ML14163A050

Summary of Conference Call with Arkansas Nuclear One, Unit 2, Regarding the Spring Steam Generator Inspections (TAC No. MF3897)

ML14163A050
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/13/2014
From:	Kulesa G J Steam Generator Tube Integrity and Chemical Engineering Branch
To:	Markley M T Plant Licensing Branch IV
Diaz-Colon M D
References
TAC MF3897
Download: ML14163A050 (4)

Text

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 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.

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 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.

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 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.

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.

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• 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.