NRC 2004-0092, Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R28

Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R28

ML042600420
Person / Time
Site:	Point Beach
Issue date:	09/07/2004
From:	Koehl D Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2004-0092
Download: ML042600420 (13)

Text

Committed to NuclearExcelle Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC September 7, 2004 NRC 2004-0092 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 Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R28 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 U1 R28 that concluded on June 8, 2004. 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.

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.

Enclosure I 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, the first 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. Koehl Site Vice-President, Point Beach Nuclear Plant Nuclear Management Company, LLC Enclosures (2) -ND41 6590 Nuclear Road

• Two Rivers, Wisconsin 54241 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 5 pages follow

FORM OAR- I OWNER'S ACTIVITY REPORT Report Number U1R28 Outage Class 1.2. and 3 ISI Examination 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. I Commercial Service Date December 21. 1970 Refueling OutageNo. UIR28 (If applicable)

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

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

Edition and Addcnda of Section XI applicable to the inspection plan 1998 Edition 2000 Addenda Date and Revision of inspection plan Julv 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. NIA Expiration Date NIA awpricable)

Signed W i o -. Date /-Z x*

_ _ H Owner or Owner's Designee, Title  ; Oz 1 a #or g f f (

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 Global Services of Hartford, Connecticut have inspected the items described in this Owner's Activity Report, during the period October 20, 2002 to June 8, 2004, 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 in' or property damage or loss of any kind arising from the connected with this inspection.

/A Commissions WI 247972

'< tor's gilrAture National Board, State, Province, and Endorsements Date

Table I Abstract of Examinations and Tests Total Total Total Total Examinations Examinations Examinations Examinations Credited (%) to Examination Required for Credited for this Credited (%) Datc for the Category the Interval Period for the Period Interval Remarks B-A 8 0.5 6 6 Deferral permissible B-B 7 2 29 29 B-D 25 5 20 20 B-F . .. ... --- --- Part of Risk-Informed ISI Program. see Examination Category R-A B-G-1 6 2 33 33 B-G-2 14 4 29 29 B-J ... .-- ... . of Risk-Informed ISI Program, see Examination Category R-A f'Part B-K 7 I 14 14 . .

B-l.-I 3 0 0 0 Deferred to the end of the interval B-L-2 1xamination I 0 see remarks 000Eaie 0 Examined only nyiifdisassembled for maintenance, repair, or volumctric xmnto iasmldfrmitnne ear rvlmti B-M-I I 0 0 0 Scheduled for the third interval B-M-2 4 0 0 0 Examined only if disassembled for maintenance, repair, or volumetric examination B-N-I 3 I 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.o 2 0 0 0 Deferred to the end of the interval B-P 7 2 100 29 Pressure tests. See Note 2.

B-Q ... --- --- ... Steam Generator tubing is examined in accordance with plant Technical Specifications C-A 9 2 22 22 C-B 18 6 33 33 C-C 12 2 17 17 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 I 0 0 0 Scheduled for the third interval C-li 51 13 76 25 Pressure tests. Sec Note 3.

D-A 7 3 43 43 D-B 21 3 43 14 Pressure tests. See Note 3.

F-A 135 61 45 45 R-A 150 35 23 23 Includes class I and 2 piping welds I . 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 Found During Scheduled Flaw Characterization Section XI Examination or Test Examination Category Item No. Item Description (IWA-3300) (Yes or No)

F-A Fl.30B SWP-PSR003 N/A Yes Pipe Support F-A F.1.30B HB-19-H262 N/A Yes Pipe Support' F-A Fl.30A HipB-19-HI N/A Yes-

_ _ __ _ __ __ __ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _P ip e _S u pp o rt'_ _ _ _ _ _ _ _ _ _ _ _

F-A l Fl.30A l HB-19-Hi24 N/A Yes F-A F1.30A . Rigid Support N/A Yes F-A F1.30B SFC-PSA-015-3 N/A Yes

____Rigid Support F-A Fl.30A SFC-PSR-016-3 N/A Yes Rigid SupportN SI-150IR-2-S842 F-A F1.20A SI-150IR-3-S842 N/A Yes

________________G uide _ _ _ _ _ _ _ _ _ _ _ _ _ _

F-A Fl .30A HB-19-H37 N/A Yes.

Pipe Hanger F-A F1.30B HB-19-H230 N/A Yes PipeSupport _ _ _ _ _ _ _ _ _ _ _ _ _ _

F-A Fl.30A HB-19-HI8 N/A Yes Pipe Hanger F-A Fl.30A igiB-19-Hd 7 N/A Yes PipeHanger _ _ _ _ _ _ _ _ _ _ _ _

HB- 19-H8 F-A FI1.3013 JB3-2-H5A N/A Yes

_________________Pipe _Hanger_ _ _ _ _ _ _ _ _ _ _ _ _

F-A F1.30A HB13-9-H51 N/A Yes

_ __ __ _ __ __ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _R igid S uppo rt_ _ _ _ _ _ _ _ _ _ _

Flaw or Relevant Condition' Found During Scheduled Flaw Characterization Section XI Examination or Test Examination Category Item No. Item Description (IWA-3300) (Yes or No)

F-A FI.20C AC-601R-2-HI N/A Yes Dual Spring Hanger F-A FI.20C AC-601R-2-H2 N/A Yes Spring Hanger F-A F1.20B SI-60IR-2-H4 N/A Yes Rigid Support F-A F1 .20C AC-60 1R-6-H21 N/A Yes Spring Hanger F-A F1.20C AC-601R-6-H20 N/A Yes Spring Hanger__ _ _ _ _ _ _ _ _ _

F-A F1.IOB 39-14-PR N/A Yes Rigid Support__ _ _ _ _ _ _ _ _

F-A FI.20A 44-28-PSSB N/A Yes I;-A___F1.IOB _ Rigid Support N/A Yes F-A FLIlOB CH-2501R-4-R73 N/A Yes

_____________ ~Rigid Support_ _ _ _ _ _ _ _ _ _

F-A F1.20C EBp-9-19 N/A Yes F-A F1.IOC RC-2501R-Z-RC2 N/A Yes Spring Hanger

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 2 Replacement Valve IMS-2016 Replace trim assembly No 5/2/2004 2004-0020 I Relaceent Component Support Replacement CI--250R-6-7PRC Replace missing nut No 4/23/2004 2004-0021 Un-named 2 Ruplacement Component Support Replace missing nut No 4/23/2004 2004-0022 ICV-200B Accident Recire Fan 3 Replacement IHX-15B motor Replace studs and nuts No 4/2312004 2004-0025 cooler end bell I Corrective Measure Reactor Vessel Remove linear indications No See note 2004-0032

_________N ozzle 26 by flap ping _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

I Repair Reactor Vessel Remove and replace No See note 2004-0035 C__________________ N ozzle 26 CRD w eld S ee n o 20t e 0 4 - 0 038 1 Corrective Measure Reactor Vessel Remove linear indications No See note 2004-0038

_ __ __ __ __ _ _ _ _ _ _N ozzle 26 by grinding _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I__ _ __ _ _ I__

Note: The repairs on Reactor Vessel Nozzle 26 are completed, however, the Work Orders are still open pending the final approval of relief requests MR 02-18-1 and MR 02-18-02, which contain an alternative repair methodology. NRC verbal approval was received on May 26, 2004.

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

-FORM OAR-I OWNER'S ACTIVITY REPORT Report Number U I R28 Outage Class MC ISI IWE Examinations Owner Nuclear Management Comnany. 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. I Commercial Service Date December 21. 1970 Refueling Outage No. UIR28 (If applicable)

Current Inspection Interval First (Ist, 2nd, 3rd, 4th, other)

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

Edition and Addenda of Section XI applicable to the inspection plan 1992 Edition 1992 Addenda Date and Revision of inspection plan August 24.2001 /rev. 0 Edition and Addenda of Section Xl applicable to repairs and replacements, if different than the inspection plan - a. . .9 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 Xl.

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

Signed n or IL ,

Owner or Owner's Designee, Title 601OI4b&Djate @ 2.i° 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 Global Services of Hartford, Connecticut have inspected the items described in this Owner's Activity Report, during the period July 1,2002 to May XX, 2004, 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 Xl.

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 r nal injury or p erty damage or loss of any kind arising from the connected with this inspection.

Commissioas WI 247972 71? f tors Signature National Board, State, Province, and Endorsements Date __ __ __ __

Table 1 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 Pcriod Interval Remarks The number of liner plates examined, expressed as a percentage of exams, does not correlate to the containment surface area examined, expressed as a 74% percentage of surface area. This is because the containment liner consists of E-A 157 24 13% 74different 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 E-B N/A N/A N/A N/A requirements specified in ASME Section Xi Code are not required.

Examination Category E-A requirements are considered sufficient to identify

_ any degraded conditions for containment penetration welds.

E-C 34 0 0 67% Approximately 100 % are examined each period The examinations percentages do not meet the IWE-2412-1 inspection program B examinations percentages because of the use of the authorized Relief Request # ERR-1. Exam category E-D, Item Number E5.10 and E5.20 E-D 75 01 01 41% were examined in accordance with ERR-I starting after September 14,2001.

The use of this ERR was authorized by the NRC in the safety evaluation for relief requests for the containment inspection program. (Dated September 14, 2001)

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

The examinations percentages do not meet the IWE-2412-1 inspection program B examinations percentages because of the use of the authorized Relief Request # ERR-6. Exam category E-G, Item Number E8.20 was E-G 38 01 0 1 21% examined in accordance with ERR-6 starting after September 14, 2001. The use of this ERR was authorized by the NRC in the safety evaluation for relief requests for the containment inspection program. (Dated September 14, 2001)

This is covered by PBNP's Containment Leakage Rate Testing Program (CLRT), which implements 10 CFR 50 Appendix J. All Examination E-P See remarks See remarks See remarks See remarks Category E-P pressure 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 All percentages are rounded to the nearest 1%.

Table 2 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Flaw or Relevant Condition w .i Found During Scheduled Flaw Characterization Section XI Examination or Test Examination Category Item No. Item Description (1WA-3300) (Yes or No)

None I None None None None

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

Code Repair, Replacement, Examination or Test Date Replacement Class or Corrective Measure Item Description Description of Work (Yes or No) Completed Plan Number Replace flange and MC Replacement Containment ICPP-56 attached valve due to No 5/27/2004 2004-0048 Penetration Flange incorrect flange installed (WO 0213478)

Containment 1CPP-56 Replace bolting MC Replacement Penetration Flange (WO 0213478) No 5/27/2004 2004-0006

_______ ______b o ltin g _ _ _ _ _ _

lVNPSR-03212 & Replace Valve with Mc Replacement IVNPSE-03244 Flange No 6/2/2004 2004-0009

__ ______ _ _ ___ ___ ___ ___ __ (W O 0400322,0400324)_ _ _ _ _ _