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MONTHYEARML15261A0392015-09-21021 September 2015 September 17, 2015, Summary of Telephone Conference Verbal Authorization of Relief Request for Palisades Nuclear Plant Project stage: Other 2015-09-21
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Category:Meeting Summary
MONTHYEARML24267A2962024-10-0101 October 2024 Summary of Conference Call Regarding Steam Generator Tube Inspections ML24257A0582024-09-26026 September 2024 Summary of August 1, 2024, Hybrid Public Meeting on the Potential Palisades Nuclear Plant Restart ML24212A0592024-08-0606 August 2024 May 15, 2024, Summary of Meeting with Holtec Decommissioning International,Llc Regarding LAR to Approve Biasi Critical Heat Flux Correlation for Use with Main Steam Line Break Analysis to Support Potential Reauthorization of Power Operation ML24166A2912024-06-25025 June 2024 April 29, 2024, Summary of Meeting with Holtec Decommissioning International, LLC Regarding Plan to Submit a Quality Assurance Program Manual to Support Potential Reauthorization of Power Operations at Palisades Nuclear Plant ML24141A0632024-05-23023 May 2024 Summary of April 17, 2024, Hybrid Public Outreach Meeting ML24089A2472024-04-0808 April 2024 March 18, 2024, Summary of Pre-Submittal Meeting with Holtec Decommissioning International, LLC Regarding Proposed Emergency Plan for Resumption of Power Operations at the Palisades Nuclear Plant ML24051A0942024-02-27027 February 2024 Summary of February 6, 2024, Pre-Submittal Meeting with Holtec Decommissioning International, LLC Regarding Technical Specifications Administrative Controls and Quality Assurance Program ML24016A0052024-01-23023 January 2024 Summary of Meeting with Holtec Decommissioning International, LLC, Regarding Power Operations Technical Specifications ML23303A2132023-11-0101 November 2023 Summary of Meeting with Holtec Decommissioning International, LLC Regarding Plan to Submit a License Transfer Request as Part of a Regulatory Path for Potentially Requesting Reauthorization of Power Operations at Palisades Nuclear Plant ML23263A0012023-09-27027 September 2023 Summary of August 29, 2023, Meeting with Holtec Decommissioning International, LLC Regarding Plan to Submit an Exemption Request as Part of a Regulatory Path for Potentially Requesting Reauthorization of Power Operations at Palisades Nuclea ML23171B1222023-06-22022 June 2023 Summary of Meeting with Holtec Decommissioning International, LLC Regarding Regulatory Path for Potentially Requesting Reauthorization of Power Operations at Palisades Nuclear Plant ML23107A1212023-04-20020 April 2023 Summary of Meeting with Holtec Decommissioning International, Llc Regarding Regulatory Path for Potentially Requesting Reauthorization of Power Operations at Palisades Nuclear Plant ML22292A2612022-10-31031 October 2022 PSDAR Meeting Summary ML22132A0892022-05-12012 May 2022 Summary of the April 26, 2022, Public Outreach to Discuss the NRC 2021 End-of-Cycle Plant Performance Assessment of Palisades Nuclear Plant ML21200A2262021-07-19019 July 2021 Summary of the July 1, 2021, Public Outreach to Discuss the NRC 2020 End-of-Cycle Plant Performance Assessment of Palisades Nuclear Plant ML21145A0482021-06-0202 June 2021 Summary of May 12, 2021, Teleconference with Entergy Nuclear Operations, Inc. to Discuss Potential License Amendment Request Related to Permanently Defueled Technical Specifications for Palisades Nuclear Plant ML21012A0382021-01-14014 January 2021 December 8, 2020, Summary of Public Teleconference with Entergy Nuclear Operations Inc. Regarding Pre-submittal of a License Transfer Application to Holtec International for Palisades Nuclear Plant ML20309A2372020-11-0606 November 2020 Summary of Public Teleconference with Entergy Nuclear Operations, Inc. to Discuss Future Request for One-Time Exemption from Certain Requirements of 10 CFR 50, Appendix E, Section Iv.F. at Palisades Nuclear Plant (EPID L-2020-LRM-0091 ML20304A1442020-11-0202 November 2020 Summary of September 21, 2020, Public Teleconference with Entergy Nuclear Operations Inc. Regarding a Proposed Alternative for Repair of Reactor Vessel Head Penetrations for Palisades Nuclear Plant ML20280A6952020-10-13013 October 2020 Letter - Palisades Nuclear Plant- Summary of September 11, 2020, Conference Call with Entergy Nuclear Operations Inc. Regarding the Fall 2020 Steam Generator Tube Inspections at Palisades Nuclear Plant EPID L-2020-LRO-0051 ML20280A6962020-10-13013 October 2020 20200912 NRC Mid Outage Q and a for Phone Call for Palisades 1R27 (Revised) ML20280A6972020-10-13013 October 2020 20200910 NRC Mid Outage Q and a for Phone Call for Palisades 1R27-Entergy Responses ML20231A2202020-08-17017 August 2020 Summary of Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of the Palisades Nuclear Plant ML19296D0632019-11-0101 November 2019 August 2019 Palisades NEIMA 108 Public Meeting Summary ML19136A2552019-05-16016 May 2019 Summary of the Public Outreach/Open House to Discuss the NRC 2018 End-of-Cycle Plant Performance Assessment of the Palisades Nuclear Plant ML18351A2382018-12-18018 December 2018 Summary of Public Teleconference Call with Entergy Nuclear Operations. Inc., Regarding Emergent Alternative Request for Repair of Central Rod Drive Nozzles at Palisades Nuclear Plant ML18340A0072018-12-0606 December 2018 Summary of Call with Entergy Nuclear Operations, Inc. - Verbal Authorization of Request for Alternative for the Repair of Reactor Vessel Closure Head Penetrations ML18268A2802018-09-26026 September 2018 Summary of Public Teleconference Call with Entergy Nuclear Operations, Inc. Regarding Upcoming License Amendment Request to Relocate Surveillance Frequencies to Licensee Control ML18107A4972018-04-27027 April 2018 April 10, 2017, Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding Upcoming License Amendment Request to Add Setpoint Verification Requirement to Technical Specification Surveillance Requirements ML18113A6592018-04-23023 April 2018 Summary of Open House to Discuss the 2017 End-of-Cycle Plant Performance Assessment of Palisades Nuclear Plant ML18099A0712018-04-16016 April 2018 March 20, 2018, Summary of Meeting with the Nuclear Energy Institute and Other Industry Representatives Regarding the Surveillance Frequency Control Program ML18008A2302018-01-10010 January 2018 Summary of Public Teleconference Meeting with Entergy Nuclear Operations, Inc., Regarding Request to Extend Enforcement Discretion for Tornado-Generated Missile Non-Conformances at Palisades Nuclear Plant ML17335A0262017-12-0505 December 2017 Summary of November 27, 2017 Public Meeting with Entergy Nuclear Operations, Inc. Regarding Request to Extend Enforcement Discretion for Tornado Missle Non-Confomances ML17338B0502017-12-0505 December 2017 Summary of November 28, 2017, Public Meeting with Entergy Nuclear Operations, Inc. Regarding a Potential Request Associated with an Alternative to the Reexamination Frequency for a Relevant Condition ML17227A2742017-08-14014 August 2017 Summary of the July 26, 2017, Public Meeting Regarding Palisades Nuclear Plant ML17173A7672017-07-28028 July 2017 Summary of 6/20/2017 Meeting with Entergy to Discuss Plan for Decommissioning Licensing Actions of Palisades, Pilgrim, Indian Point, Units 2 and 3, and Vermont Yankee ML17164A3112017-06-27027 June 2017 Summary of 06/12/2017, Pre-Submittal Meeting with Entergy Nuclear Operations, Inc. to Discuss Palisades Nuclear Plant Post Shutdown Emergency Plan and Administrative Technical Specification License Amendment Request ML17160A1812017-06-14014 June 2017 Summary of Conference Call with Palisades Nuclear Plant Regarding the Spring 2017 Steam Generator Inspections ML17080A1492017-03-23023 March 2017 Summary of March 20, 2017, Public Meeting with Entergy Nuclear Operations, Inc. Regarding the Cyber Security Plan Implementation Schedule ML16344A0862016-12-20020 December 2016 Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding National Fire Protection Association Standard 805 ML16277A6772016-10-11011 October 2016 Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding the Proposed Closure Plant for Generic Safety Issue 191, Assessment of Debris Accumulation on Pressurized Water Reactor (PWR) Sump Performance ML16182A5142016-06-30030 June 2016 Summary of the June 23, 2016, Public Meeting Regarding Palisades Nuclear Plant ML16127A1722016-05-0505 May 2016 6/23/16 Notice of Significant Public Meeting to Discuss Nrc'S End-of-Cycle Assessment of the Palisades Nuclear Plant Performance for the 2015 Calendar Year ML16035A4252016-03-0101 March 2016 Summary of January 25, 2016, Pre-Application Teleconference Meeting with Entergy Nuclear Operations to Discuss a Forthcoming License Amendment Request Regarding Steam Generator Cold Leg Alternate Repair Criteria at Palisades Nuclear Plant ( ML15294A2972015-10-27027 October 2015 Steam Generator Tube Inspection Discussion During Palisades 2015 (RF24) Outage (Preliminary Information) ML15294A2922015-10-27027 October 2015 Summary of Conference Call with Palisades Nuclear Plant Regarding the Fall 2015 Steam Generator Inspections ML15272A0652015-09-30030 September 2015 Summary of Telephone Conference on September 28, 2015, Verbal Authorization of Relief Request for Palisades Nuclear Plant ML15261A0392015-09-21021 September 2015 September 17, 2015, Summary of Telephone Conference Verbal Authorization of Relief Request for Palisades Nuclear Plant ML15119A0442015-05-0606 May 2015 Summary of April 14, 2015, Meeting with Entergy Nuclear Operations, Inc. on Plans for Volumetric Examinations of Primary Coolant System Alloy 600 Welds ML15118A0352015-04-27027 April 2015 Meeting Summary with Public to Discuss the 2014 Annual Assessment Results for Palisades Nuclear Plant 2024-09-26
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LICENSEE:
FACILITY:
SUBJECT:
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 21, 2015 Entergy Nuclear Operations, Inc. Palisades Nuclear Plant
SUMMARY
OF TELEPHONE CONFERENCE ON SEPTEMBER 17, 2015, VERBAL AUTHORIZATION OF RELIEF REQUEST FOR PALISADES NUCLEAR PLANT (TAC NO. MF6727) INTRODUCTION By letter dated September 16, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15260A371
), Entergy Nuclear Operations, Inc. (ENO, the licensee) submitted relief request (RR) 4-23, which proposes to use an alternative inspection procedure to perform inspections required by Title 10 of the Code of Federal Regulations, Part 50 ( 10 CFR 50), Paragraph 55a(g)(6)(ii)(F) at the Palisades Nuclear Plant. These inspections are related to the ultrasonic examination of nickel-based Alloy 82/182 dissimilar metal butt welds joining Alloy 600 branch connections to one hot leg and eight cold leg pipes. The proposed alternative inspection procedure does not meet the 0.125 inch root mean square (RMS) error depth sizing requirements of American Society of Mechanical Engineers (ASME) Code Case N-695 and ASME Code Section XI, Appendix VIII, Supplement
- 10. This memorandum summarizes the telephone discussion on September 17, 2015, between the U.S. Nuclear Regulatory Commission (NRC) staff and ENO regarding the relief request. During this telephone call, the NRC staff provided verbal authorization of the relief request as described below. Participants in the discussion from ENO included:
Jeff Erickson, Jeff Hardy, Mike Briley, Steve Davis, and Mike Bratton. Participants for the NRC included:
David Pelton, David Alley, Stephen Cumblidge, Jennie Rankin, Mel Holmberg, David Hills, Laura Ward, and Eric Duncan. BACKGROUND As discussed in the licensee's letter dated September 16, 2015, the licensee will be performing volumetric examinations of nine dissimilar metal piping welds during the current refueling outage and will implement the requirements of ASME Section XI, Code Case N-695. This Code Case requires that qualified procedures, equipment, and personnel shall demonstrate a flaw sizing error less than or equal to 0.125 inch RMS. The ENO vendor has attempted, but not been able to qualify personnel, equipment, and procedures for depth sizing error less than or equal to 0.125 inch RMS. The licensee is qualified for detection and length sizing on the subject welds. Pursuant to 10 CFR 50.55a(z)(1
), the licensee proposes using an inspection procedure with an alternative depth sizing RMS error of 0.242 inches on the basis that the proposed inspection procedure provides an acceptable level of quality and safety. RELIEF REQUEST TELEPHONE CALL The NRC staff discussed the following during the telephone call with Entergy on September 17, 2015, with respect to the proposed relief request: The Electric Power Research Institute has contended that nondestructive examination inspectors are able to accurately depth size flaws if they can achieve an RMS error of less than 10 percent of the weld wall thickness.
The licensee stated that the 0.242 inch RMS error achieved by the proposed inspection procedure is less than 10 percent of the wall thicknesses of each weld (i.e. each weld is greater than 2.42 inches thick). While the NRC staff has not endorsed the use of the 10 percent wall thickness as an acceptance value, the NRC staff has been working with members of ASME, the Performance Demonstration Initiative, and the Electric Power Research Institute to evaluate the appropriate RMS error for the ultrasonic examination of dissimilar metal welds. The collaborative work culminated in the development of ASME Code Case N-695-1 which allows the use of an RMS error of 0.25 inches for inspections from the inner surface of a dissimilar metal weld of 2.1 inches thick or greater. The NRC staff is currently reviewing ASME Code Case N-695-1 for inclusion in the next revision of Regulatory Guide 1.147. While this review is not complete, the NRC staff has performed sufficient review of the use of a 0.25 inch RMS error or less for depth sizing and finds the use of a 0.25 inch RMS error or less to be acceptable under these circumstances at the Palisades Nuclear Plant. The NRC staff finds that the proposed inspection procedure is acceptable because the proposed RMS error is consistent with ASME Code Case N-695-1 given that each of the nine welds is greater than 2.1 inches thick and the proposed RMS error is less than 0.25 inches. The NRC staff has determined that the proposed RMS error in the inspection procedure is acceptable and that RR 4-23 provides reasonable assurance that the structural integrity of the branch connections to the hot leg and cold leg piping will be adequately monitored to the end of the fourth inservice inspection (ISi) interval.
The NRC staff finds that RR 4-23 provides an acceptable level of quality and safety. 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
). Therefore, effective September 17, 2015, the NRC authorizes the use of RR 4-23 for the remainder of the fourth 10-year ISi interval at PNP, which began on December 13, 2006, and is scheduled to end on December 12, 2015. The NRC staff notes that all other ASME Code,Section XI and 10 CFR 55a(g)(6)(ii)(F) requirements for which relief was not specifically requested and approved in the subject request for relief remain applicable, including third party review by the Authorized Nuclear lnservice Inspector.
This verbal authorization does not preclude the NRC staff from asking additional clarification questions regarding the subject relief request while preparing the subsequent written safety evaluation.
The NRC staff's written safety evaluation will be provided by separate correspondence.
The verbal relief was authorized with the concurrence of David Pelton, Chief of the Plant Licensing Branch 111-1, Office of Nuclear Reactor Regulation (NRR), and David Alley, Chief of the Component Performance, Non-Destructive Examination, and Testing Branch, NRR. If you have any questions, please contact me at (301) 415-1530 or by e-mail at Jennivine.Rankin@nrc.gov.
Docket Nos. 50-255 cc: Distribution via Listserv en ivine Rankin, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation If you have any questions, please contact me at (301) 415-1530 or by e-mail at Jennivine.Rankin@nrc.gov.
IRA! Jennivine Rankin, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-255 cc: Distribution via Listserv DISTRIBUTION:
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