Letter Sequence Meeting |
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EPID:L-2018-LLR-0050, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability (Approved, Closed) |
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Category:Meeting Summary
MONTHYEARML22309A0062022-12-12012 December 2022 Public Non-Sensitive Meeting Summary on Clarification Call with Holtec Regarding Request for Additional Information for Indian Point Unit 2 Master Decommissioning Trust Agreement as Per Indian Point Nuclear Generating Facility Unit 1 and 2 ML21342A1402021-12-0909 December 2021 Summary of Public Meeting in Tarrytown, Ny, to Discuss Indian Point Units 1, 2, and 3 (IPEC) Post-shutdown Decommissioning Activities Report ML21055A9122021-02-24024 February 2021 (E-mail Dated 2/24/2021) Summary of Feb 8, 2021, Pre-submittal Meeting for Relief Request No. IP3-ISI-RR-16, Code Case N-513-4 Periodic Inspection Frequency Extension ML20321A0002020-11-17017 November 2020 Summary of 9/30/20 Pre-Submittal Meeting with Entergy to Discuss Proposed One-Time Exemption Request - Biennial Emergency Preparedness Onsite Evaluated Exercise Requirements ML20289A7322020-10-15015 October 2020 2020 Annual Assessment Meeting for Indian Point - Meeting Summary ML20083F5962020-03-23023 March 2020 Summary of Teleconference with the National Marine Fisheries Service for Indian Point Biological Opinion ML20059P1292020-03-0303 March 2020 Summary of Partially Closed Pre-submittal Public Meeting with Entergy Nuclear Operations, Inc. to Discuss the Proposed License Amendment Request to Replace the Indian Point Unit No. 3 Crane with a New Holtec High-Lift Crane (EPID L:2019-LRM ML19330F5182019-11-29029 November 2019 Summary of Public Meeting Between the NRC and Entergy Regarding Pre-Submittal of a License Transfer Application to Holtec International for Indian Point Energy Center ML19319A0242019-10-0202 October 2019 NEIMA Meeting - Courtney Williams Comments ML19319A0282019-10-0202 October 2019 NEIMA Meeting - Marilyn Elie Comments ML19319A0272019-10-0202 October 2019 NEIMA Meeting - Linda Puglisi Comments ML19319A0252019-10-0202 October 2019 NEIMA Meeting - Jenean Eichenholtz Comments ML19198A2392019-07-17017 July 2019 Annual Assessment Meeting for Indian Point Energy Center - Meeting Summary ML18200A2722018-07-19019 July 2018 Summary of Annual Assessment Meeting for Indian Point Energy Center ML18131A0572018-05-11011 May 2018 Summary of 04/12/2018 Meeting with the State of New York Regarding the Indian Point Generating Unit No. 2 Reactor Pressure Vessel Head Penetration Alternative Weld Repair ML18117A3162018-04-30030 April 2018 Summary of 04/03/2018 Meeting with Entergy on Planned Submittal of Propose Alternative for Reactor Pressure Vessel Head Nozzle Weld Repair ML18107A4972018-04-27027 April 2018 April 10, 2017, Summary of Public Meeting with Entergy Nuclear Operations, Inc. 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- i(i' April 30, 2018 LICENSEE: Entergy Nuclear Operations, Inc.
FACILITY: Indian Point Nuclear Generating Unit No. 2
SUBJECT:
SUMMARY
OF APRIL 3, 2018, MEETING WITH ENTERGY NUCLEAR OPERATIONS, INC. ON PLANNED SUBMITTAL OF PROPOSED ALTERNATIVE FOR REACTOR PRESSURE VESSEL HEAD NOZZLE WELD REPAIR (EPID L-2018-LLR-0050)
On April 3, 2018, from 3:00 p.m. -4:00 p.m. EDT, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Entergy Nuclear Operations, Inc. (Entergy, the licensee), via telephone conference. The purpose of the meeting was to discuss the licensee's proposed relief request submittal seeking an alternative weld repair to address a flaw identified in the Indian Point Nuclear Generating Unit No. 2 (IP2),
reactor pressure vessel head penetration. The meeting notice and agenda, dated April 3, 2018, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML18093A093. The licensee's draft relief request submittal was provided to the NRC staff via e-mail prior to the teleconference and is available in ADAMS at Accession No. ML18108A183. A list of attendees is provided in the Enclosure.
The meeting began with an introduction, an overview of meeting logistics, and an introduction of the meeting participants. Entergy then presented an overview of its planned relief request submittal which included the reason for its request, a description of the relief request and basis for use of the alternative weld repair, and its current schedule.
Reason for the Proposed Relief Request The licensee stated that on March 31, 2018, during the current Indian Point Unit 2 refueling outage, with the reactor defueled and the reactor pressure vessel head (RPVH) removed, while performing a scheduled visual examination (VT-2) of the RPVH required by Code Case N-729-4, a white substance was observed on the annulus region of RPVH Penetration No. 3. The visual examinations of the RPVH did not identify any other relevant indications or base material wastage. The licensee performed liquid penetrant and eddy current testing on the J-groove weld of RPVH Penetration No. 3 and determined the indication to be axial; and based on its location and characteristics, the indication was likely the through-weld leakage source.
Therefore, as an alternative to the defect removal and weld repair provisions of the applicable American Society of Mechanical Engineers (ASME) Code, the licensee proposed to repair the J-groove weld before IP2 is returned to service using the embedded flaw repair process in described in the Westinghouse Topical Report, WCAP-15987-P-A, "Technical Basis for the Embedded Flaw Process for Repair of Reactor Vessel Head Penetrations." Consistent with Title 10 to the Code of Federal Regulations (10 CFR) Section 50.55a(z), the proposed alternative must be submitted and authorized by the NRC prior to implementation.
Description of the Proposed Alternative Weld Repair During its presentation, the licensee indicated that the proposed embedded flaw repair process provides an acceptable level of quality and safety. The licensee also stated that all repair requirements, consistent with the Westinghouse topical report will be met and that all nondestructive examinations of the completed seal weld repair on the J-groove weld will be performed in accordance with the 10 CFR 50.55a applicable codes and standards.
The licensee also cited several precedents during the call which they indicated would be referenced in the formal submittal.
The NRC staff requested the following from the licensee:
- Additional details of the as-found indication to illustrate size, location, characteristics, etc., by providing a sketch or diagram
- Additional assessment information on fracture mechanics/fatigue growth and acceptability of using the embedded flaw repair process for the IP2 as-found indication
- Clarification on the basis of the alternative (e.g., an alternative that provides acceptable level of quality and safety or impracticality)
Action Items/Next Steps:
During the teleconference, the licensee indicated that it would be submitting its formal written request as early as April 4, 2018, as well as supplemental evaluation information prior to entering Mode 5 of its restart. The licensee requested NRC approval by the projected entrance to Mode 5 which they approximated as April 12, 2018.
No regulatory decisions were made during the public teleconference regarding the acceptability of Entergy's proposed submittal.
Public Comments and Questions Following the business portion of the meeting, members of the public, local officials, State officials, and members of the media were offered the opportunity to communicate with the NRC regarding the information presented by Entergy during the teleconference. The NRC staff responded to several questions during the question and answer (Q&A) period; topics included clarification of technical terms regarding plant operation and ASME Code repairs, previous operating experience, generic versus plant specific repair methods, and the timing to approve the proposed relief request. Aside from general and administrative follow-up requests from the public (e.g., ADAMS reference nos., copies of the meeting handouts, minutes, etc.), there were no formal follow-up action items as a result of the Q&A period.
To date, no public meeting feedback forms have been submitted through the NRG public meeting feedback system.
Please direct any inquiries to me at (301) 415-1030, or Richard.Guzman@nrc.gov.
Richard V. Guzman, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-247
Enclosure:
List of Attendees cc: Listserv
LIST OF ATTENDEES APRIL 3, 2018, MEETING WITH ENTERGY NUCLEAR OPERATIONS, INC.,
REGARDING ITS PLANNED RELIEF REQUEST SUBMITTAL CONCERNING REACTOR PRESSURE VESSEL HEAD PENETRATION WELD REPAIR DOCKET NO. 50-247 ATIENDEE ORGANIZATION David Alley U.S. Nuclear Regulatory Commission (NRC)
Jay Collins NRC John Tsao NRC Seung Min NRC Richard Guzman NRC James Danna NRC Tara Inverso NRC Jenny Weil NRC Lynnea Wilkins NRC Lawrence Burkhart NRC Brian Haagensen NRC Andrew Siwy NRC Ganesh Cheruvenki NRC Daniel Schroeder NRC Thomas Setzer NRC Mark Henrion NRC Niklas Floyd NRC Stephen Pindale NRC Michael Modes NRC Andrew Siwy NRC Jonathan Greives NRC Doug Tifft NRC Diane Screnci NRC William Sims Entergy Nuclear Operations, Inc. (Entergy)
Ed Blackand Entergy T.R. Jones Entergy Brian McCarty Entergy Mark Crosskey Entergy Rich Burrani Entergy Nelson Azevedo Entergy Richard Wright Entergy Vincent Andreozzi Entergy Bob Walpole Entergy Enclosure
Mark Richter Nuclear Energy Institute Paul Gunter Beyond Nuclear James Ostroff Platts Nuclear Publications Marvin Lewis N/A Alyse Peterson State of New York Bridget Frymire State of New York Michael Keegan Don't Waste Michigan Cory Hasson Staffer for Congresswoman Lowey's Office
Package: ML18117A307 Meeting Notice: ML18093A093 Meeting Summary: ML18117A316 Handouts: ML18108A183 OFFICE NRR/DORL/LPL 1/PM NRR/DORL/LPL 1/LA NRR/DORL/LPL 1/BC NRR/DORL/LPL 1/PM NAME RGuzman !Betts JDanna RGuzman DATE 4/27/18 4/27/18 4/30/18 4/30/18