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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARRA-23-0064, Inservice Testing Program Plan and Snubber Program Plan for Sixth 10-Year Inservice Testing (1ST) Program Interval2023-04-24024 April 2023 Inservice Testing Program Plan and Snubber Program Plan for Sixth 10-Year Inservice Testing (1ST) Program Interval RA-20-0329, Proposed Alternative for Inservice Inspection of the Containment Metallic Liner and Moisture Barriers2021-09-0707 September 2021 Proposed Alternative for Inservice Inspection of the Containment Metallic Liner and Moisture Barriers RA-21-0056, Refueling Outage 32 Steam Generator Tube Inspection Report2021-05-26026 May 2021 Refueling Outage 32 Steam Generator Tube Inspection Report RA-19-0393, Refuel 32 (R2R32) Inservice Inspection Program Ninety Day Owner'S Activity Report2021-03-0808 March 2021 Refuel 32 (R2R32) Inservice Inspection Program Ninety Day Owner'S Activity Report RA-19-0138, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections2019-07-23023 July 2019 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head2019-07-10010 July 2019 Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head RA-19-0094, Refuel 31 (R231) Owner'S Activity Report, Fifth 10-Year Inservice Inspection Interval2019-02-20020 February 2019 Refuel 31 (R231) Owner'S Activity Report, Fifth 10-Year Inservice Inspection Interval RNP-RA/17-0065, Refueling Outage 30 Steam Generator Tube Inspection Report2017-09-18018 September 2017 Refueling Outage 30 Steam Generator Tube Inspection Report RNP-RA/17-0051, Submittal of Nine Day Inservice Inspection Summary Report2017-06-29029 June 2017 Submittal of Nine Day Inservice Inspection Summary Report RNP-RA/15-0081, Submittal of Ninety-Day Inservice Inspection Summary Report2015-09-17017 September 2015 Submittal of Ninety-Day Inservice Inspection Summary Report RNP-RA/15-0063, Submittal of Ninety Day Inservice Inspection Summary Report - Supplement2015-07-0808 July 2015 Submittal of Ninety Day Inservice Inspection Summary Report - Supplement RNP-RA/14-0061, Submittal of Snubber Examination and Testing Program2014-05-29029 May 2014 Submittal of Snubber Examination and Testing Program RNP-RA/14-0040, Relief Request (RR)-10 for Expanded Applicability for Use of ASME Code Case N-532-4, Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission, Per 10 CFR 50.55(a)(3)(i)2014-05-0909 May 2014 Relief Request (RR)-10 for Expanded Applicability for Use of ASME Code Case N-532-4, Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission, Per 10 CFR 50.55(a)(3)(i) RNP-RA/14-0014, Submittal of Ninety Day Inservice Inspection Summary Report2014-01-30030 January 2014 Submittal of Ninety Day Inservice Inspection Summary Report RNP-RA/12-0119, Supplemental Response to Request for Additional Information Related to Relief Request (RR)-07 from Immediate ASME Code Repair of Refueling Water Storage Tank Drain Valve (SI-837) for Fifth Ten-Year Inservice Inspection Program...2012-11-11011 November 2012 Supplemental Response to Request for Additional Information Related to Relief Request (RR)-07 from Immediate ASME Code Repair of Refueling Water Storage Tank Drain Valve (SI-837) for Fifth Ten-Year Inservice Inspection Program... RNP-RA/12-0067, Response to the NRC Request for Additional Information Regarding Inservice Inspection Program Plan for the Fifth Ten-Year Interval2012-06-19019 June 2012 Response to the NRC Request for Additional Information Regarding Inservice Inspection Program Plan for the Fifth Ten-Year Interval RNP-RA/12-0063, Submittal of 90 Day Inservice Inspection Summary Report2012-06-15015 June 2012 Submittal of 90 Day Inservice Inspection Summary Report RNP-RA/12-0064, Response to NRC Request for Additional Information Related to Relief Requests (RR)-2 for the Fifth Ten-Year Interval Inservice Testing Program Plan2012-06-0404 June 2012 Response to NRC Request for Additional Information Related to Relief Requests (RR)-2 for the Fifth Ten-Year Interval Inservice Testing Program Plan RNP-RA/12-0056, Response to NRC Request for Additional Information for the Fifth Ten-Year Interval Inservice Testing Program Plan2012-05-10010 May 2012 Response to NRC Request for Additional Information for the Fifth Ten-Year Interval Inservice Testing Program Plan RNP-RA/12-0017, Inservice Testing Program Plan for the Fifth-Ten Year Interval2012-03-16016 March 2012 Inservice Testing Program Plan for the Fifth-Ten Year Interval RNP-RA/12-0023, Inservice Inspection Program for the Fifth Ten-Year Interval2012-03-14014 March 2012 Inservice Inspection Program for the Fifth Ten-Year Interval ML1103300852011-01-27027 January 2011 H. B. Robinson, Unit 2 - Request for Relief from ASME Boiler and Pressure Vessel Code, Section Xi, for the Fourth Ten-Year Inservice Inspection Program Program Interval (Relief Request No. RR-23) RNP-RA/10-0091, Submittal of 90 Day Inservice Inspection Summary Report2010-09-22022 September 2010 Submittal of 90 Day Inservice Inspection Summary Report RNP-RA/09-0010, Submittal of 90 Day Inservice Inspection Summary Report for Refueling Outage 252009-02-11011 February 2009 Submittal of 90 Day Inservice Inspection Summary Report for Refueling Outage 25 RNP-RA/08-0047, Response to NRC Request for Additional Information on the Steam Generator Inservice Inspection Results2008-04-30030 April 2008 Response to NRC Request for Additional Information on the Steam Generator Inservice Inspection Results RNP-RA/07-0077, Submittal of 90 Day Inservice Inspection Summary Report2007-08-0202 August 2007 Submittal of 90 Day Inservice Inspection Summary Report RNP-RA/06-0001, Submittal of 90 Day Inservice Inspection Summary Report2006-01-16016 January 2006 Submittal of 90 Day Inservice Inspection Summary Report RNP-RA/04-0110, Submittal of 90 Day Inservice Inspection Summary Report2004-08-26026 August 2004 Submittal of 90 Day Inservice Inspection Summary Report RNP-RA/03-0034, Revision to Inservice Testing Program Relief Request IST-RR-3 for Containment Spray Pump Comprehensive Pump Test Requirements2003-04-15015 April 2003 Revision to Inservice Testing Program Relief Request IST-RR-3 for Containment Spray Pump Comprehensive Pump Test Requirements RNP-RA/03-0018, Submittal of 90 Day Inservice Inspection Summary Report2003-02-11011 February 2003 Submittal of 90 Day Inservice Inspection Summary Report RNP-RA/02-0065, Relief Request Number RR-12 for the Fourth Ten-Year Interval Inservice Inspection Program2002-05-14014 May 2002 Relief Request Number RR-12 for the Fourth Ten-Year Interval Inservice Inspection Program ML0205703112002-02-20020 February 2002 Revision 1 to Inservice Testing Program Plan - Fourth Interval. 2023-04-24
[Table view] Category:Letter type:RA
MONTHYEARRA-24-0012, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2024-02-0505 February 2024 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report RA-23-0325, Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX2024-01-0808 January 2024 Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation2023-12-14014 December 2023 Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0281, Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes2023-11-0101 November 2023 Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes RA-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023 License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area RA-23-0225, Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes2023-09-20020 September 2023 Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes RA-22-0290, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2023-08-30030 August 2023 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology RA-23-0216, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2023-08-22022 August 2023 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2023-07-12012 July 2023 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-23-0135, Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory2023-06-0707 June 2023 Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory RA-23-0120, Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-05-31031 May 2023 Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 RA-23-0041, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-30030 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations RA-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 20222023-04-26026 April 2023 Duke Energy Annual Radiological Environmental Operating Report - 2022 RA-23-0044, Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.462023-04-26026 April 2023 Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-23-0064, Inservice Testing Program Plan and Snubber Program Plan for Sixth 10-Year Inservice Testing (1ST) Program Interval2023-04-24024 April 2023 Inservice Testing Program Plan and Snubber Program Plan for Sixth 10-Year Inservice Testing (1ST) Program Interval RA-23-0080, Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube2023-04-0505 April 2023 Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube RA-23-0036, Biennial Decommissioning Financial Assurance Reports2023-03-30030 March 2023 Biennial Decommissioning Financial Assurance Reports RA-23-0043, Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations2023-03-30030 March 2023 Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations RA-23-0040, Onsite Property Insurance Coverage2023-03-30030 March 2023 Onsite Property Insurance Coverage RA-23-0039, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2023-03-30030 March 2023 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-23-0055, Notice of Intent to Pursue Subsequent License Renewal for H. B. Robinson Steam Electric Plant, Unit Number 22023-03-24024 March 2023 Notice of Intent to Pursue Subsequent License Renewal for H. B. Robinson Steam Electric Plant, Unit Number 2 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) RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-23-0015, Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-02-0909 February 2023 Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2023-02-0202 February 2023 Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-23-0029, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2023-01-30030 January 2023 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) RA-23-0027, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report for 20222023-01-30030 January 2023 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report for 2022 RA-22-0256, Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-01-23023 January 2023 Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0335, Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab2022-12-0505 December 2022 Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab RA-22-0347, Transmittal of Core Operating Limits Report2022-12-0202 December 2022 Transmittal of Core Operating Limits Report RA-22-0302, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2022-11-0101 November 2022 Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) RA-22-0280, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core.2022-09-21021 September 2022 License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core. RA-22-0245, Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.162022-09-0808 September 2022 Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 RA-22-0239, Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary)2022-08-0909 August 2022 Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary) RA-22-0210, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-07-28028 July 2022 Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-22-0179, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2022-06-15015 June 2022 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RA-22-0151, Duke Energy Common Emergency Plan, Revision 2, Summary of Changes2022-05-24024 May 2022 Duke Energy Common Emergency Plan, Revision 2, Summary of Changes RA-22-0144, Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-022022-05-19019 May 2022 Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 RA-22-0148, 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory2022-05-16016 May 2022 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022 Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility RA-21-0183, Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer)2022-04-28028 April 2022 Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer) RA-22-0106, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-04-28028 April 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections 2024-02-05
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Steve Snider Vice President Nuclear Engineering 526 South Church Street, EC-07H Charlotte, NC 28202 980-382-6195 Steve.Snider@duke-energy.com Serial: RA-19-0393 10 CFR 50.55a March 8, 2021 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 / RENEWED LICENSE NO. DPR-23
SUBJECT:
H. B. Robinson Steam Electric Plant Unit No. 2, Refuel 32 (R2R32) Inservice Inspection Program Ninety Day Owners Activity Report Ladies and Gentlemen:
Pursuant to the reporting requirements of American Society of Mechanical Engineers (ASME)
Section XI, as amended by ASME Code Case N-532-5, Duke Energy Progress (Duke Energy) hereby submits the Owners Activity Report for the H. B. Robinson Nuclear Plant Unit No. 2 (RNP) outage R2R32.
No new regulatory commitments have been made in this submittal. If you have additional questions, please contact Mr. Art Zaremba, Manager - Regulatory Affairs, at 980-373-2062.
Sincerely, Steve Snider Vice President - Nuclear Engineering
Enclosures:
- 1. Ninety Day Owners Activity Report for Refueling Outage 32 cc:
L. Dudes, Regional Administrator USNRC Region II T. Hood, NRC Project Manager, NRR J. Klos, NRC Project Manager, NRR M. Fannon, NRC Senior Resident Inspector RA-19-0393 Enclosure 1 Ninety Day Owners Activity Report for Refueling Outage 32
CASE N-532-5 Report Number: _RA-19-0393____ Plant: H.B. Robinson Steam Electric Plant, 3581 West Entrance Road Hartsville, SC 29550___
Unit No.: __2___ Commercial Service Date: ___March 7, 1971___ Refueling Outage No.: __R2R32____________________
Current Inspection Interval: Fifth Interval (ISI), Third Interval (CISI)_Current Inspection Period: Third Period (ISI), Second Period (CISI)
Edition and Addenda of Section XI Applicable to the Inspection Plans: 2007 Edition through 2008 Addenda (ISI), 2013 Edition (CISI)
Date and Revision of Inspection Plans: __See the table in Attachment 1. _ _______________________________
Edition and Addenda of Section XI Applicable to Repair/Replacement Program, if Different than the Inspection Plans: _same as above Code Cases Used: N-432-1, N-508-4, N-513-3, N-516-3, N-526, N-532-5, N-586-1, N-597-2, N-600, N-613-1, N-629, N-639, N-641, N-643-2, N-648-1, N-651, N-660, N-663, N-705, N-706-1, N-716-1, N-722-1, N-729-4, N-731, N-735, N-762, N-770-5_________ ___
Certificate of Conformance ISI Inspections I certify that (a) the statements made in this report are correct; and (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and the completion of R2R32 conform to the requirements of Section XI.
Signed________________________________ Angela Staller, ISI Program Manager Date____________________
Owner or Owners Designee, Title Certificate of Conformance ISI Repair/Replacement I certify that (a) the statements made in this report are correct; and (b) the repair/replacement activities and evaluations supporting the completion of R2R32 conform to the requirements of Section XI.
Signed________________________________ Ben Babb, Repair/Replacement PM 2/25/21 Date____________________
Owner or Owners Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of South Carolina and employed by OneCIS Insurance Company of Lynn, MA. have inspected the items activities represented by this report in accordance with the requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
___________________________________Commissions_ NB #13930, Endorsements A, N, I, C_________
National Board, State, Province, and Endorsements Date_______________________________
Page 1 of 7 OAR-1 RNP R2R32
CASE N-532-5 Attachment 1 The H.B. Robinson Steam Electric Plant, Unit 2 (RNP), Fifth Ten-Year Interval Inservice Inspection (ISI) Plan, and Third Ten-Year Interval Containment Inservice Inspection (CISI) Plan complies with 10CFR50.55a(g), which implements, by reference, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.
This summary report is submitted pursuant to the reporting requirements of ASME Section XI epair/Replacement Activity Documentation Requirements and Inservice Inspection Summary Report Preparation and Submission Contained within this summary report are the Ow 1 and 2 of Code Case N-532-5 for RNP during Cycle 32 and Refueling Outage 32 (R2R32). R2R32 is the first of two outages of the third period in the fifth inspection interval for the ISI and Pressure Testing programs, and the first of two outages of the first period in the third inspection interval for the Containment ISI program. The Repair/Replacement activities from November 26, 2018 to December 9, 2020 are included. See the table below for the dates and revisions of the inspection plans.
Plan Title Document Number Date of Issue and Revision Fifth Ten-Year Interval Inservice Inspection RNP-PM-008, Rev. 10 October 21 2019 Plan Fifth Ten-Year Interval Inservice Inspection RNP-PM-009, Rev. 7 October 21 2019 Schedule Augmented Inservice Inspection (AISI) Plan RNP-PM-012, Rev. 2 December 21, 2020 and Schedule Third Ten-Year Interval Inservice IWE/IWL RNP-PM3-006, Rev. 0 September 9, 2019 Inspection Plan Third Ten-Year Interval Inservice IWE/IWL RNP-PM3-007, Rev. 0 September 9, 2019 Inspection Schedule Page 2 of 7 OAR-1 RNP R2R32
CASE N-532-5 Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Exam Category and Item Item Description Evaluation Description Number Spring Support 218/SI-3-6030: Support was evaluated as functional misalignment and acceptable for continued service F-A/F1.20C in as found condition per EC 418718.
NCR 2359256 was generated to address the condition.
Support 313/S6-1A: The fastener Support was evaluated as functional nuts on the south side support and acceptable for continued service F-A/F1.40 legs exhibited evidence of in as found condition per EC 418616.
corrosion with material wastage. NCR 2356877 was generated to address the condition.
Support 244/SI-5-6003A: A Support was evaluated as functional missing nut was discovered on and acceptable for continued service F-A/F1.20A the pipe to clevis attachment. in the as found condition per the evaluation documented on report EV-20-RN2-003. NCR 2357719 was generated to address the condition.
Support 313/SW-1-H-1: Support Support was evaluated as functional is shown as embedded on the and acceptable for continued service F-A/F1.30B design drawing but is sitting on in the as found condition per the top of the floor in the field. evaluation documented on report EV-20-RN-2002. NCR 2357078 was generated to address this condition.
Support 262/FW-3A-6007: The Support was evaluated as functional settings were found to be out of and acceptable for continued service F-A/F1.20C tolerance on the spring hanger. in the as found condition per the evaluation documented on report EV-20-RN2-004. NCR 2359031 was generated to address the condition.
Containment liner examinations EC 419006 was generated to revealed relevant conditions document acceptance of the relevant E-C/E4.111 exceeding 10% of the nominal conditions noted.
wall thickness resulting in evaluation to meet the requirements of IWE-3122.3 in accordance with IWE-3521(a).
Note 1: See information required by 10 CFR 50.55a(b)(2)(ix)(A) in Attachment 2.
Page 3 of 7 OAR-1 RNP R2R32
CASE N-532-5 Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Item Description Description of Work Date Repair/Replacement Class Completed Plan Number 1 SG-C Tubes Steam Generator One Tube Plugging 11/4/2020 20370442 2 RHR -PMP-A RHR-PMP-A Seal Replacement 12/6/2020 20437344 Page 4 of 7 OAR-1 RNP R2R32
CASE N-532-5 Attachment 2 Containment Liner Plate Requirements per 10 CFR 50.55a(b)(2)(ix)(A)(2)
For each inaccessible area identified for evaluation, the applicant or licensee must provide the following in the ISI Summary Report as (i) A description of the type and estimated extent of degradation, and the conditions that led to the degradation; (ii) An evaluation of each area, and the result of the evaluation; and (iii) A description of necessary corrective actions.
Information required to meet 10 CFR 50.55a(b)(2)(ix)(A)(2)(i):
A. Description of Degradation
- 1. During RNP Refueling Outage RO32 (Fall 2020), twenty-eight insulation panels were removed for inspection of the containment liner. The panels were in three groups: group
-50 ; group 2 ranging from oximate azimuth 350 -5 , and group 3 ranging from elevation proximate azimuth 112 -160 . Twenty-seven of these panel inspections were first time inspections. Areas of general corrosion, as well as pitting, were found on twenty-one panels that exceeded 10% loss of nominal wall thickness. It is suspected that adjacent areas of the inaccessible liner may have similar conditions.
B. Estimated Extent of Degradation
- 1. Based on the findings of inspections during RO32, and previous outages since RO18 (Spring 1998), surface corrosion on the containment liner under the containment insulation panels is consistent throughout various areas of the containment liner. Areas of general corrosion exist on the liner underneath the insulation panels, as well as some areas of pitted corrosion. In all cases, degradation continues to meet the minimum required thickness for the liner to fully function as designed.
- 2. The containment liner of the dome is accessible for visual inspection and has not exhibited degradation shown to challenge the function of the leak tight liner membrane.
- 3. Selection of panels for inspection in RO32 was based on areas identified with distorted insulation panels and insufficient caulking between the insulation panels, as documented in CR 2239389. The distorted insulation system is a general condition over much of the liner.
C. Description of Conditions That Led to the Degradation
- 1. It is estimated that moisture from the environment comes in contact with the containment liner. The containment liner is covered by insulation panels, which are protected by metal sheathing panels. These sheathing panels are caulked at the joints to Page 5 of 7 OAR-1 RNP R2R32
CASE N-532-5 create a cohesive insulation system. However, over time, the caulking of the insulation system has dried and cracked. This allows for panel distortion, and exposure of the insulation system to the containment atmosphere. It is estimated that exposure to the humid environment in areas of coating degradation cause corrosion of the containment liner.
Information required to meet 10 CFR 50.55a(b)(2)(ix)(A)(2)(ii):
A. The containment liner is covered by an insulation system, and therefore inaccessible in accordance with ASME Code Interpretation XI-1-13-25. Evaluation of inaccessible areas of the vertical liner above the floor slab are evaluated based on the degradation found during liner inspections. Data from past inspections is considered to evaluate the liner. Despite the limitations of access in some areas, it is judged that the available sample size obtained since RO18 provides a representative sample of the vertical liner.
It is expected that the areas recently inspected during RO32, as well as areas inspected throughout the history of the plant, are representative of the vertical containment liner.
Since RO18 (Spring 1998), approximately 400 insulation panels have been removed for inspection of the of the underlying liner. Examinations have taken place at various elevations and various azimuths. In some locations, physical obstructions exist, such as HVAC units, ducts, and support structures, which create hardship for inspection, particularly No inspections have been compl elevation, as e floor surface, and access is obstructed by the HVAC duct ring.
The RO32 inspection areas were targeted based off identified areas with loss of caulking adhesion between insulation panels. The row of insulation just above the ground slab at ner inspection in both the first and second inspection intervals. This elevation was previously submerged during a small break LOCA in 1975 and has been fully inspected twice. Each time a panel is inspected, it is recoated as necessary, and left with an acceptable coating in place.
The worst case of liner corrosion found in all previously performed inspections has been pitting with up to 50% wall loss. These pits are small in area. The design analysis provides that the containment liner will continue to fully function with 50% wall loss over the entirety 64% wall loss over the entirety of the liner where nominal This provides ample margin to the worst case as-found conditions for assurance that all areas of the containment liner remain acceptable to fully perform the design function.
Additionally, in RO32, an integrated leak rate test was successfully performed, providing additional assurance that no leak paths through the liner currently exist.
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CASE N-532-5 Information required to meet 10 CFR 50.55a(b)(2)(ix)(A)(2)(iii):
A. As a category E-C examination, successive inspections are required in subsequent periods in accordance with IWE-2420. A relief request for the third containment interval is under development to address this requirement. All inspected areas to date have been recoated as necessary and left with satisfactory coatings in place.
B. Additional examinations of the containment liner are planned for the remaining of the interval. This plan is contingent upon approval of the relief requests, to focus on areas which have not been previously recoated or inspected for monitoring of corrosion on the liner.
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