ML12310A066

Summary of Conference Call with Firstenergy Nuclear Operating Company to Discuss 2012 Steam Generator Tube Inspections

ML12310A066
Person / Time
Site:	Beaver Valley
Issue date:	11/13/2012
From:	Peter Bamford Plant Licensing Branch 1
To:	Harden P FirstEnergy Nuclear Operating Co
Bamford P
References
TAC ME9427
Download: ML12310A066 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 13, 2012 Mr. Paul A. Harden Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077

SUBJECT:

BEAVER VALLEY POWER STATION, UNIT NO.2 -

SUMMARY

OF CONFERENCE CALL WITH FIRSTENERGY NUCLEAR OPERATING COMPANY TO DISCUSS 2012 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. ME9427)

Dear Mr. Harden:

On October 10,2012, the Nuclear Regulatory Commission (NRC) staff participated in a conference call with FirstEnergy Nuclear Operating Company personnel to discuss the steam generator inspection activities taking place at Beaver Valley Power Station, Unit No.2, during the 2012 refueling outage. The call was conducted based on an NRC letter dated September 4,2012 (Agencywide Documents Access and Management System Accession No. ML12241A290). Enclosed is a summary of the conference call prepared by the NRC staff.

Please contact me at 301-415-2833, if you have any questions.

Sincerely, Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412

Enclosure:

As stated cc w/encl: Distribution via Listserv

SUMMARY

OF CONFERENCE CALL BEAVER VALLEY POWER STATION, UNIT 2 REGARDING THE FALL 2012 STEAM GENERATOR TUBE INSPECTIONS DOCKET NUMBER 50-412 On October 10, 2012, the staff of the U.S. Nuclear Regulatory Commission (NRC) participated in a conference call with FirstEnergy Nuclear Operating Company, Inc (FENOC, the licensee),

representatives regarding the ongoing steam generator (SG) tube inspection activities at Beaver Valley Power Station (BVPS), Unit 2. The call was conducted based on an NRC letter dated September 4, 2012 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML12241A290). In support of the conference call, the licensee provided a document summarizing some of the inspection results. This summary document is available at ADAMS Accession No. ML12289A117.

BVPS, Unit 2 is a 3-loop plant with Westinghouse Model 51M SGs. Each SG contains 3376 mill-annealed Alloy 600 tubes with a nominal outside diameter of 0.875 inches and a nominal wall thickness of 0.050 inches. The tubes are supported by a number of carbon steel tube support plates and Alloy 600 anti-vibration bars. The tubes were roll expanded at both ends for the full depth of the tubesheet. The entire length of tube within the tubesheet was shot-peened on both the hot-leg and cold-leg side of the SG, prior to operation. In addition, the U-bend region of the small radius tubes were in-situ stress relieved prior to operation.

In addition to the depth-based tube repair criteria, the licensee is also authorized to apply the voltage-based tube repair criteria for predominantly axially-oriented outside diameter stress corrosion cracking (ODSCC) at the tube support plate elevations. In addition, the licensee is authorized to leave flaws within the tubesheet region in service, provided they satisfy the F*/EF*

repair criterion.

Information provided by the licensee is summarized below:

The licensee stated that a total of 102 tubes (I.e., SG 'A' -- 52 tubes, SG 'B' - 23 tubes, and SG 'C' -- 27 tubes) will be sleeved during this outage. The licensee indicated that the Westinghouse leak limiting Alloy 800 sleeves will be used. The licensee stated that the leak limiting Alloy 800 sleeves have been used extensively in foreign and domestic plants.

The licensee elected to implement the voltage-based alternate repair criteria, consistent with Generic Letter (GL) 95-05, "Voltage-based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking," during this outage. Tube removal, per GL 95-05, was deferred until the next scheduled refueling outage. The licensee's justification for deferring the tube pull is because the maximum bobbin probe voltage indication for ODSCC was 1.8 volts (V) and the Electric Power Research Institute (EPRI) ODSCC database indicated that indications with less than 2 V are low-priority data. The licensee indicated that deferring the tube pull is consistent with a January 28, 2000, NRC letter from Jack R. Strosnider (NRC) to David J. Modeen (Nuclear Energy Institute),

Enclosure

-2 (ADAMS Accession No. ML003678700). The licensee stated that the upper voltage repair limit, without rotating pancake coil probe confirmation, is 5.87 V.

• At the time of the call, the licensee indicated that visual inspections of the SG 'A' steam drum and feedring repair patch is being performed to ensure erosion/corrosion is not occurring. The preliminary data showed no erosion/corrosion.

• The licensee stated that all loose parts identified during the foreign object search and retrieval of the tube lane and annulus regions were removed.

The NRC staff reviewed the applicability of the letter dated January 28, 2000 (ADAMS Accession No. ML003678700), to the BVPS, Unit 2, alternate repair criteria situation, and did not object to the licensee's proposed course of action. Further, the NRC staff did not identify any other issues that required follow up action at the time of the teleconference. The NRC 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 (ADAMS Accession No. ML12289A117):

DSI = Distorted Tube Support Plate Signal with Possible Indication DNI = Dent or Ding with Possible Indication TSP = Tube Support Plate

=

AVB Anti-Vibration Bar

=

SPR (Tube) Support Plate Mix Residual Signal BLG = (Tubesheet) Bulge OXP = (Tubesheet) Over-expansion FSI = Free Span Indication NQI = Non-Quantifiable Indication PLP = Possible Loose Part TIS = Top of Tubesheet

November 13,2012 Mr. Paul A. Harden Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077

SUBJECT:

BEAVER VALLEY POWER STATION, UNIT NO.2 -

SUMMARY

OF CONFERENCE CALL WITH FIRSTENERGY NUCLEAR OPERATING COMPANY TO DISCUSS 2012 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. ME9427)

Dear Mr. Harden:

On October 10,2012, the Nuclear Regulatory Commission (NRC) staff participated in a conference call with FirstEnergy Nuclear Operating Company personnel to discuss the steam generator inspection activities taking place at Beaver Valley Power Station, Unit No.2, during the 2012 refueling outage. The call was conducted based on an NRC letter dated September 4,2012 (Agencywide Documents Access and Management System Accession No. ML12241A290). Enclosed is a summary of the conference call prepared by the NRC staff.

Please contact me at 301-415-2833, if you have any questions.

Sincerely, IRA!

Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412

Enclosure:

As stated cc w/encl: Distribution via Listserv DISTRIBUTION:

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