S) ONS-2016-098, Special Report Per Technical Specification 5.6.6, Inoperability of Post Accident Monitoring Containment High Range Radiation Monitors2016-11-14014 November 2016 Special Report Per Technical Specification 5.6.6, Inoperability of Post Accident Monitoring Containment High Range Radiation Monitors ONS-2016-096, Revised Response to NRC Regulatory Issue Summary 2015-05, Preparation and Scheduling of Operator Licensing Examinations2016-11-10010 November 2016 Revised Response to NRC Regulatory Issue Summary 2015-05, Preparation and Scheduling of Operator Licensing Examinations 2018-05-15
[Table view] |
Text
Scott L. Batson DUKE EDUKE Vice President Oconee NuclearStation ENERGY Duke Energy ONOIVP I 7800 Rochester Hwy Seneca, SC 29672 ONS-2015-088 o: 864.873.3274
- f. 864.873. 4208 July 15, 2015 Scott.Batson@duke-energy.com ATTN: Document Control Desk 10 CFR 50.55a U.S. Nuclear Regulatory Commission Washington, DC 20555 Duke Energy Carolinas, LLC (Duke Energy)
Oconee Nuclear Station, Units 1, 2 and 3 Docket Numbers 50-269, 50-270, and 50-287 Renewed License Numbers DPR-38 DPR-47 and DPR-50
Subject:
Fourth Ten-Year Inservice Inspection Plan, Relief Request No. 15-ON-004, Limited Visual Examinations from 1 EOC27, 2EOC26 and 3EOC27 Outages Pursuant to 10 CFR 50.55a(g)(5)(iii), Duke Energy hereby requests NRC approval of the following relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 1998 Edition with 2000 Addenda.
The attached Relief Request applies to limited visual examinations performed on the Reactor Vessel Supports during Unit 1, EOC27, Unit 2, EOC26 and Unit 3, EOC27 outages. The relief request details are provided as an enclosure to this letter.
This submittal document contains no regulatory commitments.
If there are any questions or further information is needed you may contact David Haile at (864) 873-4742.
Sincerely, Scott L. Batson Vice President Oconee Nuclear Station Enclosure Relief Request Serial #1 5-ON-004:
Limited visual examinations per 10 CFR 50.55a(g)(5)(iii) for Unit 1, 2 and 3, Fourth Inservice Inspection Interval
ONS-2015-088 July 15, 2015 Page 2 cc (with enclosure):
Mr. Victor McCree, Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Mr. James R. Hall, Project Manager (ONS)
(by electronic mail only)
U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-8B1 Rockville, MD 20852 Mr. Jeffery Whited (by electronic mail only)
U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-8B1A Rockville, MD 20852 Mr. Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station
Enclosure to ONS-2015-088 Duke Energy Carolinas, LLC Oconee Nuclear Station, Units'l, 2, and 3 Relief Reauest Serial #15-ON-004:
Limited visual examinations per 10 CFR 50.55a(g)(5)(iii) for Unit 1, 2 and 3, Fourth Inservice Inspection Interval
Oconee Relief Request 15-ON-004 1.0 ASME Code Component(s) Affected Relief is requested pursuant to 10 CFR 50.55a(g)(5)(iii) for the following component supports:
" Unit 2 Reactor Pressure Vessel Support Skirt (RPVSS), Reactor Coolant System, Component I.D. No. 2-RPV-WR36, Summary Number 02.F1.40.0001 and ASME Code Class 1.
" Unit 3 Reactor Pressure Vessel Support Skirt (RPVSS), Reactor Coolant System, Component I.D. No. 3-RPV-WR36, Summary Number 02.F1.40.0001 and ASME Code Class 1.
2.0 Applicable Code Edition and Addenda
ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.
3.0 Applicable Code Requirement
IWF-2500, Table IWF-2500-1, Examination Category F-A, Item Number F1.40. Figure IWF-1 300-1(c) applies to the RPV Support Skirt Examination Boundary. A VT-3 visual examination of 100% of the support within the examination boundary is required once each inspection interval.
Relief is requested from the requirement to perform a VT-3 visual examination of 100%
of the RPVSS within the examination boundary.
4.0 Impracticality of Compliance (Reason for Request)
Duke Energy considers it impractical to perform a VT-3 visual examination on 100% of the interior and exterior surfaces of the Reactor Vessel Support Skirt within the Figure IWF-1300-1(c) boundary due to the existence of insulation panels that partially obstruct the visual examination surfaces. Although these insulation panels can be removed, compliance with the Code requirement to visually examine 100% of the support skirt surfaces is considered impractical due to the excessive personnel radiation dose (estimated) to remove and reinstall these insulation panels. In order to remove the bottom row of mirror insulation needed to access the entire exterior surface of the support skirt, removal of additional rows of mirror insulation is necessary because they are supported by the bottom row of insulation. Previous operating experience at Oconee Nuclear Station has shown that upper rows of these insulation panels can slip when the supporting row of insulation is removed, creating a potential personnel safety risk, as well as incurring additional unplanned radiation exposure associated with any insulation repair or replacement.
In addition, a small portion of the skirt exterior and interior surfaces is inaccessible for visual examination due to the existence of permanent insulation support attachments.
Compliance with the Code requirement to visually examine 100% of the support skirt surfaces at these support attachment locations is considered impractical because the Page 1 of3
Oconee Relief Request 15-ON-004 insulation support attachments are not designed to be removed and would have to be re-designed in order to improve the examination coverage.
Those portions of the support skirt surfaces that were visually examined, as well as those surfaces that are considered impractical to examine, are described below and reference sketch #1.
RPVSS outside diameter area; 1) Examined Surface D-E, 2) Portions of surface A-D accessible through removable inspection panels.
RPVSS inside diameter area: 1) Examined surface C-G, 2) Area B-C inaccessible not examined.
5.0 Proposed Alternative and Basis for Use For each Unit, in lieu of the requirement to perform a VT-3 visual examination of 100% of the support within the examination boundary, a VT-3 visual examination was performed on accessible surfaces of the Reactor Vessel Support Skirt shown in Attachment A Sketch #1. The calculated coverage is approximately 66.5% of the support surface areas within the examination boundary specified in Figure IWF-1300-1(c).
The VT-3 visual examinations were performed using personnel, equipment, and procedures qualified in accordance with the ASME Code,Section XI, 1998 Edition with the 2000 Addenda.
There were no unacceptable conditions or indications detected during these examinations.
6.0 Justification for Granting Relief The Reactor Vessel Support Skirts were designed, fabricated, tested and inspected in accordance with ASME Section I1l, 1965 Edition through Summer 1967 Addendum. The support skirts meet the Class 1 criteria for stress and fatigue defined in this Code. The Oconee Reactor Vessel Support Skirts were designed with significant margin and included consideration of normal operating loads plus pipe rupture loads plus the maximum hypothetical seismic loads.
Oconee has a program supporting the NRC GL 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants that provides additional assurance that loss of material of the Reactor Vessel Support Skirt is being managed.
Plant procedures require that leakage is tracked and affected components found with boric acid corrosion to be entered into corrective action program and action taken to address.
Duke Energy believes that the proposed alternative is sufficient to confirm the general mechanical and structural condition of the support skirts. All of the anchorages were examined and there were no adverse conditions detected (e.g., loose or missing parts or fasteners). Because the bottom of the support skirts were examined without obstruction, any boric acid leakage and potential resulting corrosion would have been detected had it occurred.
Duke Energy has examined the Reactor Vessel Skirt support to the extent possible utilizing approved examination techniques and equipment. Based on the acceptable examination results for the surfaces examined, coverage completed by the visual Page 2 of 3
Oconee Relief Request 15-ON-004 examination and the Reactor Vessel Support design margin it is Duke's position that the visual examination provides a reasonable assurance of continued support structural integrity.
7.0 Burden Caused by Compliance
" The minimum estimated radiation dose associated with obtaining the maximum available coverage on the exterior surfaces of the support skirt is approximately 282.4 rem for each Unit. This is the lowest dose and only access time periods for this very high radiation area.
- The minimum estimated radiation dose associated with obtaining the maximum available coverage on the interior surfaces of the support skirt is approximately 1100 mrem for each Unit.
Note that even if the above radiation dose is incurred, there will still be some portions of the RPVSS skirt interior and exterior surfaces that cannot be examined because of permanent attachments to the support skirt to which the insulation is attached. For these surfaces, the burden caused by compliance would require a redesign of the insulation supports. The estimated radiation dose associated with the redesign and replacement of these insulation supports has not been estimated.
8.0 Duration of Proposed Alternative The proposed alternative is requested for the 4th Inservice Inspection Interval for Oconee Units 1, 2, and 3.
" The 4th Inservice Inspection Interval for Oconee Unit 1 began on 01/01/2004 and ended on July 15, 2014.
" The 4th Inservice Inspection Interval for Oconee Unit 2 began on 09/09/2004 and ended on July 15, 2014.
- The 4th Inservice Inspection Interval for Oconee Unit 3 began on 01/02/2005 and ended on July 15, 2014.
Page 3 of 3
Attachment A Relief Request 15-ON-004 1EOC-27, 2EOC-26 3EOC-27 VT Limited Coverage.
Sketch 1, OM-201-1480, OM-201-3153 and OM-2201-0575. Typical all Units.
L~ ~ s~z~s~z'v A-
~~eLr ~ (LpAO~ ¶ I,0%
Skezr !~. Fi~~V J
I
'I.
I C Ac.~
1-4 I-0 3-I
-J I-IL a
I- L
'-I I,,
!S-c- lots T', 2,U
OM 24v1.R-:0003 00c o, OM 247Y, R- CC 0004 COV0V OM 241.R-- 0053 ASAREVATiONS OM 241. R--0006 A. A.-REACTARVESSEL TA-TAPHEAT A.I.P. -AEMAVADLE INSPECTIONPANEL
2 2----I
.3 I
BL.
31-7tTV.
- TING SURFACE 31--D IA" IXOIEI24-I"7AA% R- IETATUSFNO.I SEV 15SIGNS A GATE SINAI D AREAAPI RT 1Q11U DOIISt=IOE 18'-OVI-CNEF) 21 SEENOTEIIE 5ET E-A- NOCUTLET NOZZLE: gd D- - ) EBLINSULATION EE O . 120730E SUPPORSG EO.SPADEO "U A@30- o-U GEEDETAIL *A1-EI-GN1 -ETIAL-C NOTES,
- 1. C.G. SHOWN IS FORDRYVESSEL &=1HEAD ASSEMBLED WITHOUT INSULATION.
- 3. IN THE AESEL m IS -F INTESSEEI*IGGM IASUE THUEGETt'A0F RI
- 4. CENTERLINE- INDEFISE U LINEPASSING RALVET1EAL THRU ThE N OFDIA'.E N Ea G.
6.
AUA EZ~ DETAIL-K IN-SI FULLSIZE
- 7. HEAD REFERENCE OET*ISTHEFOLLOWING DRAWINGS FORREPLACEMENT CLOSURE 8~ ~~ ~~ - -G AXIS J*,*~~MNT U OINTT TRE-IETT ES 20I.50018.001 O 201N.R--001L5.0E1 OR201t.R--0053.001}
GENERAL NOTES:
- 08) 3-IýIRI HOULES ON C F NOHT 5 A. VESSEL IS DESIGNED. FABRICATED. INSPECTED & TESTED IN ACCORDANCE WITH ASMECODE. SECTION Ili. 1965EDITION AND, A. ADDENUA ASIDENTIFIED BYTHECERTIFIED DESIGN SPECIFICATION.
AU B. CERTIFIED DESIGN SPECIFICATION C. CERTIFIED STRESS REPORT B. DESIGN CONDITIONS-PRESSEUE 25I PSIG TEMPERATURE 652-F HYDROSTATIC TESTPRESSURE 3125 P-]
INAL SECTION ION I
-I- I--E ACE, OFALL COMIPONENTS.
-A. B-B & C-CONG.
SEE 1287I3E C. ALL WELDING.
NON-_ESTRUCTIVE POSTWELDEATTREATAENT TESTING GFWELDS AND IS IN ACCORDANCE WITHAPPLICABLE WELD SPECIFICATIONNUMBERS AS SHOWN ONDETAIL DRAWINGS.
D. ALL CLADOING & MACHINED SURFACES TOWAVE 250 FINISHDRBETTER EXCEPT AS NOTED ONDETAIL DWGS.
EXTERNAL SURFACES To HAVE 500 FINISH EXCEPT AS NOTED ONDETAIL DWGS.
Ar, E. ALL CARBON MIL-P-142763 STEELSURFACE HI HEAT AREPAINTED ALUMINUM EXCEPT WITH TWO (2 COATS THEIOTTMH SURFACE OF THEVESSEL SUPPORT.
PAINT TO BE APPLIED AT50- F MIN. TEMP.
F. VESSEL IS CLEANED PRIORTOSHRIPREN IN WITH APPROVED CLEANING PROCEDURE. ACCORDDANCE DETAIL-F 16-E)
COREGUIDE LUG ,25.0 U- DETAIL-N I4-El G. WEIGHTS (APPROXI VESSEL ---- ----A6, OETAIL-M 17- M. 17hDAB.C.1B) I"DIAHOLES EQ. GTODS. NUTS L WASHERS-----40.PB0 PAENAXES0. H SS SWPIPE CAP 1t6000" SFET ELOCATED ONSEUTREAST L. INSCUTAND SIDE CAEPPED.E*,
TA -D 3 3'-I'-E H. SURFACE FINISHES MAYHAVE ISOLATED TOOL HAUKS OR ETAIL -E) ID TO TINWSURFACE 14810 DIARULES DO 17/'DIA B.C.EO.
ON SIMILAR DEPRESSIONS PROVIDED THEYARE MINOR IN lýU-IlEDPIPINGCONFIGUTGTIoN D 18* SPACED STRADDLE AXES.. NATURE.
SEAL ORNOTONSURFACES PAEGSURE BOUNDARIES.
WHICH ARETO BE USED ANDDONOTVIOLATE TO XIN.
TOMATING SURFACE 3-o 1 THICKNESS REGUIRENENTS. ALLUPSET DRRAISED METIA SECTION H-H 1-El IS TOBE REMOVED RUSTBE FAIRED ANDSHARP EDGES TOATLEAST3 TO I.
OFALL DEPRESSIONS
-IE-NSI - F
- 1. P*I
.1 -pRATUE ýF -I W1!
GO IHUD 7% 1 OST24- XEXI'-S ORt GYRU ON 201.-3153 001 AIN. OUUL O'.N M-.NL
~- -.LRIG D- 1 FOTIDIA IRIII X OD I.IG
.,AR-- AII.-D .DoX I 130 DRXTAIUD.AT IAPTlUUSOATPT Pý URI OA~I 1 OA CONDITION I PTAI- 12'8 SUXLR ARRGT. REACTOR .
- DETAIL-7 -
E- CR-DITEAIT JI.-...U -OSA TXIIoI. A.o AR.I,- lI°nT o°.* : B
. DAGOXISUAD VESSEL LONG. SEC.
D 18~j //AHL1FOUL1OUGDXTID~ ........ 114P. ......
.TE ....
..... I 620-083-5K128702 E DI; AERNI - - ALL IRH.1- UODDN T- A- AR/F TIGH L - O-- NIS-E SN N.1D I-I I
' I G I 12 II ý1- I -EO
=-. -
ý--
/ -I rnAs 40 4 , ---
7 .6 AAC,. l0W
".'01A..'t01
-7TyP A-0' 6' P6o.9/A Ca0.1~ Alrr 7'0,
/9-t' qow IF/ 6,5 a 0(CO'oooowz.
8I/,/S..9
.616 *4aO*A*A2.L*F
/ J *" f L-2?--
._/_ .- 7,e A- _
a-A
.1-4 .16. I Ari-I__ -7 3~
-R-I I-S a,00j a-Il
/5I a-I70 ý4
(' ~ . aI (a)(5)6 16 I /
1/6' A42 lAO A,-.9
"-6 lAS r26-7 G-7 S-kV 604'.
I i=L (0T 19-0/.'VO-.W*ia rýs 77115 I
ýVa A-A (aA 7I4~
7l~A' 96's C0/'ASA) a 109 2201. O0575'YDOI
.0.7.9 .0-/A 0-A C-a C-Ao C-I C06455)
C-A (AA9'9 7.96' /76'S
- 1~ I 04 C-
- 96-AY4.9 il'~~~ 9 CO//AAF) l i
YYA /79/S C00A65)
AS
.9-10 1 A-/I SZ5~Ab0 A -/A .91 4-1
~-9-6
.9-7 .96' 5,4'A*L4 9170/V ~V'FLO7.V 9.
- L ,-=~-------- ~6/.A A-A -~
.09.95 ,9'o/SL'7 1. ~4IA A-IS A'AC0. .99.9
.960.907 /8795 ~I" 1 I 3/A I I I .- I I I 7AA -To.
AZI9711771 I IRRORl INPJOLATIONJ E99N:OX0,EOP y w y 5 SKIMV D)AONDP~W1 MNOUAIJM -
4 I'S I t71MCI~- +/-'Z?-~.
,1-t.rt- 90.95 O'~tA~ 1'~ .1.7km 7.,.... 1.771 .nwS na.,a.. *177k01. 1.71 - -. ~a..7.
LAHCITIP,110ON
,,5'2 ,,.S,
' 1'/1