Letter Sequence Other |
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MONTHYEARHNP-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
Project stage: Request
HNP-16-095, Relief Request l3R-16, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Third Ten-Year Interval, Non-Proprietary Version of Calculation2016-10-21021 October 2016
Relief Request l3R-16, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Third Ten-Year Interval, Non-Proprietary Version of Calculation
Project stage: Request
ML16300A1802016-10-27027 October 2016
Verbal Authorization of Relief Request I3R-16, for Reactor Vessel Closure Head Penetration Nozzle Repair Technique, Inservice Inspection Program -Third 10-Year Interval
Project stage: Other
ML16335A3442016-12-12012 December 2016
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML16343A2202016-12-27027 December 2016
Relief Request 13R-16 for Reactor Vessel Closure Head Penetration Nozzle Repair Technique, Inservice Ispection Program - Third 10-Year Interval
Project stage: Acceptance Review
2016-10-27
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Category:Memoranda
MONTHYEARML24124A0342024-05-0101 May 2024
Summary of Public Meeting Concerning Annual Assessment of Catawba Nuclear Station Units 1 and 2, McGuire Nuclear Station Units 1 and 2, Oconee Nuclear Station Units 1, 2, and 3, Brunswick Steam Electric Plant Units 1 and 2, Shearon Harris
ML23151A1232023-05-31031 May 2023
Public Meeting Summary - 2022 Annual Assessment Meeting Regarding Shearon Harris Nuclear Plant
ML22130A0302022-05-0909 May 2022
Summary of Public Meeting on 2021 Annual Assessment Meeting Regarding Brunswick Steam Electric Plant, Docket Nos. 50-325 and 50-324; and Shearon Harris Nuclear Power Plant, Docket No. 50-400, Meeting Number 20220350
ML22075A3592022-03-17017 March 2022
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
ML22034A3932022-02-16016 February 2022
Calendar Year 2021 Security Baseline Completion Memo
ML21131A1472021-05-11011 May 2021
Public Meeting Summary 2020 Annual Assessment Meeting Regarding Brunswick Steam Electric Plant, Docket Nos. 50-325 and 50-324; and Shearon Harris Nuclear Power Plant, Docket No. 50-400, Meeting Number 20210385
RA-21-0097, Notification of Permit Revision Request Regarding Copper and Zinc Limits2021-03-15015 March 2021
Notification of Permit Revision Request Regarding Copper and Zinc Limits
ML20136A2222020-05-15015 May 2020
Har - Bru 2019 Aam Meeting Summary
ML19113A0652019-05-14014 May 2019
Summary of Meeting with Duke Energy to Discuss Proposed License Amendment Request for Shearon Harris, Unit 1, Technical Specification Changes Associated with Departure from Nucleate Boiling Ratio Safety Limit
ML19123A3522019-05-0202 May 2019
Public Meeting Summary - Shearon Harris Nuclear Plant, Docket No. 50-400
ML18109A0912018-04-19019 April 2018
Summary of 2017 Annual Assessment Public Meeting Regarding Shearon Harris Nuclear Plant, Docket No. 50-400
ML18074A0202018-03-20020 March 2018
Fpra FAQ 16-0011 Closure Memo
ML17145A3142017-05-25025 May 2017
EOC Meeting Summary
ML16300A1802016-10-27027 October 2016
Verbal Authorization of Relief Request I3R-16, for Reactor Vessel Closure Head Penetration Nozzle Repair Technique, Inservice Inspection Program -Third 10-Year Interval
ML16138A0502016-05-24024 May 2016
Audit Report - Application For Amendment Shearon Harris Nuclear Power Plant, Unit 1 - The Proposed License Amendment Revises The As-Found Lift Setting Tolerance For Main Steam Line Code Safety Valves In Technical Specifications (TAC No. MF7195)
ML16134A1552016-05-12012 May 2016
Public Meeting Summary - 2015 Annual Assessment Public Meeting Regarding Shearon Harris Nuclear Plant
ML16103A2552016-04-14014 April 2016
05/02/2016 Notice of Forthcoming Closed Pre-Submittal Meeting with Duke Energy Progress, Inc., to Discuss Fuel Reload Design Methodology Reports and Proposed LAR Re. H. B. Robinson and Shearon Harris Plants (CAC Nos. MF7443 and MF7444)
ML15149A3222015-05-29029 May 2015
2014 Harris Annual Assessment Meeting Summary
ML15107A4252015-04-17017 April 2015
4/20/2015, Forthcoming Closed Meeting with Duke Energy Progress, Inc. to Discuss Shearon Harris Nuclear Power Plant, Unit 1, Relief Request I3R-15 Revision and Supplement, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspe
ML13330B6392013-11-27027 November 2013
Verbal Authorization of Relief Request 13R-13 for Reactor Vessel Closure Head Penetration Nozzle Repair Inservice Inspection Program - Third 10-Year Interval
ML13295A3062013-10-22022 October 2013
Meeting Notice with Duke Energy Carolinas, LLC Discuss the Planned Modifications Related to the Fukushima Flood Hazard Reevaluations for the Sites Operated by Duke Energy Carolinas, LLC
ML13150A0712013-05-31031 May 2013
Verbal Authorization of Relief Request I3R-11 for Reactor Vessel Closure Head Penetration Nozzel Repair Inservice Inspection Program - Third 10-Year Interval
ML13142A4672013-05-22022 May 2013
Special Inspection Charter to Evaluate Harris Reactor Vessel Head Nozzle 49 Flaw Issue
ML13120A1372013-05-0202 May 2013
Notice of Forthcoming Meeting with Duke Energy, Inc. Regarding a Non-Conservative Technical Specification Loss-of-Offsite Power Voltage Setpoint License Amendment Request for Shearon Harris, Unit 1
ML13106A3372013-04-17017 April 2013
Notice of Forthcoming Meeting with Duke Energy, Inc. Concerning the Relocation of the Emergency Operating Facilities
ML12300A4032012-10-26026 October 2012
11/8/2012 Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-design-Basis External Events
ML12284A4612012-10-12012 October 2012
Forthcoming Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-Design-Basis External Events
ML12261A0992012-09-17017 September 2012
10/2/12 - Notice of Forthcoming Public Conference Call with Duke Energy Carolinas Regarding Shearon Harris Nuclear Plant, Unit 1
ML12249A1702012-09-0606 September 2012
Notice of Forthcoming Conference Call Public Meeting with Duke Energy Regarding the Non Conservative Technical Specifications License Amendment Requests for Shearon Harris Nuclear Plant Unit 1
ML1219805572012-09-0505 September 2012
Close-Out of National Fire Protection Association Standard 805 Frequently Asked Question 12-0062: Updated Final Safety Analysis Report Content
ML12144A4402012-05-24024 May 2012
Verbal Authorization of Relief Request I3R-06 for Reactor Vessel Closure Head Penetration Nozzles Repair Inservice Inspection Program - Third 10-Year Interval
ML1127300822011-09-30030 September 2011
Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate
ML1103804972011-02-0808 February 2011
Notice of Forthcoming Preapplication Meeting with Carolina Power & Light Company and Representatives Regarding Shearon Harris Nuclear Plant, Unit 1
ML1024301722010-10-0505 October 2010
Trip Report on Observing the National Fire Protection Association 805 Readiness Self Assessment Performed at the Shearon Harris Nuclear Plant
ML1015805092010-06-0808 June 2010
the Nuclear Regulatory Commission Staff Spot-Check Review of North Carolina Eastern Municipal Power Agency'S Ownership Interest of Shearon Harris, Unit 1 and Brunswick, Units 1 and 2 on May 21, 2010 - Finding of No Potential Issues in Bank
ML1015901992010-06-0808 June 2010
the Nuclear Regulatory Commission Staff Spot-Check Review of Progress Energy Carolina'S Ownership Interest of H.B. Robinson Steam Electric Plant Unit 2, Brunswick Steam Electric Plant Units 1 and 2 & Shearon Harris Nuclear Power Plant Unit
ML1015900142010-06-0808 June 2010
the Nuclear Regulatory Commission Staff Spot-Check Review of North Carolina Eastern Municipal Power Agency'S Ownership Interest of Shearon Harris, Unit 1 and Brunswick, Units 1 and 2 on May 20, 2010 - Finding of No Potential Issues in Bank
ML1005702002010-02-26026 February 2010
Notice of Closed Meeting with Progress Energy to Observe a Live Test Fire of Mackenzie River Partner'S Remotely Operated Weapon System at the Shearon Harris Nuclear Plant
ML0936406952010-01-0707 January 2010
Notice of Meeting with Carolina Power & Light Company to Discuss Requests for Additional Information Associated with Generic Letter 2004-02
ML0916605042009-06-24024 June 2009
04/21-22/2009 Summary of Category 2 Meeting with Progress Energy Carolinas, Inc., and Duke Energy Carolinas, LLC, to Discuss Topics Involving the License Amendment Requests to Transition Shearon, Unit 1 and Oconee to NFPA 805
ML0909604362009-05-28028 May 2009
Lessons from Regulatory Audits of the Pilot Plants That Are Transitioning to a Fire Protection Licensing Basis Based on the National Fire Protection Association (NFPA) Standard NFPA 805 as Allowed by 10 CFR 5.48 (C)
ML0909905052009-04-29029 April 2009
03/20/09 Summary of Site Audit to Support the Review of a License Amendment Request for Shearon Harris to Transition to the National Fire Protection Association Standard 805 Fire Protection Licensing Basis
ML0909900182009-04-10010 April 2009
04/21-22/2009, Notice of Meeting with Progress Energy Carolinas, Inc., and Duke Energy Carolinas, LLC, to Discuss Topics Involving the License Amendment Requests to Transition the Shearon, Unit 1 and the Oconee, Units 1, 2 and 3
ML0829501872008-09-0909 September 2008
DHS Shearon Harris Consultation Report Cover Letter
ML0814002922008-08-20020 August 2008
Close-out of National Fire Protection Association (NFPA) Standard 805 Frequently Asked Question 07-0032
ML0818302602008-07-0101 July 2008
Meeting Minutes of the ACRS Plant License Renewal Subcommittee Regarding Shearon Harris, May 7, 2008
ML0816901212008-06-17017 June 2008
Forthcoming Closed Meeting with Progress Energy Carolinas, Inc., to Discuss the May 29, 2008, License Amendment Request (LAR) to Transition the Shearon Harris Nuclear Plant, Unit 1 (Harris) to National Fire Protection Association (Nfpa)..
ML0808501922008-03-26026 March 2008
Forthcoming Meeting with Cp&L to Discuss an Open Item Related to the License Renewal Review for Shearon Harris Nuclear Power Plant, Unit 1
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0807203352008-03-0303 March 2008
Comment (7) of Chatham County Board of Commissioners Opposing Generic Environmental Impact Statement (GEIS) for License Renewal of the Shearon Harris Nuclear Power Plant
2024-05-01
[Table view] |
Text
MEMORANDUM TO: FROM:
SUBJECT:
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 27, 2016 Jeanne A. Dion, Acting Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Martha Barillas, Project Plant Licensing Branch 11-2 1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 -VERBAL AUTHORIZATION OF RELIEF REQUEST 13R-16, FOR REACTOR VESSEL CLOSURE HEAD PENETRATION NOZZLE REPAIR TECHNIQUE, INSERVICE INSPECTION PROGRAM -THIRD 10-YEAR INTERVAL (CAC NO. MF8487) By letter dated October 19, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16294A218),
as supplemented by letters dated October 21, 2016 and October 24, 2016 (ADAMS Accession Nos. ML 16295A 159 and ML 16298A 133, respectively),
Duke Energy Progress, LLC (the licensee) submitted Relief Request 13R-16, Reactor Vessel Closure Head Nozzle Repair Technique, lnservice Inspection Program -Third 10-Year Interval for Shearon Harris Nuclear Power Plant, Unit 1. Pursuant to Title 10 of the Code of Federal Regulations (1 O CFR), Section 50.55a, the licensee requested the U.S. Nuclear Regulatory Commission (NRC) approval of an alternative for the repair examination requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) associated with Reactor Vessel Closure Head Penetration Nozzle Numbers 30, 40, and 51. The licensee proposed to use the alternatives in ASME Code,Section XI, Code Case N-638-1, "Similar and Dissimilar Metal Welding Using Ambient temperature Machine GTAW Temper Bead Technicque,Section XI, Division 1, and Code Case N-729-1, "Alternative Examination Requirements for PWR [Pressurized-Water Reactor]
Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration WeldsSection XI, Division 1, to complete the repair procedures and nondestructive evaluation examinations.
J. Dion The NRC staff reviewed the licensee's submittal and determined that the proposed alternative will provide an acceptable level of quality and safety. During a conference call with the licensee on October 27, 2016, the NRC staff granted a verbal authorization on the use of Relief Request 13R-16, in accordance with 10 CFR 50.55a(z)(1
). The script for the verbal authorization is enclosed.
NRC Participants:
Licensee Participants:
J. Dion S. Rose T. Hamilton B. Waldrep M. Barillas M. Riches S. O'Connor F. Dean J. Tsao J. Caves L. Martin D. Alley S. McDaniel Docket No. 50-400
Enclosure:
Verbal Authorization Script VERBAL AUTHORIZATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR RELIEF REQUEST 13R-16 ALTERNATE REPAIR OF REACTOR VESSEL CLOSURE HEAD PENETRATION NOZZLES DUKE ENERGY PROGRESS, LLC SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 1.0 Technical Evaluation Read by David Alley, Chief of the Component Performance, Non-Destructive Examination, and Testing Branch, Office of Nuclear Reactor Regulation
- By letter dated October 19, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16294A218),
as supplemented by letters dated October 21, 2016 (ADAMS Accession No. ML 16295A 159), and October 24, 2016 (ADAMS Accession No. ML 16298A133),
Duke Energy Progress, LLC (the licensee) submitted Relief Request (RR) 13R-16 for the repair of degraded Reactor Vessel Closure Head Penetration Nozzle Numbers 30, 40, and 51 at the Shearon Harris Nuclear Power Plant, Unit 1. In Relief Request 13R-16, the licensee proposed to use the inside diameter temper bead welding method to repair reactor vessel closure head nozzles in accordance with American Society of Mechanical Engineers (ASME) Code Cases N-638-1 and N-729-1 in lieu of requirements of the ASME, Sections Ill and XI, and original Construction Code. The licensee made this request in accordance with the requirements of 1 O CFR 50.55a(z)(1) on the basis that the proposed alternative repair will provide an acceptable level of quality and safety. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the proposed repair method and examinations; 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; the evaluation of loose parts from the degraded J-groove weld falling into the reactor vessel; the corrosion evaluation of the bore of the reactor vessel head penetration exposing to primary coolant; available reinforcement area calculations; and the flaw evaluation of primary water stress corrosion cracking in the remnant nozzle, without considering the abrasive water jet machining remediation.
The NRC staff noted that the licensee derived a design life of 2.2 effective full power years for the repaired reactor vessel closure head nozzles without the abrasive water jet machining remediation.
The licensee is required to examine all nozzles, including the subject nozzles, during every subsequent refueling outage, which is every 18 months, in accordance with ASME Code Case N-729-1 as conditioned in Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a(g)(6)(ii)(D).
Enclosure The NRC staff finds that the licensee's examination interval of the repaired nozzles is shorter than the design life, therefore, is acceptable to adequately monitor the condition of the repaired nozzles.
The NRC staff further finds that the licensee's flaw evaluations provide assurance that should flaws occur, the structural integrity of the repaired nozzles and reactor vessel head will be maintained.
The NRC staff determines that the proposed repair will restore the primary system pressure boundary and provide reasonable assurance that the structural integrity of the repaired reactor vessel closure head and repaired Nozzle Numbers 30, 40, and 51 will be maintained for a period of time that exceeds the inspection interval mandated by ASME Code Case N-729-1 as conditioned in 10 CFR 50.55a(g)(6)(ii)(D).
2.0 NRC Staff Conclusion
Read by Jeanne Dion, Acting Branch Chief, Plant Licensing Branch 11-2, Office of Nuclear Reactor Regulation As Acting Chief of Plant Licensing Branch 11-2, I concur with the Component Performance, Non-Destructive Examination, and Testing Branch's determinations.
The NRC staff concludes that Relief Request 13R-16 will provide an acceptable level of quality and safety for the reactor vessel head and repaired Nozzle Numbers 30, 40, and 51. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) and is in compliance with the requirements of the ASME Code,Section XI, ASME Code Case N-638-1 as conditioned in Regulatory Guide 1.147, and ASME Code Case N-729-1, as conditioned by 1 O CFR 50.55a(g)(6)(ii)(D).
Therefore, as of October 27, 2016, the NRC authorizes the use of Relief Request 13R-16 for Nozzle Numbers 30, 40, and 51 at Shearon Harris Nuclear Power Plant, Unit 1, for the remaining period of the third 10-year inservice inspection
- interval, which ends on May 1, 2017. All other requirements of ASME Code,Section XI, and 1 O CFR 50.55a(g)(6)(ii)(D) for which relief was not specifically requested and authorized by the NRC staJf remain applicable, including the third party review by the Authorized Nuclear lnservice Inspector.
This verbal authorization does not preclude the NRC staff from asking additional questions and clarifications regarding Relief Request 13R-16 while preparing the subsequent written safety evaluation.
J. Dion The NRC staff reviewed the licensee's submittal and determined that the proposed alternative will provide an acceptable level of quality and safety. During a conference call with the licensee on October 27, 2016, the NRC staff granted a verbal authorization on the use of Relief Request 13R-16, in accordance with 10 CFR 50.55a(z)(1).
The script for the verbal authorization is enclosed.
NRC Participants:
J. Dion S. Rose M. Barillas M. Riches J. Tsao D. Alley Docket No. 50-400
Enclosure:
Verbal Authorization Script DISTRIBUTION:
PUBLIC LPL2-2 R/F RidsNrrLABClayton Resource RidsNrrDorllpl2-2 Resource RidsACRS_MailCenter Resource RidsRgn2MailCenter Resource ADAMS Accession No.: ML 16300A180 Licensee Participants:
T. Hamilton B. Waldrep S. O'Connor F. Dean J. Caves L. Martin S. McDaniel RidsNrrPMShearonHarris Resource RidsNrrLABClayton Resource RidsNrrDeEpnb Resource JTsao, NRR OFFICE DORL/LPL2-2/PM DORL/LPL2-2/LA DE/EPNB DORL/LPL2-2/BC DORL/LPL2-2/PM NAME MBarillas BClayton DAiiey JD ion MBarillas (PBlechman for) DATE 10/27/16 10/27/16 10/27/16 10/27/16 10/27/16 OFFICIAL RECORD COPY
