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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARRA-23-0230, Refuel 27 (C1 R27) Inservice Inspection (ISI) Report2023-09-25025 September 2023 Refuel 27 (C1 R27) Inservice Inspection (ISI) Report RA-22-0608, Refuel 25 (C2R25) Inservice Inspection (ISI) Report2023-01-25025 January 2023 Refuel 25 (C2R25) Inservice Inspection (ISI) Report RA-22-0021, Refuel 26 (C1 R26) Inservice Inspection (ISI) Report2022-01-26026 January 2022 Refuel 26 (C1 R26) Inservice Inspection (ISI) Report RA-21-0223, Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2021-08-0202 August 2021 Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report RA-19-0391, Refuel 23 (C2R23) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2019-12-19019 December 2019 Refuel 23 (C2R23) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report RA-19-0092, Refuel 24 (C1R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2019-03-11011 March 2019 Refuel 24 (C1R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report CNS-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report2018-07-12012 July 2018 Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information CNS-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report2017-01-0606 January 2017 End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report CNS-16-067, ASME OM Code In-Service Testing Program Document2016-08-31031 August 2016 ASME OM Code In-Service Testing Program Document CNS-16-042, Snubber Program Plan for the Fourth Ten-Year Inservice Testing Interval2016-06-13013 June 2016 Snubber Program Plan for the Fourth Ten-Year Inservice Testing Interval CNS-16-020, Inservice Inspection Report for End of Cycle 22 Refueling Outage2016-03-18018 March 2016 Inservice Inspection Report for End of Cycle 22 Refueling Outage ML15280A3422015-10-0505 October 2015 Fourth Inservice Inspection Interval Steam Generator Tube Plan ML15238A8832015-08-19019 August 2015 Fourth Inservice Inspection Interval Plan and Inservice Inspection Interval Pressure Test Plan CNS-15-074, CISI-1462.10.0040, Revision 0, Fourth Interval Inservice Inspection Outage Schedule, Quality Assurance Program Related2015-08-13013 August 2015 CISI-1462.10.0040, Revision 0, Fourth Interval Inservice Inspection Outage Schedule, Quality Assurance Program Related ML15238A9002015-08-12012 August 2015 CISI-1462.10.0040, Revision 0, Fourth Interval Inservice Inspection Outage Schedule, Quality Assurance Program Related ML15238A8982015-08-12012 August 2015 CISI-1462.10.0040-ISI, Revision 1, Fourth Interval Inservice Inspection Plan CNS-15-061, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 20 Refueling Outage2015-07-0606 July 2015 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 20 Refueling Outage ML15238A8962015-06-23023 June 2015 Fourth Inspection Interval Inservice Inspection Pressure Test Plan CNS-15-047, Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage, Response to NRC Requests for Additional Information (Rais)2015-05-15015 May 2015 Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage, Response to NRC Requests for Additional Information (Rais) CNS-15-022, Request to Use a Portion of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section Xl, for Inservice Inspection Activities2015-03-16016 March 2015 Request to Use a Portion of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section Xl, for Inservice Inspection Activities CNS-14-105, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage2014-09-25025 September 2014 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage CNS-14-001, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 19 Refueling Outage2014-01-13013 January 2014 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 19 Refueling Outage ML13085A0252013-03-21021 March 2013 Inservice Inspection Report for End of Cycle 20 Refueling Outage ML12195A3462012-07-10010 July 2012 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 18 Refueling Outage ML12125A2972012-05-0303 May 2012 Proposed Alternative Request Number 11-CN-001 for the Third Ten-Year Inservice Inspection Interval Response to NRC Request for Additional Information ML1109806012011-04-0505 April 2011 Steam Generator (SG) Tube Inspection Report for End of Cycle 17 Refueling Outage Pursuant to Technical Specification (TS) 5.6.8 ML1102003222011-01-19019 January 2011 Inservice Inspection Report and Steam Generator In-Service Inspection Summary Report for End of Cycle 17 Refueling Outage ML0920104982009-07-14014 July 2009 Inservice Inspection Report and Steam Generator In-Service Inspection Summary Report for End of Cycle 16 Refueling Outage ML0927500082008-09-11011 September 2008 Inservice Inspection Report and Steam Generator In-service Inspection Summary Report for End of Cycle 17 Refueling Outage ML0805001792008-02-11011 February 2008 Inservice Inspection Report and Steam Generator In-service Inspection Summary Report for End of Cycle 15 Refueling Outage ML0732001122007-11-0808 November 2007 Request for Relief Number 07-GO-001 Alloy 600 Pressurizer Weld Overlays - Submittal of Committed Information ML0721202212007-07-30030 July 2007 Notification of Inspection and Request for Information ML0713503782007-05-0707 May 2007 Submittal of Steam Generator Inservice Inspection Documentation for Third Ten-Year Interval ML0709502752007-03-28028 March 2007 Inservice Inspection Report for End of Cycle 16 Refueling Outage ML0623403632006-08-15015 August 2006 Inservice Testing (IST) Program for Pumps and Valves - Third Ten-Year Interval Plan ML0620603112006-07-18018 July 2006 Inservice Inspection Reports for End of Cycle 14 Refueling Outage ML0607403192006-03-0606 March 2006 Submittal of Third Ten-Year Interval Inservice Inspection Plan and Inservice Inspection Pressure Test Plan ML0603901542006-02-0606 February 2006 Notification of Inspection and Request for Information ML0525905642005-09-0808 September 2005 Request for Relief Number 05-CN-004 Limited Weld Examinations During End-of-Cycle 15 Refueling Outage ML0525004942005-08-30030 August 2005 Inservice Inspection Report and Steam Generator Outage Summary Report for End-of-Cycle 15 Refueling Outage ML0518601322005-06-16016 June 2005 Submittal of Third Ten-Year Interval Inservice Inspection Plan and Inservice Inspection Pressure Test Plan ML0514002732005-05-11011 May 2005 Request for Relief Number 05-CN-003, Limited Volumetric Inspection Coverages During End-of-Cycle 12 and End-of-Cycle 13 Refueling Outages ML0508105992005-03-11011 March 2005 Duke Requests NRC Approval of an Alternative to the Requirements of the 1998 Edition Through the 2000 Addenda of the Pressure Vessel Code, Section XI for the Listed Inservice Inspection Intervals ML0502604532005-01-17017 January 2005 Inservice Inspection Report for End of Cycle 13 Refueling Outage ML0430103872004-10-19019 October 2004 Second Ten Year Inservice Inspection Interval Steam Generator C Hot Leg Nozzle Welds ML0414901162004-05-18018 May 2004 Request for Relief from Pressure Requirement at Certain Class 1 Inservice Inspection Pressure Test Boundaries ML0408502452004-03-17017 March 2004 Inservice Inspection Report for End-of- Cycle 14 Refueling Outage ML0317605962003-06-18018 June 2003 Inservice Inspection Report & Steam Generator Outage Summary Report for End of Cycle 12 Refueling Outage ML0313405102003-05-0707 May 2003 Relief, Request for Relief Number 02-002, Revision 1 Re Limited Weld Examinations for End of Cycle 13 Refueling Outage 2023-09-25
[Table view] Category:Letter
MONTHYEARIR 05000413/20230042024-02-0202 February 2024 Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 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 IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 ML23107A2542023-04-14014 April 2023 301 Examination Report Letter and Report (Merged) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl 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 IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22319A0942022-11-10010 November 2022 EN 56219 - Flowserve. 10 CFR Part 21 Report 38878-8 Solenoid Valve at Duke, Catawba Flowserve Evaluation 105 IR 05000414/20220032022-10-31031 October 2022 Integrated Inspection Report 05000414/2022003 and 05000414/2022003 IR 05000413/20224022022-10-28028 October 2022 Security Baseline Inspection Report 05000413 2022402 and 05000414 2022402 ML22276A2492022-10-25025 October 2022 Completion of License Renewal Commitment No. 10, Aging Management of Environmentally Assisted Fatigue ML22297A2642022-10-25025 October 2022 Project Manager Assignment ML22303A0052022-10-24024 October 2022 EN 56178 - Tioga Final. LTR-TP-22-29 2021 10CFR Part 21 Improper Notification of NRC ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22303A0042022-08-31031 August 2022 Final Report Notification Pursuant to 10 CFR Part 21.21, Regarding Supply of 6 NPS Sch. 40 Seamless Stainless-Steel Pipe; Manufacturer: Maxim Tubes Company Pvt. Ltd.; Heat No: N200309AW01, SR No: 7; 9 Pcs; 180 Feet Total Procured as Unquali IR 05000413/20220052022-08-26026 August 2022 Updated Inspection Plan for Catawba Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000413/2022005 and 05000414/2022005 ML22217A0792022-08-0303 August 2022 301, Corporate Notification Letter (210-day Ltr) IR 05000413/20220022022-07-29029 July 2022 Integrated Inspection Report 05000413/2022002 and 05000414/2022002 IR 07200045/20220012022-07-26026 July 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200045/2022001 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright IR 05000413/20220102022-07-21021 July 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000413/2022010 and 05000414/2022010 ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22195A2432022-07-19019 July 2022 Request for Withholding Information from Public Disclosure Regarding Reactor Vessel Closure Head Repair Alternative ML22199A2552022-07-0606 July 2022 Ds Catawba 2022 RQ Inspection Notification Letter ML22222A0092022-07-0101 July 2022 EN 55974 - Flowserve, Part 21 Report Re Solenoid Coil Failure of Model 38878-8 Solenoid Valve at Catawba Nuclear Station for Use on FWIV Actuator ML22175A0342022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000413/2022403 and 05000414/2022403 ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3572022-05-16016 May 2022 Letter Issuing Exemption to Catawba IR 05000414/20220012022-04-28028 April 2022 Integrated Inspection Report 05000413/ 2022001 and 05000414/2022001 2024-02-02
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23271A1792023-09-28028 September 2023 Request for Confirmation License Amendment Application to Revise Control Room Cooling TS 3.7.11 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) ML22336A0692022-11-28028 November 2022 Final 2023 Catawba Nuclear Station (CNS) Commercial Grade Dedication (CGD) Inspection Information Request ML22154A1312022-06-0303 June 2022 NRR E-mail Capture - Catawba Nuclear Station, Units 1 and 2 - Request for Additional Information Environmentally-Assisted Fatigue License Renewal Commitment ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22102A2962022-04-13013 April 2022 Request for Withholding Information from Public Disclosure Response to Request for Additional Information ML22063B1782022-03-0909 March 2022 Request for Additional Information Regarding LAR for Revision to the Conditional Exemption of the End of Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) NON-PROPRIETARY ML22024A1122022-01-24024 January 2022 2022 CNS POV Inspection Information Request ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21335A2252021-12-0101 December 2021 NRR E-mail Capture - Catawba Nuclear Station, Unit 2 - Request for Additional Information Spring 2021 Steam Generator Tube Inspection Report (L-2021-LRO-0043) ML21117A1232021-04-23023 April 2021 NRR E-mail Capture - Catawba Verbal Relief Request Request for Additional Information ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML20346A0212020-12-10010 December 2020 NRR E-mail Capture - Formal Release of RAIs - License Amendment to Change TS 3.8.1 Due Jan. 29, 2021 ML20338A3932020-12-0303 December 2020 Notification of Inspection and Request for Information ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20244A0462020-08-31031 August 2020 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20073F3832020-03-13013 March 2020 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station - SG Report (RA-19-0391) - C2R23 ML20052E4282020-02-21021 February 2020 Notification of NRC Fire Protection Team Inspection (Fpti) (NRC Inspection Report 05000412/2020013 and 05000414/2020013) and Request for Information ML20050D3382020-02-21021 February 2020 Letter RAI 1 MAGNASTOR-Catawba and McGuire Exemptions with Enclosure ML20003E5372020-01-0303 January 2020 NRR E-mail Capture - Catawba PT Limits LAR - RAIs ML19032A5842019-01-31031 January 2019 Emergency Preparedness Program Inspection Request for Information ML19011A1372019-01-10010 January 2019 NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML19009A5412019-01-0909 January 2019 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Esps LAR ML19007A3422018-12-21021 December 2018 NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML18068A5052018-03-0909 March 2018 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Nsws Return Pond Header LAR (CACs MG0245 and MG0246, EPID L-2017-LLA-0297) ML18058B2062018-02-27027 February 2018 Notification of Inspection and Request for Information ML18057A2182018-02-23023 February 2018 Enclosurequest for Additional Information (Letter to A. Zaremba Request for Additional Information for Review of Duke Energy'S Decommissioning Funding Plan Update) ML17335A0972017-11-29029 November 2017 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Relief Request 17-CN-001 (CACs MF9807 and MF9808, EPID L-2017-LLR-0032) ML17135A0302017-05-12012 May 2017 NRR E-mail Capture - Request for Additional Information - Catawba TSTF-197 ML17115A1422017-04-25025 April 2017 NRR E-mail Capture - Request for Additional Information - Catawba SG Report - RFO 21 ML16337A3322017-01-12012 January 2017 Request for Additional Information Regarding License Amendment Request for Electrical Power System Alignments for Shared Systems ML16355A3922016-12-29029 December 2016 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program ML16292A2252016-10-14014 October 2016 Emergency Preparedness Inspection and Request for Information ML16271A0752016-10-12012 October 2016 Request for Additional Information Regarding License Amendment Request for Electrical Power System Alignments for Shared Systems ML16222A7472016-08-0909 August 2016 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML16205A0022016-07-21021 July 2016 Notification of Inspection and Request for Information ML16187A0662016-07-0707 July 2016 Catawba Nuclear Station, Units 1 and 2 - Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program (CAC Nos. MF2936 and MF2937) ML16111B2472016-04-28028 April 2016 Request for Additional Information Re. License Amendment Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program ML16120A0872016-04-27027 April 2016 Notification of Inspection and Request for Information ML16113A0732016-04-22022 April 2016 Draft RAIs License Amendment Request to Revise TS Section 5.5.2 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML16014A7102016-01-20020 January 2016 Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme ML16007A1902016-01-20020 January 2016 Request for Additional Information Regarding License Amendment Request to Change the RCS Minimum Required Flow Rates ML15348A2602015-12-17017 December 2015 Request for Additional Information Regarding License Amendment Request to Use an Alternative Fission Gas Gap Release Fraction ML15320A3862015-11-19019 November 2015 RAI LAR to Adopt TSTF-523 ML15314A3592015-11-10010 November 2015 Duke Energy Draft RAIs Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15314A3562015-11-10010 November 2015 E-mail from J. Whited to A. Zaremba Duke Energy Draft RAIs License Amendment Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15252A4012015-09-17017 September 2015 License Amendment Request Regarding Non-Conservative Technical Specification Allowable Value ML15201A5122015-08-13013 August 2015 Request for Additional Information Regarding License Amendment Request to Support a Measurement Uncertainty Recapture Power Uprate for Catawba, Unit 1 2023-09-28
[Table view] |
Text
July 30, 2007 Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC ATTN: Mr. J. R. Morris Site Vice President Catawba Site 4800 Concord Road York, SC 29745-9635
SUBJECT:
CATAWBA NUCLEAR STATION, UNIT 2 - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Morris:
From September 24 to October 5, 2007, the NRC will perform the baseline inservice inspection (ISI) at the Catawba Nuclear Station, Unit 2 (NRC Inspection Procedure 71111.08 and Temporary Instruction 2515/150, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles). Experience has shown that this inspection is resource intensive both for the NRC inspectors and your staff. In order to minimize the impact to your on-site resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection. These documents have been divided into two groups. The first group (section A of the enclosure) identifies information to be provided prior to the inspection to ensure that the inspectors are adequately prepared. The second group (section B of the enclosure) identifies the information the inspectors will need upon arrival at the site. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection.
We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Allison Jones-Young of your organization.
Our inspection dates are subject to change based on your updated schedule of outage activities. If there are any questions about this inspection or the material requested, please contact the lead inspector Barry Miller at (404) 562-4632 (bwm1@nrc.gov).
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system
DPC 2 (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/
reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
George T. Hopper, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-414 License No. NPF-52
Enclosure:
Inservice Inspection Document Request cc w/encl:
Randy D. Hart Regulatory Compliance Manager Duke Power Company LLC d/b/a/Duke Energy Carolinas, LLC Electronic Mail Distribution George Strickland, Engineer Catawba Nuclear Station 4800 Concord Road York, SC 29745 Kay Nicholson, Technical Specialist Catawba Nuclear Station 4800 Concord Road York, SC 29745 Allison Jones-Young, Engineer Catawba Nuclear Station 4800 Concord Road York, SC 29745 Anthony Jackson, Engineer Catawba Nuclear Station 4800 Concord Road York, SC 29745 (cc w/encl contd - See page 3)
DPC 3 (cc w/encl contd)
Lawrence Rudy, Engineer Catawba Nuclear Station 4800 Concord Road York, SC 29745 Lisa F. Vaughn Associate General Counsel and Managing Attorney Duke Energy Corporation 526 South Church Street-EC 07H Charlotte, NC 28202 Kathryn B. Nolan Senior Counsel Duke Energy Corporation 526 South Church Street-EC 07H Charlotte, NC 28202 David A. Repka Winston & Strawn LLP Electronic Mail Distribution North Carolina MPA-1 Electronic Mail Distribution Henry J. Porter, Asst. Director Div. of Radioactive Waste Mgmt.
S. C. Department of Health and Environmental Control Electronic Mail Distribution R. Mike Gandy Division of Radioactive Waste Mgmt.
S. C. Department of Health and Environmental Control Electronic Mail Distribution Elizabeth McMahon Assistant Attorney General S. C. Attorney General's Office Electronic Mail Distribution Vanessa Quinn Federal Emergency Management Agency Electronic Mail Distribution (cc w/encl contd - See page 4)
DPC 4 (cc w/encl contd)
North Carolina Electric Membership Corporation Electronic Mail Distribution Peggy Force Assistant Attorney General N. C. Department of Justice Electronic Mail Distribution County Manager of York County, SC Electronic Mail Distribution Piedmont Municipal Power Agency Electronic Mail Distribution R. L. Gill, Jr., Manager Nuclear Regulatory Issues and Industry Affairs Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC 526 S. Church Street Charlotte, NC 28201-0006 Distribution w/encl:
J. Stang, NRR RIDSNRRDIRS PUBLIC
OFFICE RII:DRS RII:DRP SIGNATURE NAME BMILLER JMOORMAN DATE 8/ /2007 8/ /2007 8/ /2007 8/ /2007 8/ /2007 8/ /2007 8/ /2007 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: September 24 - October 5, 2007 Inspection Procedures: IP 71111.08 Inservice Inspection (ISI) Activities TI 2515/150 Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles Inspector: Barry Miller, Reactor Inspector A. Information Requested for the In-Office Preparation Week The following information should be sent to the Region II office in hard copy or electronic format (CD preferred), in care of Barry Miller by September 10, 2007, to facilitate the selection of specific items that will be reviewed during the onsite inspection week. The inspector will select specific items from the information requested below and then request from your staff additional documents needed during the onsite inspection week (section B of this enclosure). We ask that the specific items selected from the lists be available and ready for review on the first day of inspection. *Please provide requested documentation electronically if possible. If requested documents are large and only hard copy formats are available, please inform the inspector, and provide subject documentation during the first day of the onsite inspection. If you have any questions regarding this information request, please call the inspector as soon as possible.
A.1 ISI / Welding Programs and Schedule Information a) A detailed schedule (including preliminary dates) of:
I) Nondestructive examinations (NDEs) planned for Class 1 & 2 systems and containment, performed as part of your ASME Section XI, Risk Informed (if applicable), and augmented ISI Programs during the upcoming outage.
Provide a status summary of the NDE inspection activities vs. the required inspection period percentages for this Interval by category per ASME Section XI, IWX-2400 (Do not provide separately if other documentation requested contains this information) ii) Reactor pressure vessel head (RPVH) examinations planned for the upcoming outage.
iii) Examinations planned for Alloy 82/182/600 components that are not included in the Section XI scope. (If applicable) iv) Examinations planned as part of your Boric Acid Corrosion Control Program (Mode 3 walkdowns, bolted connection walkdowns, etc.)
Enclosure
2 v) Welding activities that are scheduled to be completed during the upcoming outage (ASME Class 1, 2, or 3 structures, systems, or components (SSCs))
b) A copy of ASME Section XI Code Relief Requests and associated NRC Safety Evaluations applicable to the examinations identified above.
c) A list of NDE reports (ultrasonic, radiography, magnetic particle, dye penetrant, visual VT-1, VT-2, and VT-3) which have identified recordable indications (geometric or flaw) on Code Class 1 & 2 systems since the beginning of the last refueling outage. This should include the previousSection XI pressure test(s) conducted during start up and any evaluations associated with the results of the pressure tests. Also, include in the list the NDE reports with recorded indications in the RPVH penetration nozzles which have been accepted for continued service. The list of NDE reports should include a brief description of the SSC where the recordable indication was identified.
d) A list with a brief description (e.g. system, material, pipe size, weld number, and NDE performed) of the welds in Code Class 1 and 2 systems which have been fabricated due to component repair/replacement activities since the beginning of the last refueling outage, or are planned to be fabricated this refueling outage.
e) If reactor vessel weld examinations required by the ASME Code are scheduled to occur during the upcoming outage, provide a detailed description of the welds to be examined, and the extent of the planned examination. Please also provide reference numbers for applicable procedures that will be used to conduct these examinations.
f) Copy of any 10 CFR Part 21 reports applicable to your SSCs within the scope of Section XI of the ASME Code that have been identified since the beginning of the last refueling outage.
g) A list of any temporary non-code repairs in service (e.g. pinhole leaks).
h) Please provide copies of the most recent self assessments for the ISI, Welding, and Alloy 600 Programs.
A.2 Reactor Pressure Vessel Head (RPVH) a) Provide the detailed scope of the planned NDE of the reactor vessel head which identifies the types of NDE methods to be used on each specific part of the vessel head to fulfill NRC commitments made in response to NRC Bulletin 2002-02 and NRC Order EA-03-009. Also, include examination scope expansion criteria and planned expansion sample sizes if relevant indications are identified.
(If applicable)
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3 b) A list of the standards and/or requirements that will be used to evaluate indications identified during NDE of the reactor vessel head (e.g. the specific industry or procedural standards which will be used to evaluate potential leakage and/or flaw indications).
A.3 Boric Acid Corrosion Control Program (BACCP) a) Copy of the procedures that govern the scope, equipment and implementation of the inspections required to identify boric acid leakage and the procedures for boric acid leakage/corrosion evaluation.
b) Please provide a list of leaks (including code class of the components) that have been identified since the last refueling outage and associated corrective action documentation. If during the last cycle, the Unit was shutdown, please provide documentation of containment walk-down inspections performed as part of the BACCP.
c) Please provide a copy of the most recent self-assessment performed for the BACCP.
A.4 Steam Generator (SG) Inspections a) A detailed schedule of:
I) SG tube inspection, data analyses, and repair activities for the upcoming outage. (If occurring) ii) SG secondary side inspection activities for the upcoming outage. (If occurring) b) Please provide a copy of your SG ISI Inspection Program and Plan. Please include a copy of the Operational Assessment from last outage, and a copy of the following documents as they become available:
I) Degradation Assessment ii) Condition Monitoring Assessment c) If you are planning on modifying your Technical Specifications such that they are consistent with TSTF-449, please provide copies of your correspondence with the NRC regarding deviations from the STS.
d) Copy of SG history documentation given to vendors performing eddy current (ET) testing of the SGs during the upcoming outage.
e) Copy of SG Eddy Current Data Analyst Guidelines, and Site Validated Eddy Current Technique. Additionally, please provide a copy of EPRI Appendix H Eddy Current Technique Qualification Records.
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4 f) Identify and quantify any SG tube leakage experienced during the previous operating cycle. Also provide documentation identifying which SG was leaking and corrective actions completed or planned for this condition. (If applicable) g) Provide past history of the condition and issues pertaining to the secondary side of the steam generators (including items such as loose parts, fouling, top of tube sheet condition, crud removal amounts, etc.)
h) Please provide copies of your most recent self assessments of the SG monitoring, loose parts monitoring, and secondary side water chemistry control programs.
I) Please also indicate where the primary, secondary, and resolution analyses are scheduled to take place.
j) Please provide a summary of the scope of the SG ISI examinations, including examination methods such as Bobbin, Rotating Pancake, or Plus Points, and the percentage of tubes to be examined. *Do not provide these documents separately if already included in other information requested.
A.5 Additional information related to all ISI activities a) A list with a brief description of ISI, BACCP, and SG ISI related issues (e.g.,
condition reports) entered into your corrective action program since the beginning of the last refueling outage (for Units 1 and 2). For example, a list based upon data base searches using key words related to piping or SG tube degradation such as: ISI, ASME Code,Section XI, NDE, cracks, wear, thinning, leakage, rust, corrosion, boric acid, or errors in piping/SG tube examinations.
b) Please provide names and phone numbers for the following program leads:
ISI contacts (Examination, planning)
Containment Exams RPVH Exams Snubbers and Supports Repair and Replacement Program Manager Licensing Contact Site Welding Engineer Boric Acid Corrosion Control Program SG Inspection Activities (site lead and vendor contact)
B. Information to be provided on-site to the inspector at the entrance meeting (September 24, 2006):
B.1 ISI / Welding Programs and Schedule Information a) Updated schedules for ISI/NDE activities, including SG ISI, planned welding Enclosure
5 activities, and schedule showing contingency repair plans, if available.
b) For ASME Class 1 and 2 welds selected by the inspector from the lists provided from section A of this enclosure, please provide copies of the following documentation for each subject weld:
I) Weld data sheet (traveler) ii) Weld configuration and system location iii) Applicable Code Edition and Addenda for weldment iv) Applicable Code Edition and Addenda for welding procedures v) Applicable weld procedures (WPS) used to fabricate the welds vi) Copies of procedure qualification records (PQRs) supporting the WPS from B.1.b.v vii) Copies of mechanical test reports identified in the PQRs above viii) Copies of the nonconformance reports for the selected welds (If Applicable) ix) Radiographs of the selected welds and access to equipment to allow viewing radiographs (If RT was performed) x) Copies of the preservice examination records for the selected welds.
xi) Copies of welder performance qualifications records applicable to WPS, including documentation that welder maintained proficiency in the applicable welding processes specified in the WPS (At least six months prior to date subject work) xii) Copies of NDE personnel qualifications (VT, PT, UT, RT) As applicable c) For the ISI related corrective action issues selected by the inspector from section A of this enclosure, provide a copy of the corrective actions and supporting documentation.
d) For the NDE reports with recordable indications on Code Class 1 & 2 systems selected by the inspector from section A above, provide a copy of the examination records, examiner qualification records, and associated corrective action documents.
e) A copy of (or ready access to) most current revision of the ISI Program Manual and Plan for the current Interval.
f) For the NDEs selected by the inspector from section A of this enclosure, provide copy of the NDE procedures used to perform the examinations (including calibration and flaw characterization/sizing procedures). For ultrasonic examination procedures qualified in accordance with ASME Code,Section XI, Appendix VIII, provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets). Also, include documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers) and NDE personnel qualification records.
B.2 Reactor Pressure Vessel Head (RPVH)
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6 a) Provide the NDE personnel qualification records for the examiners who will perform examinations of the RPVH.
b) Provide drawings showing the following: (If a visual examination is planned for the upcoming refueling outage)
I) RPVH and CRDM nozzle configurations ii) RPVH insulation configuration The drawings listed above should include fabrication drawings for the nozzle attachment welds as applicable.
c) Copy of NDE reports from the last RPVH examination.
d) Copy of evaluation or calculation demonstrating that the scope of the visual examination of the upper head will meet the 95% minimum coverage required by NRC Order EA-03-009 (If a visual examination is planned for the upcoming refueling outage).
e) Provide a copy of the procedures that will be used to identify the source of any boric acid deposits identified on the RPVH. If no explicit procedures exist which govern this activity, provide a description of the process to be followed including personnel responsibilities and expectations.
f) Provide a copy of the updated calculation of effective degradation years (EDY) for the RPVH susceptibility ranking.
g) Provide copy of the vendor qualification report(s) that demonstrates the detection capability of the NDE equipment used for the RPVH examinations. Also, identify any changes in equipment configurations used for the RPVH examinations which differ from that used in the vendor qualification report(s).
B.3 Boric Acid Corrosion Control Program (BACCP) a) Please provide boric acid walk down inspection results, an updated list of boric acid leaks identified so far this outage, associated corrective action documentation, and overall status of planned boric acid inspections.
b) Please provide any engineering evaluations completed for boric acid leaks identified since the end of the last refueling outage. Please include a status of corrective actions to repair and/or clean these boric acid leaks. Please specifically which known leaks, if any, have remained in service or will remain in service as active leaks.
B.4 Steam Generator (SG) Inspections a) Copies of the Examination Technique Specification Sheets (ETSS) and associated justification for any revisions.
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7 b) Copy of the guidance to be followed if a loose part or foreign material is identified in the SGs.
c) Please provide a copy of the ET procedures used to perform the SG ISI (specifically calibration and flaw characterization/sizing procedures, etc.). Also include documentation for the specific equipment to be used.
d) Please provide copies of your responses to NRC and industry operating experience communications such as Generic Letters, Information Notices, etc.
(As applicable to SG inspections) *Do not provide these documents separately if already included in other information requested such as the degradation assessment.
e) List of corrective action documents generated by the vendor and/or site with respect to SG inspection activities.
B.5 Codes and Standards a) Ready access to: (i.e. copies provided to the inspector to use for the duration of the inspection at the on-site inspection location, or room number and location where available)
I) Applicable editions of the ASME Code (Sections V, IX and XI) for the inservice inspection program and the repair/replacement program.
ii) EPRI and industry standards referenced in the procedures used to perform the SG tube eddy current examination.
Inspector Contact Information:
Barry Miller Reactor Inspector 404-562-4632 bwm1@nrc.gov Mailing Address:
US NRC Region 2 Attn: Barry Miller 61 Forsyth Street SW, Suite 23T85 Atlanta, GA 30303 Enclosure