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
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ML22075A3592022-03-17017 March 2022
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
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Calendar Year 2021 Security Baseline Completion Memo
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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
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Har - Bru 2019 Aam Meeting Summary
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Summary of 2017 Annual Assessment Public Meeting Regarding Shearon Harris Nuclear Plant, Docket No. 50-400
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Fpra FAQ 16-0011 Closure Memo
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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
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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)
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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
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Verbal Authorization of Relief Request I3R-11 for Reactor Vessel Closure Head Penetration Nozzel Repair Inservice Inspection Program - Third 10-Year Interval
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Special Inspection Charter to Evaluate Harris Reactor Vessel Head Nozzle 49 Flaw Issue
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Forthcoming Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-Design-Basis External Events
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2023-05-31
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 27, 2016 MEMORANDUM TO: Jeanne A. Dion, Acting Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Martha Barillas, Project Manager'--j/~-
1 Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
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. ML16294A218), as supplemented by letters dated October 21, 2016 and October 24, 2016 (ADAMS Accession Nos. ML16295A159 and ML16298A133, 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. ML16294A218), as supplemented by letters dated October 21, 2016 (ADAMS Accession No. ML16295A159), and October 24, 2016 (ADAMS Accession No. ML16298A133), 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 10 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 10 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 10 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.
ML16300A180 OFFICE DORL/LPL2-2/PM DORL/LPL2-2/LA DE/EPNB DORL/LPL2-2/BC DORL/LPL2-2/PM NAME BClayton DAiiey MBarillas JD ion MBarillas (PBlechman for)
DATE 10/27/16 10/27/16 10/27/16 10/27/16 10/27/16
