NRC 2005-0132, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R27

Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R27

ML052920029
Person / Time
Site:	Point Beach
Issue date:	10/11/2005
From:	Koehl D Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2005-0132, U2R27
Download: ML052920029 (12)

Text

99M NMC Committed to NuldearExcel Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC October 11, 2005 NRC 2005-0132 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 License No. DPR-27 Filing of Owner's Inservice Inspection SummarV Report for Point Beach Nuclear Plant Refueling Outage U2R27 In accordance with 10 CFR 50.55a, Nuclear Management Company, LLC, (NMC) is submitting Inservice Inspection Summary Reports for inspections conducted prior to and during the Point Beach Nuclear Plant (PBNP) refueling outage U2R27 that concluded on July 10, 2005. 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 Xl of the American Society of Mechanical Engineers (ASME)

Boiler and Pressure Vessel Code and ASME Code Case N-532-1. The IWE Class MC and IWL Class CC reports are submitted pursuant to the requirements of subarticle IWA-6240 of the 1992 Edition with addenda through 1992 of ASME Section Xl and ASME Code Case N-532-1. to this letter contains the summary report, which includes Form OAR-1, the Owner's Activity Report for Inservice Inspections, for the Class 1, 2, and 3 components and a separate Form OAR-1 for Class MC and CC components. The report includes the second outage of the first period of the fourth ten-year interval for Class 1, 2, and 3 systems, and the second outage of the third period of the first ten-year interval for Class MC at PBNP Unit 1.

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

Dennis L. Koehi Site Vice-President, Point Beach Nuclear Plant Nuclear Management Company, LLC a> FG Enclosures (2) 6610 Nuclear Road . Two Rivers, Wisconsin 54241-9516 Telephone: 920.755.2321

Document Control Desk Page 2 cc: Administrator, Region 111, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW Mike Verhagen, State of Wisconsin

ENCLOSURE I OAR-1, OWNER'S ACTIVITY REPORT FOR INSERVICE INSPECTION, FOR CLASS 1, 2, AND 3 COMPONENTS 4 pages follow

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number U2R27 Outage Class 1. 2. and 3 ISI Examination Owner Nuclear Mana3rement Cnmnanv- 700 First Street. Hudsnn Wisconin 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 Fourth (Ist, 2nd, 3rd, 4th, other)

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

Edition and Addenda of Section Xl applicable to the inspection plan 1998 Edition 2000 Addenda Date and Revision of inspection plan July 1.2004 / Revision 3 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan Same CERTIFICATE OF CONFORMANCE 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 Authorization No. N/A Expiration Date N/A (If applicable) ffiG/0)

Signed 7 1SI Coordinator Date 9I Owner or Owner's Designee, Title (

CERTIFICATE OF INSERVICE INSPECTION 1,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 i ry or property damage or loss of any kind arising from the connected with this inspection.

A Commissions WI 247972

~ ctoeis i ture National Board, State, Province, and Endorsements Date q-zq- Zeombi

Table I Abstract of Examinations and Tests Total Total Total Total Examinations Examinations Examinations Examinations Credited (%) to Examination Required for Credited for this Credited (%) Date for the Category the Interval Period for the Period Interval Remarks B-A 5 0.5 10 10 Deferral permissible, number of welds reduced by one due to head replacement during U2R27 B-B 7 2 29 29 B-D 25 4 16 16 B-F -- - - - Part of Risk-Informed 1S1 Program, see Examination Category R-A B-G-I 8 2 25 25 B-G-2 16 6 38 38 B-J - --- - --- Part of Risk-informed 1SI Program, see Examination Category R-A B-K 6 3 50 50 B-L-I 3 0 0 0 Deferred to the end of the interval B-L-2 --- - - Examined only if disassembled for maintenance, repair, or volumetric examination B-M-I I 0 0 0 Scheduled for the third period B-M-2 - - --- Examined only if disassembled for maintenance, repair, or volumetric examination B-N-I 3 1 33 33 Accessible portions of the vessel internal surface B-N-2 4 0 0 0 Deferred to the end of the interval B-N-3 I 0 0 0 Deferred to the end of the interval B-0 2 0 0 0 New welds installed due to RPV head replacement B-P 7 2 29 29 Pressure tests. See note 2.

B-Q - ... - --- Steam Generator tubing is examined in accordance with plant Technical Spccifications C-A 6 2 33 33 C-B 7 0 0 0 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

C-C 13 __ _ _ 8 8 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

C-D - --- - --- There are no class 2 bolts greater than 2" at PBNP C-F-I _ Part of Risk-Informed ISI Program, see Examination Category R-A C-F Part of Risk-Informed 11 Program, see Examination Category R-A C-G I 0 0 0 Scheduled for the third period C-H - 54 17 94 31 Pressure tests. See Note 3.

D-A 6 2 33 33 D-B 6 1 50 17 Pressure tests. See Note 3.

F-A 117 32 27 27 R-A 138 23 17 17 Includes class I and 2 piping welds

1. All percentages are rounded to the nearest 1%.

2. Pressure tests are conducted each outage with one extra test performed during the third period.

3. Pressure tests are conducted once each period, so each test will be conducted three times over the interval.

4. 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 Flw Ch Found During Scheduled Examination aw aractenzation Section XI Examination or Test Category Item No. Item Description (IWA-3300) (Yes or No)

F-A Pump 2P-15A Support Safety Injection Pump Support N/A Yes F-A SI-301R-1-S873 Rigid Support N/A Yes F-A SI-301R-1-2H9 Spring Hanger N/A Yes F-A SI-33 Rigid Support N/A Yes F-A SI-34 Rigid Support N/A Yes F-A AC-601R-6-2H114 Spring Hanger N/A Yes F-A AC-601R-3-2H8 Spring Hanger N/A Yes F-A HB-19-2R181 Restraint N/A Yes F-A 29-PRD Rigid Restraint N/A Yes F-A SI-601R-2-2H4 Spring Hanger N/A Yes F-A SI-601R-2-R2334 Rigid Support N/A Yes F-A RC-2501R-14-2HI Dual Spring Hanger N/A Yes N/A Pipe AC 0601R-02 Pipe Surface Planer No F-A HS-2501R-49 Snubber N/A No F-A AC-601R-3-2H6 Spring Hanger N/A Yes

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

Code or Corrective Examination or Test Date Replacement Class Measure Item Description Description of Work (Yes or No) Completed Plan Number 3 Replacement SW-307 Replace valve No 5/4/2005 2005-0016 3 Replacement SW-315 Replace valve No 5/4/2005 2005-0015 3 Replacement Piping HB-19 Replace piping No 5/25/2005 2005-0026 I. I I

ENCLOSURE 2 OAR-1, OWNER'S ACTIVITY REPORT FOR INSERVICE INSPECTION, FOR CLASS MC and CC COMPONENTS 4 pages follow

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number U2R27 Outace Class MC ISI 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 (Ist, 2nd, 3rd, 4th, other)

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

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

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

Ricmpd OM / WF & I W- Proram Fninener Date Cl _ l L _ 9 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 ersonal in or property damage or loss of any kind arising from the connected with this inspection.

Commissions WI 247972

/ tor's Signature National Board, State, Province, and Endorsements Date 140i of

Table I Abstract of Examinations and Tests Total Total Total Total Examinations Examinations Examinations Examinations Credited (%) to Examination Required for Credited for this Credited (%) Date for the Category the Interval Period for the Period Interval Remarks B-A 5 0.5 10 10 Deferral permissible, number of welds reduced by one due to head replacement during U2R27 B-B 7 2 29 29 _

B-D 25 4 16 16 B-F - -- --- -- Part of Risk-informed ISI Program, see Examination Category R-A B-G-I 8 2 25 25 B-G-2 16 6 38 38 B-1 --- __ _-- -- Part of Risk-Informed ISI Program, see Examination Category R-A B-K 6 3 50 50 B-L-I 3 0 0 0 Deferred to the end ofthe interval B-L-2 ... --- - --- Examined only if disassembled formaintenance, repair, or volumetric examination B-M-I 1 0 0 0 Scheduled for the third period B-M-2 - - - -- Examined only if disassembled for maintenance, repair, or volumetric examination B-N-I 3 1 33 33 Accessible portions of the wssel internal surface B-N-2 4 0 0 0 Deferred to the end of the interval B-N-3 I 0 0 0 Deferred to the end of the interval B-O 2 0 0 0 Newv welds installed due to RPV head replacement B-P 7 2 29 29 Pressure tests. See note 2 B-Q -- -- - - Steam Generator tubing is examined in accordance with plant Technical Specifications C-A 6 2 33 33 C-B 7 0 0 0 C-C 13 _ 8 8 C-D --- -- --- - There are no class 2 bolts greater than 2" at PBNP C-F-I - _ Part of Risk-Informed ISI Program, see Examination Category R-A C-F-2 --- --- - -- Part of Risk-Informed ISI Program, see Examination Category R-A C-G 1 0 0 0 Scheduled for the third period C-H 54 17 94 31 Pressure tests. See Note 3.

D-A 6 2 33 33 D-B 6 1 50 17 Pressure tests. See Note 3.

F-A 117 32 27 27 R-A 138 23 17 17 Includes class 1 and 2 piping welds

1. All percentages are rounded to the nearest 1%.

2. Pressure tests are conducted each outage with one extra test performed during the third period.

3- Pressure tests are conducted once each period, so each test will be conducted three times over the interval.

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

F-A Pump 2P-15A Support Safety Injection Pump Support N/A Yes F-A SI-301R-1-S873 Rigid Support N/A Yes F-A SI-301R-1-2H9 Spring Hanger N/A Yes F-A SI-33 Rigid Support N/A Yes F-A SI-34 Rigid Support N/A Yes F-A AC-601R-6-2H14 Spring Hanger N/A Yes F-A AC-601R-3-2H8 Spring Hanger N/A Yes F-A HB-19-2R181 Restraint N/A Yes F-A 29-PRD Rigid Restraint N/A Yes F-A SI-601R-2-2H4 Spring Hanger N/A Yes F-A SI-601R-2-R2334 Rigid Support N/A Yes F-A RC-2501R-14-2H1 Dual Spring Hanger N/A Yes N/A Pipe AC 060IR-02 Pipe Surface Planer No F-A HS-2501R-49 Snubber N/A No F-A AC-601R-3-2H6 Spring Hanger N/A Yes

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

Code or Corrective Examination or Test Date Replacement Class Measure Item Description Description of Work (Yes or No) Completed Plan Number 3 Replacement SW-307 Replace valve No 5/4/2005 2005-0016 3 Replacement SW-315 Replace valve No 5/4/2005 2005-0015 3 Replacement Piping HB-19 Replace piping No 5/25/2005 2005-0026