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Category:Meeting Summary
MONTHYEARML23257A2412023-09-19019 September 2023 Summary of August 15, 2023, Pre-submittal Teleconference with Entergy Operations, Inc. to Discuss Proposed License Amendment Request Concerning Pressurizer Heaters for Arkansas Nuclear One, Unit 1 ML23047A3822023-03-21021 March 2023 Summary of December 15, 2022 Periodic Advanced Reactor Stakeholder Public Meeting ML22215A1912022-08-0909 August 2022 Summary of July 13, 2022, Teleconference Meeting with Entergy Operations, Inc. to Discuss Planned License Amendment Requests to Adopt Technical Specifications Task Force (TSTF) Traveler 505, Risk-Informed Extended Completion Times ML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML22151A1302022-06-0202 June 2022 May 10, 2022, Summary of Teleconference Meeting W/Entergy Operations, Inc. to Discuss a Planned Alternative for a One-Time Schedule Extension for the In-Service Examination of Control Rod Drive Mechanism Penetration No. 1 in the Reactor Ves ML22125A2452022-05-0909 May 2022 May 3, 2022, Summary of Teleconference Meeting with Entergy Operations, Inc. to Discuss Proposed License Amendment Request for ANO, Units 1 & 2 Regarding Proposed Revision to Emergency Plan and On-Shift Staff Analysis ML22003A0562022-01-10010 January 2022 Summary of December 16, 2021, Presubmittal Teleconference with Entergy Operations, Inc. to Discuss Proposed Amendment Request Concerning TS 3.4.4, RCS Loops, Modes 1 and 2, for Arkansas Nuclear One, Unit 1 ML21323A0472021-12-0606 December 2021 Summary of Public Meeting on November 5, 2021, with the National Organization of Test, Research, and Training Reactors on Operator Licensing for Research and Test Reactors ML21288A0392021-10-18018 October 2021 September 14, 2021, Summary of Public Workshop on Scale/Melcor Source Term Demonstration Project - Pebble-Bed Molten-Salt-Cooled Reactor ML21181A3352021-07-0101 July 2021 June 23, 2021, Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project ML21158A2232021-06-0808 June 2021 Meeting Summary for Ticap Workshop 3 ML21140A3892021-05-24024 May 2021 Riv Column 1 EOC 2020 Public Meeting Summary ML21132A2952021-05-14014 May 2021 Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project ML21117A0262021-05-0505 May 2021 Summary of Teleconference with Entergy Operations, Inc. to Discuss Forthcoming LAR Concerning Reactor Coolant System Primary Activity and Primary-to-Secondary Leak Rate ML20337A1572020-12-0808 December 2020 Summary of Teleconference Meeting with Entergy Operations, Inc. to Discuss the Forthcoming Supplemental Response Concerning Generic Letter 2004-02 for Arkansas Nuclear One, Units 1 and 2 ML20287A4012020-10-26026 October 2020 Summary of September 17, 2020, Meeting with Entergy to Discuss Proposed License Amendment Request for Arkansas Nuclear One, Units 1 and 2 Request to the Extend Allowable Outage Time for the Emergency Cooling Pond ML20260G9992020-09-16016 September 2020 Summary of August 4, 2020, Teleconference Meeting with Entergy Operations, Inc. to Discuss Proposed License Amendment Request for Arkansas Nuclear One, Units 1 and 2 Regarding Adoption of 10 CFR 50.69 ML20189A2832020-07-0707 July 2020 Summary of Region IV Annual Assessment Public Meeting ML20153A2252020-06-0404 June 2020 April 29, 2020, Summary of Meeting with Entergy Operations, Inc. to Discuss a Proposed Relief Request Use of Carbon Fiber Reinforced Polymer Piping for Underground Service Water Piping at Arkansas Nuclear One, Units 1 and 2 ML19182A0332019-07-10010 July 2019 Summary of Teleconference with Entergy Operations, Inc. Regarding Proposed License Amendment Request Revised Fuel Handling Analysis and Adoption of Various TSTF Travelers for Arkansas Nuclear One, Unit 2 ML18176A1312018-06-21021 June 2018 Summary of Annual Assessment Meeting with Entergy Operations, Inc., Regarding 2017 Performance of Arkansas Nuclear One 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 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 ML17353A1542017-12-22022 December 2017 Summary of Public Meeting with Entergy Operations, Inc., on Proposed Changes to Emergency Plans to Revise Emergency Action Levels for Arkansas; Grand Gulf; River Bend; and Waterford (EPID-L-2017-LRM-0060) ML16109A3642016-04-18018 April 2016 Summary of Meeting to Discuss Supplemental Inspection Results and Annual Assessment Meeting with Entergy Operations Inc. Regarding 2015 Performance of Arkansas Nuclear One ML15348A1882016-01-0606 January 2016 Summary of October 28, 2015, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc. to Discuss Flood Analysis Associated with Arkansas Nuclear One, ML15267A4182015-09-24024 September 2015 Summary of Meeting to Discuss Arkansas Nuclear One Performance Improvement ML15225A2542015-08-14014 August 2015 Summary of 4/20-23/2015 Audit in Support of Request to Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition) ML15132A1752015-05-21021 May 2015 Summary of Annual Assessment Meeting with Entergy Operations Inc., Regarding ANO 2014 Performance ML15089A1642015-04-27027 April 2015 Summary of February 25, 2015, Partially Closed Meeting with Industry Stakeholders Regarding the Babcock and Wilcox Loss of Coolant Accident Evaluation Model Analysis ML15007A4782015-01-15015 January 2015 Summary of July 15-18, 2013, Arkansas Nuclear One, Unit 2, Audit Associated with License Amendment Request to Transition to National Fire Protection Association Standard 805 ML14356A1722014-12-22022 December 2014 Summary of Site Audit to Support the Review of a License Amendment Request for Arkansas Nuclear One, Unit 2 to Transition to the National Fire Protection Association (NFPA) Standard 805 Fire Protection Licensing Basis ML14197A5832014-09-18018 September 2014 Summary of the June 19, 2014, Category 1 Public Meeting with Entergy to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Tear Task Force Recommendation 2.1 ML14259A5972014-09-16016 September 2014 Summary of Annual Performance Assessment Meeting for Arkansas Nuclear One Performance ML14213A4272014-09-12012 September 2014 Summary of July 16, 2014, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers Nuclear Regulatory Commission, and Entergy Operations Inc. to Discuss Flooding Analysis Associated with Arkansas Nuclear One, Units 1 and 2 ML14162A3712014-06-26026 June 2014 5/22/2014 Summary of Meeting with Entergy Operations, Inc. to Discuss Flooding Hazard Reevaluation Extension Request for Arkansas Nuclear One, Units 1 and 2; Near-Term Task Force Recommendation 2.1 ML14170A0602014-06-23023 June 2014 Summary of 5/27/2014 Conference Call Regarding Refueling Outage Steam Generator Inspection ML14163A0502014-06-13013 June 2014 Summary of Conference Call with Arkansas Nuclear One, Unit 2, Regarding the Spring Steam Generator Inspections ML14128A5122014-05-0909 May 2014 Summary of Regulatory Conference to Discuss Safety Significance of Arkansas Nuclear One Unit 1 Dropped Stator ML13172A0292013-07-0909 July 2013 Summary of 5/10/2013 Conference Call with Entergy Operations, Inc., 2013 Steam Generator Tube Inspections at Arkansas Nuclear One, Unit 1 ML13142A2272013-05-22022 May 2013 Summary of Public Meeting to Discuss Results of Augmented Inspection at Arkansas Nuclear One ML13043A6112013-02-26026 February 2013 Summary of 1/25/2013 Conference Call Regarding the Upcoming 2013 Steam Generator Tube Inspections ML12276A3012012-10-12012 October 2012 Summary of October 25, November 8, and November 10, 2011, Conference Calls Related to Fall 2011 Refueling Outage Steam Generator Tube Inspections ML12275A5492012-10-0101 October 2012 Summary of Meeting with Entergy Operations, Inc., to Discuss the Performance of the Subject Facilities, Recent Organizational Changes, and Current Regulatory Issues ML12240A4162012-08-27027 August 2012 Public Meeting with Entergy Operations, Inc to Discuss the Performance of the Subject Facilities and Current Regulatory Issues ML12222A0312012-08-0808 August 2012 Arkansas Monitoring Call Summary ML12171A3662012-07-16016 July 2012 6/12-13/2012 Summary of Meeting at the Plant Site in Russellville, AR, to Discuss Entergy Operations, Inc.'S License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 at Arkansas Nuclear One, Unit 2 ML1202704162012-02-13013 February 2012 1/26/2012 - Summary of Meeting with Entergy and Exelon to Discuss Recent Once-Through Steam Generator Inservice Inspection Results ML1127903812011-11-0101 November 2011 Summary of Meeting with Entergy Operations, Inc. to Discuss Amendment Request to Revise Arkansas Nuclear One, Unit 2's Fuel Handling Accident (FHA) Analysis and Several TSTFs 51, 272, 286, and 471 That Support FHA ML1117906392011-06-28028 June 2011 Summary of Meeting with Entergy Operations Inc 2023-09-19
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November 7, 2002 LICENSEE: Entergy Operations, Inc. (Entergy)
FACILITY: Arkansas Nuclear One, Unit 1 (ANO-1)
SUBJECT:
SUMMARY
OF OCTOBER 16, 2002, MEETING AND FOLLOW-UP DISCUSSION ON REACTOR VESSEL HEAD WELD REPAIRS On October 16, 2002, the U.S. Nuclear Regulatory Commission (NRC) staff met with Entergy (at their request) to discuss the planned ANO-1 reactor vessel head weld repair technique.
Meeting attendees are listed in Enclosure 1. Slides presented by Entergy during the presentation are in Enclosure 2. Preliminary information provided by the licensee the day before the meeting is in Enclosure 3.
By way of background, on October 7, 2002, during refueling outage 1R17, a small nodule of boric acid crystals was found in the area of control rod drive mechanism (CRDM) 56. This is the same nozzle that was found to be leaking during the previous refueling outage.
The licensee presented their 1R16 (spring 2001) findings/repair on CRDM 56, their 1R17 (current inspection) non-destructive examination (NDE) findings, their planned 1R17 weld repair evaluation, and their assurance of non-leakage for the planned repair.
The only flaw found during 1R16 was an axial flaw in the weld-to-nozzle interface of CRDM 56 and it extended above the J-weld in the nozzle. The flaw was repaired with Alloy 152 weld material filling the excavated area.
The licensee informed the staff that to date (in 1R17), they have performed a 100% bare metal visual examination of the head and found only one leaking nozzle (CRDM 56) and no evidence of wastage. They have also performed an ultrasonic testing (UT) examination of 20 nozzles (about 30%) and so far, all other nozzles show a constant state from the previous outages.
CRDM 56 UT data shows six small indications with none having a circumferential component and no evidence of Alloy 52 cracking.
The licensee believes that they can perform an American Society of Mechanical Engineers Boiler and Pressure Vessel Code repair on CRDM 56 (or any other nozzle, if needed) and isolate the flaw from the primary water stress corrosion cracking (PWSCC) environment for two cycles of operation, at which time they plan to replace the head. Their repair plan options for flaw repair incorporate lessons learned, including those from the North Anna Power Station, Unit 2, repair effort, and they consist of the following to be used in combination or individually:
a 360E J-groove weld and butter overlay, a 360E nozzle inlay or overlay, a 90E nozzle inlay, or a weld overlay on the nozzle outer-diameter surface to mitigate crack initiation. The J-weld overlay will be at least 3/8-inch thick with a 3-layer minimum, and it will have at least a 1/2-inch overlap onto the stainless steel cladding. The licensee indicated that these repairs were designed with detailed analysis performed by their consultants.
In addition, the licensee stated that test/industry data show that Alloy 52 integrity is established for more than two operating cycles using acceptable crack growth rates. The licensee provided two publicly-available papers to support their position: "Fracture Toughness, Tensile and Stress Corrosion Cracking Properties of Alloy 600, Alloy 690 and their Welds in Water," by C.
M. Brown and W. J. Mills, Corrosion 90, 1996, pages 90/1-90/24; and "Effect of Water on Mechanical Properties and Stress Corrosion Behavior of Alloy 600, Alloy 690, EN82H Welds,
November 7, 2002 and EN52 Welds," by C. M. Brown and W. J. Mills, Corrosion - Volume 55, No. 2, 1999, pages 173-186. Also, the licensee believes that the planned repairs will remove all mechanistic failures that can create leak paths, and that alternative approaches (i.e., removing the entire crack) can pose new disadvantages.
The NRC staff commented that it appeared that the licensee carefully thought through the repair problem and committed to get back to the licensee with feedback on the planned repairs within one day. On October 17, 2002, the staff informed the licensee that they need to assume PWSCC in their crack growth rate calculations, and if the flaw evaluations show unacceptable results, that the inlay process be used as discussed at the meeting. In addition, the staff informed the licensee that it should perform a UT examination of the center nozzle (the licensee indicated they did not desire to perform a UT examination of this nozzle due to accessibility problems).
/RA/
Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313
Enclosures:
As stated cc w/encls: See next page
November 7, 2002 and EN52 Welds," by C. M. Brown and W. J. Mills, Corrosion - Volume 55, No. 2, 1999, pages 173-186. Also, the licensee believes that the planned repairs will remove all mechanistic failures that can create leak paths, and that alternative approaches (i.e., removing the entire crack) can pose new disadvantages.
The NRC staff commented that it appeared that the licensee carefully thought through the repair problem and committed to get back to the licensee with feedback on the planned repairs within one day. On October 17, 2002, the staff informed the licensee that they need to assume PWSCC in their crack growth rate calculations, and if the flaw evaluations show unacceptable results, that the inlay process be used as discussed at the meeting. In addition, the staff informed the licensee that it should perform a UT examination of the center nozzle (the licensee indicated they did not desire to perform a UT examination of this nozzle due to accessibility problems).
/RA/
Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313
Enclosures:
As stated cc w/encls: See next page DISTRIBUTION:
PUBLIC TTate (TLT)
PDIV Reading WReckley (WDR)
RidsNrrPMTAlexion AHiser (ALH1)
RidsOgcRp TChan (TLC)
RidsAcrsAcnwMailCenter KWichman (KRW)
RidsNrrDlpm (JZwolinski/TMarsh) RBarrett (RJB3)
RidsNrrDlpmLpdiv (WRuland) SRosenberg (SLR1)
RidsNrrDlpmLpdiv1 (RGramm) SMorris (SAM1)
RidsNrrLADJohnson RidsRgn4MailCenter (KBrockman)
MKotzalas (MXK5) : ML023120269 Package: ML023170275 : ML023120259 Accession No.: ML023170270 OFFICE PDIV-1/PM PDIV-1/LA EMCB/SC PDIV-1/SC NAME TAlexion DJohnson TChan RGramm DATE 10/28/02 10/28/02 10/29/02 10/30/02 OFFICIAL RECORD COPY
MEETING ON ANO-1 REACTOR VESSEL HEAD WELD REPAIRS OCTOBER 16, 2002 Name Organization C. Anderson Entergy B. Campbell Entergy W. Simms Entergy S. Lewis Entergy M. Krupa Entergy D. Miller Entergy B. Bevilacqua Westinghouse Electric Corporation S. Hunt Dominion Engineering T. Giannuzzi Structural Integrity Associates N. Cofie Structural Integrity Associates T. Alexion NRC T. Tate NRC W. Reckley NRC R. Gramm NRC W. Ruland NRC L. Marsh NRC A. Hiser NRC T. Chan NRC K. Wichman NRC R. Barrett NRC S. Rosenberg NRC K. Brockman NRC Enclosure 1
Arkansas Nuclear One cc:
Executive Vice President Vice President, Operations Support
& Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc. P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-1995 Wise, Carter, Child & Caraway Director, Division of Radiation P. O. Box 651 Control and Emergency Management Jackson, MS 39205 Arkansas Department of Health 4815 West Markham Street, Slot 30 Mr. Craig G. Anderson Little Rock, AR 72205-3867 Vice President, Operations ANO Entergy Operations, Inc.
Winston & Strawn 1448 S. R. 333 1400 L Street, N.W. Russellville, AR 72801 Washington, DC 20005-3502 Mr. Mike Schoppman Framatome ANP, Richland, Inc.
Suite 705 1911 North Fort Myer Drive Rosslyn, VA 22209 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse Russellville, AR 72801 March 2001