ML092330622

Review of the 2008 Steam Generator Tube Inspections

ML092330622
Person / Time
Site:	Ginna
Issue date:	09/14/2009
From:	Pickett D Plant Licensing Branch 1
To:	John Carlin Ginna
Pickett D
References
TAC MD9727
Download: ML092330622 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 14, 2009 Mr. John T. Carlin Vice President RE. Ginna Nuclear Power Plant RE. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519

SUBJECT:

RE. GINNA NUCLEAR POWER PLANT - REVIEW OF THE 2008 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MD9727)

Dear Mr. Carlin:

By letters dated September 23, 2008 (Agencywide Documents Access Management System (ADAMS) Accession No. ML082740268), and March 5, 2009 (ADAMS Accession No. ML090700555), RE. Ginna Nuclear Power Plant, LLC (the licensee), submitted information summarizing the results of the steam generator tube inspections performed at the RE. Ginna Nuclear Power Plant (Ginna) during the 2008 refueling outage.

The Nuclear Regulatory Commission has completed its review of these reports and concludes that the licensee provided the information required by the Ginna Technical Specifications. No additional followup is required at this time. The staff's review of this report is enclosed. Please contact me at 301-415-1364, if you have any questions.

Sincerely,

-~~_ V ~,-~-u4 Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244

Enclosure:

As stated cc w/encl: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 OFFICE OF NUCLEAR REACTOR REGULATION RE. GINNA NUCLEAR POWER PLANT STEAM GENERATOR TUBE INSPECTIONS FOR THE 2008 REFUELING OUTAGE DOCKET NO. 50-244 By letters dated September 23, 2008 (Agency-wide Documents Access Management System (ADAMS) Accession No. ML082740268), and March 5, 2009 (ADAMS Accession No. ML090700555), RE. Ginna Nuclear Power Plant, LLC, the licensee, submitted information summarizing the results of the steam generator (SG) tube inspections performed at the RE.

Ginna Nuclear Power Plant (Ginna) during the 2008 refueling outage.

Ginna has two SGs designed and fabricated by Babcock and Wilcox International. Each SG contains 4765 thermally treated Alloy 690 tubes. Each tube has a nominal outside diameter of

% inch and a nominal wall thickness of 0.043 inch. The tubes were hydraulically expanded at both ends for the full length of the tubesheet and are supported by a number of type 410 stainless steel lattice grid supports.

The licensee provided the scope, extent, methods, and results of the SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions, i.e., tube plugging, taken in response to the inspection findings. The tubes in both SGs were inspected this outage.

After reviewing the information provided by the licensee, the Nuclear Requlatory Commission (NRC) staff has the following comments or observations:

• As of the 2008 refueling outage, the SGs had operated for approximately 132 effective full-power months (EFPM). The SGs have operated for approximately 116 EFPM in the 144 EFPM sequential period.

• The tube in row 9 column 121 did not permit the passage of the 0.610- or 0.620-inch diameter bobbin probe during the 2008 outage due to a dent in the U-bend area of the tube. Although this condition has been present since the first inservice inspection (1997), a 0.610-inch diameter bobbin probe has passed through this tube in the inspections prior to 2008.

• Denting has been observed near the top of the tubesheet in the cold leg of SG B. These dents were not present in previous inspections. All dents detected with the bobbin probe in SG B were inspected with a rotating probe and no degradation was identified. The Enclosure

-2 dents were categorized as minor. The nominal diameter bobbin probe passed through these tubes.

• There are several tubes in which the U-bend regions are in close proximity, out of design tolerance. The licensee has inspected the affected tubes during each SG examination, including the 2008 refueling outage, and has indicated that the extent of the tube-to-tube proximity has not changed nor has any wear of the tubing been observed at these locations.

• One tube in SG B, row 78 column 24, was identified with two wear indications at the first hot-leg tube support. The two wear indications were on opposite sides of the tube. One wear indication was attributed to a loose part that had been located between the tube and the support grid, but the part was no longer present at this location. The second indication was attributed to wear with the support. The second wear indication was tapered and was hypothesized by the licensee to be caused by the presence of the loose part that had been located on the other side of the tube.

Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by the Technical Specifications. In addition, the staff concludes that there are no technical issues that warrant foliowup action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and that inspection results appear to be consistent with industry operating experience at similarly designed and operated units.

Principle Contributor: Aloysius O. Obodoako Date: September 14, 2009

September 14,2009 Mr. John T. Carlin Vice President RE. Ginna Nuclear Power Plant RE. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519

SUBJECT:

RE. GINNA NUCLEAR POWER PLANT - REVIEW OF THE 2008 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MD9727)

Dear Mr. Carlin:

By letters dated September 23, 2008 (Agencywide Documents Access Management System (ADAMS) Accession No. N1L082740268), and March 5, 2009 (ADAMS Accession No. ML090700555), RE. Ginna Nuclear Power Plant, LLC (the licensee), submitted information summarizing the results of the steam generator tube inspections performed at the RE. Ginna Nuclear Power Plant (Ginna) during the 2008 refueling outage.

The Nuclear Regulatory Commission has completed its review of these reports and concludes that the licensee provided the information required by the Ginna Technical Specifications. No additional followup is required at this time. The staff's review of this report is enclosed. Please contact me at 301-415-1364, if you have any questions.

Sincerely, IRA!

Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244

Enclosure:

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

Public LPL 1-1 RIF RidsNrrPMDPickett RidsNrrDorlLpl1-1 RidsNrrLASLittle KKarwoski RidsNrrDciCsgb AObodoako RidsOGCMailCenter GDentel, RI Accession Number: ML092330622 OFFICE LPL 1-1\GE LPL 1-'I\PM LPL 1-1\LA DCI/CSGB/BC (A) LPL1-1\BC NAME JGali DPickett SLittle MGavrilas by NSalgado memo dated DATE 09/09 I 09 09/09/09 09/08 109 09101/09 09/14/09 Official Record Copy