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Category:Meeting Summary
MONTHYEARML23257A2412023-09-19019 September 2023
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Meeting Summary for Ticap Workshop 3
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Riv Column 1 EOC 2020 Public Meeting Summary
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Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project
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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
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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
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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
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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
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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
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Public Meeting with Entergy Operations, Inc to Discuss the Performance of the Subject Facilities and Current Regulatory Issues
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Arkansas Monitoring Call Summary
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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
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1/26/2012 - Summary of Meeting with Entergy and Exelon to Discuss Recent Once-Through Steam Generator Inservice Inspection Results
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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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Text
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
