NRC 2010-0028, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R30

Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R30

ML100570447
Person / Time
Site:	Point Beach
Issue date:	02/26/2010
From:	Jim Costedio Nextera Energy, Point Beach
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2010-0028
Download: ML100570447 (5)

Text

February 26,201 0 NRC 2010-0028 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 Summarv Report for Point Beach Nuclear Plant Refueling Outaae U2R30 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 U2R30 that concluded on December 6,2009. 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) and ASME Code Case N-532-4.

The enclosure to this letter contains the summary report, which includes 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 2.

Very truly yours, NextEra Energy Point Beach, LLC James Costedio VLicensing Manager Enclosure 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 2 OAR-I, 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 U2R30 Outage Class MC and CC IS1 Examination Plant NextEra Energy Resources Point Beach Nuclear Plant. 6610 Nuclear Road. Two Rivers. Wisconsin 54241 Unit No. 2 Commercial Service Date October 1972 Refueling Outage No. U2R30 (If applicable)

Current Inspection Interval Second (lst, 2nd, 3rd, 4th, 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: January 16,2009 / Revision 1. Class CC: January 23.2009 /Revision 1 Edition and Addenda of Section XI applicable to repairs/replacements 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 repairlreplacement activities and evaluations supporting the completion of U2R30 (refueling outage number) conform to the requirements of Section XI.

Signed @!DL < R/hL wnerh>wner's 7& Z Designee, Title containment programs Coordinator Date 6 2 - ZI -/d 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 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.

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

Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Examination Category and Item Number ItemDescription Evaluation Description The difference in volume of corrosion protection medium removed and replaced for tendon 01-203 was 6.39%. This is within the acceptance criteria of 10% stated in IWL-3221.4 and L-B L2'40 Tendon does not exceed the 10 CFR 50.55a(b)(2)(viii)(D) reporting criteria of lo%, but meets the reportable condition of exceeding 5% stated in Regulatory Guide I.35, paragraph 7.4.f.

The difference in volume of corrosion protection medium removed and replaced for tendon V-239 was 8.42%. This is within the acceptance criteria of 10% stated in IWL-3221.4 and L-B L2'40 Tendon V-239 does not exceed the 10 CFR 50.55a(b)(2)(viii)(D) reporting criteria of lo%, but meets the reportable condition of exceeding 5% stated in Regulatory Guide 1.35, paragraph 7.4.f.

In accordance with 10 CFR 50.55a(b)(2)(viii)(D), any tendon grease leakage detected during general visual examination of Multiple the containment surface is to be reported. Minor grease L-A/ L 1 . l l Tendons 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 Containment the containment surface is to be reported. Grease staining from L-A/ L l . l l Concrete 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 IWE-351I.3, material loss in a local area projected to exceed 10% of nominal wall thickness prior to the next examination must be documented. Material loss of liner plate at core hole CH-04 was measured at 10% and is projected to exceed 10% at the next examination. Corrosion caused by wetting some time in

'Ontainment the past is likely responsible for the material loss. Previous Liner 'late at E-C / E4.12 evaluations have accepted conditions where the nominal 0.25 Hole inch liner plate was reduced to 0.1 70 inches (32% loss). The CH-04 indicated and projected loss is less than previously accepted material loss. Expansion joints in the concrete floor above the liner plate have been filled with caulk to prevent additional moisture intrusion. CH-04 and other core drill holes will continue to be monitored for material loss due to corrosion in accordance with IWE-2420(b).

Table 2 Abstract of RepairIReplacementActivities Required for Continued Service Repair/

Replacement Date Plan Code Class Item Description Description of Work Completed Number None - - - -