NL-07-1962, Eighteenth Maintenance/Refueling Outage Steam Generator Tube Inspection Report

Eighteenth Maintenance/Refueling Outage Steam Generator Tube Inspection Report

ML073050415
Person / Time
Site:	Farley
Issue date:	11/01/2007
From:	George B Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-07-1962
Download: ML073050415 (4)

Text

Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 November 1, 2007 SOUTHERN COMPANY A

Energy to Serve Your World SM Docket No.: 50-364 NL-07-1962 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 2 Eighteenth Maintenance/Refueling Outage Steam Generator Tube Inspection Report Ladies and Gentlemen:

In accordance with the requirements of Joseph M. Farley Nuclear Plant Technical Specification 5.6.10, Southern Nuclear Operating Company submits this report of the steam generator tube inspections performed during the Unit 2 eighteenth maintenance/refueling outage (2R18).

This letter contains no NRC commitments. If you have any questions, please advise.

SinCere~IY'

~B. J. Ge rge

--y--

Manager, Nuclear Licensing BJG/JLS/phr

Enclosure:

2R18 Steam Generator Tube Inspection Report cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Plant Farley Mr. D. H. Jones, Vice President - Engineering RType: CFA04.054; LC# 14658 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Ms. K. R. Cotton, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley

Joseph M. Farley Nuclear Plant - Unit 2 Enclosure 2R18 Steam Generator Tube Inspection Report

Joseph M. Farley Nuclear Plant - Unit 2 2R18 Steam Generator Tube Inspection Report A. The Scope of Inspections Performed on Each Steam Generator (SG)

The scope for Farley Unit 2 refueling outage 2R18 involved the inspections listed below:

1. ~ 50% Bobbin (3 SGs)

• Tubes with history based indications and those that could not be examined full length.

• Tubes identified with 2R15 dings or dents ~ 5 volts in straight lengths and U-Bends:

27 tubes in SG A; none in SG B; 1 tube in SG C

• Tubes identified having a Non-Quantifiable Signal (NQS) in 2R15

• Straight lengths of Rows 1 and 2

2. + Point (3 SGs)

• 20% Tube Sheet Hot (TSH) +/- 3 inches (selected from tubes that were tested in the 50% bobbin program)

• 50% of Row 1 and 50% Row 2 U bends

• Special Interest: + point inspection of any bobbin "I" codes as required

• All dents and dings (U-bendsl straight length) ~ 5 volts

• Locations of foreign objects remaining in the SGs. New Potential Loose Part (PLP) and wear indications were bounded.

B. Active Degradation Mechanisms Found No active degradation mechanisms were identified.

C. Nondestructive Examination Techniques Utilized for Each Degradation Mechanism N/A (since no active degradation mechanisms were identified).

D. Location, Orientation (if linear) and Measured sizes (if available) of Service Induced Indications N/A (since no service induced indications were identified).

E. Number of Tubes Plugged During the Inspection Outage for Each Active Degradation Mechanism N/A (since no active degradation mechanisms were identified).

F. Total Number and Percentage of Tubes Plugged to Date None.

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Joseph M. Farley Nuclear Plant - Unit 2 2R18 Steam Generator Tube Inspection Report G. Results of Condition Monitoring, Including the Results of Tube Pulls and In-Situ Testing Based on the Condition Monitoring Evaluation contained in the Condition Monitoring Assessment and Operational Assessment dated April 2007, inspections of tubes in service during Cycles 16,17, and 18 confirm that they all meet Regulatory Guide 1.121 Bases for II Plugging Degraded PWR Steam Generator Tubes" structural integrity requirements. There were no confirmed indications of tube degradation. Since no degradation mechanisms were detected during the Farley Unit 2 refueling outage 2R18 inspection and no primary to secondary leakage had been observed prior to the end of Cycle 18, the condition monitoring assessment requirements for Farley Unit 2 SG operation were satisfied. No challenges to the Condition Monitoring limits were identified; therefore the Condition Monitoring requirements for the Farley Unit 2 SG tube bundles at end of Cycle 18 are satisfied.

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