NRC 2007-0048, Correction to Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U2R27

Correction to Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U2R27

ML071690207
Person / Time
Site:	Point Beach
Issue date:	06/15/2007
From:	Koehl D Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2007-0048
Download: ML071690207 (7)

Text

Point Beach Nuclear Plant Committed to Nuclear Excellence Operated by Nuclear Management Company, LLC June 15,2007 NRC 2007-0048 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 Correction to lnservice lns~ectionSummarv R e ~ o rfor t Point Beach Nuclear Plant Refuelina Outaae U2R27

Reference:

(1) NMC to NRC Letter dated October 11,2005, (NRC 2005-0132),Filing of Owner's lnservice lnspection Summary Report for Point Beach Nuclear Plant Refueling Outage U2R27 (ML052920029)

On October 11,2005, Nuclear Management Company, LLC, submitted lnservice lnspection Summary reports for inspections conducted prior to and during the Point Beach Nuclear Plant refueling outage U2R27 that concluded on July 10, 2005, in accordance with Reference 1 above.

It has subsequently been identified that an incorrect set of data was submitted for Enclosure 2 of that report, OAR-1 Owner's Activity Report for lnservice lnspection for Class MC and CC Components. This has been entered into the site Corrective Action Program.

The enclosure to this letter provides a corrected OAR-1 Owner's Activity Report for lnservice lnspection for Class MC and CC Components.

This letter contains no new commitments and no revisions to existing commitments.

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Dennis L. Koehl Site Vice-President, Point Beach Nuclear Plant Nuclear Management Company, LLC 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 6610 Nuclear Road Two Rivers, Wisconsin 54241-9516 Telephone: 920.755.2321

ENCLOSURE CORRECTION TO INSERVICE INSPECTION

SUMMARY

REPORT FOR POINT BEACH NUCLEAR PLANT REFUELING OUTAGE U2R27 5 pages follow

FORM OAR- 1 OWNER'S ACTIVITY REPORT Report Number U2R27 Outage Class MC IS1 IWE Examinations Owner Nuclear Management Company, 700 First Street, Hudson, Wisconsin 54016 (Name and Address of Owner)

Plant Point Beach Nuclear Plant. 6590 Nuclear Road. Two Rivers, Wisconsin 54241 (Name and Address of Plant)

Unit No. 2 Commercial Service Date October 1, 1972 Refueling Outage No. U2R27 (If applicable)

Current Inspection Interval First (1st. 2nd, 3rd, 4th, other)

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

Edition and Addenda of Section XI applicable to the inspection plan 1992 Edition 1992 Addenda Date and Revision of inspection plan February 7,2005 1 rev. I Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan Same CERTIFICATE OF CONFORMANCE 1 certify that the statements made in the Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report conform to the requirements of Section XI.

Certificate of Authorization No. Nl A Expiration Date N/A (If applicable)

Signed /291 I IWE & IWL Proeram Engineer Date 6-13 -@7 Owner or Owner's Designee, Title 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 HSBCT of Hartford, Connecticut, have inspected the items described in this Owner's Activity Report, during the period November 22, 2003 to July 10, 2005, 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 examinations, tests, repairs, replacements, evaluations, and corrective measures 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 the connected with this inspection.

Commissions W1929625 National Board, State, Province, and Endorsements Date ~//>/b v 7

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Table I Abstract of Examinations and Tests Total Total Total Total Examinations Examinations Examinations Examinations Credited (%) Remarks Exam Required for Credited for this Credited (%) to Date for the Category the Interval Period for the Period Interval The number of liner plates examined, expressed as a percentage of exams, does not correlate to the containment surface area examined, expressed as a percentage of surface area. This is because the containment liner consists E-A 157 42 39%11 98%'~~ of different size liner plates; therefore, surface area will vary from plate to plate. The percentages reflect the surface area of the plates that were examined and not the percentages of the number of examinations performed.

Containment Penetration Welds, Examination Category E-B examination requirements specified in ASME Section XI Code are not E-B NIA NIA NIA NIA required. Examination Category E-A requirements are considered sufficient to identify any degraded conditions for containment penetration welds.

E-C 26 0 0 200%'~ 100 % is examined each period.

The exam percentages do not meet the IWE-2412-1 inspection program B examinations percents, because of the use of the authorized Relief Request ERR-1. Exam category E-D, Item Number E5.10 and E5.20 were E-D 68 o1 o1 45%'~~ examined in accordance with ERR-1 starting after September 14, 2001. The use of this ERR was authorized by the NRC in the safety evaluation dated September 14, 2001, for relief requests for the containment inspection program.

Pressure Retaining Dissimilar Metal Welds, Examination Category E-F E-F NIA NIA NIA NIA requirements specified in ASME Section XI Code are not required and shall not be implemented by PBNP.

Table 1 Abstract of Examinations and Tests (continued)

The exam percentages do not meet the IWE-2412-1 inspection program B examinations percents because of the use of the authorized Relief Request ERR-6. Exam Category E-G, Item Number E8.20 was examined in E-G 26 1 3%' 38%1>3 accordance with ERRB starting after September 14,2001. The use of this ERR was authorized by the NRC in the safety evaluation dated September 14, 2001, for relief requests for the containment inspection program.

This is covered by PBNP's Containment Leakage Rate Testing Program (CLRT), which implements 10 CFR 50 Appendix J. All See See Examination Category E-P pressure E-P See remarks See remarks remarks remarks retaining components are tested in accordance with 10 CFR 50 Appendix J, Option B and scheduled as directed by the CLRT program.

Refer to the Remarks column.

Category E-C (Augmented examinations) examinations are performed once a period, which means all of the exams will be performed three (3) times over a 10-year interval.

3 ~ 1 1percentages are rounded to the nearest 1%.

Table 2 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Flaw or Relevant Condition Found During Scheduled Section XI Examination Flaw Characterization Examination or Test Category Item No. Item Description (IWA-3300) (Yes or No)

None None None None None

Table 3 Abstract of Repairs, Replacements, or Corrective Measures Required for Continued Service Flaw or Relevant Condition Found During Scheduled Repair, Section XI Repair1 Replacement, Examination or Replacement Code or Corrective Item Description Test Date Plan Class Measure Description of Work (Yes or No) Completed Number MC None None None None None None