NRC 2010-0096, Filing of Owner'S Inservice Inspection Summary Report Refueling Outage U1R32

Filing of Owner'S Inservice Inspection Summary Report Refueling Outage U1R32

ML101790311
Person / Time
Site:	Point Beach
Issue date:	06/25/2010
From:	Jim Costedio Nextera Energy, Point Beach
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2010-0096
Download: ML101790311 (6)

Text

June 25,2010 NRC 2010-0096 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Unit 1 Docket 50-266 Renewed License No. DPR-24 Filing of Owner's Inservice Inspection Summarv Report for Point Beach Nuclear Plant Refueling Outage U l R32 NextEra Energy Point Beach, LLC (NextEra) is submitting the inservice inspection summary report for inspections conducted prior to and during the Point Beach Nuclear Plant (PBNP) refueling outage U1R32 that concluded on April 4, 2010. The enclosed IWE Class MC and IWL Class CC report is submitted pursuant to the requirements of Subarticle IWA-6240 of the 2001 Edition with Addenda through 2003 of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code and ASME Code Case N-532-4.

The enclosure to this letter contains Form OAR-1, "Owner's Activity Report" for inservice inspections for the Class MC and CC components. The report is for the second outage of the First Period of the Second 10-Year Interval for Class MC and CC at PBNP Unit I.

Very truly yours, NextEra Energy Point Beach, LLC 4&%4-James Costedio Licensing Manager Enclosures cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW Mike Verhagen, State of Wisconsin NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241

ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 1 OAR-1, OWNER'S ACTIVITY REPORT FOR INSERVICE INSPECTION, FOR CLASS MC and CC COMPONENTS 4 pages follow

Report Number UlR32 Outage Class MC and CC IS1 Examination Plant FPLE Point Beach Nuclear Plant, 6610 Nuclear Road, Two Rivers, Wisconsin 54241 Unit No. 1 Commercial Service Date December 1970 Refueling Outage No. UlR32 (If applicable)

Current Inspection Interval Second (Ist, 2nd, 3rd, 4t11, other)

Current Inspection Period First (1st, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition 2003 Addenda Date and Revision of inspection plans Class MC: Januarv 16.2009 / Revision 1. Class CC: Januarv 23.2009 /Revision 1 Edition and Addenda of Section XI applicable to repairslreplacements activities, if different than the inspection plans Same Code Cases used: N-532-4 (If applicable)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of UlR32 (refueling outage number) conform to the requirements of Section XI.

Signed &/k dwner or Owner's Designee, Title Containment Promams Coordinator Date 6 -2I Z"l CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler of CT have inspected the items described in this Owner's Activity Report, and state that, to the best of my lcnowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repairlreplacement activities and evaluations described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Commissions WI 929625 A,I,N National Board, State, Province, and Endorsements C . / "/

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Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Examination Category and ltem Number ltem Description Evaluation Description In accordance with 10 CFR 50.55a(b)(2)(viii)(D),

. . . . . . any tendon grease leakage detected during general visual examination of the containment surface is to be reported. Minor grease leakage from multiple tendon end caps and vent plugs was noted during the visual examination of the containment surface.

In accordance with 10 CFR 50.55a(b)(2)(viii)(D), any tendon grease leakage detected during general visual examination of the containment surface is to be reported. Grease staining from external sources (tendon end caps and vent plugs) was noted in several areas during the visual examination of the containment surface.

In accordance with the acceptance standard of IWL-3221.4, corrosion protection medium (grease) is acceptable when the reserve alkalinity of all samples are within the limits specified in Table IWL-2525-1. Per Table IWL-2525-1, Note 3, the base number shall be at least 50% of the as-installed value, unless L-B L2'40 Tendon D3-27 Grease Sample the installed value is 5 or less, in which case the base number shall be no less than zero. The reported value for tendon 03-27, shop end, was ~0.50,as 0.50 is the lower limit of measurability for the prescribed test. A supplemental test, based on ASTM D-974-87, was to determine the acid number for the grease sample. The result was reported as ~0.50,which with the previous result indicates that sample was essentially neutral, neither acid or base.

In accordance with the acceptance standard of IWE-3511.3, material loss in a local area that exceeds 10% of nominal wall thickness must be documented. For the pipe penetration 1CPP-45, this corresponds to a minimum housing wall thickness of 0.3375 inches. Thickness of the penetration housing for 1CPP-45 at one location was measured at 0.329 inches. Corrosion caused by condensation some time in the E-C / E4.12 I Containment Pipe Penetration past is likely responsible for the material loss.

Calculation 1999-0109 presents an evaluation for several pipe penetrations on both units, including ICPP-45, which determined that the minimum acceptable pipe penetration housing thickness is 0.31 inches, representing a 17.3% loss from the nominal 0.375 inch thickness. The indicated and projected loss is less than previously accepted material loss.

ICPP-45 will continue to be monitored for material loss in accordance with IWE-2420(b).

Examination Category and ltem Number Item Description Evaluation Description In accordance with the acceptance standard of IWE-3511.3, material loss in a local area that exceeds 10% of nominal wall thickness must be documented. For the pipe penetration 1CPP-46, this corresponds to a minimum housing wall thickness of 0.3375 inches. Thickness of the penetration housing for 1CPP-46 at one location was measured at 0.335 inches. Corrosion caused by condensation some time in the E-C E4'12 Containment past is likely responsible for the material loss.

Pipe Penetration Calculation 1999-0109 presents an evaluation for several pipe CPP-46 penetrations on both units, including 1CPP-46, which determined that the minimum acceptable pipe penetration housing thickness is 0.31 inches, representing a 17.3% loss from the nominal 0.375 inch thickness. The indicated and projected loss is less than previously accepted material loss.

1CPP-46 will continue to be monitored for material loss in accordance with IWE-2420(b).

Table 2 Abstract of RepairlReplacement Activities Required for Continued Service Repair/

Replacement Date Plan Code Class Item Description Description of Work Completed Number Replaced fuel transfer tube Fuel Transfer Tube 3/28/2010 2010-0058 MC flange bolting with new.

Flange Bolting WO-367214-02.