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| | number = ML14163A050 | | | number = ML14163A050 |
| | issue date = 06/13/2014 | | | issue date = 06/13/2014 |
| | title = Summary of Conference Call with Arkansas Nuclear One, Unit 2, Regarding the Spring Steam Generator Inspections (TAC No. MF3897) | | | title = Summary of Conference Call with Arkansas Nuclear One, Unit 2, Regarding the Spring Steam Generator Inspections |
| | author name = Kulesa G J | | | author name = Kulesa G |
| | author affiliation = NRC/NRR/DE/ESGB | | | author affiliation = NRC/NRR/DE/ESGB |
| | addressee name = Markley M T | | | addressee name = Markley M |
| | addressee affiliation = NRC/NRR/DORL/LPLIV | | | addressee affiliation = NRC/NRR/DORL/LPLIV |
| | docket = 05000368 | | | docket = 05000368 |
| | license number = NPF-006 | | | license number = NPF-006 |
| | contact person = Diaz-Colon M D | | | contact person = Diaz-Colon M |
| | case reference number = TAC MF3897 | | | case reference number = TAC MF3897 |
| | document type = Meeting Summary, Memoranda | | | document type = Meeting Summary, Memoranda |
| | page count = 4 | | | page count = 4 |
| | project = TAC:MF3897 | | | project = TAC:MF3897 |
| | stage = | | | stage = Other |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter: June 13, 2014 MEMORANDUM TO: Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Gloria J. Kulesa, Chief /RA/ Steam Generator Tube Integrity and Chemical Engineering Branch Division of Engineering Office of Nuclear Reactor Regulation | | {{#Wiki_filter:June 13, 2014 MEMORANDUM TO: Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Gloria J. Kulesa, Chief /RA/ |
| | Steam Generator Tube Integrity and Chemical Engineering Branch Division of Engineering Office of Nuclear Reactor Regulation |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SUMMARY OF CONFERENCE CALL WITH ARKANSAS NUCLEAR ONE, UNIT 2, REGARDING THE SPRING 2014 STEAM GENERATOR INSPECTIONS (TAC NO. MF3897)
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| On May 27, 2014, the staff of the Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) of the Division of Engineering participated in a conference call with representatives of Entergy Nuclear Operations, Inc. (the licensee) regarding the ongoing steam generator (SG) inspection activities at Arkansas Nuclear One, Unit 2. In support of the conference call, the licensee provided the document attached to the enclosed conference call summary. Please include Kenneth J. Karwoski, Andrew B. Johnson, and me on distribution of the final document. Please include me on concurrence only if you have made significant changes to the enclosed summary. Please close this TAC upon issuance of the enclosed summary. ESGB formally reviews all SG inspection summary report(s) submitted by licensees in accordance with the plant's technical specification (TS) requirements. The licensees submit the summary report(s) following the completion of the SG tube inspections at a frequency defined by their TSs. Therefore, please provide the report(s) and a work request to me when submitted.
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| The process for handling our review of SG inspection summary reports, as well as the SG conference calls, is outlined in a March 12, 2009, memo from Michele G. Evans to Joseph G. Giitter (Agencywide Documents Access and Management System Accession Number ML090710575). We appreciate your support in this matter.
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| Docket No. 50-368 | | ==SUMMARY== |
| | OF CONFERENCE CALL WITH ARKANSAS NUCLEAR ONE, UNIT 2, REGARDING THE SPRING 2014 STEAM GENERATOR INSPECTIONS (TAC NO. MF3897) |
| | On May 27, 2014, the staff of the Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) of the Division of Engineering participated in a conference call with representatives of Entergy Nuclear Operations, Inc. (the licensee) regarding the ongoing steam generator (SG) inspection activities at Arkansas Nuclear One, Unit 2. In support of the conference call, the licensee provided the document attached to the enclosed conference call summary. Please include Kenneth J. Karwoski, Andrew B. Johnson, and me on distribution of the final document. Please include me on concurrence only if you have made significant changes to the enclosed summary. Please close this TAC upon issuance of the enclosed summary. |
| | ESGB formally reviews all SG inspection summary report(s) submitted by licensees in accordance with the plants technical specification (TS) requirements. The licensees submit the summary report(s) following the completion of the SG tube inspections at a frequency defined by their TSs. Therefore, please provide the report(s) and a work request to me when submitted. |
| | The process for handling our review of SG inspection summary reports, as well as the SG conference calls, is outlined in a March 12, 2009, memo from Michele G. Evans to Joseph G. Giitter (Agencywide Documents Access and Management System Accession Number ML090710575). We appreciate your support in this matter. |
| | Docket No. 50-368 |
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| ==Enclosure:== | | ==Enclosure:== |
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| As stated | | As stated CONTACT: Marioly Diaz Colon, NRR/DE 301-415-2849 |
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| CONTACT: Marioly Diaz Colon, NRR/DE 301-415-2849 June 13, 2014 MEMORANDUM TO: Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Gloria J. Kulesa, Chief /RA/ Steam Generator Tube Integrity and Chemical Engineering Branch Division of Engineering Office of Nuclear Reactor Regulation
| | June 13, 2014 MEMORANDUM TO: Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Gloria J. Kulesa, Chief /RA/ |
| | Steam Generator Tube Integrity and Chemical Engineering Branch Division of Engineering Office of Nuclear Reactor Regulation |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SUMMARY OF CONFERENCE CALL WITH ARKANSAS NUCLEAR ONE, UNIT 2, REGARDING THE SPRING 2014 STEAM GENERATOR INSPECTIONS (TAC NO. MF3897)
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| On May 27, 2014, the staff of the Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) of the Division of Engineering participated in a conference call with representatives of Entergy Nuclear Operations, Inc. (the licensee) regarding the ongoing steam generator (SG) inspection activities at Arkansas Nuclear One, Unit 2. In support of the conference call, the licensee provided the document attached to the enclosed conference call summary. Please include Kenneth J. Karwoski, Andrew B. Johnson, and me on distribution of the final document. Please include me on concurrence only if you have made significant changes to the enclosed summary. Please close this TAC upon issuance of the enclosed summary. | | ==SUMMARY== |
| | OF CONFERENCE CALL WITH ARKANSAS NUCLEAR ONE, UNIT 2, REGARDING THE SPRING 2014 STEAM GENERATOR INSPECTIONS (TAC NO. MF3897) |
| | On May 27, 2014, the staff of the Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) of the Division of Engineering participated in a conference call with representatives of Entergy Nuclear Operations, Inc. (the licensee) regarding the ongoing steam generator (SG) inspection activities at Arkansas Nuclear One, Unit 2. In support of the conference call, the licensee provided the document attached to the enclosed conference call summary. Please include Kenneth J. Karwoski, Andrew B. Johnson, and me on distribution of the final document. Please include me on concurrence only if you have made significant changes to the enclosed summary. Please close this TAC upon issuance of the enclosed summary. |
| | ESGB formally reviews all SG inspection summary report(s) submitted by licensees in accordance with the plants technical specification (TS) requirements. The licensees submit the summary report(s) following the completion of the SG tube inspections at a frequency defined by their TSs. Therefore, please provide the report(s) and a work request to me when submitted. |
| | The process for handling our review of SG inspection summary reports, as well as the SG conference calls, is outlined in a March 12, 2009, memo from Michele G. Evans to Joseph G. Giitter (Agencywide Documents Access and Management System Accession Number ML090710575). We appreciate your support in this matter. |
| | Docket No. 50-368 |
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| ESGB formally reviews all SG inspection summary report(s) submitted by licensees in accordance with the plant's technical specification (TS) requirements. The licensees submit the summary report(s) following the completion of the SG tube inspections at a frequency defined by their TSs. Therefore, please provide the report(s) and a work request to me when submitted.
| | ==Enclosure:== |
| The process for handling our review of SG inspection summary reports, as well as the SG conference calls, is outlined in a March 12, 2009, memo from Michele G. Evans to Joseph G. Giitter (Agencywide Documents Access and Management System Accession Number ML090710575). We appreciate your support in this matter. Docket No. 50-368
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| ==Enclosure:==
| | As stated CONTACT: Marioly Diaz Colon, NRR/DE 301-415-2849 DISTRIBUTION: |
| | DE R/F EMurphy AObodoako RidsNrrPMArkansas JDrake ADAMS Accession Number: ML14163A050 OFFICE NRR/DE/ESGB NRR/DE/ESGB NRR/DE NRR/DE/ESGB NAME MDiaz-Colon AJohnson KKarwoski GKulesa DATE 06/ 12 /2014 06/ 12 /2014 06/ 12 /2014 06/ 13 /2014 OFFICIAL RECORD COPY |
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| | CONFERENCE CALL |
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| As stated CONTACT: Marioly Diaz Colon, NRR/DE 301-415-2849
| | ==SUMMARY== |
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| DISTRIBUTION: DE R/F EMurphy AObodoako RidsNrrPMArkansas JDrake ADAMS Accession Number: ML14163A050 OFFICE NRR/DE/ESGB NRR/DE/ESGB NRR/DE NRR/DE/ESGB NAME MDiaz-Colon AJohnson KKarwoski GKulesa DATE 06/ 12 /2014 06/ 12 /2014 06/ 12 /2014 06/ 13 /2014 OFFICIAL RECORD COPY Enclosure CONFERENCE CALL SUMMARY ARKANSAS NUCLEAR ONE, UNIT 2, REGARDING SPRING 2014 STEAM GENERATOR INSPECTIONS DOCKET NO. 50-368 TAC NO. MF3897 On May 27, 2014, the staff of the Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) of the Division of Engineering participated in a conference call with representatives of Entergy Nuclear Operations, Inc. (the licensee) regarding the ongoing steam generator (SG) inspection activities at Arkansas Nuclear One, Unit 2 (ANO-2). In support of the conference call, the licensee provided the document attached to this conference call summary.
| | ARKANSAS NUCLEAR ONE, UNIT 2, REGARDING SPRING 2014 STEAM GENERATOR INSPECTIONS DOCKET NO. 50-368 TAC NO. MF3897 On May 27, 2014, the staff of the Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) of the Division of Engineering participated in a conference call with representatives of Entergy Nuclear Operations, Inc. (the licensee) regarding the ongoing steam generator (SG) inspection activities at Arkansas Nuclear One, Unit 2 (ANO-2). In support of the conference call, the licensee provided the document attached to this conference call summary. |
| Additional clarifying information not included in the document provided by the licensee is summarized below. | | Additional clarifying information not included in the document provided by the licensee is summarized below. |
| * ANO-2 replaced the original SGs with Westinghouse Model Delta 109 SGs. The replacement SGs have been in service for 14 calendar years. The fourth SG inservice inspections are being performed in the current refueling outage (refueling outage 23). The SGs are at the end of their first inspection interval defined by the technical specifications. ANO-2 has been inspecting the SGs every third refueling outage. | | * ANO-2 replaced the original SGs with Westinghouse Model Delta 109 SGs. The replacement SGs have been in service for 14 calendar years. The fourth SG inservice inspections are being performed in the current refueling outage (refueling outage 23). The SGs are at the end of their first inspection interval defined by the technical specifications. ANO-2 has been inspecting the SGs every third refueling outage. |
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| * No tube-to-tube wear was identified in the current outage. | | * No tube-to-tube wear was identified in the current outage. |
| * There were a total of 80 AVB indications in both SGs in the previous inspection. | | * There were a total of 80 AVB indications in both SGs in the previous inspection. |
| * The inspections identified no wear associated with loose parts. | | * The inspections identified no wear associated with loose parts. |
| - 2 -
| | Enclosure |
| * The secondary side inspections performed in both SGs did not identify any erosion or cracks in the feed ring, primary or secondary steam separators, or the outlet venturi. | | * The secondary side inspections performed in both SGs did not identify any erosion or cracks in the feed ring, primary or secondary steam separators, or the outlet venturi. |
| * The licensee clarified that the three machine remnants referenced on page 5 refer to very small machine turnings (i.e., lathe turning). | | * The licensee clarified that the three machine remnants referenced on page 5 refer to very small machine turnings (i.e., lathe turning). |
| * An evaluation of blockage of the top support plate will be done as part of the eddy current auto-analysis that is verifying the position of the AVBs. | | * An evaluation of blockage of the top support plate will be done as part of the eddy current auto-analysis that is verifying the position of the AVBs. |
| * At the time of the call, the licensee stated that approximately 100 percent of the eddy current analysis was complete and the AVB location analysis still had two weeks until completion. | | * At the time of the call, the licensee stated that approximately 100 percent of the eddy current analysis was complete and the AVB location analysis still had two weeks until completion. |
| * The licensee confirmed that the replacement SGs did not have a stay cylinder, that the center region formerly occupied by the stay cylinder had been filled in with tubes, and that there was a six-inch wide open lane in the middle of the replacement SGs. The following abbreviations are used in the document provided by the licensee: | | * The licensee confirmed that the replacement SGs did not have a stay cylinder, that the center region formerly occupied by the stay cylinder had been filled in with tubes, and that there was a six-inch wide open lane in the middle of the replacement SGs. |
| 2R22 = Unit 2 Refueling Outage 22 ANO2 = Arkansas Nuclear One, Unit 2 CMOA = Conditional Monitoring Operational assessment CR-ANO-2-2014-01539 = Condition Report EPRI = Electric Power Research Institute ETSS = examination technique specification sheet NEI 97-06 = Nuclear Energy Institute Steam Generator Program Guidelines N/A = not applicable NDE = nondestructive evaluation PWR = pressurized water reactor REV = Revision TTS = Top of tubesheet The staff did not identify any issues that required follow-up action at this time; however, the staff asked to be notified in the event that any unusual conditions were detected during the remainder of the outage. | | The following abbreviations are used in the document provided by the licensee: |
| | | 2R22 = Unit 2 Refueling Outage 22 ANO2 = Arkansas Nuclear One, Unit 2 CMOA = Conditional Monitoring Operational assessment CR-ANO-2-2014-01539 = Condition Report EPRI = Electric Power Research Institute ETSS = examination technique specification sheet NEI 97-06 = Nuclear Energy Institute Steam Generator Program Guidelines N/A = not applicable NDE = nondestructive evaluation PWR = pressurized water reactor REV = Revision TTS = Top of tubesheet The staff did not identify any issues that required follow-up action at this time; however, the staff asked to be notified in the event that any unusual conditions were detected during the remainder of the outage.}} |
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Letter Sequence Other |
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MONTHYEARML14104B6092014-04-17017 April 2014
Discussion Points for Telephone Conference on 5/22/14 for Upcoming Steam Generator Tube Inservice Inspection
Project stage: Other
ML14163A0502014-06-13013 June 2014
Summary of Conference Call with Arkansas Nuclear One, Unit 2, Regarding the Spring Steam Generator Inspections
Project stage: Other
ML14170A0602014-06-23023 June 2014
Summary of 5/27/2014 Conference Call Regarding Refueling Outage Steam Generator Inspection
Project stage: Other
2014-06-13
[Table View] |
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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
ML14184B2432014-07-10010 July 2014
Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Arkansas Nuclear One, Units 1 and 2
ML14163A0502014-06-13013 June 2014
Summary of Conference Call with Arkansas Nuclear One, Unit 2, Regarding the Spring Steam Generator Inspections
ML13269A2082013-12-12012 December 2013
Cover Memo from B. Caldwell to M. Markley RAI for Arkansas Nuclear One (ANO) Revision 15 Security Plan Review
ML13255A4872013-09-10010 September 2013
Request for Additional Information to Entergy Operations, Arkansas Nuclear One-Units 1 and 2, Regarding NTTF Recommendation 9.3 Phase 1 Staffing Assessment Submittal
ML12324A4222012-11-14014 November 2012
Meeting Notice with Entergy Operations, Inc. to Discuss the Status of the Revised Application for Arkansas Nuclear One, Unit 2 to Transition to National Fire Protection Association (NFPA) Standard 805
ML12319A1222012-11-14014 November 2012
Notice of Forthcoming Meeting with Entergy Operations, Inc. to Discuss Resubmittal of License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 at Arkansas Nuclear One, Unit 2
ML12271A2482012-09-27027 September 2012
10/9/2012 Notice of Forthcoming Meeting with Entergy Operations, Inc. to Discuss Resubmittal of License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 at Arkansas Nuclear One, Unit 2
ML12166A1002012-06-18018 June 2012
Forthcoming Meeting on 6/29/12 with Entergy Operations, Inc. to Discuss License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 at Arkansas Nuclear One, Unit 2
ML1214600172012-05-30030 May 2012
June 12-13, 2012, Notice 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
ML1134801002011-12-19019 December 2011
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Review of Amendment 22 of Safety Analysis Report - Period from 10/6/2008 Through 3/18/2010
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Notice of Forthcoming Meeting with Entergy Operations, Inc., to Discuss Proposed License Amendment Request to Adopt NFPA 805 for Arkansas Nuclear One, Units 1 and 2
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3/15/11 Notice of Forthcoming Meeting with Entergy Operations, Inc. to Discuss Arkansas Nuclear One, Unit 1 Planned License Amendment Request for Technical Specification Change Service Water System Related Support Features
2024-05-08
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June 13, 2014 MEMORANDUM TO: Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Gloria J. Kulesa, Chief /RA/
Steam Generator Tube Integrity and Chemical Engineering Branch Division of Engineering Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF CONFERENCE CALL WITH ARKANSAS NUCLEAR ONE, UNIT 2, REGARDING THE SPRING 2014 STEAM GENERATOR INSPECTIONS (TAC NO. MF3897)
On May 27, 2014, the staff of the Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) of the Division of Engineering participated in a conference call with representatives of Entergy Nuclear Operations, Inc. (the licensee) regarding the ongoing steam generator (SG) inspection activities at Arkansas Nuclear One, Unit 2. In support of the conference call, the licensee provided the document attached to the enclosed conference call summary. Please include Kenneth J. Karwoski, Andrew B. Johnson, and me on distribution of the final document. Please include me on concurrence only if you have made significant changes to the enclosed summary. Please close this TAC upon issuance of the enclosed summary.
ESGB formally reviews all SG inspection summary report(s) submitted by licensees in accordance with the plants technical specification (TS) requirements. The licensees submit the summary report(s) following the completion of the SG tube inspections at a frequency defined by their TSs. Therefore, please provide the report(s) and a work request to me when submitted.
The process for handling our review of SG inspection summary reports, as well as the SG conference calls, is outlined in a March 12, 2009, memo from Michele G. Evans to Joseph G. Giitter (Agencywide Documents Access and Management System Accession Number ML090710575). We appreciate your support in this matter.
Docket No. 50-368
Enclosure:
As stated CONTACT: Marioly Diaz Colon, NRR/DE 301-415-2849
June 13, 2014 MEMORANDUM TO: Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Gloria J. Kulesa, Chief /RA/
Steam Generator Tube Integrity and Chemical Engineering Branch Division of Engineering Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF CONFERENCE CALL WITH ARKANSAS NUCLEAR ONE, UNIT 2, REGARDING THE SPRING 2014 STEAM GENERATOR INSPECTIONS (TAC NO. MF3897)
On May 27, 2014, the staff of the Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) of the Division of Engineering participated in a conference call with representatives of Entergy Nuclear Operations, Inc. (the licensee) regarding the ongoing steam generator (SG) inspection activities at Arkansas Nuclear One, Unit 2. In support of the conference call, the licensee provided the document attached to the enclosed conference call summary. Please include Kenneth J. Karwoski, Andrew B. Johnson, and me on distribution of the final document. Please include me on concurrence only if you have made significant changes to the enclosed summary. Please close this TAC upon issuance of the enclosed summary.
ESGB formally reviews all SG inspection summary report(s) submitted by licensees in accordance with the plants technical specification (TS) requirements. The licensees submit the summary report(s) following the completion of the SG tube inspections at a frequency defined by their TSs. Therefore, please provide the report(s) and a work request to me when submitted.
The process for handling our review of SG inspection summary reports, as well as the SG conference calls, is outlined in a March 12, 2009, memo from Michele G. Evans to Joseph G. Giitter (Agencywide Documents Access and Management System Accession Number ML090710575). We appreciate your support in this matter.
Docket No. 50-368
Enclosure:
As stated CONTACT: Marioly Diaz Colon, NRR/DE 301-415-2849 DISTRIBUTION:
DE R/F EMurphy AObodoako RidsNrrPMArkansas JDrake ADAMS Accession Number: ML14163A050 OFFICE NRR/DE/ESGB NRR/DE/ESGB NRR/DE NRR/DE/ESGB NAME MDiaz-Colon AJohnson KKarwoski GKulesa DATE 06/ 12 /2014 06/ 12 /2014 06/ 12 /2014 06/ 13 /2014 OFFICIAL RECORD COPY
CONFERENCE CALL
SUMMARY
ARKANSAS NUCLEAR ONE, UNIT 2, REGARDING SPRING 2014 STEAM GENERATOR INSPECTIONS DOCKET NO. 50-368 TAC NO. MF3897 On May 27, 2014, the staff of the Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) of the Division of Engineering participated in a conference call with representatives of Entergy Nuclear Operations, Inc. (the licensee) regarding the ongoing steam generator (SG) inspection activities at Arkansas Nuclear One, Unit 2 (ANO-2). In support of the conference call, the licensee provided the document attached to this conference call summary.
Additional clarifying information not included in the document provided by the licensee is summarized below.
- ANO-2 replaced the original SGs with Westinghouse Model Delta 109 SGs. The replacement SGs have been in service for 14 calendar years. The fourth SG inservice inspections are being performed in the current refueling outage (refueling outage 23). The SGs are at the end of their first inspection interval defined by the technical specifications. ANO-2 has been inspecting the SGs every third refueling outage.
- In the ANO2 SG Primary to Secondary Leakrate (H-3) Gallons per Day (GPD) graph on page 7 of the attachment, the y-axis units are GPD.
- Verification of anti-vibration bar (AVB) positions will be performed with eddy current auto analysis after the SG tube inspections are complete. The estimated time to complete the verification is two weeks.
- The licensee confirmed that the reference Westinghouse letter to Entergy, MPENT-12-001 on page 2 of the attachment was referring to the Nuclear Safety Advisory Letter 12-01.
- The wear growth rate of the preliminary operational assessment for the current outage (at 95/50 probability/confidence interval values) is 4.5 percent.
- Plugging AVB indications greater than or equal to 30 percent through wall allows the licensee to operate on a three-cycle inspection schedule.
- No tube-to-tube wear was identified in the current outage.
- There were a total of 80 AVB indications in both SGs in the previous inspection.
- The inspections identified no wear associated with loose parts.
Enclosure
- The secondary side inspections performed in both SGs did not identify any erosion or cracks in the feed ring, primary or secondary steam separators, or the outlet venturi.
- The licensee clarified that the three machine remnants referenced on page 5 refer to very small machine turnings (i.e., lathe turning).
- An evaluation of blockage of the top support plate will be done as part of the eddy current auto-analysis that is verifying the position of the AVBs.
- At the time of the call, the licensee stated that approximately 100 percent of the eddy current analysis was complete and the AVB location analysis still had two weeks until completion.
- The licensee confirmed that the replacement SGs did not have a stay cylinder, that the center region formerly occupied by the stay cylinder had been filled in with tubes, and that there was a six-inch wide open lane in the middle of the replacement SGs.
The following abbreviations are used in the document provided by the licensee:
2R22 = Unit 2 Refueling Outage 22 ANO2 = Arkansas Nuclear One, Unit 2 CMOA = Conditional Monitoring Operational assessment CR-ANO-2-2014-01539 = Condition Report EPRI = Electric Power Research Institute ETSS = examination technique specification sheet NEI 97-06 = Nuclear Energy Institute Steam Generator Program Guidelines N/A = not applicable NDE = nondestructive evaluation PWR = pressurized water reactor REV = Revision TTS = Top of tubesheet The staff did not identify any issues that required follow-up action at this time; however, the staff asked to be notified in the event that any unusual conditions were detected during the remainder of the outage.
