NRC 2007-0059, Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R30

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Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R30
ML072180594
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 08/06/2007
From: Koehl D
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2007-0059
Download: ML072180594 (7)


Text

Point Beach Nuclear Plant Cornmined to Nuclear Excellence Operated by Nuclear Management Company, LLC August 6,2007 NRC 2007-0059 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 License No. DPR-24 Filing of Owner's lnservice Inspection Summarv Report for Point Beach Nuclear Plant Refueling Outage U1R30 Nuclear Management Company, LLC (NMC), is submitting the lnservice lnspection Summary Report for inspections conducted prior to and during the Point Beach Nuclear Plant (PBNP) refueling outage U1R30 that concluded on May 7, 2007. The enclosed Class I , 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-532-1.

For Class MC and CC components, no Code-required examinations were performed and no new indications of component degradation, as described in 10 CFR 50.55a, were observed between the end of U1R29 and the end of U1R30. Subsequently, there is no new information to report. The OAR-1 report for U1R29 submitted via NMC letter dated February 22, 2006, accurately summarizes owner activities for Class MC and CC components to date. of this letter contains the summary report, which includes Form OAR-1, the "Owner's Activity Report," for lnservice Inspections, for the Class 1, 2 and 3 components.

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

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 1 POINT BEACH NUCLEAR PLANT, UNIT 1 OAR -1, OWNER'S ACTIVITY REPORT FOR INSERVICE INSPECTION, FOR CLASS 1 , 2 AND 3 COMPONENTS 5 pages follow

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number UlR30 Outage Class 1.2. and 3 IS1 Examination Owner Nuclear Management Company, 700 First Street, Hudson, Wisconsin 54016 (Name and Address of Owner)

Plant Point Beach Nuclear Plant, 6610 Nuclear Road, Two Rivers, Wisconsin 54241 (Name and Address of Plant)

Unit No. 1 Commercial Service Date December 2 1, 1970 Refueling Outage No. UlR30 (If applicable)

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

Current Inspection Period Second (Ist, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the inspection plan 1998 Edition 2000 Addenda Date and Revision of inspection plan February 17,2006 1 Revision 5 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan Same I 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 Author' Expiration Date NIA 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, during the period November 24, 2005 to May 7, 2007 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 operty damage or loss of any kind arising from the connected with this inspection.

Commissions WI 929625 National Board, State, Province, and Endorsements

Table 1 Abstract of Examinations and Tests Total Total Total Total Examinations Exam Examinations Examinations Examinations Credited Remarks Category Required for Credited for Credited (%)

to Date for the Interval this Period for the Period the B-A 7 0 0 0 Partial deferral permissible B-B 7 2 28.5 57.1 B-D 25 8 32 52


------ ------ ------ Part of the Risk-Informed B-F Program, see Category R-A B-G- 1 7 2 28.5 57.1 B-G-2 12 2 16.6 58.3


------ ------ ------ Part of the Risk-Informed B-J Program, see Category R-A B-K 6 0 0 33.3 Deferred to the end of the B-L-1 3 0 0 0 interval Examined only if disassembled B-L-2 1 0 0 0 for maintenance, repair, or volumetric examination B-M-1 1 0 0 0 Scheduled for third period Examined only if disassembled B-M-2 4 0 0 0 for maintenance, repair, or volumetric examination Accessible portions of the B-N-1 3 1 33.3 66.6 vessel internal surface 10-year exam scheduled B-N-2 4 0 0 0 U1R31 10-year exam scheduled B-N-3 1 0 0 0 U1R31 B-0 1 0 0 0 Class 1 pressure test performed every refueling B-P 8 2 25 50 outage plus 1 end of interval exam for extended boundaries


------ ------ ------ Examined in accordance with B-Q plant Technical Specifications C-A 9 2 22.2 44.4 C-B 18 6 33.3 66.6 C-C 11 4 36.3 54.5


------ ------ ------ No Class 2 bolts greater than C-D 2" at PBNP

Table 1 Abstract of Examinations and Tests (continued)

Total Total Total Total Examinations Exam Examinations Examinations Examinations Credited (%) Remarks Category Required for Credited for Credited (%)

to Date for the Interval this Period for the Period the


------ ------ ------ Part of the Risk-Informed C-F-1 Program, see Category R-A


------ ------ ------ Part of the Risk-Informed C-F-2 Program, see Category R-A C-G 1 0 0 0 Scheduled for Third Period All pressure tests performed once per period. One test was C-H 50 12 24 56 split in the second period resulting in 5 instead of 6 tests D-A 8 3 37.5 75 All pressure tests are D-B 21 3 14.2 47.6 performed once per period F-A 150 45 30 71.3 Includes Class 1 and 2 piping R-A 139 53 38.1 63.3 welds Notes:

1. All numbers are truncated in calculating percentages.
2. Limited examinations will be submitted to the NRC for relief in accordance with 10 CFR 50.55a.

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

B Steam Generator N/A N/A N/A No Hot Leg Manway R-A R1.20-4 Valve Body N/A No F-A F1.I0s PORV Snubber N/A Yes F-A F1.40B SG B Ring Girder N/A Yes F-A F1.20C Spring Hanger N/A Yes F-A F1.308 Rigid Support N/A Yes F-A F1.20C Spring Hanger NIA Yes F-A F1.20C Spring Support NIA Yes F-A F1.20C Spring Support N/A Yes F-A F1.20B Rigid Support NIA Yes Augmented IN 91-05 B SI Accumulator N/A No F-A F1.20A Rigid Support N/A Yes F-A F1.20C Dual Spring Support N/A Yes F-A F1.20A Rigid Support N/A Yes

Table 3 Abstract of Repairs, Replacements or Corrective Measures Required for Continued Service Flaw or Relevant Condition Repair, Found During Repair/

Code Replacement ltem Description Scheduled Date Replacement Class or Corrective Description of Work Section XI Completed Plan Measure Examination or Number Test (Yes or No)

Valve Replace 3 Replacement NO 4/02/2006 2006-0005 SW-00322 Valve Valve Replace RH-00714B NO 4/30/2007 2007-0012 Bolting Replace Flow Element 4/22/2007 2007-0015 2 Replacement plug and Yes FE-00601 seal weld Valve Replace NO 411612007 2007-0033 SI-00871B Bolting Valve Replace SW-00015B NO 4/29/2007 2007-0036 Bolting Piping Flange Replace 1 NO 5/4/2007 2007-0038 1C V - 3 0 8 ~ Bolting Support Replace Replacement NO 4/28/2007 2007-0039 AC152N10-H69 Bolting