NRC 2003-0008, Filing of Owners'S Inservice Inspection Summary Report

Filing of Owners'S Inservice Inspection Summary Report

ML030310363
Person / Time
Site:	Point Beach
Issue date:	01/17/2003
From:	Cayia A Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2003-0008
Download: ML030310363 (105)

Text

NM- c Committed to NuclearExcellen b Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC NRC 2003-0008 January 17, 2003 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 POINT BEACH NUCLEAR PLANT DOCKET 50-266 FILING OF OWNER'S INSERVICE INSPECTION

SUMMARY

REPORT Enclosed is the Owner's Inservice Inspection Summary Report, submitted in accordance with ASME Section XI, Subsection IWA-6230. This summary report includes the Owner's Report for Inservice Inspections (Form NIS-1). This is required by IWA-6000 of the ASME Section XI as follows:

"* Class MC: 1992 Edition with Addenda through 1992

"* Class 1, 2, and 3:1998 Edition with 2000 Addenda Also included are the Owner's Reports for Repair or Replacements (Form NIS-2).

The information contained in the enclosed report reflects Inservice Inspection activities conducted since the previous submittal. This includes the first outage of the first period of the fourth ten-year interval for Class 1, 2 and 3, and the first outage of the second period of the first ten-year interval for Class MC at Point Beach Nuclear Plant Unit 1.

Sit ice-Pre ent cc gional Administrator, USNRC, Region Ill oject Manager, Point Beach Plant, USNRC, NRR P

NRC Resident Inspector - Point Beach Nuclear Plant PSCW Mike Verhagen, State of Wisconsin Attachments 6590 Nuclear Road 0 Two Rivers, Wisconsin 54241 Telephone. 920.755 2321

NIS-1 INSERVICE INSPECTION

SUMMARY

REPORT FOR CLASS MC U1R27 Nuclear Management Company, LLC 700 First Street Hudson, Wisconsin 54016 Point Beach Nuclear Plant Unit 1 6610 Nuclear Road Two Rivers, Wisconsin 54241 Commercial Operating Date: December 21, 1970 Report Date: January 16, 2003 Written by: Date: I--/3 -p,3 Reviewed by: Y*.*-&'S4'.

• Date: /

Approved by:a Date:

FORM NIS-1 OWVNER'S REPORT FOR INSERVICE INSPECTIONS

1. Owner: Nuclear Management Company, 700 First Street Hudson, Wisconsin 54016

2. Plant: Point Beach Nuclear Plant, 6610 Nuclear Road, Two Rivers, Wisconsin 54241

3. Plant Unit: 1 4. Owner Certificate of Authorization: Docket 50-266

5. Commercial Service Date: December 21, 1970 6. National Board Number for Unit: N/A

7. Components Inspected Manufacturer or State or Component or Manufacturer or Installer Serial Province National Board Appurtenance Installer No. No. No.

Containment Bechtel N/A U009971 N/A Bechtel Group, Inc.

2280 Bates Avenue Concord, CA 94520

8. Examination Dates: September 10, 2001 to October 17, 2002

9. Inspection Period Identification: Second Period

10. Inspection Interval Identification: First Interval

11. Applicable Edition of Section XI: 1992 Addenda 1992

12. Date / Revision of Inspection Plan: August 24, 2001 / rev. 0

13. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current Interval.

An Inservice Examination of containment metallic liner Class MC components of Nuclear Management Company's (NMC) Point Beach Nuclear Plant (PBNP) Unit 1 was performed during the time period of September 10, 2001 to October 17, 2002. This is the second period of the first ten-year interval.

Page 2 of 19

The containment liner was examined in accordance with the IWE Containment Inspection Program, which was prepared in accordance with the requirements of the American Society of Mechanical Engineers (ASME)Section XI, 1992 Edition, 1992 Addenda.

No Code Cases were used in the performance of examinations, tests, and repairs and replacements.

Visual examinations were conducted in accordance with ASME Section XI. We Energies, Nuclear Management Company, and Lambert MacGill Thomas, Inc. personnel performed the examinations.

See Attachment 1 for examinations.

No repair or replacements were performed on Class MC components during this IWE report period.

All examinations required for the preservice (implementation) period have been completed . This meets the requirements of Inspection Program B of ASME Section XI with approximately 61 %

examination completed for this Interval and all augmented examinations completed for this period.

14. Abstract of Conditions Noted:

Mechanical Penetrations Several mechanical penetrations were noted to have failed coatings.

Containment Liner Plates Several liner plates contained areas of coating chips and scrapes.

Keyway liner plates Keyway liner plates were noted to have discoloration and flaking of the coating.

Core Drilled Hole Nine often core drilled holes were noted to have indications.

Flange Bolting Nine of ten core drilled holes were noted to have indications.

Page 3 of 19

15. Abstract of Corrective Measures Recommended and Taken.

Mechanical Penetrations Volumetric examinations were completed for affected mechanical penetrations. Surface coatings were reapplied with required visual examinations completed. Four of the mechanical penetrations had readings of base metal loss greater than 10% nominal thickness. As found conditions evaluated as acceptable. Affected mechanical penetrations are on augmented examination schedule.

Containment Liner Plates Several liner plates had indication of coatings failure with no degradation to base metal. These plates will receive touch up painting next refueling outage.

Keyway Liner Plates The keyway liner plates are designated as augmented. No significant degradation was noted since previous period examinations. No action required with remaining augmented examinations scheduled for next period.

Core Drilled Holes Visual and volumetric examinations were completed for core drilled holes at 8 ft. elevation and the keyway area. These exams are for augmented components and no significant degradation was noted since previous period exams. No action required with remaining augmented examinations scheduled for next period. ICH-10 core drilled hole in the keyway area, was installed during previous period and corrosion rate will be monitored each refueling outage until stabilized due to the closeness to acceptability as dispositioned in previous period.

Flange Bolting The bolting had surface corrosion only and was evaluated as acceptable. Adequate torque and Appendix J testing confirmed evaluation as acceptable. Bolting will be replaced next refueling outage.

Page 4 of 19

We 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) corrective measures taken conform to the rules of the ASME Code,Section XI.

Certificate of Authorization No. (if applicable): NRC Docket 50-266 Expiration Date: N/A Date: J5- 03 9- Signed: Nuclear Management Co., LLC by ,

Owner 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 Hartford Connecticut, have inspected the components described in this Owner's Report during the period September 10, 2001 to October 17, 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

a_. /- &__&.,_*__, Commissions WI 100128 Inspector's Sigature National Board, State, Province, and Endorsements Date ,,t. ,**, ioo Page 5 of 19

Nuclear Management Company Commercial Service Date 12/21/70 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unit I National Board Number for Unit N/A Attachment 1 Unit 1 Second Period IWE Containment Inspection Program U1R27 Examination Summary Page 6 of 19

Commercial Service Date: 12/21/70 Nuclear Management Company Docket 50-266 700 First Street Hudson, Wisconsin 54016 Pt Beach Unit I National Board Number for Unit N/A U1R27 Examination Summary Component Category Item Exam Type NDE Data Sheet Completed RRM # IDR Notes date 08-Oct-02 RP-IB, ORT-12 1C-3 E-G E8 20 Torque E4 11 VT-t 02U1-760E001 20-Sep-02 1 CH-01 E-C E-C E4 12 UT 02UI-114EOOI 20-Sep-02 02UI-760E002 20-Sep-02 02UI-E015 Previously evaluated OIUI-E004 1 CH-02 E-C E4 11 VT-I E4 12 UT 02Ul-114E002 20-Sep-02 02UI-E015 Previously evaluated OIUI-E004 E-C 02U1-760E003 20-Sep-02 02UI-E009 Previously evaluated OIUI-E004 1CH-03 E-C E4 11 VT-I E412 UT 02U-I-14E003 20-Sep-02 02UI-E009 Previously evaluated O1UI-E004 E-C 02U1-760E004 20-Sep-02 02U1-EOIO Previously evaluated 01UI-E005 1 CH-04 E-C E-4 11 VT-I E4 12 UT 02U1-114E004 20-Sep-02 02UI-EOIO Previously evaluated OIUI-E005 E-C 02UI-760E005 20-Sep-02 02UI-EOII Previously evaluated 01UI-E004 1CH-05 E-C E4 11 VT-I E-C E3412 UT 02UI-114E005 20-Sep-02 02UI-EOII Previously evaluated 0UI-E004 02UI-760E006 20-Sep-02 02U1-E012 Previously evaluated 0UI-E004 1CH-06 E-C E4 11 VT-I 13412 UT 02UI- 114E006 20-Sep-02 02UI-E012 Previously evaluated O U1-E004 E-C Page 7 of 19

Nuclear Management Company Commercial Service Date 12/21/70 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unit I National Board Number for Unit N/A U1R27 Examination Summary Component Category Item Exam Type NDE Data Sheet Completed RRM # IDR Notes date 02UI-760E007 20-Sep-02 02UI-E013 Previously evaluated 01UI-E004 1CH-07 E-C E4.1I VT-I E-C E4 12 UT 02U1-114E007 20-Sep-02 02UI-E013 Previously evaluated 0UI-E004 E4 11 VT-I 02Ul-760E008 17-Sep-02 02UI-E006 1 CH-08 E-C E--C E4.12 UT 02Ul-l 14E008 17-Sep-02 02UI-E006 E-D E5.30 VT-3 02U1-760E011 20-Sep-02 02UI-E006 I

02UI-760E009 17-Sep-02 02UI-EO07 1 CH-09 E-C E4 11 VT-I E-C E4 12 UT 02UI-114E008 17-Sep-02 02U1-E007 E-D E5.30 VT-3 02Ul-760E012 20-Sep-02 02UI-E007 02Ul-760E010 17-Sep-02 02U1-E008 Previously evaluated 0lUI-E002 ICH-10 El-C E4 11 VT-I E.-C E4 12 UT 02Ul-1 14E008 17-Sep-02 02UI-EO08 Previously evaluated OIUI-E002 E-D E5 30 VT-3 02Ul-760EO13 20-Sep-02 02UI-EO08 Previously evaluated 01UI-E002 02UI-760E014 26-Sep-02 1 CP-025 E-A El.12 VT-3 VT-3 02Ul-760EO15 26-Sep-02 1CP-026 E-A E1.12 ICP-027 E-A El.12 VT-3 02Ul-760E016 26-Sep-02 Page 8 of 19

Commeicial Service Date- 12/21/70 Nuclear Management Company Docket 50-266 700 First Street Pt Beach Unit I Hudson, Wisconsin 54016 National Board Number for Unit N/A U 1R27 Examination Summary Component Category Item Exam Type NDE Data Sheet Completed RRM # IDR Notes date El 12 VT-3 02UI-760E017 26-Sep-02 1CP-028 E-A 1CP-029 E-A El 12 VT-3 02UI-760E018 26-Sep-02 El 12 VT-3 02UI-760E019 26-Sep-02 1CP-030 E-A ICP-031 E-A El 12 VT-3 02UI-760E020 26-Sep-02 E-A El 12 VT-3 02UI-760E021 26-Sep-02 ICP-032 1CP-033 E-A El.12 VT-3 02UI-760E022 26-Sep-02 E1.12 VT-3 02U1-760E023 26-Sep-02 ICP-034 E-A EI.12 VT-3 02UI-760E024 26-Sep-02 1CP-035 E-A 1CP-036 E-A El 12 VT-3 02UI-760E025 26-Sep-02 Page 9 of 19

Commercial Service Date: 12/21/70 Nuclear Management Company Docket 50-266 700 First Street Pt Beach Unit 1 Hudson, Wisconsin 54016 National Board Number for Unit N/A U1R27 Examination Summary Category Item Exam Type NDE Data Sheet Completed RRM # IDR Notes Component date El 12 VT-3 02U1-760E026 26-Sep-02 1CP-037 E-A E1.12 VT-3 02Ul-760E027 26-Sep-02 ICP-038 E-A El.12 VT-3 02UI-760E028 26-Sep-02 1CP-039 E-A E-A El 12 VT-3 02UI-760E029 26-Sep-02 1CP-040 1l.12 VT-3 02U1-760E030 26-Sep-02 1CP-041 E-A E-A El.12 VT-3 02UI-760E031 26-Sep-02 1CP-042 El 12 VT-3 02UI-760E032 26-Sep-02 ICP-043 E-A El.12 VT-3 02UI-760E033 26-Sep-02 ICP-044 E-A E-A EI.12 VT-3 02U1-760E034 26-Sep-02 1CP-045 El 12 VT-3 02UI-760E035 26-Sep-02 1CP-046 E-A Page 10 of 19

Commercial Service Date 12/21/70 Nuclear Management Company Docket 50-266 700 First Street Pt Beach Unit I Hudson, Wisconsin 54016 National Board Number for Unit. N/A U 1R27 Examination Summary Component Category Item Exam Type NDE Data Sheet Completed RRM # IDR Notes date I CP-047 E-A E1.12 VT-3 02U1-760E036 26-Sep-02 ICP-048 E-A EI.12 VT-3 02U1-760E037 26-Sep-02 El.12 VT-3 02U1-760E038 25-Sep-02 02UI-E014 1CP-049 E-A El3.12 VT-3 02UI-760E039 25-Sep-02 02U1-E014 1CP-050 E-A 1 CP-051 E-A El.12 VT-3 02U1-760E040 01-Oct-02 El.12 VT-3 02U1-760E041 25-Sep-02 02U1-E014 1CP-052 E-A El 12 VT-3 02UI-760E042 25-Sep-02 02U1-E014 ICP-053 E-A El.12 VT-3 02U1-760E043 25-Sep-02 02U1-E014 1CP-054 E-A VT-3 02U1-760E044 25-Sep-02 02UI-E014 1CP-055 E-A El.12 E-A El 12 VT-3 02U1-760E045 26-Sep-02 02U1-E014 I CP-056 Page 11 of 19

Commercial Service Date 12/21/70 Nuclear Management Company Docket 50-266 700 First Street Pt Beach Unit I Hudson, Wisconsin 54016 National Board Number for Unit. N/A U 1 R27 Examination Summary Category Item Exam Type NDE Data Sheet Completed RRM # IDR Notes Component date 02Ul-760E046 26-Sep-02 02UI-E014 ICP-057 E-A El 12 VT-3 02UI-760E047 26-Sep-02 02U1-E014 1CP-058 E-A E1.12 VT-3 02Ul-760E048 26-Sep-02 02UI-E014 ICP-059 E-A El.12 VT-3 VT-3 02Ul-760E049 25-Sep-02 02UI-EO14 1CP-060 E-A E1.12 E-.12 VT-3 02Ul-760E050 26-Sep-02 ICP-061 E-A 02Ul-760E051 25-Sep-02 02U1-E014 ICP-062 E-A E-1.12 VT-3 E!.12 VT-3 02UI-760E052 25-Sep-02 ICP-063 E-A VT-3 02U1-760E053 25-Sep-02 02U1-E014 1CP-064 E-A El.12 El 12 VT-3 02Ul-760E054 25-Sep-02 1CP-065 E-A 25 02 E1.12 VT-3 02UI-760E055 -Sep-I CP-066 E-A Page 12 of 19

Nuclear Management Company Commercial Service Date 12/21/70 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unit I National Board Number for Unit: N/A U 1 R27 Examination Summary Component Category Item Exam Type NDE Data Sheet Completed RRM # IDR Notes date El 12 VT-3 02Ul-760E056 25-Sep-02 02U1-E014 1CP-067 E-A El 12 VT-3 02Ul-760E057 26-Sep-02 02UI-E014 1CP-068 E-A E1.12 VT-3 02UI-760E058 26-Sep-02 02U1-E014 1CP-069 E-A E1.12 VT-3 02U1-760E059 26-Sep-02 02UI-E014 1CP-070 E-A E13.12 VT-3 02U1-760E060 26-Sep-02 02UI-1E014 1CP-071 E-A El.12 VT-3 02UI-760E061 26-Sep-02 02UI-E014 1CP-072 E-A E1.12 VT-3 02Ul-760E062 19-Sep-02 1CP-073 E-A E1.12 VT-3 02U1-760E063 19-Sep-02 1CP-074 E-A E-1.12 VT-3 02U1-760E64 19-Sep-02 1CP-075 E-A 1CP-076 E-A El 12 VT-3 02U1-760E065 19-Sep-02 Page 13 of 19

Nuclear Management Company Commercial Service Date 12/21/70 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unit I National Board Number for Unit N/A U1R27 Examination Summary Component Category Item Exam Type NDE Data Sheet Completed RRM # IDR Notes date ICP-077 E-A El.12 VT-3 02UI-760E066 19-Sep-02 1CP-078 E-A E1.12 VT-3 02U1-760E067 19-Sep-02 1CP-079 E-A E11.12 VT-3 02U1-760E068 19-Sep-02 ICP-080 E-A E1.12 VT-3 02U1-760E069 19-Sep-02 1CP-081 E-A El 12 VT-3 02UI-760E070 19-Sep-02 ICP-082 E-A EI.12 VT-3 02UI-760E071 19-Sep-02 1CP-083 E-A El 12 VT-3 02UI-760E072 19-Sep-02 1CP-084 E-A El.12 VT-3 02UI-760E073 19-Sep-02 ICP-130 E-C E4 11 VT-I 02UI-760E074 18-Sep-02 CR 99-2873, Supplemental, O0UI E001 E-C E4 12 UT 02UI-1l14E011 18-Sep-02 CR99-2873, Supplemental, O0UI EOO1 Page 14 of 19

Commercial Service l)ate 12/21/70 Nuclear Management Company 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unt National Board Number for Unit: N/A U 1R27 Examination Summary Category Item Exam Type NDE Data Sheet Completed RRM # IDR Notes Component date 02U1-760E075 17-Sep-02 02UI-E001 Previously evaluated 01 U1-E001 ICP-133 E-C E4.11 VT-1 UT 02Ul -I 14E008 17-Sep-02 02UI-E001 Previously evaluated 01 UI-E001 E-C E4.12 02UI-760E076 17-Sep-02 02UI-E002 Previously evaluated 01UI-E00I ICP-134 E-C E4 11 VT-I E4.12 UT 02UI- 114E008 17-Sep-02 02UI-E002 Previously evaluated 01UI-E001 E-C UT 02UI -114E008 17-Sep-02 02UI-E003 (gnd) Previously evaluated O1U1 ICP-135 E001 E4 11 VT-I 02UI-760E077 17-Sep-02 02UI-E003 Previously evaluated O0UI-E001 E-C 02 Previously evaluated 0lUl-E001 E-C E4 12 UT 02Ui-1 14E008 17-Sep- 02UI-E003 02 02U0-E004 VT-I 02UI-760E078 17-Sep-ICP-136 E4.12 UT CANCELLED E-C 7 2 02UI-E005 VT-I 02U1-760E079 1 -Sep-0 ICP-137 02 Previously evaluated O0UI-E001 E-C E4 12 UT 02UI-114E008 17-Sep- 02U1-E005 02U1-760E080 17-Sep-02 Previously evaluated 01U I-E001 ICP-138 E-C E4.11 VT-I 2

2-C 1412 UT 02U1 -I 14E008  ! 7 -Sep-0 Previously evaluated O0UI-E001 Page 15 of 19

Commercial Service Date 12/21/70 Nuclear Management Company Docket 50-266 700 First Street Pt. Beach Unit I Hudson, Wisconsin 54016 National Board Number for Unit N/A U1R27 Examination Summary Category Item Exam Type NDE Data Sheet Completed RRM # IDR Notes Component date 02UI-I 14E008 17-Sep-02 (gnd) Previously evaluated 01UI ICP-139 UT E001 VT-I 02UI-760E081 17-Sep-02 Previously evaluated O0UI-E001 E-C E4.11 UT 02UI-114E008 17-Sep-02 Previously evaluated O0UI-EOO1 E-C E4 12 02UI-760E082 29-Sep-02 Previously evaluated 99UI-E002 ICPP-35 E-C E4.11 VT-I 2 Previously evaluated 99U1-E002 E-C E4 12 UT 02UI-114E021 29-Sep-0 02UI-760E083 30-Sep-02 02UI-E017 Previously evaluated 99U1-EO03 1CPP-36 E-C E4 11 VT-I UT 02UI-114E022 30-Sep-02 02UI-E017 Previously evaluated 99U1-EO03 E-C E4 12 02UI-760E084 03-Oct-02 Previously evaluated 99U1-E004 1CPP-37 E-C E4.11 VT-I UT 02UI-114E023 03-Oct-02 Previously evaluated 99U1-E004 E-C E4.12 02UI-760E085 03-Oct-02 Previously evaluated 99U1-E005 1CPP-38 E-C E34.11 VT-I UT 02U1-114E024 03-Oct-02 Previously evaluated 99UI -E005 E-C E4.12 02U1-760E086 29-Sep-02 Previously evaluated 99U0l-E006 1CPP-39 E-C E4 11 VT-1 UT 02U1-1 14E025 29-Sep-02 Previously evaluated 99UI-E006 E-C E4 12 02UI-760E087 03-Oct-02 Previously evaluated 99UI -E007 ICPP-40 E-C E4 11 VT-I UT 02UI-114E026 03-Oct-02 Previously evaluated 99U1 -E007 E-C E4.12 Page 16 of 19

Commercial Service Date 12/21/70 Nuclear Management Company Docket 50-266 700 First Street Pt Beach Unit I Hudson, Wisconsin 54016 National Board Number for Unit: N/A U1R27 Examination Summary Category Item Exam Type NDE Data Sheet Completed RRM # IDR Notes Component date 02UI-760E088 29-Sep-02 Previously evaluated 99Ul-E008 ICPP-43 E-C E4 11 VT-I UT 02Ul-114E027 29-Sep-02 Previously evaluated 99Ul-E008 E-C E4 12 02UI-760E089 30-Sep-02 Previously evaluated 99U1 -E009 ICPP-44 E-C E4 It VT-I E4 12 UT 02UI-114E028 30-Sep-02 Previously evaluated 99Ul-E009 E-C 02U1-760E090 01 -Oct-02 Previously evaluated 99U 1-E010 1CPP-45 E-C E4 11 VT-I E4 12 UT 02U1-114E029 0 1-Oct-02 Previously evaluated 99Ul-EOIO E-C 02UI-760E091 30-Sep-02 Previously evaluated 99UI-EOI I 1CPP-46 E-C E4.11 VT-I UT 02U-1. 14E030 30-Sep-02 Previously evaluated 99UI-EOI I E-C E4.12 02Ul-760E092 29-Sep-02 Previously evaluated 99Ul-E012 1 CPP-47 E-C E4.11 VT-I UT 02U I-114E031 29-Sep-02 Previously evaluated 99UI-E012 E-C E4 12 02UI-760E093 03-Oct-02 Previously evaluated 99Ul-E013 ICPP-48 E-C E4 11 VT-I E4 12 UT 02U1-114E032 03-Oct-02 Previously evaluated 99Ul-E013 E-C 02UI-760E094 03-Oct-02 02Ul-E019 Previously evaluated 99Ul-E014 1 CPP-50 E-C E4.11 VT-I UT 02UI-114E033 03-Oct-02 02UI-E019 Previously evaluated 99Ul-E014 E-C E4 12 Page 17 of 19

Nuclear Management Company Commercial Service Date 12/21/70 700 rirst Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unit I National Board Number for Unit: N/A U IR27 Examination Summary Component Category Item Exam Type NDE Data Sheet Completed RRM # IDR Notes date 02U1-760E095 03-Oct-02 02UI -E020 Previously evaluated 99UI -E015 1 CPP-51 E-C E4.1 I VT-I E-C E4 12 UT 02UI- 14E034 03-Oct-02 02UI-E020 Previously evaluated 99UI-E015 02UI-760E098 25-Sep-02 1CPP-56 E-A El.12 VT-3 E-G E8 10 VT-I Bolting 02UI-760E096 07-Oct-02 02UI-E021 WO 0206995 for TM 02-030 E-G E8 20 Torque 07-Oct-02 WO 0206995 for TM 02-030 2 02 EI.12 VT-3 02U1-760E099 5-Sep-1CPP-57 E-A El.12 VT-3 02UI-760EI00 25-Sep-02 1 CPP-58 E-A E-A E11.12 VT-3 02U1-760E101 25-Sep-02 1CPP-V-I E-A E1.12 VT-3 02U1-760EI102 25-Sep-02 1CPP-V-2 VT-I 02U1-760E103 01 -Oct-02 Supplemental directed by 01 Ul-L004 IQ-15 UT 02U1-I 14E035 0 1-Oct-02 Supplemental directed by 01 U1-L004 VT-3 02U1-760E104 30-Sep-02 02U1-E016 1Z-529 E-D E5 30 Page 18 of 19

Nuclear Management Company Commercial Service Date 12/21/70 700 First Street Docket 50-266 Hludson, Wisconsin 54016 Pt Beach Unit I National Board Number for Unit N/A U 1 R27 Examination Summary Component Category Item Exam Type NDE Data Sheet Completed RRM # IDR Notes date UI- PB 02U1-762E003 30-Sep-02 Reference Bars CONTAINMENT E-A El 11 GV 02UI-762E002 02-Oct-02 Inside Containment E-A El 11 GV 02UI-762E001 02-Oct-02 02UI-EOI8 Outside Containment Page 19 of 19

NIS-1 Inservice Inspection Summary Report for Class 1 and 2 Components U1R27 Nuclear Management Company, LLC 700 First Street Hudson, Wisconsin 54016 Point Beach Nuclear Plant Unit 1 6610 Nuclear Road Two Rivers, Wisconsin 54241 Commercial Service Date: December 21, 1970 Report Date: January 7, 2003 Written by: 2*..7g*.*, ~~- 7 Date: 3 Reviewed by: Sd *. * . Date: j-,t .'_

i01 Approved by: Date:

I

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS

1. Owner: Nuclear Management Company LLC 700 First Street Hudson, Wisconsin 54016

2. Plant: Point Beach Nuclear Plant, 6610 Nuclear Road, Two Rivers, Wisconsin 54241

3. Plant Unit: 1

4. Owner Certificate of Authorization: N/A

5. Commercial Service Date: December 21, 1970

6. National Board Number for Unit: NBO138

7. Components Inspected Manufacturer or State or Component or Manufacturer or Installer Serial Province National Board Appurtenance Installer No. No. No.

Reactor Pressure Babcock and Wilcox 610-0115 U010615 NB-0138 Vessel Pressurizer Westinghouse 16A6256-1 U010618 Unknown Reactor Pump A Coolant Westinghouse 1-618J-741G01 N/A N/A Regenerative Heat 3996A3-1/ NB-0349 Exchanger Sentry 3996-3E N/A NB-0350 NB-0351 Accumulator T-34A Delta Southern Co. 41035-67-1 U010611 N/A Accumulator T-34B Delta Southern Co. 41035-67-2 U010612 N/A Class 1 Piping Westinghouse/ N/A N/A N/A Bechtel Class 2 Piping Westinghouse/ N/A N/A N/A Bechtel N/A N/A N/A

8. Examination Dates: July 1, 2002 to 10/19/2002

9. Inspection Period Identification: First Period from July 1, 2002 to June 30, 2005

10. Inspection Interval Identification: Fourth Interval from July 1, 2002 to June 30, 2012

11. Applicable Editions of Section XI: 1998 Edition, 2000 Addenda

12. Date/Revision of Inspection Plan: March 11, 2002, revision 0 Page 1 of 5

Nuclear Management Company LLC Commercial Service Date 12/21/70 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unit I National Board Number for Unit N/A

13. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for the Inspection Plan:

An Inservice Examination of selected Class 1 and 2 components and piping systems of Nuclear Management Company's (NMC) Point Beach Nuclear Plant (PBNP) Unit 1 was performed during the time period of July 1, 2002 to October 19, 2002, which included the Unit I Refueling 27 outage (UIR27). This is the first outage of the first period of the fourth ten-year interval.

The components and piping systems examined were selected in accordance with the Fourth Ten Year Inservice Inspection Program, which was prepared in accordance with the requirements of the American Society of Mechanical Engineers (ASME)Section XI, 1998 Edition with addenda through 2000, and applicable relief requests. In addition, augmented examinations were performed on the Safety Injection Accumulators and Reactor Pressure Vessel in accordance with various commitments.

Snubber functional testing and visual examinations were conducted in accordance with the OM Code, 1987 Edition with OMa-1988. We Energies, NMC, and LMT personnel performed the examinations. See Attachment 2 for test results and the ISI Examination Tables for examination results.

Manual ultrasonic, visual, and liquid penetrant non-destructive techniques were used to examine components, piping, and their supports. We Energies and NMC personnel, supported by examiners supplied by LMT, performed the examinations. See Attachment 3 for the listing on Class I and 2 components examined.

Manual Ultrasonic examinations were performed on the water level nozzles of the Safety Injection Accumulators to address concerns addressed in Information Notice 91-05. These examinations revealed indications on the inside surface of five nozzles. All remaining nozzles were examined for similar indications as a conservative measure.

System Pressure testing was conducted by the plant to ASME Section XI and applicable Plant Procedures. We Energies, NMC, and LMT personnel performed the examinations. Minor leakage was noted at mechanical connections. See the attached tables for a summary of examinations.

Repairs and replacements were performed on Class 1 and 2 Section XI components since the previous outage. The NIS-2 reports are included with this report. NIS-2 reports are also filed at the plant in the permanent record system.

14. Abstract of Results of Examinations and Tests:

See Attachment I for numbers and percentages of examinations or tests completed.

Every indication noted was accepted as-is by evaluation, however, the indications were addressed by Work Orders to return the component to their design configuration where needed.

For leakage at mechanical connections, Work Orders were initiated to correct the leakage. On valve stem leakage, operations or engineering personnel adjusted the packing so leakage was stopped or slowed down to an acceptable limit. Leakage collection systems were operational in each case.

Page 2 of 5

Nuclear Management Company LLC Commercial Service Date 12/21/70 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unit 1 National Board Number for Unit N/A Class 1 Systems Reactor Pressure Vessel Volumetric and visual examinations were performed on various portions of the RPV, including vessel welds, the upper head, and flange bolting. Remote ultrasonic examinations were performed on the CRD to head welds. No reportable indications were noted. Direct visual examinations were performed on four thermal sleeves and the outside surface of the head around the nozzle penetrations. No relevant indications were noted.

The interior of the reactor vessel was examined using remote visual equipment on accessible areas to the extent practical. No relevant indications were noted.

Pressurizer Visual examinations were performed on the manway bolting. One bolt was noted as having galled threads. The bolt was replaced. No other recordable indications were noted.

Steam Generators Visual examinations were performed on manway bolting (removed from the vessel) due to boric acid residue being noted. No indications were noted.

Reactor Coolant Pumps Visual examinations were performed on the seal bolting. No reportable indications were noted.

Accumulators Manual Ultrasonic examinations were performed on the water level nozzles of the Safety Injection Accumulators to address concerns addressed in Information Notice 91-05. These examinations revealed indications on the inside surface of five of the nozzles. The nozzle portion protruding from the accumulators were removed from service, the inside surface was examined for any additional indications, and the piping was reattached to the nozzle remnants.

All remaining nozzles, including 3/4" and 1", were examined for similar indications as a conservative measure.

Regenerative Heat Exchanger Volumetric, surface, and visual examinations were performed on the shell welds, nozzle welds and inside radius sections, welded attachments, and support of the regenerative heat exchanger. Insufficient thread engagement was noted on the support. This was evaluated as being acceptable. No other indications were noted.

Auxiliary Coolant Volumetric examinations were performed on selected Auxiliary Coolant welds. No recordable indications were noted.

Reactor Coolant Volumetric examinations were performed on selected Reactor Coolant welds. No recordable indications were noted. Visual examinations were performed on piping flange bolting No recordable indications were noted.

Page 3 of 5

Nuclear Management Company LLC Commercial Service Date. 12/21/70 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unit 1 National Board Number for Unit N/A Safety Injection Volumetric examinations were performed on selected Safety Injection welds. No recordable indications were noted. Visual examinations were performed on selected supports. No relevant indications were noted. Baseline visual examinations were performed on the bolting of several valves. No reportable indications were found.

Pressure Tests Pressure tests were conducted on Class 1 systems. These tests met the requirements for periodic Pressure Testing. Several areas of leakage were noted at mechanical joints. These were addressed through plant procedures. No through wall leakage was noted.

Class 2 Regenerative Heat Exchanger Volumetric examinations were performed on the shell welds of the regenerative heat exchanger. No reportable indications were noted.

Main Steam System Volumetric examinations were performed on selected Main Steam welds. Geometric indications from the root were noted. No other indications were noted.

Visual examinations were performed on selected supports. One support was noted as having a snap ring partially out of its groove. The support was evaluated as being acceptable and the snap ring was reinstalled per design.

Pressure Tests Pressure tests were conducted on Class 2 systems. These tests met the requirements for periodic Pressure Testing. Several areas of leakage were noted at mechanical joints. These were addressed through plant procedures. No through wall leakage was noted.

15. Abstract of Corrective Measures.

On the Safety Injection Accumulators, five of the eight water level sensor nozzles had indications noted on the inside surface. All of these nozzles were removed and the piping was rewelded to the accumulators, removing all traces of the indications.

Several supports had indications noted on them that were evaluated as being acceptable as-is.

In each case, Work Orders were written to return the supports to their design condition where required.

The visual examinations on the pressurizer bolting showed one bolt with galled threads. The bolt was replaced.

The water level nozzles on the Safety Injection Accumulators showed indications on the inside surface of five nozzles. The nozzle portion protruding from the accumulators were removed from service, the inside surface was examined for any additional indications. The piping was reattached to the remaining portion of the nozzle.

Page 4 of 5

Nuclear Management Company LLC Commercial Service Date 12/21/70 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unit I National Board Number for Unit N/A We 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) corrective measures taken conform to the rules of the ASME Code,Section XI.

Certificate of Authorization No. (if applicable): N/A Expiration Date: N/A Date: // -/;2500 Signed: Nuclear Management Co. by .

"Owner 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 of Wisconsin and employed by Hartford Steam Boiler of Hartford, Connecticut, have inspected the components described in this Owner's Report during the period July 1, 2002 to October 19, 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.

By Signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

140 0 & t Aý Commissions WI 100128 Inspector's Signature" National Board, State, Province, and Endorsements Date Th-'. , *cz9z3 Page 5 of 5

Nuclear Management Company LLC Commercial Service Date. 12/21/70 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unit 1 National Board Number for Unit N/A Attachment 1 Status of Examinations for the Period/Interval

Nuclear Management Company LLC Commercial Service Date 12/23/70 Docket 50-266 700 First Street Pt. Beach Unit I Hudson, Wisconsin 54016 National Board Number for Unit: N/A 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 8 0 0 0 Partial deferral permissible B-B 7 2 29 29 B-D 25 4 16 16 B-F .....-

--- --- Part of Risk-informed ISI Program, see Category R-A B-G-I 6 2 33 33 B-G-2 14 4 29 29 B-J --- --- --- --- Part of Risk-Informed ISI Program, see Category R-A B-K 8 1 13 13 B-L-1 3 0 0 0 Deferred to the end of the interval Examined only if disassembled for maintenance, repair, or volumetric B-L-2 00 examination B-M-I 1 0 0 0 Scheduled for the third interval B-M-2 4 0 0 0 Examinations will be performed when valves are opened 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 1 0 0 0 Deferred to the end of the interval B-0 2 0 0 0 Deferred to the end of the interval B-P 7 1 14 14 Pressure tests cross class boundaries B-Q --- .--- --- Examined in accordance with plant Technical Specifications C-A 9 2 22 22 C-B 6 0 0 0 C-C 12 0 0 0 C-D 0 0 0 0 There are no class 2 bolts greater than 2" at PBNP C-F-I --- --- -- ... Part of Risk-Informed ISI Program, see Category R-A C-F-2 --- -- --- --- Part of Risk-Informed ISI Program, see Category R-A C-H 57 7 12 12 Pressure tests cross class boundaries C-G  ! 0 0 0 Scheduled for the third interval F-A 106 7 7 7 Class I and 2 component supports R-A 124 18 15 15 Includes class l and 2 piping welds Note: all numbers rounded to the nearest 1%.

Nuclear Management Company LLC Commercial Service Date 12/21/70 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unit I National Board Number for Unit. N/A Attachment 2 Snubber Functional Testing The following snubbers were functionally tested:

Equipment System Manufacturer Code Iso. No. Results-Date Number Class HS-5 MS Anker-Holth 2 ISI-1201 SAT - 9/17/2002 HS-601R-90 RC Grinnell N/A 0870 005-001 SH. 1 SAT - 9/17/2002 HS-2501R-51 RC Grinnell N/A 0870 005-001 SH. 1 SAT - 9/17/2002 HS-16 SI Grinnell 2 P-128 SAT - 9/16/2002 HS-11 FW Grinnell 2 ISI-1245 SAT - 9/19/2002 HS-19 RC Grinnell 1 ISI-1101 SAT - 9/15/2002 a

Nuclear Management Company LLC Commercial Service Date 12/21170 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unit I National Board Number for Unit N/A Attachment 3 Class 1 and 2 Examination Tables

Nuclear Management Company LLC Commercial Service Date- 12/21/70 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unit I National Board Number for Unit N/A Examination Results Guide DATE: 01/09/03 POINT BEACH NUCLEAR PLANT UNIT 1 PAGE: 00 (A) INSERVICE INSPECTION RESULTS

SUMMARY

(C)

INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)

CLASS 1 CPAB COMPONENTS (B)

Reactor Pressure Vessel (D)

N I 0

-STATUS G N G T R S E H Remarks

SUMMARY

EXAMINATION AREA CATGY EXAM E I 0 E **Calibration Block**

NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET C G MR WO Number System ID - R-1, Drawing No. ISI-1101 (E) 001000 RPV-14-683 (G) (J) B-A C UT 5 168-0001 - - - X 9/19/2002 - UT complete.

(F) Shell to Flange (H) (K) B1.21 (L) UT 11 168-0001 - - - X Geometric Reflectors from UT 18 168-0001 - - - X the flange radius.

(M) (N) (P) ** 5-PTB**

WO 9931092 (R)

(A) Date the report table was printed (B) Specific outage and report information (Note: Class "P" components are for pressure tests. Many of the systems cross class boundary's, requiring a multiple class designation.)

(C) Page number (D) System description (E) System / ISI drawing number (F) Summary number of the record (unique, for computer tracking only)

(G) Component or Component Support identification (H) Component or Component Support Description (J) ASME Code category (K) ASME Code item number (L) Shows status of examination C - Code completed L - Limited code complete P - Partial examination A - Augmented examination B - Baseline (Preservice exam)

R - Removed from service E - Expanded (additional) sample examination (Other codes may be used as necessary)

(M) NDE methods (N) Data sheet number (P) Types of indications found (R) Remarks, Calibration Block, and Work Order Number

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 1 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS 1 CLPABER COMPONENTS Reactor Pressure Vessel N I 0

- STATUS N 0 G T R S H REMARKS E

SUMMARY

EXAMINATION AREA CATEGY EXAM E I X O

E ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C G R WO NUMBER System ID - R-1, Drawing No. ISI-1101 001000 RPV-14-683 B-A P UT 5 168-0001 X 9/19/2002 - UT complete.

UT 11 168-0001 X Shell to Flange B1.30 Geometric reflectors from the UT 18 168-0001 X flange radius sections noted.

Examined from the seal surface only. **5-PTB**

WO 9950774 004100 RPV Interior Surface B-N-i C VT-3 756-0001 X 9/24/2002 - VT-3 complete. No B13. 10 VT-3 754-0029 X recordable indications.

Vessel Interior VT-3 754-0030 X Surfaces X Examined accessible areas of the VT-3 754-0031 X upper internals and vessel VT-3 754-0032 interior. 10/6/2002 - Baseline VT-3 complete on new thermal sleeves. Examined sleeves 1, 31, 32, and 33.

WO 9950777 004220 HS-19 A VT-i 750-0015 X 9/15/2002 - VT-3 complete.

Snubber VT-3 754-0039 X Rusty u-bolts noted. 10/2/2002 VT-3 754-0040 X

- VT-i on conduit and VT-3 on IDR 7-014 snubber complete. No recordable AR CA 026407 indications. WO 9945448 was initial work order.

WO 0212688

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 2 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS 1 CLPABER COMIONENTS Reactor Pressure Vessel Bolting and CRD Housings NI 0 F

STATUS ON UT R SE H REMARKS

SUMMARY

EXAMINATION AREA CATEGY EXAM ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO Mj"THOD PROCEDURE C a 2 PR WO NUMBER System ID - R-i, Drawing No. ISI-1103 004500 CRD Housings B-O A SUR 451-0003 - - - X 9/25/2002 - Augmented PT Housings 1 thru 49 BI4.10 IDR 7-005 - - - - complete. One acceptable linear indication noted.

WO N/A S................................................................................................................................................................................................

004700 RPV Closure Head Nuts B-U-1 P VT-i 750-0001 X - - - 9/22/2002 - VT-i complete. No 1 thru 48 B6.10 recordable indications.

Examined nuts 1 through 16.

WO 9950772 S................................................................................................................................................................................................

004800 RPV Closure Head Studs B-0-1 P UT 0 169-0001 X - - - 9/22/2002 - UT complete. No 1 thru 48 B6.30 recordable indications.

Examined studs 1 through 16.

• • 23A-REG**

WO 9950772 004900 RPV Closure Head B-a-i P VT-i 750-0002 X - - - 9/22/2002 - VT-i complete. No Washers B6.50 recordable indications.

1 thru 48 Examined washers 1 through 16.

WO 9950772 005000 RPV Threads in Flange B-a-1 C UT 0 165-0001 X - - - 9/19/2002 - UT complete. No 1 thru 48 B6.40 recordable indications.

• • 21-PTB**

HO 9950774

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 3 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)

CLASS 1 CLPABER COMPONENTS Pressurizer T-1 N I 0

-STATUS

SUMMARY

NUMBER EXAMINATION AREA IDENTIFICATION CATEGY ITEM NOj F EXAM METHOD PROCEDURE 0

R E

C N

a S

I a

E 0

x T

H E

R REMARKS

• • CALIBRATION BLOCK **

WO NUMBER System ID - T-001, Drawing No. ISI-1104 006000 PZR Manway Bolts B-G-2 C VT-I 750-0003 X 9/20/2002 - VT-i complete on all 1 thru 16 B7 .20 VT-i 750-0011 X 16 bolts. Galling of threads on IDR 7-007 bolt no. 13. 9/22/2002 AR CAP029619 Baseline VT-i complete on new bolt. No recordable indications.

NO 9942120

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 4 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (UlR27)

CLASS 1 CLPABER COMPONENTS Regenerative Heat Exchanger HX-2 N I 0 F

-STATUS O N a T R S E H REM.ARXS

SUMMARY

EXAMINATION AREA CATEGY EXAM E I 0 E ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO ME1THOD PROCEDURE C a M R WO TNU*ER System ID - HX-002, Drawing No. ISI-1107 010000 RHE-01 B-B L UT-45 176-0005 X - - - 9/16/2002 - UT complete. No Head to Shell B2.51 UT-60 176-0005 X - - - recordable indications. Limited examination due to support interference. **17-PTB**

WO 9950778 010100 RHE-02 B-B C UT 45 176-0006 X - - - 9/16/2002 - UT complete. No Shell to Tube Sheet B2 .80 recordable indications. Limited examination due to nozzle position. **17-PTB**

WO 9950778 010600 RHE-Ni B-D CUT 45 176-0001 X - - - 9/16/2002 - UT complete. No Inlet Nozzle to Shell B3.150 UT 60 176-0001 X - - - recordable indications. Limited examination due to clamp on the shell. **61-PTB, 62-PTB**

WO 9950778 010700 RPE-Nl-IRS B-D L UT3O/70/70 176-0002 X - - - 9/16/2002 - UT complete. No PEE Nozzle Inner B3.160 recordable indications. Limited Radius Section examination due to nozzle configuration. **61-PTB**

WO 9950778 S................................................................................................... .............................................................................................

010800 PEE-N4 B-D C UT 45 176-0003 X - - - 9/16/2002 - UT complete. No Shell to Outlet Nozzle B3.150 UT 60 176-0003 X - - - recordable indications. Limited examination due to clamp on the shell. **61-PTB, 62-PTB**

WO 9950778 010900 REHE-N4-IRS B-D L UT30/70/70 176-0004 X - - - 9/16/2002 - UT complete. No RHE Nozzle Inner B3.160 recordable indications. Limited Radius Section examination due to nozzle configuration. **61-PTB**

WO 9950778 S.................................................................................................................................................................................................

012200 RHE Shell Support F-A C VT-3 754-0001 - - - X 9/16/2002 - VT-3 complete. Two Component Support F1.40 IDR 7-001 - - - - areas of insufficiant thread AR CAP 029503 ---

engagement were noted. These are acceptable as-is by evaluation.

Wo 9950778

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT I PAGE: 5 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS 1 CLPABER COMPONENTS Regenerative Heat Exchanger HX-2

-STATUS N I 0 O N G T R S E H REMARKS SUMTMARY EXAMINATION AREA CATEGY EXAM E I 0 H ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO j ETHOD PROCEDURE C a M R WO NUMBER System ID - HX-002, Drawing No. ISI-1107 012300 RHE-IWA-I B-K C PT 451-0001 X - - - 9/16/2002 - PT complete. No Welded Attachment B10.10 recordable indications.

Bottom Shell WO 9950778 S................................................................................................................................................................................................

POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 6 DATE: 01/14/03 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS 1 CLPABER COMPONENTS Reactor Coolant Pump Flange and Bolting NI ON G 0T STATUS R SE H REM4ARKS

SUMMARY

EXAMINATION AREA CATEGY EXAM El1 0 E ** CALIBRATION BLOCK

• NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C G M R WO NUMBER System ID - P-001A, Drawing No. ISI-I1I0 017300 RCP A SEAL BOLTS B-G-2 C VT-I 750-0004 X - - - 9/20/2002 - VT-I complete. No 18 Seal Bolts B7.60 recordable indications.

Examined 18 bolts.

WO 9950773

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 7 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)

CLASS 1 CLPABER COMPONENTS Steam Generators HX-lA and HX-lB

-- STATUS N I 0

SUMMARY

NUMBER EXAMINATION AREA IDENTIFICATION CATEGY ITEM NOj F EXAM METHOD PROCEDURE 0 N R S E I C G G

E 0

M T

H E

R REMARKS

• • CALIBRATION BLOCK **

WO NUMBER System ID - HX-001A, Drawing No. ISI-PRI-1112 019100 SG A Manway Inlet B-G-2 A VT-I 750-0016 X - - - 10/5/2002 - VT-i complete on Bolting B7 .30 VT-I 750-0019 X - - - bolts 6, 7, 11, and 13. No Manway Bolting recordable indications.

10/7/2002 - VT-3 complete on bolt 3. No recordable indications.

WO 0212452 System ID - HX-001B, Drawing No. ISI-PRI-1112 020100 SO B Manway Inlet B-G-2 A VT-i 750-0017 X - - - 10/5/2002 - VT-I complete on Bolting B7.30 bolts 6, 7, 9, and 15. No Manway Bolting recordable indications.

WO 0212697 020200 SO B Manway Outlet B-G-2 A VT-i 750-0017 X - - - 10/5/2002 - VT-i complete on Bolting B7.30 VT-i 750-0018 X - - - bolts 7 and 16. No recordable Manway Bolting indications. 10/7/2002 - VT-I complete on bolt 2. No recordable indications.

WO 0212697

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 8 INSERVICE INSPECTION RESULTS SUMMdARY INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS 1 CLPABER COMPONENTS RER Suction off Loop A

-STATUS NI 0 ON UT R SE H REMARKS

SUMMARY

EXAMINATION AREA CATEGY EXAM ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO METHOD p2ROCEDURE C U M R NO NTUMBER System ID - Pipe RC 2501R-16, Drawing No. ISI-1122 032100 RC-10-AC-1001-02 R-A C THICK 109-0018 - - - - 9/25/2002 - Thickness data Elbow to Pipe R1.20 UT 45 173-0001 X acquired and UT complete. No recordable indications.

• • 51-PTB**

NO 9950779 032300 RC-10-AC-1001-03 R-A C THICK 109-0017 - - - - 9/25/2002 - Thickness data Pipe to Elbow R1.11 UT 45 173-0002 X - - - acquired and UT complete. No recordable indications.

• • 51-PTB**

NO 9950779 S.................................................................................................................................................................................................

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 9 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS 1 CLPABER COMPONENTS Accumulator B to Loop B N I 0 F

STATUS O N G T R S E H REMARKS

SUMMARY

EXAMINATION AREA CATEGY EXAM E I 0 E ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C U M R WO NTUMBER System ID - Pipe SI 2501R-01, Drawing No. ISI-PRI-1123 039100 AC-10-SI-1001-17 R-A C THICK 109-0013 - - - - 9/24/2002 - Thickness data R1.20 UT 45 173-0003 X - - - acquired and UT complete. No Pipe to Elbow recordable indications.

• • S1-PTB**

WO 9950780 039200 AC-10-SI-1001-18 R-A C THICK 109-0007 - - - - 9/24/2002 - Thickness data R1.20 UT 45 173-0004 X - - - acquired and UT complete. No Elbow to Pipe recordable indications.

• • 51-PTB**

WO 9950780 039400 AC-10-SI-1001-19 R-A L THICK 109-0008 9/24/2002 - Thickness data UT 45 173-0005 K - - acquired and UT complete. No Pipe to Valve ISI-867B R1.11 UT 60 173-0005 K - - -

recordable indications. No examination downstream due to valve. **51-PTB**

WO 9950780

-1 DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 10 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS 1 CLPABER COMPONENTS RHR to Accumulator B Line NI 0 STATUS 0 N 0 T R S E H REMARKS

SUMMARY

EXAMINATION AREA CATEGY EXAM E I 0 E ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO 24ETHOD PROCEDURE C G M R WO NUMBER System ID - Pipe SI 2501R-02, Drawing No. ISI-PRI-1124 042000 SIS-10-SI-1002-06 R-A C THICK 109-0002 - - - - 9/24/2002 - Thickness data Pipe to Elbow R1.20 UT 45 173-0006 X - - - acquired and UT complete. No recordable indications.

• • 51-PTB**

WO 9950781 042200 SIS-10-SI-1002-07 R-A C THICK 109-0003 - - - - 9/24/2002 - Thickness data Elbow to Pipe R1.20 UT 45 173-0007 X - - - acquired and UT complete. No recordable indications.

• • 51-PTB**

WO 9950781 042300 SIS-10-SI-1002-08 R-A C THICK 109-0004 - - - - 9/24/2002 - Thickness data Pipe to Elbow R1.20 UT 45 173-0008 X - - - acquired and UT complete. No recordable indications.

• • 51-PTB**

WO 9950781 042400 SIS-10-SI-1002-09 R-A C THICK 109-0005 - - - - 9/24/2002 - Thickness data Elbow to Pipe R1.20 UT 45 173-0009 X - - - acquired and UT complete. No recordable indications.

• • 51-PTB**

WO 9950781 System ID - N/A, Drawing No. ISI-PRI-1124 SI-2501R-2-SI1 F-A C VT-3 754-0002 X - - - 9/23/2002 - VT-3 complete. No 042600 Variable Spring F1.10C recordable indications.

WO 9950781

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 11 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE I (UIR27)

CLASS 1 CLPABER COMPONENTS Reactor Vessel Injection and Core Deluge to RPV N I 0

-STATUS N T 0 a R S E H REMARKS

SUMMARY

EXAMINATION AREA CATEGY EXAM E I 0 E ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C a X R WO NUMBER System ID - N/A, Drawing No. ISI-1127 051700 SI-2501R-5-SI7A F-A C VT-3 NDE-754 X - - - 9/16/2002 - VT-3 complete. No Rigid Support Fl.10B recordable indications.

WO 9950778 053500 Valve ISI-853D-BLT B-0-2 B VT-i 750-0020 X - - - 9/20/2002 - Baseline VT-i 6" Check Valve Bolting B7.70 complete on 12 studs and nuts.

No recordable indications.

WO 0212465 053700 RC-2501R-5-RC9 F-A B VT-3 754-0027 X 10/3/2002 - Agmented VT-3 Fl.10A VT-3 754-0028 X - complete. Loose nuts noted on Rigid Support IDR 7-013 both rods. This examination was performed at the request of the plant prior to disassembly of valve 1SI-853D for repaLr.

10/6/2002 - Baseline VT-3 complete after support reinstallation. No recordable indications.

WO 0212465

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 12 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)

CLASS 1 CLPABER COMPONENTS Core Deluge to RPV NI 0 F

-STATUS ON 0 T R SE H REMARKS

SUMMARY

EXAMINATION AREA CATEGY EXAM El1 0 E ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C a M R WO NUMBER System ID - N/A, Drawing No. ISI-1129 059100 Valve ISI-853A-DLT B-G-2 B VT-I 750-0021 X - - - 9/9/2002 - Baseline VT-I 6" Check Valve Bolting B7.70 complete. No recordable indications. Examined 12 studs and nuts.

WO 9946177

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 13 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)

CLASS 1 CLPABER COMPONENTS Pressurizer Safety N I 0

-STATUS

SUMMARY

NUMBER EXAMINATION AREA IDENTIFICATION CATEGY ITEM NOj F EXAM METHOD PROCEDURE 0

R E

C N

S I

a a

0 X

T H

E R

REMARKS

• • CALIBRATION BLOCK **

WO NUMBER System ID - N/A, Drawing No. ISI-1131 066900 RC-04-PR-1001-09-FB B-G-2 C VT-i 750-0006 X - - - 9/20/2002 - VT-i complete. No Flange Bolting B7.50 recordable indications. WO 9944661 initiated for valve refurbishment. Examined 16 nuts and 8 studs.

WO 9950775 System ID - Pipe RC 2501R-03, Drawing No. ISI-1131 068900 RC-04-PR-1002-09-FB B-G-2 C VT-i 750-0007 X - - - 9/20/2002 - VT-I complete. No Flange Bolting B7.50 recordable indications.

Examined 16 nuts and 8 studs.

WO 9950776

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 14 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)

CLASS 1 CLPABER COMPONENTS Pressurizer Power Operated Relief Valve Discharge

-STATUS NI 0 R SE H REMARKS

SUMMARY

EXAMINATION AREA CATEGY EXAM ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C a M R WO NUMBER System ID - N/A, Drawing No. ISI-PRI-I135 089500 RC-2501R-2-HSS1 F-A A VT-3 754-0041 - - X 9/17/2002 - VT-3 complete. Rust Snubber FI.10S VT-3 754-0042 - - X noted on bolting. 10/4/2002 IDR 7-004 Rust noted on VT-3 complete.

bolting. Accepted as-is by engineering evaluation.

Examined as HS-2501R-51.

WO 9945448

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 15 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS 1 CLPABER COMPONENTS Loop B RTD Bypass STATUS N I 0 ON UT R S E H REMARKS

SUMMARY

EXAMINATION AREA CATEGY EXAM E I 0 E ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEK NO METHOD PROCEDURE C O X R WO NUMBER System ID - Pipe RC 2501R-14, Drawing No. ISI-1137 107600 RC-03-BP-1002-06 R-A C THICK 109-0009 - - - - 9/17/2002 - Thickness data Pipe to Elbow R1.20 UT 45 173-0010 X - - - acquired and UT complete. No recordable indications.

• • 2-PTB**

WO 9950782 S.................................................................................................................................................................................................

107700 RC-03-BP-1002-07 R-A C THICK 109-0010 - - - - 9/17/2002 - Thickness data Elbow to Pipe R1.20 UT 45 173-0011 X - - - acquired and UT complete. No recordable indications.

• • 2-PTB**

WO 9950782 S.................................................................................................................................................................................................

107800 RC-03-BP-1002-08 R-A C THICK 109-0011 - - - - 9/17/2002 - Thickness data Pipe to Elbow R1.20 UT 45 173-0012 X - - - acquired and UT complete. No recordable indications.

• • 2-PTB**

WO 9950782 S................................................................................................................................................................................................

107900 RC-03-BP-1002-09 R-A C THICK 109-0012 - - - - 9/17/2002 - Thickness data Elbow to Pipe R1.20 UT 45 173-0013 X - - - acquired and UT complete. No recordable indications.

• • 2-PTB**

WO 9950782 S................................................... ............................ I................................................................................................................

108000 RC-03-BP-1002-10 R-A C THICK 109-0014 - - - - 9/17/2002 - Thickness data Pipe to Pipe R1.20 UT 45 173-0014 X - - - acquired and UT complete. No recordable indications.

• • 2-PTB**

WO 9950782 S................................................................................................................................................................................................

01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 16 DATE:

INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS 1 CLPABER COMPONENTS Letdown from Loop B Cold Leg

-STATUS NX 0NI 1 0T O

R SE H REMARKS

SUMMARY

EXAMINATION AREA CATEGY EXAM El1 0 E ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO METHOD P1ROCEDURE C a M R WO NUMBER System ID - Pipe RC 2501R-I0, Drawing No. ISI-1146 144000 RC-08-DR-1001-01 R-A L THICK 109-0001 - - - - 9/23/2002 - Thickness data R1.20 UT 45 173-0015 X - - - acquired and UT complete. No Branch Connection to UT 60 173-0015 X - - - recordable indications. No Pipe examination upstream due to branch connection configuration.

• • 17-PTB**

WO 9950782 144100 RC-08-DR-1001-02 R-A P THICK 109-0006 - - - - 9/23/2002 - Thickness data Pipe to Reducer R1.20 UT 45 173-0016 X - - - acquired and UT complete. No UT 60 173-0016 X - - - recordable indications. No examination downstream due to reducer configuration.

• • 17-PTB**

WO 9950782

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 17 INSERVICE INSPECTION RESULTS SUMMA-RY INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS 1 CLPABER COMPONENTS Safety Injection to Loop B Cold Leg STATUS NI 0

SUMMARY

EXAMINATION AREA CATEGY R SE H REMARKS EXAM ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C a M R WO NUMBER System ID - Pipe SI 2501R-06, Drawing No. ISI-1149 160550 1-SI-878B-4 F-A C VT-3 754-0005 X - - - 9/24/2002 - VT-3 complete. No Rigid Support F1.10A recordable indications.

WO 9950780

POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 18 DATE: 01/14/03 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS 2 CLPABER COMPONENTS Steam Generator's HX-1A and HX-lB NI 0 F

STATUS ON G T R SE H REMARKS SUNNARY EXAMINATION AREA CATEGY EXAM El1 0 E ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITED NOj METHOD PROCEURE C G M R AO NUMBER System ID - N/A, Drawing No. ISI-PRI-1201 202000 HS-5 F-A C VT-3 754-0033 x - - 9/17/2002 - VT-3 complete prior Snubber F1.20S VT-3 754-0034 x - - - to removal. No recordable IDR 7P-009 9/26/2002 - VT-3 indications.

complete after reinstallation.

No recordable indications.

WO 9945448

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 19 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS 2 CLPADER COMPONENTS Regenerative Heat Exchanger HX-2

--STATUS N I 0 O N G T R S E H REMARKS

SUMMARY

EXAMINATION AREA CATEGY EXAM E 0 E ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C a M R HO NUMBER System ID - HX-002, Drawing No. ISI-1107 206000 RHE-03 C-A C UT 45 176-0007 X - - - 9/16/2002 - UT complete. No Shell to Tube Sheet Cl.30 UT 60 176-0007 X - - - recordable indications. Limited examination due to nozzle proximity. **17-PTB**

HO 9950778 206100 RHE-04 C-A C UT 45 176-0008 X - - - 9/16/2002 - UT complete. No Shell to Head C1.20 UT 60 176-0008 X - - - recordable indications. Limited examination due to support.

• • 17-PTB**

HO 9950778

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 20 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)

CLASS 2 CLPABER COMPONENTS RHA Heat Exchangers HX-11A and HX-liB N I 0 F

-STATUS 0 N G T R S E H REMARKS

SUMMARY

EXAM4INATION AREA CATEGY EXAM E 1 0 E ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NOj 24ETHOD PROCEDURE C a M R WO NUMBER System ID - HX-011A, Drawing No. ISI-PRI-1204 208200 RHR-A-N1 C-B C VT-2 I-PT-RH-i X - - - 10/12/2002 - VT-2 complete. No Nozzle to Shell C2.33 recordable indications.

WO 9945418 208300 RHR-A-N2 C-B C VT-2 1-PT-RH-i X - - - 10/12/2002 - VT-2 complete. No Shell to Nozzle C2.33 recordable indications.

WO 9945418 System ID - HX-011B, Drawing No. ISI-PRI-1204 209200 RHR-B-NI C-B C VT-2 1-PT-RH-I X - - - 10/12/2002 - VT-2 complete. No Nozzle to Shell C2 .33 recordable indications.

Wo 9945418 209300 RHR-B-N2 C-B C VT-2 1-PT-RH-I X - - - 10/12/2002 - VT-2 complete. No Shell to Nozzle C2.33 recordable indications.

WO 9945418

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 21 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)

CLASS 2 CLPABER COMPONENTS Loop B Main Steam Outside Containment N I 0 STATUS ON G T R S H REMARKS

SUMMARY

EXAMINATION AREA CATEGY EXAM E I 0 E ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C G M R WO NUMBER System ID - Piping EB-01, Drawing No. ISI-1243 306000 MS-30-MS-1002-17 R-A C THICK 109-0015 9/27/2002 - Thickness data UT 45 172-0001 X - -

Pipe to Tee R1.20 acquired and UT complete. No UT 60 172-0001 K - - -

recordable indications.

• • 46-PTB**

WO 9950784 306100 MS-30-MS-1002-18 R-A C THICK 109-0016 - - - - 9/27/2002 - Thickness data Tee to Valve IMS-2017 R1.20 UT 45 172-0002 X - - - acquired and UT complete. No UT 60 172-0002 X - - - recordable indications.

• • 46-PTB**

WO 9950784 S................................................................................................................................................................................................

System ID - N/A, Drawing No. ISI-1243 307200 EB-l-E9 F-A C VT-3 754-0006 X - - - 9/18/2002 - VT-3 complete. No Rigid Support FZ.20A recordable indications.

WO 9950784 S................................................................................................................................................................................................

POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 22 DATE: 01/14/03 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)

CLASS 2 CLPABER COMPONENTS Feedwater Loop A Inside Containment N I 0 STATUS F

O N G T R S E H REMARKS CATEGY EXAM 0 E ** CALIBRATION BLOCK *t

SUMMARY

EXAMINATION AREA E I NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C a x R WO NUMBER System ID - N/A, Drawing No. ISI-PRI-1245 F-A A VT-3 754-0036 - X 9/26/2002 - VT-3 completed 318200 ES-lI F1.20S VT-3 754-0037 X - - - pre-removal. Loose bolt, Snubber IDR 7-008 bushing out of place, rust, and inadequate clearance. Accepted by engineering evalaution.

10/5/2002 - VT-3 completed after re-installation. No recordable indications.

WO 9945448

POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 23 DATE: 01/14/03 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS 2 CLPABER COMPONENTS Safety Injection Pump P-15A Discharge NI ON 1T 0

-STATUS R SE H REMARKS

SUMMARY

EXAMINATION AREA CATEGY EXAM ** CALIBRATION BLOCK **

METHOD PROCEURE C 0 M R WO NUMBER NUMBER IDENTIFICATION ITEM Na System ID - Pipe SI 1501R-01, Drawing No. ISI-PRI-1252 R-A B PT 450375 X - - - 9/21/2002 - Baseline PT 348450 SIS-04-SI-1005-25A Rl.20 complete. No recordable 2" Branch Connection indications.

WO 0205506 348460 SIS-04-SI-1005-25B R-A B PT 450375 X - - - 9/21/2002 - Baseline PT Weldolet to Reducing Rl.20 complete. No recordable Insert indications.

WO 0205506

POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 24 DATE: 01/14/03 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS 2 CLPABER COMIPONENTS Loop A Main Steam Inside Containment N I 0 STATUS 0 N a T R S E H REM{ARKS

SUMMARY

EXAMINATION AREA CATEGY EXAM E I 0 E ** CALIBRATION BLOCK **

PROCEDURE C G M R WO NUMBER NUMBER IDENTIFICATION ITEM NO METHOD System ID - PS EB-01-MS-H4, Drawing No. ISI-1261 F-A C VT-3 754-0007 - - x 9/18/2002 - VT-3 complete. The 390800 EB-1-MS-H4 F1.20C IDR 7-002 snap ring was out of the groove Spring Hanger VT-3 754-0010 X on the pivot pin. A pin movement of 1/16" noted.

Accepted as-is by evaluation.

WO written to correct.

9/24/2002 - VT-3 re-examination complete after pin adjusted and clip moved back into position under WO 0212668. No recordable indications.

WO 9950783

POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 25 DATE: 01/14/03 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE I (U1R27)

CLASS 2 CLPABER COMPONENTS Loop B Main Steam Inside Containment NI 0

-STATUS ON G T

SUMMARY

NUMBER EXAMINATION AREA IDENTIFICATION CATEGY ITEM NOj F EXAM METHOD PROCEDURE R

El1 0 C G0M SE H E

R REMARKS

• • CALIBRATION BLOCK **

WO NUM2BER System ID - N/A, Drawing No. ISI-PRI-1262 F-A A VT-3 1-PT-SS-1 - X 9/15/2002 - VT-3 complete.

392500 HS-4 F1.20S Loose nut noted on snubber Snubber attachment found to be loose.

Accepted as-is and tightened.

WO 9945448

POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 26 DATE: 01/14/03 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)

CLASS P CLPABER COMPONENTS Pressure Test N I 0 STATUS O N G T R S E H REMARKS

SUMMARY

EXAMINATION AREA CATEGY l EXAM E 00 E ** CALIBRATION BLOCK **

NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C a X R WO NUMBER System ID - N/A, Drawing No. N/A 700100 I-PT-AF-i P C VT-2 1-PT-AF-1 X 10/14/2002 - VT-2 complete.

Auxilary Feedwater Leakage noted at several System mechanical conections. Work Orders were written to correct.

WO 9945418 700300 I-PT-CS-i P C VT-2 I-PT-CS-I X - - - 9/13/2002 - VT-2 complete. No Feedwater (Condensate) recordable indications.

System WO 9945429 700400 1-PT-CC-1 P C VT-2 1-PT-CC-i X- 9/25/2002 - VT-2 complete.

Component Cooling Leakage noted at mechanical Water System connections. Corrected by FIN team during test.

WO 9945426 701500 I-PT-RH-i P C VT-2 1-PT-RH-i - - - X 10/12/2002 - VT-2 complete. No Residual Heat Removal through wall leakage noted.

System Leakage found at mechanical connections. FIN team will clean and inspect. One WO written on Air Opearated Valve for packing adjustment.

WO 9945418 702000 I-PT-SI-4 P C VT-2 I-PT-SI-4 - - - X 9/30/2002 - VT-2 complete.

Safety Injection Leakage noted at mechanical System connections. All leakage was corrected by FIN Team.

WO 9945441 702100 I-PT-SI-5 P C VT-2 1-PT-SI-5 - - - X 9/30/2002 - VT-2 complete.

Safety Injection TCN 2002-0632 - - - - Leakage noted at mechanical System connections. All leakage was corrected by FIN Team. Piping in the Facade not examined.

WO 9945442

DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 PAGE: 27 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)

CLASS P CLPABER COMPONENTS Pressure Test

-STATUS N I 0 ON a T

SUMMARY

EXAMINATION AREA CATEGY EXAM R S E H REMARKS E I 0 E ** CALIBRATION BLOCK **

NU"MBER IDENTIFICATION ITEM NO METHOD PROCEDURE C a M R WO NIUMBER System ID - N/A, Drawing No. N/A 703000 I-PT-SW-I P C VT-2 I-PT-SW-i - - X 10/2/2002 - VT-2 complete. One Service Water System valve leaking at the packing.

Packing was adjusted.

WO 9945449 S.................................................................................................................................................................................................

703500 1-PT-RCS-1 P C VT-2 I-PT-RCS-1 X 10/14/2002 - VT-2 complete.

Reactor Coolant System Leakage noted at several mechanical connections. Leakage was stopped during the test or Work Order written to correct.

WO

UNIT 1 REFUELING 27

SUMMARY

LIST FOR FORM NIS-2

This report includes a listing of Unit 0 and Unit 1 NIS-2 reports and a copy of the forms for the time period of May 13, 2001 to October 17, 2002.

RRM: 2000-0019 Component: T-013 Dated: January 14, 2002 RRAI: 2001-0074 Component: CV-01299 Dated: October 29, 2001 RRM: 2001-0077 Component: AC-152N-15-H43 Dated: November 15, 2001 RRM: 2002-0019 Component: CV-00296, valve bonnet and plug Dated: October 21, 2002 RRM: 2002-0042 Component: Piping AC-0601R-06 Dated: October 22, 2002 RRMI: 2002-0051 Component: RC-00435 Dated: October 21, 2002 RRM: 2002-0052 Component: Piping SI- 1501R-02 and Piping SI-1501R-03 Dated: October 31, 2002 RRM: 2002-0056, 2002-0057, 2002-0090 Component: MS-02005, MS-02007, and bolting Dated: November 5, 2002 RRM: 2002-0064 Component: CV-00369A Dated: October 21, 2002 RRM: 2002-0066, 2002-0067, 2002-0098, 2002-0104 Component: RC-00570A, RC-00570B, RC-00575A, RC-00575B, RC-00580A, RC-00580B, 1 RC-2507R-1 Piping, I-RC-2507R-1 Supports Dated: November 8, 2002 Page 2 of 4

RRM: 2002-0073, 2002-0079 Component: SI-00853A, studs, and nuts Dated: October 15, 2002 RRM: 2002-0075, 2002-0099 Component: T-013, manway bolting, and manway nuts Dated: October 16, 2002 RRM: 2002-0080, 2002-0086 Component: SI-00853B and bolting Dated: October 14, 2002 RIRI: 2002-0081, 2002-0087 Component: SI-00853 and bolting Dated: October 23, 2002 RRM: 2002-0082 Component: SI-00892A, Piping 2"-SI-902R-2 Dated: October 22, 2002 RRM: 2002-0085, 2002-0109 Component: HX-004 Dated: October 14, 2002 RRM: 2002-0089 Component: T-001 bolting Dated: October 21, 2002 RRAI: 2002-0092 Component: R-1 Dated: October 21, 2002 RRM: 2002-0093 Component: RH-0700 and cap Dated: October 22, 2002 RRM: 2002-0094, 2002-0100, 2002-0102, 2002-0105 Component: T-034A Dated: October 31, 2002 RRM: 2002-0095, 2002-0101, 2002-0103 Component: T-034B Dated: October 9, 2002 Page 3 of 4

RRM: 2002-0096 Component: PS-1 Dated: October 5, 2002 RRM: 2002-0097 Component: MS-00218 and piping Dated: October 28, 2002 RRM: 2002-0106 Component: CC-00763A Dated: September 30, 2002 RRM: 2002-0107 Component: MS-2017 Dated: October 21, 2002 RRM: 2002-0108 Component: FM-Thimbles Dated: October 22, 2002 RRM: 2002-0112 Component: SI-00830B, SI-00830C, piping, and bolting Dated: October 18, 2002 RRM: 2003-0001 Component: CV-00203 Dated: September 27, 2002 Page 4 of 4

FORMI NIS-2 OWNNTER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date Jianuary 14, 2002 700 First Street, Hudson, WI 54016 Sheet- I of 1

2. Plant Point Beach Nuclear Plant Unit I 6610 Nuclear Road, Two Rivers, WI 54241 WO 9924865 Repair Organization P 0 No, Job No Etc 3 Wolk Performed By: We Energies Type Code Symbol Stamp N/A narme 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A riddrev

4. Identification of System: Safety Injection Bechtel Spec M-21

5. (a) Applicable Construction Code API Standard 650, 3 d Ed 19 N/A Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Edition, No Addenda 6 Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME National Replaced, Code Name of Name of Manufacturer Board Other Year or Stamped Component Manufacturer Serial No. No Identification Built Replacement (Yes or No)

IT-013 Graver 1660-IA 1968 N/A T-13 Unknown Replacement No

7. Description of Work: Install 28 new anchors to the base and reinforce 25 existing anchor chairs 8 Tests Conducted: Hydrostatic E] Pneumatic E Nominal Operating Pressure El Other 0 Pressure _ psi Test Temp. F F__

None required 9 Remarks RRM2000-0019, CR01-2428 C,'. -95'C'"¢ Anolicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI. repair or replacement Type Code Symbol Stamp: N/A Certificate of Authorization No. Docket 50-266 Expiration Date N/A Signed ISI Coordinator Date / / /12 >"

Owner or Owner's Desigee. 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 of Province of Wisconsin and employed by HSB CT have inspected the components described in this Owner's Report during the period April 22. 2000 to January 14, 2002, and state that to the best of my knowledge and belief, the Owner has performed exarmnations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measuies desctibed in this Ownet's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind atising from or connected x~ith this inspection L.A ý- 0.-&y Commissions WI-100128 lihpector' Signatut e National Board, State, Province, and Endorsements Date- 1-1 , tI(', t,, . ' 3 PBF-7050 Revision 1 05/17/02 SEM 7 l 1

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date October 29, 2001 700 First Street, Hudson, WI 54016 Sheet: I of 1

2. Plant Point Beach Nuclear Plant Unit I 6610 Nuclear Road, Two Rivers, WI 54241 WO 9946071 Repair Organization P.O No , Job No Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N/A 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A

4. Identification of System: Chemical and Volume Control WEST Spec. 676258

5. (a) Applicable Construction Code B31.1 19 67 Edition, No Addenda, No!Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Edition, No Addenda

6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME National Replaced, Code Name of Name of Manufacturer Board Other Year or Stamped Component Manufacturer Serial No No. Identification Built Replacement (Yes or No)

CV-01299 Darling Valve S350-W-DD N/A CV-1299 Unknown Replacement No

7. Description of Work: Seal welding of body-to-bonnet joint and replacement of carbon steel bolts and nuts.

S. Tests Conducted: Hydrostatic 7] Pneumatic DI Nominal Operatingo Pressure El Other El Pressure psi Test Temp. OF None

9. Remarks RRM 2001-0074 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair/replacement conforms to the rules of the ASME Code,Section XI. repair or replacenrynt Type Code Symbol Stamp: N/A Certificate of Authorization No. Docket 50-266 Expiration Date N/A Signed ISI Coordinator Date zA :i 61--1 21 wnc r;ý r r%Nmc-- n e si gncc Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid comnussion issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Wisconsin and employed by HSB CT have inspected the components described in this Owner's Report during the period September 7, 2001 to October 29, 2001, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions WI-100128 lnspector'/'Signature National Board, State, Province, and Endorsements Date: - ,2e'r 2.-

PBF-7050 Revision 1 05/17/02 SEM 7.11 1

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date November 15, 2001 700 First Street, Hudson, WI 54016 Sheet- 1 of 1 2 Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 9937084 Repair Organization P 0 No, Job No Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A

4. Identification of System. Component Cooling Water Bechtel Spec 6118-M-78 Rev. 6, AWS D1.1

5. (a) Applicable Construction Code B31.1 19 67 Edition, No Addenda, NoCode Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Edition No Addenda

6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME National Replaced, Code Name of Name of Manufacturer Board Other Year or Stamped Component Manufacturer Serial No No Identification Built Replacement (Yes or No)

AC-152N-15-H43 Westinghouse 6455 N/A None Unknown Replacement No

7. Description of Work: Replaced adjustment assembly on piping support.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Other El Pressure __ psi Test Temp. _ 'F None

9. Remarks RRM 2001-0077 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI. repair or replacement Type Code Symbol Stamp: N/A Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed I t, J~L ISI Coordinator Date 4 /7/,o Z-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 of Province of Wisconsin and employed by HSB CT have inspected the components described in this Owner's Report during the period August 28, 2001 to November 14, 2001, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

,'/¢'4 r,*-..-.~ Commissions WI-100128 Inspector's>nature National Board, State, Province, and Endorsements Date: // - "C2--

PBF-7050 Revision 1 05/17/02 SEM 7 11 1

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI Date October 21, 2002 I Owner Nuclear Management Corpotation Sheet 1 of 1 700 First Street, Hudson, WI 54016

2. Plant Point Beach Nuclear Plant Unit: I WO 9949106 6610 Nuclear Road, TNxo Rivets, WI 54241 Repair Organization P 0 No, Job No Etc 3 Work Performed By: We Eneigies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No N/A Expiiation Date N/A Two Rivels, WI 54241

4. Identification of System- Chemucal and Volume Control West Spec 676270

5. (a) Applicable Construction Code B31 V/ASA B16 5 19 67/67/ Edition, No/No Addenda, No/NoCode Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Edition, No Addenda

6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME National Replaced, Code Name of Name of Manufacturer Board Other Year or Stamped Component Manufacturer Serial No No. Identification Built Replacement (Yes or No)

Copes Vulcan N/A NIA CV-296 Unknown Replacement No CV-00296 Valve bonnet & Copes Vulcan N/A N/A None Unknown Replaced No plug 7 Description of Work- Replacement of opeiators, modification of valve packing configuration, changeout Sal e stem, replacement of other valve internals including plug and bonnet.

I Nominal Operating Pressure 8 Tests Conducted: Hydrostatic El Pneumatic E]

2259.5 psi Test Temp. 547 OF Other El Pressure System Leakage Test

9. Remarks RRM 2002-0019 A ,1,.. ai.. I I . ni., RenortA to he attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the repoit are correct and this replacement conforms to the rules of the ASME Code,Section XI. repair or replacement Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ,/i..-.,,f/,,.* ISI Coordinator Date ON tier or Oxkiict's Designee, Title CERTIFICATE OF INSERVICE INSPECTION Vessel I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Inspectors and the State of Province of Wisconsin and employed by HSB CT have inspected the components that to the described in this Owner's Report during the period February 22, 2002 to October 21, 2002, and state has performed examinations and taken corrective measures described in best of my knowledge and belief, the Owner this Owner's Repoit in accordance with the iequiiements of ASME Code, Section XI By signing this ceitificate, neither the Inspector nor his employer makes any warranty, expressed or implied, neither the concerning the examinations and corrective measures described in this Owner's Report. Fuithermore, or a loss of any Inspector nor his employer shall be liable in any manner for any peisonal injury or property damage kind arising from or connected with this inspection P" f Commissions jp'. , ,

inspcCtor't Sleia1ture National Board, State, Piovince, and Endoisements Date. J/1qw' i4t" ze -r PBF-7050 SEM 7 11 1 Revision 1 05/17/02

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 22, 2002 700 First Street, Hudson, WI 54016 Sheet: 1 of I

2. Plant Point Beach Nuclear Plant Unit: I 6610 Nuclear Road, Two Rivers, WI 54241 WO 0202449 Repair Organization P.O No., Job No. Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N/A lime 6610 Nuclear Road Authorization No. N/A Expiration Date N/A TTwo Rivers, WI 54241 a

4 Identification of System Residual sddrem Heat Removal WEST G676262

5. (a) Applicable Construction Code B31 1 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Edition, No Addenda

6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME National Replaced, Code Name of Name of Manufacturer Board Other Year or Stamped Component Manufacturer Serial No. No Identification Built Replacement (Yes or No)

Piping N/A N/A N/A N/A Unknown Replacement No AC-0601 R-06

7. Description of Work: Drill 2" diameter hole to facilitate FME removal and add vent valve.

8. Tests Conducted: Hydrostatic ED Pneumatic Rl Nominal Operating Pressure I Other El Pressure 350 psi Test Temp. 80 OF System Leakage Test

9. Remarks RR 2002-0042, CAP 030632, Code Case N-416-1

&4...,..f..p,,,.....'p fl,, P,,-,fl, to isp nttsrhecl CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI. repair or replacement Type Code Symbol Stamp. N/A Certificate of Authorization No. Expiiation Date N/A Signed ?2" 7.6 - ISI Coordinator Date SConoajoo0 N*.vner or (*\,.'ner'* I)egionee_ Title owner or 6%%mees Desi"cc 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 of Province of Wisconsin and employed by HSB CT have inspected the components described in this Owner's Report during the period May 28, 2002 to October 22, 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

//(* {.. 2' f /Commissions WI-100128 Inspecot 's"Signature National Board, State, Province, and Endorsements Date: t . /, Za'- e eA PBF-7050 SEM 7 It 1 Re),ision I 05/17/02

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 21, 2002 700 First Street, Hudson, Wl 54016 Sheet: 1 of 1

2. Plant Point Beach Nuclear Plant Unit: I 6610 Nuclear Road, Two Rivers, WI 54241 WO 9944661 Repair/Replacement Organization P.O. No, Job No Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address 4 Identification of System: Reactor Coolant West 676279

5. (a) Applicable Construction Code ASME Section III, 19 68 Edition, No Addenda, No code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Year Corrected, Code Name of Name of Manufacturer Board Other Removed or Stamped Component Manufacturer Serial No No Identification Built Installed (Yes or No)

RC-00435 Crosby XX05950176 N/A RC-435 Unknown Removed Yes RC-00435 Crosby XX05950199 N/A RC-435 Unknown Installed Yes

7. Description of Work: Like-for-like replacement of valve per ASME OM-1-1981.

8. Tests Conducted. Hydrostatic El Pneumatic D Nominal Operating Pressure El Exempt 11 547 OF Other 0 Pressure 2235 psi Test T emp.

System Leakage Test

9. Remarks RR 2002-0051 np__i.--au- PI-.i..atLUI...^.) rsaia aq.-^u i I+.)* *=

AppiicaoLe Mtalltulacturc s l.atal. eporttuo*eatt,.cie~

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A S ig ned m " e ' -1 ISI Coordinator Date ZZ el; 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 of Wisconsin and employed by HSBCT have inspected the components described in this Ownei's Report during the period June 24, 2002 to October 21, 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Z/ -- . </4, Commissions WI-100128 Inspector's Sigtature National Board, State, Province, and Endorsements Date: //, 2,L3 PBF-7050 Revision 2 12/02/02 SEM7II 7

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 31, 2002 700 First Street, Hudson, WI 54016 Sheet: 1 of 1

2. Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WOs 0205506, 0205507, 0205508 Repair/Replacement Organization P.O. No, Job No Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West Spec G676262

5. (a) Applicable Construction Code B31.1. 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No No. Identification Built Installed (Yes or No)

Piping SI-1501R- N/A N/A N/A None 2002 Installed No 02 Piping SI-1501R- N/A N/A N/A None 2002 Installed No 03 1 1

7. Description of Work: Added cleanout holes for FME, added vent valves

8. Tests Conducted: Hydrostatic 0i Pneumatic El Nominal 0 perating Pressure 0 Exempt El Other E] Pressure 1540 psi Test Temp. 79 "OF System Leakage Test

9. Remarks RR 2002-0052 C,-f 3c (-, c/-

Ai,,.,i,1. M,.,,,f h,,,.,', ri,,, In h, ehei CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ISI Coordinator Date Owner 6orOwner'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 of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period July 12, 2002 to September 27, 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

,/ 2 L_ Commissions WI-100128 Inspector's Signature National Board, State, Province, and Endorsements Date:

PBF-7050 Revision 2 12/02/02 SEM 7 11.1

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date November 5, 2002 700 First Sheet, Hudson, WI 54016 Sheet: 1 of 2 2 Plant Point Beach Nuclear Plant Unit. I 6610 Nuclear Road, Two Rivers. WI 54241 WO 9921983, 9921984 Repair/Replacement Organization P 0 No, Job No Etc

3. Woik Performed By: Crane Movats Type Code Symbol Stamp VR namne 2825 Cobb International Blvd Authorization No. 475 Kennesaw, Ga 30152 Expiration Date 10/22/2002 addi ess

4. Identification of System: Main Steam Bech Spec 6118-M-183-AC Rev. 1

5. (a) Applicable Construction Code Section I1I, 19 65 Edition, Wintei 66 Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed Addenda thri 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No No. Identification Built Installed (Yes or No)

See Attached Page

7. Description of Woik: Replacement of safety valves with pre-tested spares, replaced galled bolting.

8. Tests Conducted: Hydrostatic 2 Pneumatic El Nominal Operating Pressure El Exempt El Other [] Piessure 2200 psi Test Temp. Unknown OF

9. Remarks RR 2002-0056, 2002-0057, 2002-0090, Installed by WE Energies, 6610 Nuclear Rd, Two Rivers, Wi 54241, Hydio test performed by repair organization Annntribie MAn,,f.rturcr' lalr.it. Rennri*tc hnIw*

nttneIlOeA CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI Type Code Symbol Stamp: N/A Certificate of Authotization No. Expiration Date N/A Signed __z- *-j'.- Signed ISI Coordinator Date ,,,J~'*.r '-

// /

,-)')/ 7

-it , *,*f ,

O0%er or O.ner's Desigpee, Tatle 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 of Wisconsin and employed by HSBCT have inspected the components described in this Ow*ner's Report during the period July 12, 2002 to November 5. 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employei makes any warranty, expressed oi implied, concerning the exantiinations and corrective measuies described in this Owner's Report Furthermore, neither the Inspector nor his employer shall be liable in any mainer for any peisonal injury or property damage or a loss of any kind arising from oi coimected wvith this inspection Commissions W'I-100128 Inspector'b Sqgftare National Boaid, State, Province, and Endoisements Date- is; 2--

P1BF-7050 Reision 2 12/02/02 SEM 7 It 1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY (CONTINUATION)

As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date November 5, 2002 700 First Street, Hudson, WI 54016 Sheet. 2 of 2 2 Plant Point Beach Nuclear Plant Unit. I 6610 Nuclear Road, Two Rivers, WI 54241 WO 9921983, 9921984 Repair/Replacement Organizatuon P 0 No, Job No Etc

3. Work Performed By: Crane Movats Type Code Symbol Stamp VR name 2825 Cobb International Blvd Authorization No. 475 Kennesaw, Ga 30152 Expiration Date 10/22/2002 address 4 Identification of System: Main Steam Bech Spec 6118-M-183-AC Rev. 1

5. (a) Applicable Construction Code Section III 19 65 Edition, Winter 66 Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Ed, Add thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No Identification Built Installed (Yes or No)

MS-02005 Crosby XX0595112 N/A MS-2005 Unknown Removed Yes MS-02005 Crosby N82743 N/A MS-2005 1994 Installed Yes 0001 MS-02005 Unknown N/A N/A N/A Unknown Removed No Bolting MS-02005 Victor Products N/A N/A N/A Unknown Installed No Bolting Corp MS-02007 Crosby XX0595114 N/A MS-2007 Unknown Removed Yes MS-02007 Crosby N82743 N/A MS-2007 1994 Installed Yes 0004 MS-02007 Unknown N/A N/A N/A Unknown Removed No Bolting MS-02007 Victor Products N/A N/A N/A Unknown Installed No Bolting Corp 4 +/- 4 +/-

4 4 4 4-4 + 4 + + 4 +

4 + 4 + + 4 +/-

4 .4- 4 4- 4- 4 + + + 4 4 +

4 4 4- 4 4 4 4 4- 4 4 .1________________ L .1. _____________ L I. A PBF-7050a Revision 2 12/02/02 SEMt 7 1 1 1

FORAI NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 21, 2002 700 First Street, Hudson, WI 54016 Sheet: 1 of 1

2. Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 9937802 Repair/Replacement Organization P.O No, Job No Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Chemical and Volume Control West. 676241, 676242

5. (a) Applicable Construction Code B31.1, 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Cemoved or Stamped Component Manufacturer Serial No No. Identification Built Installed (Yes or No)

CV-00369A Edward Vogt N/A N/A CV-369A Unknown Removed No Machine Co CV-00369A Edward Vogt N/A N/A CV-369A Unknown Installed No Machine Co

7. Description of Work: Replaced soft seat valve with hard faced seat valve.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Op erating Pressure 0 Exempt El Other Dl Pressure 350 psi Test Temp 110 OF System Leakage Test

9. Remarks RR 2002-0064, CAP 030632 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed 27V, Z< ISI Coordinator Date Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding valid commission issued by the National Board of Boiler and Pressure Vessel a

Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period July 23, 2002 to October 21, 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection

/" Commissions WI-100128 Inspector's S/6nature National Board, State, Province, and Endorsements Date: A.-, ,'-/5, Z "U'3 PBF-7050 Revision 2 12/02/02 SEM 7.11.1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI Nuclear Management Corporation Date Nov'ember 8, 2002

1. Owner Sheet: 1 of 2 700 First Street, Hudson, WI 54016 Unit: I

2. Plant Point Beach Nuclear Plant WO 9812062 6610 Nuclear Road, Two Rivers, WI 54241 Repair/Replacement Organization P 0 No, Job No Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Expiration Date N/A Two Rivers, WI 54241 address

4. Identification of System: Reactor Coolant Supports: D1.1, 1967

5. (a) Applicable Construction Code Section III, 19 77 Edition, W78 Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed., Add. thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Manufacturer Board Other Year Removed or Stamped Name of Component Manufacturer Serial No No. Identification Built Installed (Yes or No)

See Attached Page

7. Description of Work: Replaced valves, replaced immediate piping, and modified supports.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Exempt El Other Z Pressure 2259 psig psi Test Temp. 547 OF System Leakage Test

9. Remarks RR 2002-0066, 2002-0067, 2002-0098, 2002-0104 Applicable Manufacturers Data Reports to be attacned CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ISI Coordinator Date 2Zeýý t'*pr ~r tt~ar' 13~l*naeTitle

., I.

nmcr or ONmees Desi-ce Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel this Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in August 8, 2002 to November 8, 2002, and state that to the best of my knowledge Owner's Report during the period Report in and belief, the Owner has performed examinations and taken corrective measures described in this Owner's accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the of any Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss kind arising from or connected with this inspection.

2 *. i, Commissions WI-100128 Inspectors 'Signature National Board, State, Province, and Endorsements Date: /-/3-. C.3 PBF-7050 SEM 7.11 1 Revision 2 12/02/02

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY (CONTINUATION)

As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date NoNvember 8, 2002 700 First Stieet, Hudson, WI 54016 Sheet: 2 of 2

2. Plant Point Beach Nuclear Plant Unit- I 6610 Nuclear Road, Two Rivers, WI 54241 WO 9812062 Repair/Replacement Organization P 0 No, Job No Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Reactor Coolant Supports: DI.1, 1967 5 (a) Applicable Construction Code Section III 19 77 Edition, W78 Addenda, NoCode Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Ed, Add thru 2000 (c) Applicable Section XI Code Cases None 6 Identification of Components ASM E National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No No Identification Built Installed (Yes or No)

RC-00570A Target Rock Corp N/A N/A RC-570A Unknown Removed Yes RC-00570A Target Rock Corp N/A N/A RC-570A Unknown Installed Yes RC-00570B Target Rock Corp N/A N/A RC-570B Unkown Removed Yes RC-00570B Target Rock Corp N/A N/A RC-570B Unknown Installed Yes RC-00575A Target Rock Corp N/A N/A RC-575A Unknown Removed Yes RC-00575A Target Rock Corp N/A N/A RC-575A Unknown Installed Yes RC-00575B Target Rock Corp N/A N/A RC-575B Unknown Removed Yes RC-00575B Target Rock Corp N/A N/A RC-575B Unknown Installed Yes RC-00580A Target Rock Corp N/A N/A RC-580A Unknown Removed Yes RC-00580A Target Rock Corp N/A N/A RC-580A Unknown Installed Yes RC-00580B Target Rock Corp N/A N/A RC-580B Unknown Removed Yes RC-00580B Target Rock Corp N/A N/A RC-580B Unknown Installed Yes I-RC-2507R-1 Unknown N/A N/A None Unknown Removed No Piping IRC-2507R-1 Unknown N/A N/A None Unknown Installed No Pipng IRC-2507R-I Unknown N/A N/A None Unknown Removcd No Supports 1RC-2507R-1 Unknown N/A N/A None Unknown Installed No Supports PBF-7050a Revision 2 12/02/02 SEM 7 11 1

FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES*

As Required by the Provisions of the ASME Code,Section III, Division 1 Pg. 1 of 2 I Manufactured and certified by Target Rock: 19j6E Broadhol'ow Road, E Farmingdale, NY 11735 (name and address of N Certificate Holder) 2 Manufactured for Wisconsin Electnc: 6610 Nuclear Rd: Two Rivers WI (name and address of Purchaser) 3 Location of installation Point Beach Nuclear Plant, 6610 Nuclear Rd : Two nivers, WI (nam3 and address) 4 Model No. Series No.. or Type 80B-00163-3.. Draving 80B-001BB-3 Rev. A CF;N i /A 1977 Winter 1978 2 None 5 ASME Code, Section Ile. Division 1:

(edition) (addenda date) (class) (Code Case no) 6 Pump or valve Valve Nominal inlet size 1 Outlet size I (in.) (in)

Material Body SAIL2 F316L . Bonnet SA479 XM19 Disc SA564 630 Bolting SA453 660 7

(a) (b) (c) (d) (e)

Cero Nat'l Body Bonnet Disc Holder's Board Serial Serial Serial Senal No No No No. No.

48 n/a 287 0128 145 49 316 0150 149 309 (1147 151 51 324 0149 143 52 314 0138 087 53 282 0134 101 If/a j - = £3

• Supplemental ilformafon i i 1:rm of ists. sketches, or d'awirgs may be used pro,. ded (1) size is 812 x 11. (2) information in 'lems 1 througi 4 on this Oata Refa rtis included on each s"-sel. (3) eah sheet is numbered and the number ol sheets is recorded at the lop of this form (12 1FS,Th s form (E00037) may be obtained from tre Order Dept. AStLE. 22 Lat Dnve Bo4 2300. Fa rfield NJ 07007-2300 REPR'NT 6 93

FORM NPV-1 (BACK- Pg 2 of 2)

Certificate Holder's Senal No 48 - 53 -

IF or valve pressure class - N/A (1) 8 Des:gn conditions .2. 5,- psi 700 (pressure) (temperature) 9 Cold working pressure 4372 psi at 100 'F nsi

10. Hydrostaic test 6575 . psi Disc differential test pressure 4825

11. Remarks- Indicator Tube SA479 316 SIN's 4961.4965,4966.4964,4962.4963 Clamr Ring, SA479 XM19, SIN 393,392-389,388.391, 390 CERTIFICATION OF DESIGN T L Kettles P.E. State NY Reg No 029729 Design Specification certified by P E State . -- Reg. No. -_-_-

Design Report certified by Not applicable CERTIFICATE OF COMPLIANCE this pump -.r valve conforms to the ruies for We certify that the statements made in this report are cor-ect and that construction of the ASME Code, Section III, Division 1.

N-1947 _ Expires 1211212001 N Certificate of Authonzation No Date /O/Z.'/ZOO, Name Target Rock Sign d' d* -.

z R E Glazier, a Ma.ger, Q E (N Certificate Holder) (authorized representative)

CERTIFICATE OF INSPECTION of Boier and Pressure Vessel Inspectors I, the undersig"ed, holding a valid commission issucd by the National Board New York and employed by Commercial Union Ins I and the State of Provic2 of in this Data Report on01__-,,__,____

Boston, MA _ have irspected the pump, or valve described of Holder has constructed this pump or valve, in ana slate that to the best if m/ knowledge and belief, the Certificate accordance w=,tfthe ASME Code. Section II1,Divison 1.

any warranty, expressed or implied.

By signing this certificate, noither the inspector nor his employer makes neither the inspec:or nor his employer shall cnncerninq the corponent descnbed in this Data Report Furthermore, be liable in any manner for any personal injury or property damage or a loss of any kind arising ,rom or conneucteu v.,th this inspecton r Oate/C-2-,"/ Sr;ged _t 1 Ccrrmissons _____

(uthC*- 'ns~ecicr) (Nal I Bd (,ci eridnrsae~nts) and sate or riov and rv)

/ ff (1) For manualy ope-atrd val.,os on',

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 15, 2002 700 First Street, Hudson, WI 54016 Sheet: 1 of 2

2. Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 9946177 Repair/Replacement Organization P 0. No, Job No Etc 3 Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection Westinghouse Spec 676241 5 (a) Applicable Construction Code USAS 16.5, 19 66 Edition, No Addenda, NoCode Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No No Identification Built Installed (Yes or No)

See attached

7. Description of Work: replaced bolting and seal welded valve

8. Tests Conducted: Hydrostatic [] Pneumatic El Nominal Operating Pressure [] Exempt [

Other El Pressure psi Test Temp OF

9. Remarks RR2002-0073, 2002-0079; CAP 030712 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ISI Coordinator Date / / *,

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid cormmrission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Ownei's Report during the pei od August 23. 2002 to October 15, 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

/7 -I,.y Commissions WI-100128 Inspector's S(ignature National Board, State, Province, and Endorsements Date: lAi.', /.I :'c"?

PBF-7050 Revision 2 12/02/02 7.11 1 SEM%1

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY (CONTINUATION)

As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date Oct ober 15, 2002 700 First Street, Hudson, WI 54016 Sheet: 2 of 2 Unit: 1

2. Plant Point Beach Nuclear Plant WO 9946177 6610 Nuclear Road, Two Rivers, WI 54241 0 No, Job No Etc Repair/Replacement Organization 10

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Rd Authorization No. N/A Expiration Date N/A Two Riveis, WI 54241 address

4. Identification of System: Safety Injection Westinghouse spec 676241 5 (a) Applicable Construction Code USAS 16 5 19 66 Edition, No Addenda, NoCode Case (b) Applicable Edition of Section XI Used foi Repair/Replacement Activity 1998 Ed Addenda tlni 2000 (c) Applicable Section XI Code Cases None 6 Identification of Comtonents ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Manufacturer Serial No. No Identification Built Installed (Yes or No)

Component Velan Unknown N/A SI-853A Unknown Corrected No SI-00853A Unknown None N/A N/A Unknown Removed No Studs/Nuts Nova None N/A N/A Unknown Installed No Studs/Nuts

______ I I 4- 1 1 I t I I + I I t T 1 4- 4 i I t T I 1- t t-

______ .1. 4. + +

4. 1 + 4 t I

4. I I I I

________ I. I l* l* I

______ I I 4- 1 1 I I 1 4 + I I t 1 I 4. 4 I I t I

______ 1 4. I 4- 1 4 4

______ 1 4. I + + 4 4

______ 4. I I + 4 I 4

___________________________.1___________________________

.1________________________ - ______________________- _________--

PBF-7050O SEN1 7 11 I R*,*s wIll2 I2,02,02

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corpoiation Date Oct ober 16, 2002 700 First Street, Hudson, WI 54016 Sheet- I of 2 2 Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 9945054 Repair/Replacement Organization 110 No, Job No Etc 3 Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address 4 Identification of System- Safety Injection Bech 6118-M21; Graver Dwg L-24015 and L-24016

5. (a) Applicable Construction Code API 650 19 66 Edition, N/A Addenda, None Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No No Identification Built Installed (Yes or No)

See Page 2

7. Description of Work: Correcterd minor boric acid leak; replaced CS manway bolting with SS.

8 Tests Conducted. Hydrostatic Pneumatic El Nominal Operating Pressure [] Exempt El Other El Pressure See Remar ks psi Test Temp Ambient OF

9. Remarks RR 2002-0075, 2002-0099; CAP 030632; Pressure calculated at 28.3 psi at 99.5% capacity.

Antficable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the repoit are coirect and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp. N/A Certificate of Authorization No. Expiration Date N/A Signed ISI Coordinator Date I///7 /)-?eel Owner or Owniers DesZnee, Title / 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 of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period September 13, 2002 to October 16, 2002, and state that to the best of my knowledge and belief, the Owner has performed examnations and taken corrective measures desclibed in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind aiising from or connected with this inspection.

• 2 "/. Conmmssions WI-100128 Inspector's Sign~ature National Board, State, Province, and Endoisements Date- ,4io. 1'/ Ze'Os PBF-7050 Revision 2 12/02/02 SEM 7 I1 1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY (CONTINUATION)

As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 16, 2002 700 First Street, Hudson, WI 54016 Sheet: 2 of 2

2. Plant Point Beach Nuclear Plant Unit. I 6610 Nuclear Road, Two Riveis, WI 54241 WO 9945054 Repair/Replacement Organimzaion 1P0 No . Job No Etc

3. Work Perfotmed By: We Energies Type Code Symbol Stamp N/A namre 6610 Nuclear Road Authorization No. N/A

-Two Rivers, WI 54241 Expiration Date N/A addiess

4. Identification of Svstem- Safety Injection Bech 6118-M21; Graver Dwg L-24015 and L-24016

5. (a) Applicable Construction Code API 650 19 66 Edition, N/A Addenda, None Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Ed. Add thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Comoonents ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No Identification Built Installed (Yes or No)

T-013 Graver Tank and 1660-1A 1968 N/A T-13 Unknown Corrected No Mfg Co.

T-013 Manway Gravei Tank and N/A N/A Man%\ay UnknoNn Removed No Bolting Mfg Co Bolting T-013 Manway Cordinal N/A N/A Bolts Unknown Installed No Bolts Industrial Products Inc.

T-013 Manway Nova Machine N/A N/A Nuts Unknown Installed No Nuts Products Corp I I I I + { I i I

________ 1 4- 4 1 t 1 4 +/- 1 1 1-I 4 1 t t t t I 4 1 + t t t

________ .1- 1 + -t t 4- 1 1- t t T 1- I 1 4 -i Ii PBF-7050a Re%ision 2 12/02/02 SEM 7 11 1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner Nuclear Management Corporation Date October 14, 2002 700 First Street, Hudson, WI 54016 Sheet: I of 1

2. Plant Point Beach Nuclear Plant Unit: I 6610 Nuclear Road, Two Rivers, WI 54241 WO 0212380 Repair/Replacement Oiganization t' 0 No, Job No Etc.

3 Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System- Safety Injection West. Spec 676241

5. (a) Applicable Construction Code USAS B31.1, 19 66 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No No Identification Built Installed (Yes or No)

SI-00853B Velan N/A N/A SI-853B Unknown Corrected No SI-00853B Velan N/A N/A Studs and Unknown Removed No Nuts and Installed

7. Description of Work: Corrected body to bonnet leak and replaced damaged bolting (seal welded).

8. Tests Conducted: Hydrostatic E] Pneumatic [] Nominal Operating Pressure [] Exempt 19 Other Fl Pressure psi Test Temp. OF None

9. Remarks RR 2002-0080 and 2002-0086; CAP 030712 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed

.- a '-,. ,

Owler or Owner's Designee, Title ISI Coordinator Date /7/ / 6O5 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 of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period September 11, 2002 to October 14, 2002. and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures desciibed in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

66< 7 ,_>.6.,, Commissions WI-100128 Inspector's Sig(ature National Boatd, State, Province, and Endorsements Date: ,, 2-e"63..

2-,',3 PBF-7050 Re', ision 2 12/02/02 SEM 7 11 1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 23, 2002 700 First Street, Hudson, WI 54016 Sheet: I of 2

2. Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 0212465 Repair/Replacement Organization P 0 No, Job No Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authoiizaton No. N/A Two Rivets, WI 54241 Expiration Date N/A address

4. Identification of System- Safety Inlection West Spec 676241

5. (a) Applicable Constiuction Code USAS B31.1. 19 66 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repaiis/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No No Identification Built Installed (Yes or No)

See Attached Page

7. Description of Work: Seal welded body to bonnet leak and replaced bolting.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Opera ting Pressure LI Exempt 0 Other 0I Pressure psi T est Temp. OF

9. Remarks RR 2002-008 1, 2002-0087, CAP 030630, CAP 030697 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp. N/A Certificate of Authorization No Expiration Date N/A Signed *-/.7. / -. "., ISI Coordinator Date ///6.2cu~2 Owner or Owneies Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding valid commission issued by the National Board of Boiler and Pressure Vessel a

Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period September 11, 2002 to October 23, 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions WI-100128 Inspector's'Signature National Board, State, Province, and Endorsements Date: P2-, I1- - 3 pNri-' 10/

[(~La min 2 12/02/02 SEM 7 11 1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY (CONTINUATION)

As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 23, 2002 700 First Street, Hudson, WI 54016 Sheet: 2 of 2 2 Plant Point Beach Nuclear Plant Unit 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 0212465 Repair/Replacement Organization 1P0 No, Job No. Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West Spec 676241

5. (a) Applicable Construction Code USAS B31.1 19 66 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Ed. Add. thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No No Identification Built Installed (Yes or No)

SI-00853D Velan None N/A SI-853D Unkown Corrected No SI-00853D Unknown None N/A Studs and Unknown Removed No bolting nuts SI-00853D Markson None N/A Studs and Unknown Installed No bolting nuts PBF-7050a Revision 2 12102/02 SEM 7 I1 1

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 22, 2002 700 First Street, Hudson, WI 54016 Sheet: 1 of 2

2. Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 0207877 Repair/Replacement Organization P.O No, Job No. Etc.

Work Performed By: We Energies Type Code Symbol Stamp N/A 3.

name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West Spec 676241

5. (a) Applicable Construction Code B16 5, 19 No Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Manufacturer Board Other Year Removed or Stamped Name of Component Manufacturer Serial No No. Identification Built Installed (Yes or No)

See Attached Page

7. Description of Work: Replaced valve pipe pup piece.

8. Tests Conducted: Hlydrostatic E] Pneumatic D Nominal Operating Pressure M Exempt 0 Other 1:1 Pressure 725-735 psi Test Temp. Ambient OF System Leakage Test

9. Remarks RR 2002-0082 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE ASME Code, I certify that the statements made m the report are correct and that this conforms to the rules of the Section XI.

Type Code Symbol Stamp: N/A Certificate of Autliorization No. Expiration Date N/A Signed ISI Coordinator Date Owner or r'1DLSIguce.I, Itl/

n*%% /

CERTI FiCATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel described in this Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components the best of my Owner's Report during the period September 11, 2002 to October 22, 2002, and state that to measures described in this knowledge and bhi.f, the Owxner has performed examinations and taken corrective Owner's Report in accordance with the requirements of ASME Code,Section XI.

or implied, By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed Ownei's Report. Furthermore, neither the concerning the examinations and coliective measures described in this any personal injury or property damage or a loss of any Inspector nor his employei shall be liable in any manner for kind arising from oi coinxtcd with this inspection.

Commissions WI-100128 Inspectoc'/-Z',iht!C National Board, State, Province, and Endorsements Date: .**'-/?w /, ?" 3 PBF-7050 SEM 7.11.1 Revision 2 12/02/02

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY (CONTINUATION)

As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corpoiation Date October 22, 2002 700 First Street, Hudson, WI 54016 Sheet- 2 of 2

2. Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Riveis, WI 54241 WO 0207877 Repair/Replacement Organization P0 No. Job No Etc

3. Work Performed By. We Energies type Code Symol Stamp NA-*

name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address 4 Identification of System- Safety Injection West Spec 676241

5. (a) Applicable Construction Code B16 5 19 No Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Ed. Add. thri 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME Corrected, Code 7o National Manufacturer Board Other Year Removed or Stamped Name of Name of Installed (Yes or No)

• .,IOl r, No o ,rS1 No Identification Built Component SI-00892A N/A SI-892A Unknown Removed No Rockwell Mfg NIA Co SI-00S92A 1987 No SI-00892A Rockwell Mfg CD 857 N/A SI-892A Installed Co 2"-SI-902R-2 N/A NT 6179H Unknown Installed No Sandvik N/A 2"-SI-902R-2 2"-SI-902R-2 N/A N/A Unknown Removed No unknown N/A 2'-ST-902R-2 PBF-7050a SEM771 1 Revision 2 12/02/02

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 14, 2002 700 First Street, Hudson, WI 54016 Sheet: 1 of I

2. Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 0212464 Repair/Replacement Organization P.O No, Job No Etc

3. Work Performed By: Day & Zimmerman Type Code Symbol Stamp R name 1866 Colnial Village Ln, Suite Authorization No. R-1958 101 Lancaster, PA 17601 Expiration Date 10/26/02 address

4. Identification of System: Component Cooling Water West Spec 676241 Rev 0 5 (a) Applicable Construction Code ASME VIII, 19 68 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

HX-004 Sentry Equipment 3996-3E NB 0331 HX-4 1968 Corrected Yes Corp

7. Description of Work: Corrected flange to shell leak by seal welding.

8 Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure [: Exempt N Other El Pressure psi Test Temp. `F 0 t, 1?1P '1)A19.f(1(If 9(1(19_(111 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code, Sectton XI.

Type Code Symbol Stamp. N/A Certificate of Authorization No. Expiration Date N/A Signed ISI Coordinator Date 9 - -11 - -- 1; -

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 of Wisconsin and employed by HSBCT have inspected the components described in this Owvner's Report during the period September 17, 2002 to October 14, 2002, and state that to the best of my "knowledgeand belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner foi any personal injury or property damage or a loss of any kind arising from or connected with this inspection

<- - L.- Commissions WI-100128 Inspector's Si gature National Board, State, Province, and Endorsements Date: ,.ft //, C/f;!_3 PBF-7050 Revision 2 12/02/02 SEM 7 11 1

lii'Proi iiioit-. of d-16 %:)il ;~ C

%I inulik A lorlr A-u2Du. iii,. iir I'.;- 't kii.-

1, -.. 11 ..1

.1 s 0C13993E :i'jso.3.. No.. lAd rI si,.a. i n. I . to h, .ini1 .). ad Io r *inl g UtlA , %i % s (sot It .1 is .urtanksl. 1-ilk i% of ,imk~tc it ss l or %h( 1%o it hr itn.x, hang, rs.

N~,c.in t ikim 7

7 I. t~ orT.

Oh.SPrc Mi, T Ticncs~jn.Allowancc/3n.

S.l 0im.F t.- -51 ~ onitj 7L17

~ ~ilAM'.

~1C3______ itti I T. I) t~or C. S,,ectionted - Ifficienc y.2 ~ ~ sciesat DT .i'Tz7.7-p. (lult) 'ic .Cplet I lie..'orNo) flyO C ii

.~r 2 IT.I2....... IHA. -_____ Sect ioned ____\o. of ( ourse s 6 rm 6i. 111A)-Zt  :.tittrii ISLrlJ L t -:J ..

T.S. -

en..

0QQ (11)Matecrial ..---

Ellsiptical I. A C ... ca.I l 2IT.S flmhpercics 14.l.1 I F at

_60,CGOO...

Side to r-ek-,r ii.. cd) Thi.,-,, idiw.

Ws.,i.n Rtiu o Apes Angle Redi.. Diam.,ter (Corivee or Concave) 1.) =.:Z0.. in____IT__01 _____ ______

if rrnts~b bolts uscc!____

maeilspec No..SSze umher)

Other fastening ... lrcldici...........

(rescribe or Attach Sketch)

-. STV~O~~ ~t-i~7;if~If hol low -_____ Attachimnc _ _____ Pitch_____X_________

tN;i7-l-(Size of Hole) (Threiaded, lheledoriz.) (Vant.) (Nominal)

JKl-AC. T (I (EJI :________ _________

(De~ce~beooj~m1Jt7tVi-T FCi.... i, dimension, i f b olted. descrileo kth Co.totrut ted titr m~ix. (he 'Te.stmp ing prt s%

ol'ta~..rk __J.50 psi at mak. temp...425G r. less than -2Oo) re____

s~tci 2u.~cs.~.p lIit m% 1I Lin IoI to lie Citmflth ted for t ube sections%

11) TLIII Sill L.TS: Stationary. Material..51h Li2-1004(ubec Mam Prssre In. cme f1'CdC~i I loating. N1itecial __Kind __&_______No Diam.-____ In Thickness -In. Attachment_______

S .-213 No Inchese II T1Il 11;: mIatt r.tiI12 (Kind 4...O.D)......?....

-,P;. fN.

In. Thickness -04 I~e sme ume

~ I. ....... Type .co.Ci..........

f51ti.i,ht or UI)

Iltk-in.12-l% inil to bt compli led for inner chnmbi.rs of jackeited vi.ss Is, or channel% of heat echangers.

Nomninal Corrosion 12 SIII.LI. kMattrial _________ T.S. ________Thikit.-nss __ In. Allowance .. Jn. IDiam ___Ft.-__In. Length - It -in (ksind rid~pec.Noa i Rll.orFk3 LS Ipec. Min. T.S It riseted de.

13. SLAMS- Long ____________IIT. R.T. _______Sectioned E_____ifficiency........ e' scribe ..eams fikeloed, Dbl..Single. Lap.Dutti 5. rY Nol' (Spot or Complete) TY-e. or No) futly on re.

Girth __________II.T. -______ f.T. -____ _Secetioned -____ No.of courses - Ifor.

I . Ill-ADS (a) Maiterial ...SA 7.1871. GI. T.S. ...60,CM (b) Material -____ T.S. ______ c) Material ______T.S. _______

Crown knuckle Elliptical Conical Hemlspheriest Flat Side to Pressure Locat ion Thicknessa Radius Radius Ratio Apes Angle Radius Diameter (Canves 4ir Conicave)

(a) Top, bot to m,ends _____ __________ _____ _____ ___________________

(b) Channel . i...... at___ 300.'~ in 4 r-3 7 MVn.

(c) Floating ____________ _____ _____ _____ ________

If remosable, bolts used (a) (LMtil. pe No~ (b) h 193 ,,2,00 4 (c) ________________________Other fastening llDescribe or Attach`Sketch, Hlydrostratic

15. Constructed for max. Min. temp. (when -'- Test allossabll ssorktn 3. press.L 2 1,ý8 psi at max. temp.....6 .?F. less than-20 )

0 0 F. Pes 3...Isi.p Items hr ltotc to he completed for all vessels where applictbibl.

16. SAl 1.1 1) VALVL OUTLETS. Number _____________Size ___________Location ___________

17. NO/.ZI. S Purpo se (Inlet, Reinforcement How 0~l,%1t. Drai) Number Ofamn or Size Type Material Thickness. material Attached 2 114," sof"c -- 8-11, 01An

'ItpostmelId Seat-treated. List under remarks other internal or axtternal pressures with coincident temrperatuare when applicable.

l' ili\I f- I (litkL)

IS. l\ *.Ol t" i hO\ %tii,lh .b-s. \o. ___________________Stc, ____________ .o~zatuon__________________________________

. I I1,lhol. ,. No. t . _ , L cS,

[.o ation

• .)I'l \l\,

Sitc L.ocation Thrt.ded, No.

l.ugs L gs Other Attachtd

19. St II'POKS '.rt-.

,:-l Si,- - ,,2 ^z---On V" L' part.)

kl~riet description of purpose of the vessel, as Air Tank. Alter Cooler. Jacketed Cooker. etc. State conventw of each

'.t c'trltf thal t the slatements made in this rtport irc corrc t rnod thatt all details of design, matcrial, construction, and v.orkmanshtp of this vcsscl conlorm to the AS\IE Code for Unfired PIressure Vessels.

Datec. " ... 196. . Sirgncd Scn :ip-rt l-y*_ t M=,.n iif~cturer " r .- "*

6 c rtl,,,*te of Auttra.. tton I:spmres...-!, ." rL-31.--1 9 C:EIfI FICATE 01" .'11l01 IN' I'EC'1IIO VESSEL MADE BY S:iM_*1ipOatJ--- ' at C-lo.=p W coilsii Vessel Inspectors and/or I. the undersigned, holding a vklid commission issued by the National Board of Boiler and Pressure

- " t'tr" t",*' -or

"; a=!:!n and employed byD-Pt Of .

tI-c S:ate or Proince have inspected the pressure vessel described in this manufacturer's "data report on - 7 19 and state that to the best of my knowledge and belief, the manufac the ASME Boiler and Pressure Vessel lurer has constructed this pressure vessel in accordance with the applicable secttons of Code.

or implied, concerning the B) sigring this certllcate neither -the Inspector nor his employer makes any warranty, expressedhis employer shall be hable pressure vessel described in thts minufacturer's data report. Furthermore, neither the Inspector nor or connected with this inspection.

tn an) manner for any personal injury or property damage or a loss of any kind arising from D.te 2'- 7 1968 V11____ 41:4 -___ Commissions JIM-..LB92J.i Nat'1 iosrO or State and No.

Inspectors Stinature CERTIF:I" VI E OF FIEIEL) ASSEMBILY IN'WECTION of Boiler and Pressure Vessel Inspectors and/or 1, the undersigned. holding a valid commission issued by the National Board of the Slzate or Pro'tnce and employed by have compared the statements in this manufacturer's data report with the described pressure vessel and state that parts referred to as data items and that to the best of my knowledge and belief not included in the certificate of shop inspection have been inspected by me with the applicable sections of the ASME the manufacturer has constructed and assembled this pressure vessel in accordance subjected to a hydrostatic test of - psi.

Boiler and Pressure Vessel Code. The described vessel %,asinspected and any warranty, expressed or implied, concerning the By signing this certificate neither the Inspector nor his employer makes neither the Inspector nor his employer shall be liable pressure vessel described in this n anufacturer's data report. Furthermore, any kind arising from or connected with this insp*ection.

in any manner for any personal injury or property damage or a lose of Date 19 Commission$ I Inapector'a Signature 67 Nat'l Board Or State and No

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 21,2002 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 9942120 Repair/Replacement Organization P 0 No, Job No Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N/A nanme 6610 Nuclear Road Authotization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System Reactor Coolant Westinghouse Spec 676402 Rev. 1; West. Dwgs. 4417D40 & 651B293 5 (a) Applicable Construction Code N/A, 19 No Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None 6 Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No No Identification Built Installed (Yes or No)

T-001 Westinghouse 16A6256-1 unknown Bolting Unknown Removed No T-001 Westinghouse 16A6256-1 unknown Bolting 1984 Installed No

7. Description of Work: Replacement of bolt due to galling.

8. Tests Conducted. Hydrostatic El Pneumatic Ml Nominal Operating Pressure E] Exempt Z Other M Pressure psi Test Temp OF

9. Remarks RR 2002-0089; CAP 030702 ApphlLable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report ate correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp. N/A Certificate of Authorization No N/A Expiiation Date N/A Signed , . ISI Coordinator Date Owner or Owners Designee, Title t, 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 of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period September 22, 2002 to October 21, 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied.

concerning the examinations and corrective measures described in this Owner's Report. Furthermote, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

SKCommissions WI-100128 Inspectoi's gniature National Board, State, Province, and Endorsements Date: ."*,-". /-5;' '3 PBF-7050 Reviston 21 12u2/U2 SiMt 7 11 1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 21, 2002 700 First Street, Hudson, WI 54016 Sheet: 1 of I

2. Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 9941998 Repair/Replacement Organization P.O. No, Job No. Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N//j 7 L, name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Reactor Coolant

5. (a) Applicable Construction Code Section III, 19 65 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Add. through 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

R-1 Babcock & 610-0115 NB 0138 Conoseal 1968 Removed/ Yes Wilcox Co. Flanges Installed

7. Description of Work: Replacement of two reactor head instrumentation port conoseal male flanges.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure 0 Exempt El Other El Pressure 2255 psi Test Temp. 547 OF System Leakage Test

9. Remarks RR 2002-0092 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A

,igne ISI Coordinator Date //* /P o

_e__Designee,-ide Signed o Owner's Designee, Ttfle Owner or / -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 of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period September 24, 2002 to October 21, 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

41 -,-, Commissions WI-100128 Inspector's Signature National Board, State, Province, and Endorsements Date: 7,

-/', '

-3 PBF-7050 Revision 2 12/02/02 SEM7 11 1

t*SsICr7OL VErsa, I P 6./f 0. SS D FORM& N-1AA P\A "..FCUES IWOTFUNUCLU.A2 \ SSLS

(,Q,1&'Alternlatce)a 2c 10o ile (TI r-.kr Lr ýco...pletnly 7 .A -Lop ed Vae-se!s G' A,- required by the P~oaisicrns offthe .~IE'Code t(riles zid 0~:e Nal~onail fzt~-

r'~ss.

by Mrnuftctuýet

'--2. Mtan ufI`cwred for Wes3 ti-nChc us3-zA:'--) Wi CDZ71 tJ:L L:;.

,~.Ž~'.-

• ic~i 3.Tp V...e..... VsslN.( 6 -o.nr  :- (NaIme and idc:-tss of F'tirchistr'ý16 (H-oriz or Ver S8r.l 1.re (S8t & SttN SLA-302B* ý Mtr+/-. - rg 2

4. .. Ok~. 8O5 .505- Th 6 cc""- 66 1i:

Shl Sh Ml:'oer:al... .-:..

l find & 5Spec. No )

Y..... ...... T ....

(l.1in. of tr.-ce specified)

.. ~ ... hk .. t. z. - Allow ...... In. DiC-i1 .. ......

tt9 !n Lcng:b .. 2. ... ....

3 Oe-13c S. Seams Long dtt.. ..... T. e ~cec.........

E o (if Class 0)

Girth B.t ld .... .H.T. yes R. 3

. R..... ....... No. of Courses ... . .. 0....

6. Hleads- (;,) Material *0 3kOŽ Pn.9" ()roea. 5¶i~S~2.....*S Location Crown Knuckle Elliptical Conical1 fllEisphecriczal Flat Side to 4rTZ!bL.c (Top. bottorl, ends) Thickness Radius Vadius Ratio Apex Angle .adjus Otame-ter (Con vex at (a). TOT) 486 5/?6C&.ci if~~~~~~~~ . - . rT.

( i.oa ~~~~~~~~...

A4.Ohrfutr r.r.

....... / ... ..........

bot.s.......Ž52.Ab ~~~~..... ...... .......

(Material. Spec. NIo., 7.5., Size. Namrber) (Describe or A ttachb'.p: XrM)~ 1

7. Constructed fo£hap im ac ....... H fl, Tes operating presz. 2 . . . . . 21j .

PSI. at nlax. cetup..2 5 902 at;tepTf2 F e~-

in_ iPess.3107

8. Safety or Xeltef Valve Outlets: .4uMer ........... ..... Size........ ..... Loca-tton .......................

9. Nozzles:

• c1/2Cd ~t13 3) 4d Ccd~t Ca.o 13 Purpose (Inlet, Mo14d. Code 133532l3-2. 2 Renfnrce'rent HowF Outlet. Drain) Nunbcr Diazr. a: Si,,e Type Materj:.1 Thtck-iess Materialt11c

~, (P

~ i>;uJK~~.ariho'cs, "A41ah bS'.'h Z~17..

......... .. 59 9 . .. .::MJS.

10.Insecton No.................... Sie. ........ Location. ... ............. ........................ .......... ..................

Openings: -andholcs, No ....................... Size_. ...... .. Location.. .... . ....

Threaded., No ...... .......... ic.............Si:

.- LocationL . .......... '..............

(Yes of No) ~ N iriber) C (Nu'nbe-) (De: , ( Hobi-

............ .V2.I.3I:... V "T.YtZZrr  :... ..

2 -- U9'*.I.-J4 7  :

hfl r~ . 2 .&. ....... L.~ )~.............

-U ' .i........................... m.-- '$r

ýLL..SP............v4 1......... ........... ...... . ..........................

......... . ................... 6...................... .................. ....... ....

(Brief description 31 purpose of the vessel - State Contents.)

hIt Postwetd Het-Ireai-ctcd.

2 Last oth.Žr intornatl or exiernzd presst-re with coincident temrperature when applicable.

We certify thast the statements marde in this re'-ort arc correct end that all details of material design, cosiýdwor,-&stip of 1' vessel conform to ?he A5.I.E Code for Nuclear Vesrels cn>e,&3 ~L~;

Dae.Decen~bzr 4~. ..... 1998.. Signed Bbzck WZ

'J`. z ~

Certificate of Authorization Expires L. 7i.?z.r...........

in_!1Lau.-Vj()J ..............-

Dasigo infomation on fle at The OF DESIGN! abr~

Strssnalsisreprtefile at ýeBLs B~C~

t~~

~ .

n

.~. . ............

Design specification~s certified by ... L. R. KS: PrfEn. . Stt.A .PŽgN.. 7>

Stress. ana1.5 sis report certified by ..... ........ ...... Q r..............

........ Prof Eng .......... State .. ... h. Reg Nc. .&99Z3/4 CEIITIVEl ATE OF SHOP INSPECTION' VESSEL M.ADE BY . .. The Bbz::k & .- yCzse -,? 4 at Mt Vr . n .. n`-...,

1, the undersigned, hold.-ng a valid cammr.-sston tss~ed by Cie National Ba~rd of Bailer and Pres:ure Vess :1 In spectors  :.ztz:z

. ....................and employed by T.' s0 S.B I  :. .£ of

.hxir . . 'Th-

!c.'7ff-: d ~

4 ive inspected the p~estuv:e vessel dnscrtbed in tHis n.:-n_'2!a:Ur~r's data re.-orx or .. ...... .... ................ /. el _< 19 6~

ale that to the best of -. y knowledge zod belief. the man=Ufacturer his consi-3cerd this pressure vessel in accorddace %itih in-c %S :E C~ode for Nuclear Ve-ssels.

fly signing this certificate neither hýe Inspe-ctor no- his -wnpic: er makes any wa::an~y, eyp~et:ed ar impliad, conconinir. the ~t¶'

vessel described in this rnarnufac'urer's datar;o. Fu.::htr:ro.e, neiZhe: the? lnspecur nor his e~rplo),ar shall be hab~e in any maI:,se fat any personal injury or prop-rt-- darrage cr a losz of aniy &:.nd ariziaot from or cornnected with th's inspect.on

- Insrectors SLinature Nationpl Dosed or Siate arnd No.

FORM NIS-22 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI Nuclear Management Corporation Date Octcober 22, 2002

1. Owner of 1 Sheet: 1 700 First Street, Hudson, WI 54016 Unit: 1

2. Plant Point Beach Nuclear Plant WO 9937845 6610 Nuclear Road, Two Rivers, WI 54241 Repair/Replacement Organization P.O No., Job No Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Expiration Date N/A Two Riveis, WI 54241 address

4. Identification of System. Residual Heat Removal

5. (a) Applicable Construction Code B31 1, 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Year Corrected, Code Name of Manufacturer Board Other Removed or Stamped Name of Manufacturer Serial No No Identification Built Installed (Yes or No)

Component N/A N/A RH-700 Unknown Corrected No RH-00700 Darling Valve Co.

Unknown NIA N/A None Unknown Installed No RH-0700 Cap

7. Description of Work: Replaced capped end of the leak off line due to minor leakage.

Exempt LI

8. Tests Conducted- Hydrostatic El Pneumatic Dl Nominal Operating Pressure Z Other 11 Pressure 2260 psi Test Temp. 546 OF System Leakage Test

9. Remarks RR 2002-0093 . eAt 03406*.

AppllLable ioanuracturer's Data Reprs to oc attac e CERTIFICATE OF COMPLIANCE Code, I certify that the statements made in the iepoit ate coirect and that this conforms to the rules of the ASME Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed

• J,...*/' Z.. *-*,- Z - ISI Coordinator Date j6iý6 uv,1Ivr ul lick t f 0%&nerorV'A11e15 CSIý-IICC.

I C CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel described in this Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components state that to the best of my Owrner's Report during the period September 25, 2002 to October 22, 2002, and measures described in this knowledge and belief, the Owner has performed examinations and taken corrective Owner's Report in accordance with the requirements of ASME Code, Section XI.

expressed or implied, By signing this certificate, neither the Inspector nor his employer makes any warranty, Owner's Report. Furthermore, neither the concerning the examinations and corrective measures described in this injury or property damage or a loss of any Inspector nor his employer shall be liable in any manner for any personal kind arising from or connected with this inspection Conmnissions 1%VI-100128 Inspector's Signature National Boai d, State, Province, and Endorsements Date: J - 7 PBF-7050 SEM 7 11 1 Revision 2 12/02/02

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 31, 2002 Sheet: 1 of 1 700 First Street, Hudson, WI 54016 Unit: 1

2. Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241 WO 0212624, 0212683, 0212695 Repair/Replacement Organization P.O. No , Job No Etc.

Type Code Symbol Stamp NR

3. Work Performed By: Welding Services Inc.

name 2225 Skyland Ct. Authorization No. NR-69 Expiration Date 11/07/2004 Norcross, GA 30071 address

4. Identification of System: Safety Injection West Spec G676262

5. (a) Applicable Construction Code Section III, 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

Delta Southern 41035-67-1 N/A T-34A 1967 Corrected Yes T-034A Co. nozzles

7. Description of Work: Modified nozzles to remove indications on the inside surface.

8. Tests Conducted: Hydrostatic El Pneumatic Ml Nominal Operating Pressure 0 Exempt El Other El Pressure 735 psi Test Temp. Ambient *F System Leakage Test

9. Remarks RR 2002-0094, 2002-0100, 2002-0102, 2002-0105 nppiciiuic LVk411U14L1u1;I .JaLa .sLIu, Appllhcabe MVanIuI ct;Ur l ttta ep.Ult os 0

• Lvl CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ISI Coordinator Date L7 1-2 &,, 53 S* w** *T fl*.-re nr fluSre6 fl.... nee .....

m f /

owner or Ownees Desi-ee 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 of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period September 26, 2002 to October 31, 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

L.A A*"

• Commissions WI-100128 Inspector's SIgnature National Board, State, Province, and Endorsements Date: -",,A' 5', Zecr..

PBF-7050 SEM 7 11.1 Revision 2 12/02/02

MODIFICATION F_ OR INSTALLATION OF REPLACEMENT(S) [

FORM NR-1 REPORT OF REPAIR F-TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Job N .3214 Wpldmna Services Inc. Job No 32142

1. Work performed by .. rdinr nn*nltin' PO no. lob no. etcIc (name) frecair o-anization's P 0 no job no , etc )

(address)

2. Owner Nuclear Management Company, LLC (name) 6590 Nuclear Road. Two Rivers WI. 54241 (address) 3 Name, address & identification of nuclear power plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers WI. 54241

4. System Safety Injection System

5. a: Component repaired, modified or replaced Repair b: Name of manufacturer Delta Southern Company N/A WI U009976 1-T34A 1967 c: Identifying nos. 41035-67-1 (biner) (year built)

(rrmrs senal no ) (Nat I Bd No) purisoctional no Section III.1967 Edition N/A N/A N/A d: Construction Code (addenda) (Code Case(s)j (Code Cass)

(editon) 1998 Edition Through 2000 N/A

6.Section XI (addenda) (Code Case(s)j (edition) 1998 Edition Through 2000 N/A

7. Applicable edition of ASME Code Section XI (addenda) [Code Case(s

(edition) under which repairs, modifications, or replacements were made Section III 1992 No NIA

8. Applicable edition of Construction Code (edition) (addenda) [Code Case(s)l under which repairs. modifications, or replacements were made (Code)

9. Design responsibilities Nuclear Management Company, LLC pneumatic - design pressure = pressure By Others psi

10. Tests conducted: hydrostatic -

11. Description of work: Machined existing nozzles "A" and reattached piping inis accordance to customer provided design and (use of additional sneet(s) or sketchtes) acceptaole if properly identilied) calculations Reference No. PBCH-01Q-301 12 Remarks.

CERTIFICATE OF COMPLIANCE or replacement of the items descnbed above conforms to Section XI of the ASME We certify that the statements made in this report are correct and the repair, modification Code and the National Board rules as defined in the publication NB-102, current edition November 7 . 19 2004 Certificate of Authonzation No NR-69 to use the "NR" stamp expires Signed _ Site QA Manager Date October 3 2002 Name Welding Services Inc (Authorized Reoresentatlvebl (Title) (Reoair Oroanization) CERTIFICATE OF INSPECTION and Pressure Vessel Inspectors and certificate of competency issued by the state of 1, the undersigned, holding a valid commission issued by the National Board of Boiler of _- Province of s,,. ns' and employed by Ms 13 C -, C'j? '3, .19 Z C0 2. , and state that, to the have inspected the repair, modification or replacement descnbed in this report on Board rules as been made in accordance with Section XI of the ASME Code and the National best of my knowledge and belief, this repair, modification or replacement has NB-102, current edition By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied. conceming the defined in the publication or the Inspector nor his employer shall be liable in any manner for any personal injury repair, modification or replacement descnbed in this report Furthermore, neither property damage or loss of any kind ansing frorijorconnted wi, this inspection Date (D.c -a, Z.ec 2 Signed 4.. ('( Commissions ,.'2 e., , i ,A (Authonzednsoector) [Nat'l Bd No (incl Endorsements) State or Prov and No I Nn5m-8 01*or . e....an r*~....... i t= ... iii... *. .vn* Pnr~~ Ar, ni,'., O 422 Ti fom.ayb.otand.ro..e.aioa This form may be obtained from The National Bsoardof OTBoiler and P'ressure vessel In-.pecto, av...,v, -P .... ......... I NB-8! Rew6

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 9, 2002 700 First Street, Hudson, WI 54016 Sheet- I of 1

2. Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivets, WI 54241 WO 0212602, 0212615, 0212696, 0212682 Repair/Replacement Organization P 0 No , Job No Etc 3 Woik Performed By: Welding Ser ices Inc. Type Code Symbol Stamp NR name 2225 Skyland Ct. Authorization No. NR-69 Norcross, GA 30071 Expiration Date 11/07/2004 address

4. Identification of System: Safety Injection West Spec 676441 Rev. 1 & 677051 Rev. 1

5. (a) Applicable Construction Code Section III Class C, 19 65 Edition, N__ Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed Addenda thru 2000 (c) Applicable Section XI Code Cases None 6 Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

T-034B Delta Southern 41035-67-2 N/A T-34B 1967 Corrected Yes Co

7. Description of Work: Modified nozzles to remove indications on the inside surface.

8. Tests Conducted: Hydrostatic E] Pneumatic n] Nominal Operatin Pressure 0 Exempt []

Other [] Pressure 720 psi Test Temp. Ambient OF System Leakage Test

9. Remarks RR 2002-0095, 2002-0101, 2002-0103; CAP 030632, CAP 030681; Work also performed by We Enermies, 6610 Nuclear Road, Two Rivers, WI 54241.

n...-.I,..,II 1,.,,,f,, ,,....Yc fl*w, Rennrt In he nnneIed CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code, Section XI. Type Code Symbol Stamp: N/A Certificate of Authorization No Expiration Date N/A Signed ISI Coordinator Date T tO)wner or Ow,,net's Des,,nice. 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 of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period September 30. 2002 to October 9, 2002, and state that to the best of my "knowledgeand belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code, Section XI. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection Z_* 4 (Commissions WI-100128 Inspector's Siý(nature National Board, State, Province, and Endorsements Date: .d/?z't /.; ZCtE3 PBF-7050 Revision 2 12/02/02 SEI7 I1 1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 5, 20}02 700 First Street, Hudson, WI 54016 Sheet: 1 of I

2. Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 0212611 Repair/Replacement Organization P.O. No, Job No Etc Type Code Symbol Stamp N/A

3. Work Performed By: We Energies name 6610 Nuclear Road Authorization No. N/A Expiration Date N/A Two Rivers, WI 54241 address

4. Identification of System: Reactor Coolant

5. (a) Applicable Construction Code B31.1, 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Add thru 2000 (c) Applicable Section XI Code Cases No

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No Identification Built Installed (Yes or No)

PS-1 N/A N/A N/A N/A Unknown Corrected No

7. Description of Work: Rewelded support PS-1 which was cut to remove RV shroud.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pr essure El Exempt 0 F

Other Eli Pressure psi Test TenLIp. 0 V. n-t- 'PP '2flf2-09.Qf

                                                                             *.  .... ...      fl?,

n4 "... ^-.nn -n 1'. ott wl CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code, Section XI. Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ISI Coordinator Date

                ---   1                                                                                                            115 /2- 4; 1L.-5 Chv n,'ne'fl)e*1e-iee_Titde
                                ,')amr 5,-----r6w--eesDesi-ee Tide 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 of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period September 25. 2002 to October 5, 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code, Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

               -                                                   Commissions            WI-100128 2!

Inspector's 4nature National Board, State, Province, and Endorsements Date: ,7,4, 6, zev. PBF-7050 SEM 7.11.1 Revision 2 12/02/02

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI Date October 28, 2002

1. Owner Nuclear Management Corporation Sheet. I of I 700 First Street, Hudson, WI 54016 Unit: 1 2 Plant Point Beach Nucleat Plant WO 0212621 6610 Nuclear Road, Two Rivers, WI 54241 Repaii/Replacement Oiganization P 0 No, Job No Etc.

We Energies Type Code Symbol Stamp N/A 3 Work Performed By: name 6610 Nuclear Road Authorization No. N/A Expiiation Date N/A Two Rivers, WI 54241 address

4. Identification of System: Main Steam Piping: Bech. Spec M-78; Valve: Bech ASpec M-332U

5. (a) Applicable Construction Code B31.1, 19 67 Edition, No Addenda, N.o Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Manufacturer Board Other Year Removed or Stamped Name of Manufacturer Serial No No Identification Built Installed (Yes or No)

Component None None MS-218 1999 Removed/ Yes MS-00218 Velan Inc Installed Unknown None None None Unknown Removed/ No Piping Installed

7. Description of Work: Replacement of valve, immediate piping and elbow.

Pneumatic Fl1 Nominal Operating Pressure 0 Exempt I

8. Tests Conducted: Hydrostatic n]

El Pressure 1000 psi Test Temp 547 OF Other

9. Remarks RR 2002-0097 Applicable Manufacturers uata Report, to e ata,,

CERTIFICATE OF COMPLIANCE of the ASME Code, I certify that the statements made in the report are correct and that this conforms to the rules Section XI. Type Code Symbol Stamp N/A Certificate of Authorization No. Expiration Date N/A Signed 2-- Owieror Owneifs Designee, Title ISI Coordinator Date 11/72 &) CERTIFICATE OF INSERVICE INSPECTION and Pressure Vessel I, the undersigned, holding a valid comnu*ssion issued by the National Board of Boiler have inspected the components described in this Inspectors and the State of Wisconsin and employed by HSBCT to October 28. 2002, and state that to the best of my Owner's Report during the period September 25. 2002 examinations and taken corrective measures described in this knowledge and belief, the Owner has performed Ownei's Report in accordance with the requirements of ASME Code, Section XI. expressed or implied, By signing this certificate, neither the Inspector nor his employer makes any warranty, corrective measures described in this Owner's Report Furthermore, neither the concerning the examinations and damage or a loss of any Inspector nor his employer shall be liable in any manner for any personal injury or property kind arising from or connected with this inspection. Commissions WI-100128 National Board, State, Province, and Endorsements Date"-/. 's/S 1 gnaur Date-PBF-7050 SENt 7 11 1 Revision 2 12/02/02

DATA PAC.KXGE NO. 991121 P.3 FORMN NPV-1 CERTIFICATE HOLflE:RS IDATA REEPORT FOR NUCLEAPR PZW7M 3 OR VALVES* As Required by the Provision.s of the ASME Code, Section 111, Di-ision 1 Pg. 2.of 2

1. Manufactured and certifr~ed by VELAN INC. 2125 WARD AVE,MCNP.ALtBE C CA.'UDA P4MI'T6 (name and addrtss of.N Cefi~cnte HcrIder)

2. Manufactured for I'XXTCMZ TECH-NLOGIES 3315-A OLD FOREST PD.LfLYC11URG,VA. USA 24501 iname and addrms of pti-cbasei)

3. Location of installion _______ NI!-.

name and addrm')

4. Model No., Seri~es No., or T'ype: GATE Drawing P1-76600-NOI Rev F CHNT N/A

5. ASM-E Code, Secti.on 111, DiN ission 1: 1989 NONE 1 X/A (edition) (addenda date) (class) lCode Ciast no

6. Pump or valve VALVE !Nom~inal lnlelt size 2 Outlet size 2 (iti.) (in )

7. Material: Body, SA-1O5,CS Bonne tSA-105,CS Disk SA-351,CFEM Bolta-ng SA-194. 211

!A-193,37, (a) (b) (c) (d) (a)

Cart. Nat I1 Body Bonnet Holder's Board Serial Serial Serial No. No. No. Mo. No.

          .. 991121-2                            N/A                         H/C:tiFD                              H/C:     C-B, RFD                                  c-B                            H/:86Z 991121-3                                                                  HF-D                                 c-B                                86Z FrD                                 C-B                                86 Z
        -~*991121-6                                                                    HFD                                  C-B HFL)                                 C-B HFD_                                 C-B
    .'upplemnenta inrorm~non in fmnO ofim   sai.keichmi urdran~io m3% be U'ed pro%)dnJ (111su sS1~I.)~ff~t~                               nie,      tr~        on ihi, V~jtl RCPpitt is included on cacb sheet. (3) each shect isnumbcrtd acd ihe nunit'ee or     ~tectt   is iecorde I at 'the top oh this foriii.

(118.s)l This form t1000Cr)m i tusbeot)tXAanrj ror'stheOrdier tpl-. sAS%1!-'. ZLiII' 1 (C 30Iaifd.% .aV3O

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                                                                                                                              .4 BIEST COPY AVAILAB1-LE                                                                                          I     --    - - -

2

a. - P01 .V I

FORM NPV-I (Back - Pg. 2 of 2 ) PA4 Certificate Holder's Serial No. 99112!

6. Design conditions 1975 psi 100 *F or valve pressure class S00 (1)

(pressure) (temperature)

9. Cold working pressure 1975 psi at IC0'F

10. Hydrostatic test 3000 psi. Disk differential tcst pressure 2200 psi

11. Remarks: MATERIALS H-ET ASME SECTION II EDITION: 1989 ADDENDA: NONE CERTIFICATE OF CO!PLIANCE We certify that the statements made in this report are correct and that this pilnp or valve conforms to the rules for construction of the ASME Code, Section III, Division 1.

N Certificate of Authorization No. N-2797-1 Expires FAY 2.2001 Date OCT 2 9 'rName VELAN INC. Signed (culo rý,r CERTIFICATE OF 1.1SPECTION I, the undersigned, holding a valid ccrmission issued by the National Board cf Sciler and Pressure Vessel Inspectors and the State or Province of QLTBEC and employed by REGIE DU BATIMNT of QUcEBEC - have inspected the pump, or valve, dascribed in this Data Report o id state that to the best of my knowledge and belief, the Certificate Holder has co str cted this pump, or valve, in accordance with the ASIM Code, Sc-ction IIi, Division 1. By signing this certificate, neither the inspector nor his employer makes any %arrenty, Gxpressed or implied. concerning the ccmponent described in this Data Report. Furthermore, neither the inspectcr nor his employer shall bu liable in any manner for any perscnal *n]ury or property age or a lois of an kin arising from or connacted with this inspection.

                                /""°Ccmissicns                                             QUEBEC       V M21tor em%. xrid no. Ii    z V',                          Si&

(1) For manually operated valves only. 5r- P " VAIk'i3E UMMOM jg'l 1ýýIiii'll 1'11111ý6'1

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI Nuclear Management Corporation Date September 30, 2002

1. Owner 1 of I Sheet 700 First Street, Hudson, WI 54016

2. Plant Point Beach Nuclear Plant Unit: I WI 54241 WO 9937372 6610 Nuclear Road, Two Rivers, Repair Organization P0 No ,Job No Etc Crane Nuclear Type Code Symbol Stamp N/A

3. Work Performed By:

nnme 2825 Cobb Internation Blvd. Authorization No. N/A Expiration Date N/A Kennesaw, GA 30152 jdfire~q

4. Identification of System- Component Cooling Water West Spec G-676257

5. (a) Applicable Construction Code Section VIII 19 65 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Edition, No Addenda 6 Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME National Replaced, Code Name of Manufacturer Board Other Year or Stamped Name of Manufacturer Serial No No Identification Built Replacement (Yes or No)

Component Crosby 51032- N/A CC-763A Unknown Replacement No CC-00763A I RV763A WEP

7. Description of Work: Replacement of guide, spring, nozzle, spindle disc, and disc bushing.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Other [ Pressure psi Test Temp. F O__

None

9. RemarKs lu"I'*VI /-UUL-U I UU Applicable fLlIlU ldicUICI * .a'ta CJ'PO ,

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. repair or replacement Type Code Symbol Stamp: N/A Certificate of Authonzation No. Expiration Date N/A Signed  ? r ,-,1A! o'X ' ISI Coordinator Date /./C)ýL ) ) 3 micror Nne CERTIFICATE OF INSERVICE INSPECTION Vessel I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure CT have inspected the components Inspectors and the State of Province of Wisconsin and employed by HSB state that to the described in this Owner's Report during the period September 26, 2002 to September 30, 2002, and and taken corrective measures described in best of my knowledge and belief, the Owner has performed examinations this Owner's Report in accordance with the requirements of ASME Code, Section XI. implied, By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or described in this Owner's Report. Furthemiore, neither the concerning the examinations and corrective measures any manner for any personal injury or property damage or a loss of any Inspector nor his employer shall be liable in kind arising from or connected with this inspection. 7 f- 6441- Commissions WI-100128

      /     -

Inspector's Signature National Board, State, Province, and Endorsements Date: -- //,?c? PBF-7050 SEM 7 11 1 Revision 1 05/17/02

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date Oct Ober 21, 2002 700 First Street, Hudson, WI 54016 Sheet: I of 1 2 Plant Point Beach Nucleai Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 9918412 Repatr/Replacement Organtzatton P 0 No , Job No Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address 4 Identification of System: Main Steam Bech Spec 6118-N-87 5 (a) Applicable Construction Code B31 JL19 67 Edition, No Addenda, N..o Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None 6 Identification of Components ASME National Year Corrected, Code Name of Name of Manufacturer Board Other Remno ed or Stamped Component Manufacturer Serial No No. Identification Built Installed (Yes or No)

MS-2017 Atwood & N/A N/A MS-2017 Unknown Installed No Morrill MS-2017 Unknown N/A N/A MS-2017 Unknown Removed No

7. Description of Work: Replaced disc/disc pin.

8. Tests Conducted: Hydrostatic EL Pneumatic LI Nominal Operating Pressure El Exempt 0 Other LI Pressure psi Test Temp. OF

9. Remarks RR 2002-0107 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code, Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No Expiration Date N/A Signed z .. z.,/*, j -.. ISI Coordinator Date 1/ /,12e-6,i Ohuer or ON&nc's Designee. Tatle * / CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commi-ssion issued by the National Board of Boiler and Pressure Vessel Inspectois and the State of Wisconsin and employed by HSBCT have inspected the components desciibed in this Ownei's Report during the period September 30, 2002 to October 21, 2002, and state that to the best of my "knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code, Section XI. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied. cunceining the examinations and corrective measures descsibed in this Owner's Report. Furthermote, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection Conmiussions WI-100128 Inspector's Sigo<ture National Board, State, Province, and Endorsements Date: 4*":-27. /4-, 2e? 3 PBF-7050 Revision 2 12/02/02 SEM 7 11 I

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI Date October 22, ?002

1. Owner Nuclear Management Corporation Sheet: 1 of I 700 First Street, Hudson, WI 54016 Unit: 1

2. Plant Point Beach Nuclear Plant WO 9942381 6610 Nuclear Road, Two Rivers, WI 54241 Repair/Replacement Organization P 0 No, Job No Etc Type Code Symbol Stamp N/A 3 Work Performed By: We Energies name 6610 Nuclear Road Authorization No. N/A Expiration Date N/A Two Rivers, WI 54241 address 4 Identification of System Incore Flux Mapping West Dwg WEST 685J441 Sheets A&D, West Spec 952464 Rev. 4

5. (a) Applicable Construction Code B31 1, 19 Unknown Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. with Add thru 2000 (c) Applicable Section XI Code Cases No

6. Identification of Components T r I ASME Code National Corrected, Year Removed or Stamped Name of Manufacturer Board Other Name of Built Installed (Yes or No)

S, -t,,nnnon M *nil fact"llirer" Serial No No Identification N/A N/A N/A N/A Unknown Removed No FM-Thimbles Swagelock N/A N/A N/A Unknown Installed No FM-Thimbles

7. Description of Work: Replacement of union fittings due to degradation.

Nominal C)perating Pressure [:I Exempt [9

8. Tests Conducted: Hydrostatic El Pneumatic El Test Temp. OF Other El Pressure psi None ILU.AlJ AI.Jn

9. Remarks D D Atpplicable M*anufacturer s 1,ata e~lpui:,ts c attache CERTIFICATE OF COMPLIANCE ASME Code, I certify that the statements made in the report are correct and that this conforms to the rules of the Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No Expiration Date N/A Signed ISI Coordinator Date L Z2,1,,e,5 Owner or 0Wiieis Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel described in this Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components that to the best of my knowledge Owner's Report during the period October 1, 2002 to October 22, 2002, and state described in this Owner's Report in and belief, the Owner has performed examinations and taken corrective measures accordance with the requirements of ASME Code, Section XI or implied, By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed in this Owner's Report. Furthermore, neither the concerning the examinations and corrective measures described personal injury or property damage or a loss of any Inspector nor his employer shall be liable in any manner for any kind arising from or connected with this inspection S . (.rCommissions WI-100128 Inspector's Sigyiture National Board, State, Province, and Endorsements Date: it ý.A Ii. _Z_t, PBF-7050 SEM 7 11.1 Revision 2 12/02/02

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 18, 2002 700 First Street, Hudson, WI 54016 Sheet- 1 of 2

2. Plant Point Beach Nuclear Plant Unit- 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 0212972 RepairReplacement Organization P 0 No Job No Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No N/A Two Rivers, WI 54241 Expiration Date N/A address 4 Identification of System- Safety Injection West E-Spec G-676262

5. (a) Applicable Construction Code B31 L 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed Addenda thru 2000 (c) Applicable Section XI Code Cases None 6 Identification of Components ASME National Year Corrected, Code Name of Name of Manufacturer Board Other Removed or Stamped Component Manufacturer Serial No No. Identification Built Installed (Yes or No)

See Attached page

7. Description of Work: Installed temporary relief valve and gagged shut original relief valve

8. Tests Conducted: Hydrostatic El Pneumatic Ml Nominal Operating Pressure El Exempt El Other Z Pressure NOP psi Test Temp. NOT OF System Leakage Test

9. Remarks RR 2002-0112; CAP 030715 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are conrect and that this conforms to the rules of the ASME Code, Section XI.

Type Code Symbol Stamp N/A Certificate of Authorization No Expiration Date N/A Signed . .O t-r 0Anr ' Designece," Title wiiefs ISI Coordinator Date Z///C/() CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid comnmssion issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 14, 2002 to October 18, 2002, and state that to the best of my "knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code, Section XI. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection

       "~ "Commissions                                                             WI-100128 lnspdctoi's Si.gnature                                                          Natonal Board, State, Province, and Endorsements Date.         ,

PBF-7050 SE.N17111 Revision 2 12/02/02

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY (CONTINUATION) As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 18, 2002 700 First Street, Hudson, WI 54016 Sheet: 2 of 2

2. Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 0212972 Repair/Replacement Organization P 0 No., Job No Etc

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West E-Spec G-676262

5. (a) Applicable Construction Code B31 1 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Ed. Add thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No No Identification Built Installed (Yes or No)

SI-00830C Crosby N69959 N/A SI-830C/ Unknown Installed No 0015 Relief Valve SI-00830B Crosby N69959 N/A SI-830B/ Unknown Removed No 0019 Relief Valve Piping Sandvik Steel N/A N/A None Unknown Installed No Bolting Nova Machine N/A N/A None Unknown Installed No Products Corp. IIIII 4 + + 1- 1 4 + +/- t 1 1 I I I 4- + i 4 F F + +/- F ________ F F F + I F PBF-7050a SPI' 7 1 1 1 Re%tsloo 2 12'02/02

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner Nuclear Management Corporation Date September 2 7, 2002 700 Fust Stieet, Hudson, %VI 54016 Sheet I of 1 2 Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 0207001 Repair/Replacement Organization P 0 No , Job No Etc 3 Work Performed By: Crane Movats Type Code Symbol Stamp VR namne 2825 Cobb Inteinational Blvd Authotization No. 475 Kennesaw, GA 30152 Expiation Date 10/22/2002 address

4. Identification of System: Chemucal Volume Control

5. (a) Applicable Construction Code Section VIII, 19 65 Edition, No Addenda, NoCode Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None 6 Identification of Components ASME National Cot rected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No No. Identification Built Installed (Yes or No)

CV-00203 Crosby 0072 N/A CV-203 Unknown Corrected Yes 7 Description of Work: Rebuild valve, new nozzle and internal parts 8 Tests Conducted Hydrostatic E] Pneumatic rI Nomi nal Operating Pressure 0 Exemrpt OF psi Test Temp. 547 oF Other nI Pressure 2250 IT-230, 1-PT-RCS-1

9. Remarks RR 2003-0001, Valve removed and installed by We Energies, 6610 Nuclear Road, Two Rivers, WI 54241, CAP 030677 A nliahle Manufacturer's Data Renorls tobe attached CERTIFICATE OF COMPLIANCE I ceitify that the statements made in the report are correct and that this conforms to the rules of the ASME Code, Section XI.

Type Code Symbol Stamp. N/A Certificate of Authorization No N/A Expiration Date N/A Signed . ISI Coordinator Date n%%n r or Owners Dcsi ee Title

                                                                                                                    /     ,, -

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressute Vessel Inspectois and the State of Wisconsin and employed by HSBCT have inspected the components desciibed in this Owneifs Report during the peliod Januaiv 10. 2003 to September 27, 2002, and state that to the best of my knowledge and belief, the Ownei has performed examinations and taken corrective measures described in tlis Owner's Repoit in accoi dance with the requirements of ASME Code, Section XI By signing this certificate, neithei the Inspector nor his employer makes any warianty, expressed or implied, concerning the exammations and corrective measuies desciibed in this Ownei's Report. Furthermoie, neither the Inspector nor his employer shall be liable in any maimer for any personal injury or property damage or a loss of any kind arising from or connected with this inspection (f *

• Commissions WI-100128 Inspectoi's Si-enature National Board, State, Province, and Endoisements Date. "3 Aq,v. Iq _e-,-3 PBF-7050 Revision 2 12/02/02 SEM 7 11 1}}