NRC 2012-0019, Filing of Owner'S Class 1, 2, and 3 Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R33

Filing of Owner'S Class 1, 2, and 3 Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R33

ML12068A368
Person / Time
Site:	Point Beach
Issue date:	03/07/2012
From:	Jim Costedio Point Beach
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
NRC 2012-0019
Download: ML12068A368 (5)

Text

March 07,2012 NRC 2012-0019 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 Class 1. 2. and 3 Inservice Inspection Summary Report for Point Beach Nuclear Plant Refuelins Outage U1R33 NextEra Energy Point Beach, LLC (NextEra) is submitting inservice inspection summary reports for inspections conducted prior to and during the Point Beach Nuclear Plant (PBNP) refueling outage U1R33 that concluded on December 17,201 1. The enclosed Class 1,2 and 3 report is submitted pursuant to the requirements of Subarticle IWA-6240 of the 1998 Edition with Addenda through 2000 of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code and ASME Code Case N-532-4.

Enclosure 1 of this letter contains the alternate summary report, Form OAR-1, "Owner's Activity Report" for inservice inspections for the Class 1, 2 and 3 components. The report is for the second outage of the third period of the fourth ten-year interval for Class 1, 2 and 3 systems at PBNP Unit 1.

Very truly yours, NextEra Energy Point Beach, LLC

/me' ames Costedio

~ i c e n s i nManager

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

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number UlR33 Outage Class 1,2. and 3 IS1 Examination Plant NextEra Ener~yPoint Beach Nuclear Plant, 6610 Nuclear Road, Two Rivers, Wisconsin 54241 Unit No. 1 Commercial Service Date December 21, 1970 Refueling Outage No. UlR33 (If applicable)

Current Inspection Interval Fourth (lst, 2nd, 3rd, 4th, other)

Current Inspection Period Third (lst, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the inspection plans 1998 Edition 2000 Addenda Date and Revision of inspection plans December 1. 2010 /Revision 11 Edition and Addenda of Section XI applicable to repairs/replacementsactivities, if different than the inspection plans Same Code Cases used: N-460, N-498-4 (CL 3 onlv). N-532-4. N-533-1, N-566-2, N-624, N-648-1, N-722, N-729-1 (If applicable)

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 repairlreplacement activities and evaluations supporting the completion of UlR33 (refueling outage number)

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 ernployed 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 knowledge 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 repair/replacement 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.

Conlmissions WI 929625 A,I,N National Board, State, Province, and Endorsements Date I

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1 1

Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Examination Category and ltem Number Item Description Evaluation Description Spring hanger setting did not match drawing. Setting F-A I Spring Hanger was evaluated as being within allowable tolerance, F1.20C no further actions were required.

Loose nut noted on angle iron. Determined to be a F-A I non-load bearing spreader bar and did not affect the Rigid Support F1.20A ability of the support to carry its intended load.

Tightened for long term health and good practice.

Table 2 Abstract of RepairIReplacement Activities Required for Continued Service Repair1 Replacement Date Plan Code Class Item Description Description of Work Completed Number Feedwater Pipe Replacement of section of 2 Segment - 121191201 1 2010-0104 pipe and elbow due to FAC ICSEB09-043 Component 3 Coo'ing Water Weld repair of eroded areas 612412011 201 1-0027 Heat Exchanger Flange