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MONTHYEARHNP-15-010, Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique Inservice Inspection Program - Third Ten-Year Interval2015-04-0202 April 2015 Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique Inservice Inspection Program - Third Ten-Year Interval Project stage: Request HNP-15-034, Relief Request I3R-15 Revision and Supplement, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program - Third Ten-Year Interval2015-04-15015 April 2015 Relief Request I3R-15 Revision and Supplement, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program - Third Ten-Year Interval Project stage: Supplement HNP-15-037, Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique, Response to Request for Additional Information2015-04-24024 April 2015 Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique, Response to Request for Additional Information Project stage: Response to RAI ML15201A1872015-08-24024 August 2015 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML15197A5052015-08-24024 August 2015 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML15203A7022015-09-18018 September 2015 Relief Request 13R-15 for Reactor Vessel Closure Head Penetration Nozzle Repair Technique, Inservice Inspection Program - Third 10 - Year Interval Project stage: Acceptance Review 2015-04-24
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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARRA-23-0011, End of Cycle 24 (H1R24) Inservice Inspection Program Owner'S Activity Report2023-01-26026 January 2023 End of Cycle 24 (H1R24) Inservice Inspection Program Owner'S Activity Report RA-22-0172, Duke Energy Progress, LLC - Supplement to Relief Request HNP-IST-004-RR1 for Inservice Testing Program Plan - Fourth Ten-Year Interval2022-06-10010 June 2022 Duke Energy Progress, LLC - Supplement to Relief Request HNP-IST-004-RR1 for Inservice Testing Program Plan - Fourth Ten-Year Interval RA-21-0200, End of Cycle 23 (H1R23) Inservice Inspection Program Owner'S Activity Report2021-08-11011 August 2021 End of Cycle 23 (H1R23) Inservice Inspection Program Owner'S Activity Report RA-21-0067, Response to Request for Additional Information - Relief Request, Service Water Pinhole Leak in a Socket Weld, Inservice Inspection Program, Fourth Ten-Year Interval2021-02-25025 February 2021 Response to Request for Additional Information - Relief Request, Service Water Pinhole Leak in a Socket Weld, Inservice Inspection Program, Fourth Ten-Year Interval RA-20-0082, Submittal of 180-Day Steam Generator Tube Inspection Report2020-04-0808 April 2020 Submittal of 180-Day Steam Generator Tube Inspection Report RA-20-0025, Cycle 22 Owner'S Activity Report2020-02-12012 February 2020 Cycle 22 Owner'S Activity Report RA-19-0206, Proposed Alternative for the Third 10-Year Inservice Inspection Program2019-04-30030 April 2019 Proposed Alternative for the Third 10-Year Inservice Inspection Program RA-18-0066, Cycle 21 Owner'S Activity Report2018-07-31031 July 2018 Cycle 21 Owner'S Activity Report HNP-17-025, Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan2017-10-23023 October 2017 Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan HNP-16-092, Relief Request I3R-16, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Third Ten-Year Interval2016-10-19019 October 2016 Relief Request I3R-16, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Third Ten-Year Interval HNP-15-064, Submits 90-day Inservice Inspection Summary Report2015-08-0505 August 2015 Submits 90-day Inservice Inspection Summary Report HNP-15-037, Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique, Response to Request for Additional Information2015-04-24024 April 2015 Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique, Response to Request for Additional Information HNP-15-034, Relief Request I3R-15 Revision and Supplement, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program - Third Ten-Year Interval2015-04-15015 April 2015 Relief Request I3R-15 Revision and Supplement, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program - Third Ten-Year Interval HNP-15-010, Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique Inservice Inspection Program - Third Ten-Year Interval2015-04-0202 April 2015 Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique Inservice Inspection Program - Third Ten-Year Interval HNP-14-099, Relief Request I3R-14, Deferral of Reactor Vessel Inspections Inservice Inspection Program - Third Ten-Year Interval Response to Request for Additional Information2014-09-0808 September 2014 Relief Request I3R-14, Deferral of Reactor Vessel Inspections Inservice Inspection Program - Third Ten-Year Interval Response to Request for Additional Information HNP-13-119, Relief Request I3R-13, Reactor Vessel Closure Head Nozzle 37, Inservice Inspection Program - Third Ten-Year Interval2013-11-22022 November 2013 Relief Request I3R-13, Reactor Vessel Closure Head Nozzle 37, Inservice Inspection Program - Third Ten-Year Interval HNP-13-071, Day Inservice Inspection Summary Report Corrections2013-06-26026 June 2013 Day Inservice Inspection Summary Report Corrections HNP-13-057, Relief Request I3R-11 Reactor Vessel Closure Head Nozzles Lnservice Inspection Program - Third Interval2013-05-22022 May 2013 Relief Request I3R-11 Reactor Vessel Closure Head Nozzles Lnservice Inspection Program - Third Interval HNP-12-091, Day Inservice Inspection Summary Report2012-09-0505 September 2012 Day Inservice Inspection Summary Report HNP-12-018, Day Inservice Inspection (ISI) Summary Report Corrections2012-04-11011 April 2012 Day Inservice Inspection (ISI) Summary Report Corrections HNP-11-045, 180-Day Steam Generator Tube Inspection Report2011-05-0505 May 2011 180-Day Steam Generator Tube Inspection Report HNP-11-017, 90-Day Inservice Inspection (ISI) Summary Report2011-02-10010 February 2011 90-Day Inservice Inspection (ISI) Summary Report HNP-09-095, Response to Request for Additional Information Regarding Relief Requests 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, & 2R2-011 for the Second 10-Year Inservice Inspection Program2009-09-24024 September 2009 Response to Request for Additional Information Regarding Relief Requests 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, & 2R2-011 for the Second 10-Year Inservice Inspection Program ML0923103532009-08-27027 August 2009 Correction to 10-Year Inservice Inspection Interval Enumerated in Relief Request 13R-02 Issued on April 30, 2009 HNP-09-076, 90-Day Inservice Inspection (ISI) Summary Report2009-08-0606 August 2009 90-Day Inservice Inspection (ISI) Summary Report HNP-08-067, Supplement to Third Interval Inservice Inspection Relief Request 13R-02 Submittal2008-06-19019 June 2008 Supplement to Third Interval Inservice Inspection Relief Request 13R-02 Submittal ML0804600932008-02-0808 February 2008 RFO13 90 Day Inservice Inspection (ISI) Summary Report ML0813304642008-01-30030 January 2008 Rev. 0 to PEN02.G03, Shearon Harris Nuclear Plant ISI Program Plan, Third 10-Year Inspection Interval. Cover to Page 8-2 ML0813304652008-01-30030 January 2008 Rev. 0 to PEN02.G03, Shearon Harris Nuclear Plant ISI Program Plan, Third 10-Year Inspection Interval. Attachment 1: Welds & Supports Schedule ML0813304662008-01-30030 January 2008 Rev. 0 to PEN02.G03, Shearon Harris Nuclear Plant ISI Program Plan, Third 10-Year Inspection Interval. Page 288 to End HNP-07-179, 90-Day Inservice Inspection (ISI) Summary Report2008-01-18018 January 2008 90-Day Inservice Inspection (ISI) Summary Report HNP-07-145, Inservice Inspection Relief Request 1, Summary of Ultrasonic Examinations of Preemptive Weld Overlays for Pressurizer Nozzle Locations Containing Alloy 600 Materials2007-10-22022 October 2007 Inservice Inspection Relief Request 1, Summary of Ultrasonic Examinations of Preemptive Weld Overlays for Pressurizer Nozzle Locations Containing Alloy 600 Materials HNP-07-143, Inservice Inspection Relief Request 1 Re Weld Overlay Repair Stress Analysis Summary2007-10-19019 October 2007 Inservice Inspection Relief Request 1 Re Weld Overlay Repair Stress Analysis Summary HNP-07-042, Revision of the Relief Request from ASME OM Code Inservice Testing Requirements for the Third Ten-Year Interval Plan2007-03-22022 March 2007 Revision of the Relief Request from ASME OM Code Inservice Testing Requirements for the Third Ten-Year Interval Plan HNP-06-141, Relief Request from ASME OM Code Inservice Testing Requirements for the Third Ten-Year Interval Plan2006-12-18018 December 2006 Relief Request from ASME OM Code Inservice Testing Requirements for the Third Ten-Year Interval Plan HNP-06-091, Relief Requests from ASME Code Inservice Testing Requirements to Allow Online Disassembly of Certain Check Valves2006-09-0707 September 2006 Relief Requests from ASME Code Inservice Testing Requirements to Allow Online Disassembly of Certain Check Valves HNP-06-081, Submittal of Inservice Inspection Summary Report for Harris Nuclear Plant2006-08-10010 August 2006 Submittal of Inservice Inspection Summary Report for Harris Nuclear Plant HNP-05-088, One-Year Special Report - Steam Generator Tube Inservice Inspection Results2005-08-0101 August 2005 One-Year Special Report - Steam Generator Tube Inservice Inspection Results HNP-05-018, Inservice Inspection Summary Report2005-02-15015 February 2005 Inservice Inspection Summary Report HNP-04-076, One Year Special Report, Steam Generator Tube Inspection Results2004-05-0707 May 2004 One Year Special Report, Steam Generator Tube Inspection Results HNP-03-081, Inservice Inspection Summary Report2003-08-13013 August 2003 Inservice Inspection Summary Report HNP-02-051, Part 2 of 2, Shearon Harris Nuclear Power Plant, Inservice Inspection Summary Report, Class 2 Through End2002-04-0101 April 2002 Part 2 of 2, Shearon Harris Nuclear Power Plant, Inservice Inspection Summary Report, Class 2 Through End HNP-01-170, Inservice Inspection Summary Report for Harris Nuclear Plant2002-01-24024 January 2002 Inservice Inspection Summary Report for Harris Nuclear Plant 2023-01-26
[Table view] Category:Letter
MONTHYEARIR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 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 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications 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 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) ML23234A2542023-08-22022 August 2023 RQ Inspection Notification Letter IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter IR 05000400/20243012023-05-15015 May 2023 Notification of Licensed Operator Initial Examination 05000400/2024301 IR 05000400/20230012023-05-10010 May 2023 Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 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 ML23118A1392023-04-28028 April 2023 Submittal of Updated Final Safety Analysis Report (Amendment 65), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 ML23033A5272023-02-0808 February 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment No. 196 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) 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 ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000400/20220032022-11-10010 November 2022 Integrated Inspection Report 05000400/2022003 IR 05000400/20223012022-11-0202 November 2022 NRC Operator License Examination Report 05000400/2022301 ML22271A6202022-09-29029 September 2022 Notification of Shearon Harris Nuclear Power Plant Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2023010 ML22258A1262022-09-14014 September 2022 NRC Operator Licensing Examination Approval 05000400/2022301 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22227A0682022-09-0202 September 2022 Alternative to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance for Certain Target Rock Solenoid Valves IR 05000400/20220052022-08-24024 August 2022 Updated Inspection Plan for Shearon Harris Nuclear Power Plant (Report 05000400/2022005) IR 05000400/20224032022-08-23023 August 2022 Security Baseline Inspection Report 05000400/2022403 ML22126A0082022-08-0909 August 2022 Issuance of Amendment No. 194 Revise Technical Specifications Related to Reactor Protection System Instrumentation P7 IR 05000400/20220022022-08-0505 August 2022 Integrated Inspection Report 05000400/2022002 ML22161B0332022-07-28028 July 2022 Issuance of Amendment No. 193 Regarding Revision of Surveillance Requirements to Remove Shutdown Limitation IR 05000400/20220112022-07-20020 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000400 2022011 IR 05000400/20224022022-06-30030 June 2022 Material Control and Accounting Program Inspection Report 05000400/2022402 (OUO Removed) IR 05000400/20220102022-06-13013 June 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000400/2022010 ML22138A4012022-05-26026 May 2022 Project Manager Reassignment ML22101A2822022-05-0606 May 2022 Regulatory Audit Summary Related to the Review of License Amendment Regarding Revising the Flood Hazard Protection Scheme IR 05000400/20220012022-05-0404 May 2022 Integrated Inspection Report 05000400/2022001 IR 05000400/20224012022-03-24024 March 2022 Security Baseline Inspection Report 05000400/2022401 ML22020A0072022-03-10010 March 2022 Issuance of Amendment No. 192 Regarding Removal of Extraneous Content and Requirements from the Renewed Facility Operating License and Technical Specifications ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 IR 05000400/20210062022-03-0202 March 2022 Annual Assessment Letter for Shearon Harris Nuclear Power Plant (Report No. 05000400/2021006) ML21351A4722022-02-10010 February 2022 Issuance of Amendment No. 190 Regarding Revision to Containment Spray Nozzle Test Frequency IR 05000400/20210042022-02-0404 February 2022 Integrated Inspection Report 05000400/2021004 ML22034A5352022-02-0202 February 2022 Notification of Licensed Operator Initial Examination 05000400/2022301 2024-01-30
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Benjamin C. Waldrep Vice President Harris Nuclear Plant 5413 Shearon Harris Rd New Hill NC 27562-9300 919-362-2502 10 CFR 50.55a April 24, 2015 Serial: HNP-15-037 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
-0001 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50
-400/Renewed License No. NPF
-63
Subject:
Relief Request I3R
-15, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program -Third Ten-Year Interval, Response to Request for Additional Information Ladies and Gentlemen:
Duke Energy Progress, Inc.
(Duke Energy), request ed NRC approval of relief request I3R-15 for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP) inservice inspection program in a letter dated April 2, 2015 (ADAMS Accession No. ML15092A236). At the time of the request, there were no known flaws that required repair in the reactor vessel closure head nozzles. HNP subsequently identified three flaws that require repair as a result of examinations of the reactor head performed in the current refueling outage. In response, Duke Energy revised and supplemented relief request I3R
-15 in a letter dated April 15, 2015 (ADAMS Accession No. ML15105A521
), which superseded the original request. The revised relief request requested an expedite d approval by April 28, 2015. The NRC transmitted a draft request for information to HNP on April 20, 2015, which was discussed in a teleconference that afternoon. The formal request for information was received on April 21, 2015. The Duke Energy response to that request is enclosed.
As a result of a change to the outage schedule, the need date for approval of this request is extended to May 1, 2015, to support startup from the current refueling outage.
This document contains no new regulatory commitments.
U.S.
Commission Page 2 Please refer any questions regarding this to Dave HNP Affairs Manager, at (919) 362-3137.
Response to Request for Additional Information cc: Mr. J. D. Austin, NRC Sr. Resident HNP Ms. M.
NRC Project Manager, HNP Mr. M. McCree, NRC Regional Administrator, Region U.S. Nuclear Regulatory Commission RR I3R-15 RAI Response HNP-15-037 Enclosure Page 1 of 3 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50
-400/Renewed License No. NPF
-63 Relief Request I3R
-15 , Reactor Vessel Closure Head Nozzle Repair Technique Inservice Inspection Program
- Third Ten-Year Interval Response to Request for Additional Information Duke Energy Progress, Inc.
(Duke Energy), request ed NRC approval of relief request I3R-15 for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP) inservice inspection program in a letter dated April 2, 2015 (ADAMS Accession No. ML15092A236). At the time of the request, there were no known flaws that required repair in the reactor vessel closure head nozzles. HNP subsequently identified three flaws that require repair as a result of examinations of the reactor head performed in the current refueling outage. In response, Duke Energy revised and supplemented relief request I3R
-15 in a letter dated April 15, 2015 (ADAMS Accession No. ML15105A521), which superseded the original request.
The NRC staff determined that additional information was needed to complete its review. The Duke Energy response to that request follows.
Request 1 Section 4 of the relief request (page 5 of 27) states that abrasive water jet machining (AWJM) remediation on the portion of the remaining nozzle will be optional as part of the repair procedure.
Discuss the technical basis why the AWJM remediation is an optional step in the proposed relief request whereas it is a required step in previous repairs. Response 1 AWJM remediation removes a thin layer of material and also imparts compressive residual stresses to the remediated surfaces. If the inside diameter temper bead (IDTB) "half nozzle" weld repair is not remediated with AWJM, the life expectancy for the modification, as stated in Section 6 of the Relief Request, relative to primary water stress corrosion cracking (PWSCC) is estimated at 2.2 effective full power years (EFPY) for a postulated flaw in the repaired Alloy 600 nozzle to reach the ASME limit of 75
-percent through
-wall. The estimate is based on a quantitative approach to PWSCC life expectancy that considers immediate PWSCC initiation, a constant rapid crack growth rate independent of stress intensity, and ASME B&PV Code Section XI acceptance criteria.
The minimum design life of a non
-AWJM IDTB modification exceeds two calendar years.
HNP refueling outages are scheduled approximately every 18 months. If flaws attributable to PWSCC have been identified, the re
-inspection interval is every refueling outage as required by 10 CFR 50.55a(g)(6)(ii)(D)(5). Any potential flaw in the inspected region should be detected prior to reaching the ASME Code limit of 75
-percent through
-wall and HNP would take corrective actions. Assurance of safety is provided without the use of AWJM, which is therefore considered optional in the request.
U.S. Nuclear Regulatory Commission RR I3R-15 RAI Response HNP-15-037 Enclosure Page 2 of 3 Request 2 Section 6 of the relief request (page 13 of 27) states that the design life of the repair without the AWJM remediation is 2.2 effective full power years (EFPY). (a) Discuss the approximate calendar days associated with 2.2 EFPY. (b) Discuss the month and year of the scheduled refueling outages between now and the end of the third inservice inspection interval which ends on May 1, 2017. (c) Discuss the approximate calendar days for the reactor vessel head inspections between the refueling outages.
Response 2 (a) 2.2 effective full power years is 803 effective full power days. Conservatively discounting the impact of operation at less than full power, including time for refueling outages, we can consider the 2.2 EFPY to correspond to 803 calendar days.
(b) There is only one refueling outage scheduled between now and May 1, 2017. Refueling outage 20 is currently scheduled to start on or about October 8, 2016. Refueling outage 21 is currently scheduled to start on or about April 14, 2018.
(c) There are 53 3 calendar days from April 2 4, 2015, to October 8, 2016.
There are 5 5 3 calendar days from October 8, 2016, to April 14, 2018.
Request 3 Section 6 of the relief request (page 13 of 27) states that the Harris Nuclear Plant (HNP) will examine all repaired RVCH penetration nozzles every refueling outage in accordance with ASME Code Case N
-729-1 as conditioned by 10 CFR 50.55a(g)(6)(ii)(D). (a) 10 CFR 50.55a(g)(6)(ii)(D)(5) requires that all reactor vessel head penetration nozzles be examined once primary water stress corrosion cracking is found in a nozzle.
Confirm that all reactor vessel head penetration nozzles at Unit 1 will be examined in all future refueling outages. (b) Discuss the examination method for the non
-repaired nozzles in the future inservice inspections. Response 3 (a) All RVCH penetration nozzles at Unit 1 will be examined in all future refueling outages until the head is replaced.
(b) N on-repaired RVCH nozzles will be examined in accordance with Code Case N
-729-1 and 10 CFR 50.55a(g)(6)(i i)(D), using a qualified ultrasonic examination procedure with demonstrated leak path assessment capability.
U.S. Nuclear Regulatory Commission RR I3R-15 RAI Response HNP-15-037 Enclosure Page 3 of 3 Request 4 The licensee stated in the April 15, 2015, cover letter that "...Calculations supporting this relief request were previously docketed supporting relief request I3R
-13 in Duke Energy letter dated November 25, 2013 (ADAMS Accession No. ML13330A996)..." Discuss whether all calculations in relief request I3R
-13 bound all reactor vessel head penetration nozzles as proposed in relief request I3R
-15 dated April 15, 2015.
The affected calculations include the evaluation of a postulated flaw in the J
-groove weld that propagates into the reactor vessel head, the evaluation of a postulated flaw at the triple point, and the evaluation of the potential for the J
-groove weld fragments falling into the reactor vessel and becoming loose parts.
The discussion should include (a) applied loading conditions, (b) existing and future flaw sizes and configurations, (c) nozzles in all reactor vessel head locations, considering the impact of the uphill and downhill side, and (d) J
-groove weld configurations, considering the impact of the uphill and downhill si de. The licensee needs to demonstrate that the worst
-case in terms of nozzles and flaws were used in the affected calculations. Response 4 The calculations in relief request I3R
-13 bound all reactor vessel head penetration nozzles as proposed in relief request I3R
-15 dated April 15, 2015.
- 1. J-groove Weld Flaw Evaluation For the J-groove weld flaw evaluation, the outermost penetration was explicitly modeled. At those locations, the applied loading conditions are either the same as or worse than all other locations in the RVCH.
The initial flaw size for the J
-groove weld is conservatively assumed to include all of the weld and buttering. This is highly conservative since the buttering sees post weld heat treatment, which would tend to reduce any welding residual stress in it, making it less susceptible to PWSCC. While the analysis considers crack growth on both uphill and downhill sides, the weld on the downhill side of the outermost nozzle has the largest area. Therefore, the largest possible initial flaw size on the downhill side is considered.
- 2. Triple Point Anomaly For the triple point anomaly evaluation, the outermost penetration was explicitly modeled. At those locations, the applied loading conditions are either the same as or worse than all other locations in the RVCH.
The initial flaw size for the triple point anomaly analysis is 0.100 inches, which is the same as or larger than any other relief request submission for a half nozzle IDTB repair configuration. Crack growth analysis determines the future flaw size and concludes that it is acceptable for the stated life. The outermost hillside nozzle is explicitly modeled, meaning that both extremes of interaction between the IDTB weld and the original J
-groove weld are considered (i.e., these welds are very close to each other on the uphill side, and are relatively far away from each other on the downhill side).
- 3. J-groove weld fragments becoming loose parts The evaluation for potential fragments of J
-groove weld falling into the reactor vessel is generic with respect to location. It concludes that there are no known service conditions that could drive radial cracks and transverse cracks to intersect to produce a loose part.