NRC 2011-0084, Filing of Owner'S Lnservice Inspection Summary Report for Refueling Outage U2R31

Filing of Owner'S Lnservice Inspection Summary Report for Refueling Outage U2R31

ML112560019
Person / Time
Site:	Point Beach
Issue date:	09/12/2011
From:	Jim Costedio Point Beach
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
NRC 2011-0084
Download: ML112560019 (5)

Text

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BEACH September 12, 201 1 NRC 201 1-0084 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Unit 2 Docket 50-301 Renewed License No. DPR-27 Filing of Owner's lnservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U2R31 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 U2R31 that concluded on June 19,2011. 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 the summary report, which includes completed Form OAR-1, "Owner's Activity Report" for inservice inspections for the Class MC and CC components. The report is for the first outage of the Second Period of the Second 10-year Interval for Class MC and CC at PBNP Unit 2.

Very truly yours, NextEra Energy Point Beach, LLC ames Costedio R i c e n s i n g 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, 66 10 Nuclear Road, Two Rivers, WI 54241

ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 2 OAR-1, OWNER'S ACTIVITY REPORT FOR INSERVICE INSPECTION, FOR CLASS MC and CC COMPONENTS 3 pages follow

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number U2R3 1 Outage Class MC and CC IS1 Examination Plant NextEra Energy Point Beach Nuclear Plant, 6610 Nuclear Road, Two Rivers, Wisconsin 54241 Unit No. 2 Comn~ercialService Date October 1972 Refueling Outage No. U2R3 1 (If applicable)

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

Current Inspection Period Second (lst, 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: January 7,201 1 /Revision 2. Class CC: June 11,2010 /Revisio112 Edition and Addenda of Section XI applicable to repairslreplace~~ients activities, if different than the inspection plans Same Code Cases used: N-532-4. N-739. N-753 (If applicable)

I certify that (a) the statenlents 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 repairlreplacement activities and evaluations supporting the completion of (refueling outage number) conform to the requirements of Section XI.

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 Repo~t,and state that, to the best of nly knowledge and belief, the Owner has perfonned all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his enlployer makes any warranty, expressed or implied, concerning the repairlreplacen~ent activities and evaluations described in this report. Furthennore, neither the Inspector nor his employer shall be liable in any manner for any personal inju~yor property damage or loss of any kind arising froin or connected with this inspection.

Con~niissions WI 929625 A,I,N National Board, State, Province, and Endorsements u/ I /

/ "

Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Examination Category and ltem Number Item Description Evaluation Description Containment Cracking of the containment concrete, thought to exceed Dome Concrete, recording criteria, was found to be about 0.010 inches in width L-A 1 L1.l I viewable from and shows no apparent growth in three years.

platform PLTF-H-3 Embedded wood just below the concrete surface and partially Containment exposed is in very good condition, indicating that the wood has Concrete, not been exposed to moisture that would rot the wood or cause L-A / L1.I1 viewable from reinforcing steel in the concrete to corrode. A drummy area of walkway about 0.75 square feet does not show evidence of degradation WKWY-LM-5 of the concrete to affect the strength of the containment structure.

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 2CPP-48, this corresponds to a minimum housing wall thickness of 0.3375 inches. Thickness of the penetration housing for 2CPP-48 at one location was measured at 0.333 inches. Corrosion caused by condensation some time in the

'Ontainrnent past is likely responsible for the material loss.

E4'12 Pipe Penetration Calculation 1999-0109 discusses an evaluation for several pipe 2CPP-48 penetrations on both units, including 2CPP-48, 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.

2CPP-48 will continue to be monitored for material loss in accordance with IWE-2420(b).

Table 2 Abstract of RepairIReplacement Activities Required for Continued Service Repair1 Replacement Date Plan Code Class Item Description Description of Work Completed Number None