NRC 2003-0008, Filing of Ownerss 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-b Committed to Nuclear Excellen c
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 P
oject Manager, Point Beach Plant, USNRC, NRR 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:
9-J5- 03 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.
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Commissions WI 100128 Inspector's Sigature National Board, State, Province, and Endorsements Date
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Nuclear Management Company 700 First Street Hudson, Wisconsin 54016 National Board Number for Unit N/A Commercial Service Date 12/21/70 Docket 50-266 Pt Beach Unit I Unit 1 Second Period IWE Containment Inspection Program U1R27 Examination Summary Page 6 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 1 C-3 E-G E8 20 Torque 08-Oct-02 RP-IB, ORT-12 1 CH-01 E-C E4 11 VT-t 02U1-760E001 20-Sep-02 E-C E4 12 UT 02UI-114EOOI 20-Sep-02 1 CH-02 E-C E4 11 VT-I 02UI-760E002 20-Sep-02 02UI-E015 Previously evaluated OIUI-E004 E-C E4 12 UT 02Ul-114E002 20-Sep-02 02UI-E015 Previously evaluated OIUI-E004 1CH-03 E-C E4 11 VT-I 02U1-760E003 20-Sep-02 02UI-E009 Previously evaluated OIUI-E004 E-C E412 UT 02U-I-14E003 20-Sep-02 02UI-E009 Previously evaluated O1UI-E004 1 CH-04 E-C E-4 11 VT-I 02U1-760E004 20-Sep-02 02U1-EOIO Previously evaluated 01UI-E005 E-C E4 12 UT 02U1-114E004 20-Sep-02 02UI-EOIO Previously evaluated OIUI-E005 1CH-05 E-C E4 11 VT-I 02UI-760E005 20-Sep-02 02UI-EOII Previously evaluated 01UI-E004 E-C E3412 UT 02UI-114E005 20-Sep-02 02UI-EOII Previously evaluated 0UI-E004 1CH-06 E-C E4 11 VT-I 02UI-760E006 20-Sep-02 02U1-E012 Previously evaluated 0UI-E004 E-C 13412 UT 02UI-114E006 20-Sep-02 02UI-E012 Previously evaluated O U1-E004 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 1CH-07 E-C E4.1I VT-I 02UI-760E007 20-Sep-02 02UI-E013 Previously evaluated 01UI-E004 E-C E4 12 UT 02U1-114E007 20-Sep-02 02UI-E013 Previously evaluated 0UI-E004 1 CH-08 E-C E4 11 VT-I 02Ul-760E008 17-Sep-02 02UI-E006 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 1 CH-09 E-C E4 11 VT-I 02UI-760E009 17-Sep-02 02UI-EO07 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 ICH-10 El-C E4 11 VT-I 02Ul-760E010 17-Sep-02 02U1-E008 Previously evaluated 0lUI-E002 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 1 CP-025 E-A El.12 VT-3 02UI-760E014 26-Sep-02 1CP-026 E-A E1.12 VT-3 02Ul-760EO15 26-Sep-02 ICP-027 E-A El.12 VT-3 02Ul-760E016 26-Sep-02 Page 8 of 19 I
Commeicial Service Date-12/21/70 Docket 50-266 Pt Beach Unit I Nuclear Management Company 700 First Street Hudson, Wisconsin 54016 National Board Number for Unit N/A U 1 R27 Examination Summary Page 9 of 19 Component Category Item Exam Type NDE Data Sheet Completed RRM #
IDR Notes date 1CP-028 E-A El 12 VT-3 02UI-760E017 26-Sep-02 1CP-029 E-A El 12 VT-3 02UI-760E018 26-Sep-02 1CP-030 E-A El 12 VT-3 02UI-760E019 26-Sep-02 ICP-031 E-A El 12 VT-3 02UI-760E020 26-Sep-02 ICP-032 E-A El 12 VT-3 02UI-760E021 26-Sep-02 1 CP-033 E-A El.12 VT-3 02UI-760E022 26-Sep-02 ICP-034 E-A E1.12 VT-3 02U1-760E023 26-Sep-02 1CP-035 E-A EI.12 VT-3 02UI-760E024 26-Sep-02 1CP-036 E-A El 12 VT-3 02UI-760E025 26-Sep-02
Commercial Service Date: 12/21/70 Docket 50-266 Pt Beach Unit 1 Nuclear Management Company 700 First Street Hudson, Wisconsin 54016 National Board Number for Unit N/A U1R27 Examination Summary Component Category Item Exam Type NDE Data Sheet Completed RRM #
IDR Notes date 1CP-037 E-A El 12 VT-3 02U1-760E026 26-Sep-02 ICP-038 E-A E1.12 VT-3 02Ul-760E027 26-Sep-02 1CP-039 E-A El.12 VT-3 02UI-760E028 26-Sep-02 1CP-040 E-A El 12 VT-3 02UI-760E029 26-Sep-02 1CP-041 E-A 1l.12 VT-3 02U1-760E030 26-Sep-02 1CP-042 E-A El.12 VT-3 02UI-760E031 26-Sep-02 ICP-043 E-A El 12 VT-3 02UI-760E032 26-Sep-02 ICP-044 E-A El.12 VT-3 02UI-760E033 26-Sep-02 1CP-045 E-A EI.12 VT-3 02U1-760E034 26-Sep-02 1CP-046 E-A El 12 VT-3 02UI-760E035 26-Sep-02 Page 10 of 19
Commercial Service Date 12/21/70 Docket 50-266 Pt Beach Unit I Nuclear Management Company 700 First Street Hudson, Wisconsin 54016 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 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 1 CP-049 E-A El.12 VT-3 02U1-760E038 25-Sep-02 02UI-E014 1CP-050 E-A El3.12 VT-3 02UI-760E039 25-Sep-02 02U1-E014 1 CP-051 E-A El.12 VT-3 02U1-760E040 01-Oct-02 1CP-052 E-A El.12 VT-3 02U1-760E041 25-Sep-02 02U1-E014 ICP-053 E-A El 12 VT-3 02UI-760E042 25-Sep-02 02U1-E014 1CP-054 E-A El.12 VT-3 02U1-760E043 25-Sep-02 02U1-E014 1CP-055 E-A El.12 VT-3 02U1-760E044 25-Sep-02 02UI-E014 I CP-056 E-A El 12 VT-3 02U1-760E045 26-Sep-02 02U1-E014 Page 11 of 19
Commercial Service Date 12/21/70 Docket 50-266 Pt Beach Unit I Nuclear Management Company 700 First Street Hudson, Wisconsin 54016 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 ICP-057 E-A El 12 VT-3 02Ul-760E046 26-Sep-02 02UI-E014 1CP-058 E-A E1.12 VT-3 02UI-760E047 26-Sep-02 02U1-E014 ICP-059 E-A El.12 VT-3 02Ul-760E048 26-Sep-02 02UI-E014 1CP-060 E-A E1.12 VT-3 02Ul-760E049 25-Sep-02 02UI-EO14 ICP-061 E-A E-.12 VT-3 02Ul-760E050 26-Sep-02 ICP-062 E-A E-1.12 VT-3 02Ul-760E051 25-Sep-02 02U1-E014 ICP-063 E-A E!.12 VT-3 02UI-760E052 25-Sep-02 1CP-064 E-A El.12 VT-3 02U1-760E053 25-Sep-02 02U1-E014 1CP-065 E-A El 12 VT-3 02Ul-760E054 25-Sep-02 I CP-066 E-A E1.12 VT-3 02UI-760E055 2 5-Sep-0 2 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 1CP-067 E-A El 12 VT-3 02Ul-760E056 25-Sep-02 02U1-E014 1CP-068 E-A El 12 VT-3 02Ul-760E057 26-Sep-02 02UI-E014 1CP-069 E-A E1.12 VT-3 02UI-760E058 26-Sep-02 02U1-E014 1CP-070 E-A E1.12 VT-3 02U1-760E059 26-Sep-02 02UI-E014 1CP-071 E-A E13.12 VT-3 02U1-760E060 26-Sep-02 02UI-1E014 1CP-072 E-A El.12 VT-3 02UI-760E061 26-Sep-02 02UI-E014 1CP-073 E-A E1.12 VT-3 02Ul-760E062 19-Sep-02 1 CP-074 E-A E1.12 VT-3 02U1-760E063 19-Sep-02 1CP-075 E-A E-1.12 VT-3 02U1-760E64 19-Sep-02 1CP-076 E-A El 12 VT-3 02U1-760E065 19-Sep-02 Page 13 of 19
Commercial Service Date 12/21/70 Docket 50-266 Pt Beach Unit I Nuclear Management Company 700 First Street Hudson, Wisconsin 54016 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
Nuclear Management Company Commercial Service l)ate 12/21/70 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt Beach Unt 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 ICP-133 E-C E4.11 VT-1 02U1-760E075 17-Sep-02 02UI-E001 Previously evaluated 01 U1-E001 E-C E4.12 UT 02Ul -I 14E008 17-Sep-02 02UI-E001 Previously evaluated 01 UI-E001 ICP-134 E-C E4 11 VT-I 02UI-760E076 17-Sep-02 02UI-E002 Previously evaluated 01UI-E00I E-C E4.12 UT 02UI-114E008 17-Sep-02 02UI-E002 Previously evaluated 01UI-E001 ICP-135 UT 02UI -114E008 17-Sep-02 02UI-E003 (gnd) Previously evaluated O1U1 E001 E-C E4 11 VT-I 02UI-760E077 17-Sep-02 02UI-E003 Previously evaluated O0UI-E001 E-C E4 12 UT 02Ui-1 14E008 17-Sep-0 2 02UI-E003 Previously evaluated 0lUl-E001 ICP-136 VT-I 02UI-760E078 17-Sep- 0 2 02U0-E004 E-C E4.12 UT CANCELLED ICP-137 VT-I 02U1-760E079 17-Sep-0 2 02UI-E005 E-C E4 12 UT 02UI-114E008 17-Sep-0 2 02U1-E005 Previously evaluated O0UI-E001 ICP-138 E-C E4.11 VT-I 02U1-760E080 17-Sep-0 2 Previously evaluated 01U I-E001 2-C 1412 UT 02U1 -I 14E008
! 7-Sep-0 2 Previously evaluated O0UI-E001 Page 15 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-139 UT 02UI-I 14E008 17-Sep-02 (gnd) Previously evaluated 01UI E001 E-C E4.11 VT-I 02UI-760E081 17-Sep-02 Previously evaluated O0UI-E001 E-C E4 12 UT 02UI-114E008 17-Sep-02 Previously evaluated O0UI-EOO1 ICPP-35 E-C E4.11 VT-I 02UI-760E082 29-Sep-02 Previously evaluated 99UI-E002 E-C E4 12 UT 02UI-114E021 29-Sep-02 Previously evaluated 99U1-E002 1CPP-36 E-C E4 11 VT-I 02UI-760E083 30-Sep-02 02UI-E017 Previously evaluated 99U1-EO03 E-C E4 12 UT 02UI-114E022 30-Sep-02 02UI-E017 Previously evaluated 99U1-EO03 1CPP-37 E-C E4.11 VT-I 02UI-760E084 03-Oct-02 Previously evaluated 99U1-E004 E-C E4.12 UT 02UI-114E023 03-Oct-02 Previously evaluated 99U 1-E004 1CPP-38 E-C E34.11 VT-I 02UI-760E085 03-Oct-02 Previously evaluated 99U1-E005 E-C E4.12 UT 02U1-114E024 03-Oct-02 Previously evaluated 99UI -E005 1CPP-39 E-C E4 11 VT-1 02U1-760E086 29-Sep-02 Previously evaluated 99U0l-E006 E-C E4 12 UT 02U1-1 14E025 29-Sep-02 Previously evaluated 99UI-E006 ICPP-40 E-C E4 11 VT-I 02UI-760E087 03-Oct-02 Previously evaluated 99UI -E007 E-C E4.12 UT 02UI-114E026 03-Oct-02 Previously evaluated 99U1 -E007 Page 16 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 ICPP-43 E-C E4 11 VT-I 02UI-760E088 29-Sep-02 Previously evaluated 99Ul-E008 E-C E4 12 UT 02Ul-114E027 29-Sep-02 Previously evaluated 99Ul-E008 ICPP-44 E-C E4 It VT-I 02UI-760E089 30-Sep-02 Previously evaluated 99U1 -E009 E-C E4 12 UT 02UI-114E028 30-Sep-02 Previously evaluated 99Ul-E009 1CPP-45 E-C E4 11 VT-I 02U1-760E090 01 -Oct-02 Previously evaluated 99U 1 -E010 E-C E4 12 UT 02U1 -114E029 0 1 -Oct-02 Previously evaluated 99Ul-EOIO 1CPP-46 E-C E4.11 VT-I 02UI-760E091 30-Sep-02 Previously evaluated 99UI-EOI I E-C E4.12 UT 02U-1. 14E030 30-Sep-02 Previously evaluated 99UI-EOI I 1 CPP-47 E-C E4.11 VT-I 02Ul-760E092 29-Sep-02 Previously evaluated 99Ul-E012 E-C E4 12 UT 02U I-114E031 29-Sep-02 Previously evaluated 99UI-E012 ICPP-48 E-C E4 11 VT-I 02UI-760E093 03-Oct-02 Previously evaluated 99Ul-E013 E-C E4 12 UT 02U1-114E032 03-Oct-02 Previously evaluated 99Ul-E013 1 CPP-50 E-C E4.11 VT-I 02UI-760E094 03-Oct-02 02Ul-E019 Previously evaluated 99Ul-E014 E-C E4 12 UT 02UI-114E033 03-Oct-02 02UI-E019 Previously evaluated 99Ul-E014 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 I R27 Examination Summary Component Category Item Exam Type NDE Data Sheet Completed RRM #
IDR Notes date 1 CPP-51 E-C E4.1 I VT-I 02U1-760E095 03-Oct-02 02UI -E020 Previously evaluated 99UI -E015 E-C E4 12 UT 02UI-14E034 03-Oct-02 02UI-E020 Previously evaluated 99UI-E015 1CPP-56 E-A El.12 VT-3 02UI-760E098 25-Sep-02 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 1CPP-57 E-A EI.12 VT-3 02U1-760E099 25-Sep- 0 2 1 CPP-58 E-A El.12 VT-3 02UI-760EI00 25-Sep-02 1CPP-V-I E-A E11.12 VT-3 02U1-760E101 25-Sep-02 1CPP-V-2 E-A E1.12 VT-3 02U1-760EI102 25-Sep-02 IQ-15 VT-I 02U1-760E103 01 -Oct-02 Supplemental directed by 01 Ul-L004 UT 02U1-I 14E035 0 1-Oct-02 Supplemental directed by 01 U1-L004 1Z-529 E-D E5 30 VT-3 02U1-760E104 30-Sep-02 02U1-E016 Page 18 of 19
Commercial Service Date 12/21/70 Docket 50-266 Pt Beach Unit I Nuclear Management Company 700 First Street Hludson, Wisconsin 54016 National Board Number for Unit N/A U 1 R27 Examination Summary Page 19 of 19 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
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:
Reviewed by:
Approved by:
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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 Coolant Pump A 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
tAý Commissions WI 100128 Inspector's Signature" National Board, State, Province, and Endorsements Date Th-'.
, *cz9z3 Page 5 of 5
Nuclear Management Company LLC 700 First Street Hudson, Wisconsin 54016 National Board Number for Unit N/A Commercial Service Date. 12/21/70 Docket 50-266 Pt Beach Unit 1 Status of Examinations for the Period/Interval
Nuclear Management Company LLC 700 First Street Hudson, Wisconsin 54016 National Board Number for Unit: N/A Commercial Service Date 12/23/70 Docket 50-266 Pt. Beach Unit I 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 700 First Street Hudson, Wisconsin 54016 National Board Number for Unit. N/A Commercial Service Date 12/21/70 Docket 50-266 Pt Beach Unit I 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 700 First Street Hudson, Wisconsin 54016 National Board Number for Unit N/A Commercial Service Date 12/21170 Docket 50-266 Pt Beach Unit I 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)
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 M R 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 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)
CLASS 1 CLPABER COMPONENTS Reactor Pressure Vessel STATUS
SUMMARY
EXAMINATION AREA CATEGY EXAM NUMBER IDENTIFICATION ITEM NO METHOD System ID -
R-1, Drawing No. ISI-1101 001000 RPV-14-683 Shell to Flange B-A B1.30 P UT 5 UT 11 UT 18 N
0 R
E PROCEDURE C
168-0001 168-0001 168-0001 I N S
I G
G X
E O
0 T
H E
R X
X X
REMARKS CALIBRATION BLOCK **
WO NUMBER 9/19/2002 -
UT complete.
Geometric reflectors from the flange radius sections noted.
Examined from the seal surface only. **5-PTB**
WO 9950774 004100 RPV Interior Surface Vessel Interior Surfaces B-N-i C VT-3 B13. 10 VT-3 VT-3 VT-3 VT-3 756-0001 754-0029 754-0030 754-0031 754-0032 X
X X
X X
9/24/2002 -
VT-3 complete.
No recordable indications.
Examined accessible areas of the upper internals and vessel interior.
10/6/2002 - Baseline VT-3 complete on new thermal sleeves.
Examined sleeves 1, 31, 32, and 33.
WO 9950777 004220 HS-19 Snubber A VT-i VT-3 VT-3 IDR AR 750-0015 754-0039 754-0040 7-014 CA 026407 X
X X
9/15/2002 -
VT-3 complete.
Rusty u-bolts noted.
10/2/2002
- VT-i on conduit and VT-3 on snubber complete.
No recordable indications.
WO 9945448 was initial work order.
WO 0212688 PAGE: 1
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)
CLASS 1 CLPABER COMIONENTS Reactor Pressure Vessel Bolting and CRD Housings STATUS
SUMMARY
EXAMINATION AREA CATEGY F
EXAM NUMBER IDENTIFICATION ITEM NO Mj "THOD NI 0
ON UT R
SE H
PROCEDURE C
a 2 PR REMARKS CALIBRATION BLOCK **
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 PAGE: 2
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)
CLASS 1 CLPABER COMPONENTS Pressurizer T-1
-STATUS
SUMMARY
EXAMINATION AREA CATEGY F
EXAM NUMBER IDENTIFICATION ITEM NOj METHOD System ID - T-001, Drawing No.
ISI-1104 N
0 R
E PROCEDURE C
I N
S I
a a
E 0
x 0
T H
E R
REMARKS
- CALIBRATION BLOCK **
WO NUMBER 006000 PZR Manway Bolts 1 thru 16 B-G-2 B7.20 C VT-I VT-i IDR AR 750-0003 750-0011 7-007 CAP029619 X
X 9/20/2002 -
VT-i complete on all 16 bolts.
Galling of threads on bolt no. 13.
9/22/2002 Baseline VT-i complete on new bolt.
No recordable indications.
NO 9942120 PAGE: 3
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT -
UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (UlR27)
CLASS 1 CLPABER COMPONENTS Regenerative Heat Exchanger HX-2
-STATUS
SUMMARY
EXAMINATION AREA CATEGY F
EXAM NUMBER IDENTIFICATION ITEM NO ME1THOD System ID -
HX-002, Drawing No.
ISI-1107 N
I O
N R
S E
I PROCEDURE C
a a
E 0
M 0
T H
E R
REM.ARXS
- CALIBRATION BLOCK **
WO TNU*ER 010000 RHE-01 Head to Shell B-B L UT-45 B2.51 UT-60 176-0005 176-0005 X
9/16/2002 -
UT complete.
No X
recordable indications.
Limited examination due to support interference. **17-PTB**
WO 9950778 010100 RHE-02 Shell to Tube Sheet B-B B2.80 C UT 45 176-0006 X
9/16/2002 -
UT complete.
No recordable indications.
Limited examination due to nozzle position. **17-PTB**
WO 9950778 010600 RHE-Ni Inlet Nozzle to Shell 010700 RPE-Nl-IRS PEE Nozzle Inner B-D CUT 45 B3.150 UT 60 B-D B3.160 176-0001 176-0001 L UT3O/70/70 176-0002 X
9/16/2002 -
UT complete.
No X
recordable indications.
Limited examination due to clamp on the shell. **61-PTB, 62-PTB**
9/16/2002 -
UT complete.
No 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 PAGE: 4
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT I INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)
CLASS 1 CLPABER COMPONENTS Regenerative Heat Exchanger HX-2
-STATUS SUMTMARY EXAMINATION AREA CATEGY EXAM NUMBER IDENTIFICATION ITEM NO j ETHOD N
I O
N R
S E
I PROCEDURE C
a G
E 0
M 0
T H
H R
REMARKS CALIBRATION BLOCK **
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................................................................................................................................................................................................
PAGE: 5
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT -
UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)
CLASS 1 CLPABER COMPONENTS Reactor Coolant Pump Flange and Bolting
SUMMARY
EXAMINATION AREA CATEGY NUMBER IDENTIFICATION ITEM NO STATUS EXAM METHOD NI 0
ON G
T R SE H
El1 0 E
PROCEDURE C
G M
R REM4ARKS CALIBRATION BLOCK WO NUMBER System ID - P-001A, Drawing No.
ISI-I1I0 017300 RCP A SEAL BOLTS 18 Seal Bolts B-G-2 B7.60 C VT-I 750-0004 X
9/20/2002 - VT-I complete.
No recordable indications.
Examined 18 bolts.
WO 9950773 PAGE: 6
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT -
UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)
CLASS 1 CLPABER COMPONENTS Steam Generators HX-lA and HX-lB
-- STATUS
SUMMARY
EXAMINATION AREA CATEGY F
EXAM NUMBER IDENTIFICATION ITEM NOj METHOD N
I 0 N R
S E
I PROCEDURE C
G G
E 0
M 0
T H
E R
REMARKS CALIBRATION BLOCK **
WO NUMBER System ID - HX-001A, Drawing No.
ISI-PRI-1112 019100 SG A Manway Inlet Bolting Manway Bolting B-G-2 B7.30 A VT-I VT-I 750-0016 750-0019 X
10/5/2002 - VT-i complete on X
bolts 6, 7,
11, and 13.
No 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 PAGE: 7
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT -
UNIT 1 INSERVICE INSPECTION RESULTS SUMMdARY INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)
CLASS 1 CLPABER COMPONENTS RER Suction off Loop A
-STATUS
SUMMARY
EXAMINATION AREA CATEGY EXAM NUMBER IDENTIFICATION ITEM NO METHOD p2 System ID -
Pipe RC 2501R-16, Drawing No.
ISI-1122 NI 0
ON UT R
SE H
ROCEDURE C
U M
R REMARKS
- CALIBRATION BLOCK **
NO NTUMBER 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.................................................................................................................................................................................................
PAGE: 8
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)
CLASS 1 CLPABER COMPONENTS Accumulator B to Loop B STATUS
SUMMARY
EXAMINATION AREA CATEGY F
EXAM NUMBER IDENTIFICATION ITEM NO METHOD N
I O
N R
S E
I PROCEDURE C
U G
E 0
M 0
T H
E R
REMARKS CALIBRATION BLOCK **
WO NTUMBER System ID - Pipe SI 2501R-01, Drawing No.
039100 AC-10-SI-1001-17 Pipe to Elbow R-A R1.20 C THICK UT 45 109-0013 173-0003 9/24/2002 - Thickness data X
acquired and UT complete.
No recordable indications.
- S1-PTB**
WO 9950780 039200 AC-10-SI-1001-18 Elbow to Pipe R-A R1.20 C THICK UT 45 109-0007 173-0004 9/24/2002 - Thickness data X
acquired and UT complete.
No recordable indications.
- 51-PTB**
WO 9950780 039400 AC-10-SI-1001-19 R-A Pipe to Valve ISI-867B R1.11 L THICK UT 45 UT 60 109-0008 173-0005 173-0005 K
K 9/24/2002 -
Thickness data acquired and UT complete.
No recordable indications.
No examination downstream due to valve. **51-PTB**
WO 9950780 PAGE: 9 ISI-PRI-1123
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 042600 SI-2501R-2-SI1 F-A C VT-3 754-0002 X
9/23/2002 -
VT-3 complete.
No Variable Spring F1.10C recordable indications.
-1
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE I (UIR27)
CLASS 1 CLPABER COMPONENTS Reactor Vessel Injection and Core Deluge to RPV
SUMMARY
EXAMINATION AREA CATEGY NUMBER IDENTIFICATION ITEM NO
-STATUS EXAM METHOD N
0 R
E PROCEDURE C
I N S
I a
a E 0
X 0
T H
E R
REMARKS
- CALIBRATION BLOCK **
WO NUMBER System ID - N/A, Drawing No.
ISI-1127 051700 SI-2501R-5-SI7A Rigid Support F-A Fl.10B C VT-3 NDE-754 X
9/16/2002 - VT-3 complete.
No 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 Rigid Support F-A B VT-3 Fl.10A VT-3 IDR 754-0027 754-0028 7-013 X
10/3/2002 - Agmented VT-3 X
complete.
Loose nuts noted on 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 PAGE: 11
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)
CLASS 1 CLPABER COMPONENTS Core Deluge to RPV
-STATUS
SUMMARY
EXAMINATION AREA CATEGY F
EXAM NUMBER IDENTIFICATION ITEM NO METHOD System ID - N/A, Drawing No.
ISI-1129 NI 0
ON 0 T R
SE H
El1 0 E
PROCEDURE C
a M R
REMARKS CALIBRATION BLOCK **
WO NUMBER 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 PAGE: 12
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT -
UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)
CLASS 1 CLPABER COMPONENTS Pressurizer Safety
-STATUS
SUMMARY
EXAMINATION AREA CATEGY F
EXAM NUMBER IDENTIFICATION ITEM NOj METHOD System ID -
N/A, Drawing No. ISI-1131 N
I 0
N R
S E
I PROCEDURE C
a a
0 X
0 T
H E
R REMARKS CALIBRATION BLOCK **
WO NUMBER 066900 RC-04-PR-1001-09-FB Flange Bolting B-G-2 B7.50 C VT-i 750-0006 System ID -
Pipe RC 2501R-03, Drawing No.
ISI-1131 068900 RC-04-PR-1002-09-FB Flange Bolting B-G-2 B7.50 C VT-i 750-0007 X
9/20/2002 - VT-i complete.
No recordable indications.
WO 9944661 initiated for valve refurbishment.
Examined 16 nuts and 8 studs.
9/20/2002 - VT-I complete.
No recordable indications.
Examined 16 nuts and 8 studs.
WO 9950776 PAGE: 13
PAGE: 14 DATE: 01/14/03 POINT BEACH NUCLEAR PLANT -
UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)
CLASS 1 CLPABER COMPONENTS Pressurizer Power Operated Relief Valve Discharge
-STATUS
SUMMARY
EXAMINATION AREA CATEGY EXAM NUMBER IDENTIFICATION ITEM NO METHOD System ID - N/A, Drawing No.
ISI-PRI-I135 089500 RC-2501R-2-HSS1 Snubber F-A A VT-3 FI.10S VT-3 IDR NI 0
R SE H
PROCEDURE C
a M R
754-0041 754-0042 7-004 X
X REMARKS CALIBRATION BLOCK **
WO NUMBER 9/17/2002 - VT-3 complete.
Rust noted on bolting.
10/4/2002 VT-3 complete.
Rust noted on bolting.
Accepted as-is by engineering evaluation.
Examined as HS-2501R-51.
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................................................................................................................................................................................................
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)
CLASS 1 CLPABER COMPONENTS Letdown from Loop B Cold Leg
-STATUS
SUMMARY
EXAMINATION AREA CATEGY EXAM NUMBER IDENTIFICATION ITEM NO METHOD P1 System ID - Pipe RC 2501R-I0, Drawing No.
ISI-1146 NX 1 O
0NI 0T R SE H
El1 0 E ROCEDURE C
a M
R REMARKS CALIBRATION BLOCK **
WO NUMBER 144000 RC-08-DR-1001-01 Branch Connection to Pipe R-A R1.20 L THICK UT 45 UT 60 109-0001 173-0015 173-0015 9/23/2002 -
Thickness data X
acquired and UT complete.
No X
recordable indications.
No 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 PAGE: 16
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 INSERVICE INSPECTION RESULTS SUMMA-RY INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)
CLASS 1 CLPABER COMPONENTS Safety Injection to Loop B Cold Leg
SUMMARY
EXAMINATION AREA CATEGY NUMBER IDENTIFICATION ITEM NO STATUS EXAM METHOD NI 0
R SE H
PROCEDURE C
a M R
REMARKS CALIBRATION BLOCK **
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 PAGE: 17
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT -
UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)
CLASS 2 CLPABER COMPONENTS Steam Generator's HX-1A and HX-lB STATUS SUNNARY EXAMINATION AREA CATEGY F
EXAM NUMBER IDENTIFICATION ITED NOj METHOD System ID - N/A, Drawing No.
ISI-PRI-1201 NI 0
ON G
T R
SE H
El1 0 E PROCEURE C
G M R REMARKS
- CALIBRATION BLOCK **
AO NUMBER 202000 HS-5 Snubber F-A C VT-3 F1.20S VT-3 IDR 754-0033 754-0034 7P-009 x
x 9/17/2002 - VT-3 complete prior to removal.
No recordable indications.
9/26/2002 -
VT-3 complete after reinstallation.
No recordable indications.
WO 9945448 PAGE: 18
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)
CLASS 2 CLPADER COMPONENTS Regenerative Heat Exchanger HX-2
--STATUS
SUMMARY
EXAMINATION AREA CATEGY EXAM NUMBER IDENTIFICATION ITEM NO METHOD N
I 0
O N
G T
R S
E H
E 0 0 E PROCEDURE C
a M
R REMARKS CALIBRATION BLOCK **
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 PAGE: 19
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)
CLASS 2 CLPABER COMPONENTS RHA Heat Exchangers HX-11A and HX-liB
-STATUS
SUMMARY
EXAM4INATION AREA CATEGY F
EXAM NUMBER IDENTIFICATION ITEM NOj 24ETHOD N I 0
0 N G
T R
S E H
E 1 0 E
PROCEDURE C
a M R
REMARKS
- CALIBRATION BLOCK **
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 Nozzle to Shell C-B C2.33 C VT-2 1-PT-RH-I X
10/12/2002 - VT-2 complete.
No recordable indications.
Wo 9945418 PAGE: 20 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.
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)
CLASS 2 CLPABER COMPONENTS Loop B Main Steam Outside Containment
SUMMARY
EXAMINATION AREA CATEGY NUMBER IDENTIFICATION ITEM NO STATUS EXAM METHOD N I
ON R
S E
I PROCEDURE C
G G
0 M
0 T
H E
R System ID - Piping EB-01, Drawing No.
ISI-1243 306000 MS-30-MS-1002-17 Pipe to Tee R-A R1.20 C THICK UT 45 UT 60 109-0015 172-0001 172-0001 X
K -
REMARKS CALIBRATION BLOCK WO NUMBER 9/27/2002 -
Thickness data acquired and UT complete.
No 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................................................................................................................................................................................................
PAGE: 21
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT -
UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)
CLASS 2 CLPABER COMPONENTS Feedwater Loop A Inside Containment STATUS
SUMMARY
EXAMINATION AREA CATEGY F
EXAM NUMBER IDENTIFICATION ITEM NO METHOD System ID - N/A, Drawing No. ISI-PRI-1245 N
I O
N R
S E
I PROCEDURE C
a G
E 0
x 0
T H
E R
REMARKS CALIBRATION BLOCK *t WO NUMBER 318200 ES-lI Snubber F-A A VT-3 F1.20S VT-3 IDR 754-0036 754-0037 7-008 X
X 9/26/2002 - VT-3 completed pre-removal.
Loose bolt, 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 PAGE: 22
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)
CLASS 2 CLPABER COMPONENTS Safety Injection Pump P-15A Discharge
-STATUS
SUMMARY
EXAMINATION AREA CATEGY EXAM NUMBER IDENTIFICATION ITEM Na METHOD NI 0
ON 1T R
SE H
PROCEURE C
0 M R
REMARKS CALIBRATION BLOCK **
WO NUMBER System ID - Pipe SI 1501R-01, Drawing No.
ISI-PRI-1252 348450 SIS-04-SI-1005-25A R-A 2" Branch Connection Rl.20 B PT 450375 X
9/21/2002
- Baseline PT complete.
No recordable 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 PAGE: 23
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)
CLASS 2 CLPABER COMIPONENTS Loop A Main Steam Inside Containment STATUS
SUMMARY
EXAMINATION AREA CATEGY EXAM NUMBER IDENTIFICATION ITEM NO METHOD N
0 R
E PROCEDURE C
I N
S I
G a
E 0
M 0
T H
E R
System ID - PS EB-01-MS-H4, Drawing No.
ISI-1261 390800 EB-1-MS-H4 Spring Hanger F-A C VT-3 F1.20C IDR VT-3 754-0007 7-002 754-0010 x
X REM{ARKS CALIBRATION BLOCK **
WO NUMBER 9/18/2002 - VT-3 complete.
The snap ring was out of the groove 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 PAGE: 24
DATE: 01/14/03 PAGE: 25 POINT BEACH NUCLEAR PLANT -
UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE I (U1R27)
CLASS 2 CLPABER COMPONENTS Loop B Main Steam Inside Containment
-STATUS
SUMMARY
EXAMINATION AREA CATEGY F
EXAM NUMBER IDENTIFICATION ITEM NOj METHOD NI 0
ON G
T R
SE H
El1 0 E PROCEDURE C
G0M R REMARKS
- CALIBRATION BLOCK **
WO NUM2BER System ID - N/A, Drawing No.
ISI-PRI-1262 392500 HS-4 F-A A VT-3 1-PT-SS-1 X
9/15/2002
- VT-3 complete.
Snubber F1.20S Loose nut noted on snubber attachment found to be loose.
Accepted as-is and tightened.
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT -
UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (UIR27)
CLASS P CLPABER COMPONENTS Pressure Test STATUS
SUMMARY
EXAMINATION AREA CATEGY l
EXAM NUMBER IDENTIFICATION ITEM NO METHOD System ID - N/A, Drawing No.
N/A N I 0
O N
G T
R S
E H
E 0
0 E PROCEDURE C
a X R REMARKS CALIBRATION BLOCK WO NUMBER 700100 I-PT-AF-i Auxilary Feedwater P
C VT-2 1-PT-AF-1 X
10/14/2002 - VT-2 complete.
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 Component Cooling Water System P
C VT-2 1-PT-CC-i X-9/25/2002 - VT-2 complete.
Leakage noted at mechanical 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 PAGE: 26
DATE: 01/14/03 POINT BEACH NUCLEAR PLANT - UNIT 1 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 4, PERIOD 1, OUTAGE 1 (U1R27)
CLASS P CLPABER COMPONENTS Pressure Test
-STATUS
SUMMARY
EXAMINATION AREA CATEGY EXAM NU"MBER IDENTIFICATION ITEM NO METHOD System ID -
N/A, Drawing No.
N/A N
I ON R
S E
I PROCEDURE C
a a
E 0
M 0
T H
E R
REMARKS CALIBRATION BLOCK **
WO NIUMBER 703000 I-PT-SW-I Service Water System P
C VT-2 I-PT-SW-i X
10/2/2002 - VT-2 complete.
One valve leaking at the packing.
Packing was adjusted.
WO 9945449 S.................................................................................................................................................................................................
703500 1-PT-RCS-1 Reactor Coolant System P
C VT-2 I-PT-RCS-1 X
10/14/2002 - VT-2 complete.
Leakage noted at several mechanical connections.
Leakage was stopped during the test or Work Order written to correct.
WO PAGE: 27
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:
Component:
Dated:
RRAI:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
RRMI:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
2000-0019 T-013 January 14, 2002 2001-0074 CV-01299 October 29, 2001 2001-0077 AC-152N-15-H43 November 15, 2001 2002-0019 CV-00296, valve bonnet and plug October 21, 2002 2002-0042 Piping AC-0601R-06 October 22, 2002 2002-0051 RC-00435 October 21, 2002 2002-0052 Piping SI-1501R-02 and Piping SI-1501R-03 October 31, 2002 2002-0056, 2002-0057, 2002-0090 MS-02005, MS-02007, and bolting November 5, 2002 2002-0064 CV-00369A October 21, 2002 2002-0066, 2002-0067, 2002-0098, 2002-0104 RC-00570A, RC-00570B, RC-00575A, RC-00575B, RC-00580A, RC-00580B, 1 RC-2507R-1 Piping, I-RC-2507R-1 Supports November 8, 2002 Page 2 of 4
RRM:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
RIRI:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
RRAI:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
2002-0073, 2002-0079 SI-00853A, studs, and nuts October 15, 2002 2002-0075, 2002-0099 T-013, manway bolting, and manway nuts October 16, 2002 2002-0080, 2002-0086 SI-00853B and bolting October 14, 2002 2002-0081, 2002-0087 SI-00853 and bolting October 23, 2002 2002-0082 SI-00892A, Piping 2"-SI-902R-2 October 22, 2002 2002-0085, 2002-0109 HX-004 October 14, 2002 2002-0089 T-001 bolting October 21, 2002 2002-0092 R-1 October 21, 2002 2002-0093 RH-0700 and cap October 22, 2002 2002-0094, 2002-0100, 2002-0102, 2002-0105 T-034A October 31, 2002 2002-0095, 2002-0101, 2002-0103 T-034B October 9, 2002 Page 3 of 4
RRM:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
RRM:
Component:
Dated:
2002-0096 PS-1 October 5, 2002 2002-0097 MS-00218 and piping October 28, 2002 2002-0106 CC-00763A September 30, 2002 2002-0107 MS-2017 October 21, 2002 2002-0108 FM-Thimbles October 22, 2002 2002-0112 SI-00830B, SI-00830C, piping, and bolting October 18, 2002 2003-0001 CV-00203 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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241 3
Wolk Performed By:
We Energies narme 6610 Nuclear Road Two Rivers, WI 54241 Date Ji Sheet-I anuary 14, 2002 of 1
Unit I
WO 9924865 Repair Organization P 0 No, Job No Etc Type Code Symbol Stamp N/A Authorization No.
Expiration Date N/A 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 PBF-7050 Revision 1 05/17/02 SEM 7 l 1 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-
, I(',
, t t,,
3 1-1
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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
We Energies 6610 Nuclear Road Two Rivers, WI 54241 Date October 29, 2001 Sheet:
I of 1
Unit I
WO 9946071 Repair Organization P.O No, Job No Etc Type Code Symbol Stamp N/A Authorization No.
Expiration Date N/A 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 PBF-7050 Revision 1 05/17/02 SEM 7.11 1 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 ISI Coordinator Date Signed zA
- i 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.-
wnc r
Nmc e
gn r;ý r%
-- n si cc Title 61--1 21
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 700 First Street, Hudson, WI 54016 2
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
We Energies name 6610 Nuclear Road Two Rivers, WI 54241 Date November 15, 2001 Sheet-1 of 1
Unit:
1 WO 9937084 Repair Organization P 0 No, Job No Etc.
Type Code Symbol Stamp N/A Authorization No.
Expiration Date N/A 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 PBF-7050 Revision 1 05/17/02 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--
4 /7/,o Z-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 I
Owner Nuclear Management Corpotation 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, TNxo Rivets, WI 54241 3
Work Performed By:
We Eneigies name 6610 Nuclear Road Two Rivels, WI 54241
- 4.
Identification of System-Chemucal and Volume Control Date Sheet Unit:
I WO 9949106 October 21, 2002 1
of 1
Repair Organization P 0 No, Job No Etc Type Code Symbol Stamp N/A Authorization No Expiiation Date N/A N/A 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)
CV-00296 Copes Vulcan N/A NIA CV-296 Unknown Replacement No 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.
8 Tests Conducted:
Hydrostatic El Other El System Leakage Test
- 9.
Remarks RRM 2002-0019 Pneumatic E]
Pressure 2259.5 psi Nominal Operating Pressure Test Temp.
547 OF PBF-7050 Revision 1 05/17/02 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 ISI Coordinator Date Signed
,/i..-.,,f/,,.*
ON tier or Oxkiict'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 February 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 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, concerning the examinations and corrective measures described in this Owner's Report. Fuithermore, neither the Inspector nor his employer shall be liable in any manner for any peisonal injury or property damage or a loss of any 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 SEM 7 11 1 I
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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
We Energies lime 6610 Nuclear Road TTwo Rivers, WI 54241 sddrem a
4 Identification of System Residual Heat Removal Date October 22, 2002 Sheet:
1 of I
Unit:
I WO 0202449 Repair Organization P.O No., Job No. Etc Type Code Symbol Stamp N/A Authorization No.
Expiration Date N/A N/A 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 Description of Work:
Drill 2" diameter hole to facilitate FME removal and add vent valve.
Tests Conducted:
Hydrostatic ED Other El Pneumatic Rl Pressure 350 psi Nominal Operating Pressure I
Test Temp.
80 OF System Leakage Test
- 9.
Remarks RR 2002-0042, CAP 030632, Code Case N-416-1 PBF-7050 Re),ision I 05/17/02
- 7.
8.
&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 SCono aj oo0 Signed
?2" 7.6 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:
e t
eA
/, Za'-
SEM 7 It 1 owner or 6%%mees Desi"cc Title ISI Coordinator Date N*.vner or (*\\,.'ner'* I)egionee_ Title
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 700 First Street, Hudson, Wl 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
We Energies name 6610 Nuclear Road Two Rivers, WI 54241 Date October 21, 2002 Sheet:
1 of 1
Unit:
I WO 9944661 Repair/Replacement Organization P.O. No, Job No Etc Type Code Symbol Stamp N/A Authorization No.
Expiration Date 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 Other 0
Pressure 2235 psi Test T System Leakage Test
- 9.
Remarks RR 2002-0051 Pressure El Exempt emp.
547 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 n e d m
" e ' -1 Owner or Owner's Designee, Title ISI Coordinator Date PBF-7050 Revision 2 12/02/02 N/A N/A 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 SEM7II 7
11 OF ZZ el;
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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
We Energies name 6610 Nuclear Road Two Rivers, WI 54241 Date Sheet:
October 31, 2002 1
of 1
Unit:
1 WOs 0205506, 0205507, 0205508 Repair/Replacement Organization P.O. No, Job No Etc Type Code Symbol Stamp N/A Authorization No.
Expiration Date N/A 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 Other E]
Pressure 1540 psi System Leakage Test
- 9.
Remarks RR 2002-0052 C,-f 3c (-, c/-
perating Pressure 0
Exempt Test Temp.
79 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 PBF-7050 Revision 2 12/02/02 El "OF SEM 7 11.1 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:
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 700 First Sheet, Hudson, WI 54016 2
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers. WI 54241
- 3.
Woik Performed By:
Crane Movats namne 2825 Cobb International Blvd Kennesaw, Ga 30152 Date Sheet:
November 5, 2002 1
of 2
Unit.
I WO 9921983, 9921984 Repair/Replacement Organization P 0 No, Job No Etc Type Code Symbol Stamp VR Authorization No.
Expiration Date 475 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:
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 ISI Coordinator Date
//
/
Signed __z-
- -j'.-
,,,J~'*.r '-
,-)')/ 7 P1BF-7050 Reision 2 12/02/02 SEM 7 It 1 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-
-it
- ,*f
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 700 First Street, Hudson, WI 54016 2
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
Crane Movats name 2825 Cobb International Blvd Kennesaw, Ga 30152 Date November 5, 2002 Sheet.
2 of 2
Unit.
I WO 9921983, 9921984 Repair/Replacement Organizatuon P 0 No, Job No Etc Type Code Symbol Stamp VR Authorization No.
Expiration Date 475 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
.1 ________________
L
.1. _____________
L I.
A PBF-7050a Revision 2 12/02/02
- 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 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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
We Energies name 6610 Nuclear Road Two Rivers, WI 54241 Date October 21, 2002 Sheet:
1 of 1
Unit:
1 WO 9937802 Repair/Replacement Organization P.O No, Job No Etc Type Code Symbol Stamp N/A Authorization No.
Expiration Date N/A 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 Other Dl Pressure 350 psi System Leakage Test
- 9.
Remarks RR 2002-0064, CAP 030632 erating Pressure 0
Exempt Test Temp 110 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 27 V, Z<
ISI Coordinator Date PBF-7050 Revision 2 12/02/02 El OF 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 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 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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
We Energies name 6610 Nuclear Road Two Rivers, WI 54241 address
- 4.
Identification of System:
Reactor Coolant Date Nov Sheet:
1 Unit:
I WO 9812062 Repair/Replacement Organization P 0 No, Job No Etc Type Code Symbol Stamp N/A Authorization No.
Expiration Date 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 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:
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
- 9.
Remarks System Leakage Test 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 t'*pr ~r tt~ar' 13~l*naeTitle ISI Coordinator Date I.
PBF-7050 Revision 2 12/02/02 SEM 7.11 1
'ember 8, 2002 of 2
N/A N/A 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 August 8, 2002 to November 8, 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 *.
i, Commissions WI-100128 Inspectors 'Signature National Board, State, Province, and Endorsements Date:
/-/3-. C.3 nmcr or ONmees Desi-ce Title 2Zeýý
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 700 First Stieet, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
We Energies name 6610 Nuclear Road Two Rivers, WI 54241 Date NoN Sheet:
2 Unit-I WO 9812062 vember 8, 2002 of 2
Repair/Replacement Organization P 0 No, Job No Etc Type Code Symbol Stamp N/A Authorization No.
Expiration Date N/A 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 1 RC-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 5
ASME Code, Section Ile. Division 1:
1977 Winter 1978 2
None (edition)
(addenda date)
(class)
(Code Case no) 6 Pump or valve Valve Nominal inlet size 1
Outlet size I
(in.)
(in) 7 Material Body SAIL2 F316L Bonnet SA479 XM19 Disc SA564 630 Bolting SA453 660 (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 8
Des:gn conditions
.2.
5,-
psi 700 (pressure)
(temperature) 9 Cold working pressure 4372 psi at 100 'F I F or valve pressure class -
N/A (1)
- 10. Hydrostaic test 6575 psi Disc differential test pressure
- 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 Design Specification certified by T L Kettles P.E. State NY Reg No 029729 Design Report certified by Not applicable P E State Reg. No.
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are cor-ect and that this pump -.r valve conforms to the ruies for construction of the ASME Code,Section III, Division 1.
N Certificate of Authonzation No N-1947 Expires 1211212001 Date /O/Z.'/ZOO, Name Target Rock Sign d*
d' (N Certificate Holder)
R E Glazier, Ma.ger, z
a Q
E (authorized representative)
CERTIFICATE OF INSPECTION I, the undersig"ed, holding a valid commission issucd by the National Board of Boier and Pressure Vessel Inspectors I and the State of Provic2 of New York and employed by Commercial Union Ins of Boston, MA have irspected the pump, or valve described in this Data Report on 01__-,,__,____
ana slate that to the best if m/ knowledge and belief, the Certificate Holder has constructed this pump or valve, in accordance w=,tf the ASME Code. Section II1, Divison 1.
By signing this certificate, noither the inspector nor his employer makes any warranty, expressed or implied.
cnncerninq the corponent descnbed in this Data Report Furthermore, neither the inspec:or nor his employer shall 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',
nsi 4825
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:
[]
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 SEM%17.11 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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
We Energies name 6610 Nuclear Rd Two Riveis, WI 54241 address
- 4.
Identification of System:
Safety Injection Date Oct Sheet:
2 Unit:
1 WO 9946177 ober 15, 2002 of 2
Repair/Replacement Organization 10 0 No, Job No Etc Type Code Symbol Stamp N/A Authorization No.
Expiration Date N/A N/A 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
___________________________.1 ___________________________
.1 ________________________
PBF-7050O R*,*s wIll 2 I 2,02,02 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-00853A Velan Unknown N/A SI-853A Unknown Corrected No Studs/Nuts Unknown None N/A N/A Unknown Removed No Studs/Nuts Nova None N/A N/A Unknown Installed No I
I 4-1 1
I t
I I
+
I I
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- 4.
+
+
- 4.
1
+
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- 4.
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- 4.
I 4-1 4
4 1
- 4.
I
+
+
4 4
- 4.
I I
+
4 I
4 SEN1 7 11 I
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 700 First Street, Hudson, WI 54016 2
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241 3
Work Performed By:
We Energies name 6610 Nuclear Road Two Rivers, WI 54241 Date Oct Sheet-I Unit:
1 WO 9945054 ober 16, 2002 of 2
Repair/Replacement Organization 11 0 No, Job No Etc Type Code Symbol Stamp N/A Authorization No.
Expiration Date N/A 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:
Correcter 8
Tests Conducted.
Hydrostatic Other El d minor boric acid leak; replaced CS manway bolting with SS.
Pneumatic El Pressure See Remar Nominal Operating Pressure
[]
Exempt El 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 PBF-7050 Revision 2 12/02/02 SEM 7 I1 1
/
I Owner or Owniers DesZnee, 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 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
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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Riveis, WI 54241
- 3.
Work Perfotmed By:
We Energies namre 6610 Nuclear Road
-Two Rivers, WI 54241 addiess Date Sheet:
October 16, 2002 2
of 2
Authorization No.
Expiration Date
- 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 PBF-7050a Re% ision 2 12/02/02 Unit.
I WO 9945054 Repair/Replacement Organimzaion 1P 0 No. Job No Etc Type Code Symbol Stamp N/A N/A N/A 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
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4
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1 1
1-I 4
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+
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4
-i Ii 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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241 3
Work Performed By:
We Energies name 6610 Nuclear Road Two Rivers, WI 54241 Date October 14, 2002 Sheet:
I of 1
Unit:
I WO 0212380 Repair/Replacement Oiganization t' 0 No, Job No Etc.
Type Code Symbol Stamp N/A Authorization No.
Expiration Date N/A 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.
8.
Description of Work:
Corrected body to bonnet leak and replaced damaged bolting (seal welded).
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
ISI Coordinator Date
/7/
/ 6O5 PBF-7050 Re', ision 2 12/02/02 Owler 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 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 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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
We Energies name 6610 Nuclear Road Two Rivets, WI 54241 Date October 23, 2002 Sheet:
I of 2
Unit:
1 WO 0212465 Repair/Replacement Organization P 0 No, Job No Etc Type Code Symbol Stamp N/A Authoiizaton No.
Expiration Date N/A 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 Other 0I Pressure psi T
ting Pressure LI Exempt 0
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 ISI Coordinator Date
///6.2cu~2 pNri-'
10/
[(~La min 2 12/02/02 Owner or Owneies 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 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
SEM 7 11 1 Signed
- -/.7.
/
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 700 First Street, Hudson, WI 54016 2
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
We Energies name 6610 Nuclear Road Two Rivers, WI 54241 Date Sheet:
Unit 1
WO 0212465 October 23, 2002 2
of 2
Repair/Replacement Organization 1P 0 No, Job No. Etc Type Code Symbol Stamp N/A Authorization No.
Expiration Date N/A 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.
- 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 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
- 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 I certify that the statements made m 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 Autliorization No.
Expiration Date N/A Signed ISI Coordinator Date Owner or n*%%
r'1 DLSIguce. I, I tl/
/
CERTI FiCATE 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 22, 2002, and state that to the best of my knowledge and bhi.f, the Owxner 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 coliective measures described in this Ownei's Report. Furthermore, neither the Inspector nor his employei shall be liable in any manner for any personal injury or property damage or a loss of any 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 Revision 2 12/02/02 SEM 7.11.1 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
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 National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped r,
o,rS1 No No Identification Built Installed (Yes or No)
Component SI-00S92A 2"-SI-902R-2 2'-ST-902R-2 Rockwell Mfg Co Rockwell Mfg Co Sandvik unknown NIA CD 857 N/A N/A N/A N/A N/A N/A SI-892A SI-892A NT 6179H N/A Unknown 1987 Unknown Unknown Removed Installed Installed Removed No No No No PBF-7050a Revision 2 12/02/02 SEM7 71 1 7o
- .,IOl I IpUll l l t SI-00892A SI-00892A 2"-SI-902R-2 2"-SI-902R-2
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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
Day & Zimmerman name 1866 Colnial Village Ln, Suite 101 Lancaster, PA 17601 Date October 14, 2002 Sheet:
1 of I
Unit:
1 WO 0212464 Repair/Replacement Organization P.O No, Job No Etc Type Code Symbol Stamp R
Authorization No.
Expiration Date R-1958 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 s 8
Tests Conducted:
Hydrostatic El Pneumatic El Other El Pressure eal welding.
Nominal Operating Pressure
[:
Exempt N
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 PBF-7050 Revision 2 12/02/02 SEM 7 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 "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 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 9 - -11 1;
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of d-16 %:)il ;~
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% % s (sot It.1 is.urtanksl. 1-ilk i% of,im k~tc i t ss l or %h( 1% o it hr itn.
x, hang, rs.
Ticncs~jn.Allowancc/3n.
0im.
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itti
~1C3______ I T.
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L t -:J en..
Ellsiptical C... ca.I 14.l.1 flmhpercics I
F at Side to r-ek-,r ii.. cd)
Thi.,-,,
Ws.,i.n idiw.
Rtiu o Apes Angle Redi..
Diam.,ter (Corivee or Concave) 1.)
=.:Z0..
in____IT__01 if rrnts~b bolts uscc!____
Other fastening...lrcldici...........
maeilspec No..SSze umher)
(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)
AC.
JKl-T (I (EJI :________
(De~ce~beooj~m1Jt7tVi-T FCi.... i, dimension, i f b olt ed. descrileo kth
- o.
C totrut ted titr m~ix.
'Te.stmp (he ol'ta~..rk ing prt s% __J.50 psi at mak. temp...425G r. less than -2Oo) re____
s~tci 2u.~cs.~.p lIit m% 1I Lin Io I 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.
N1 itecial
__Kind
__&_______No Diam.-____
In Thickness
-In.
Attachment_______
S.-213 Inchese No I I T1Il 11; : mIatt r.tiI 12 4...O.D)......?....
In. Thickness
-04 I~e sme ~ I.
....... Type.co.Ci..........
(Kind -,P;.
fN.
ume 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. orF k3 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 at___
i......
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 ssorktn3. press.L 2 1, ý8 psi at max. temp.....6
.?F.
less than-20 0) 0 F.
p Pes 3...Isi.
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
'It postmelId 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'l \\l\\,
. I I1,lhol.,. No.
L cS, t
, [.o ation Thrt.ded, No.
Sitc L.ocation
- 19. St II'POKS -.
'.rt l.ugs L gs Other Attachtd
- ,:-l Si,-
,,2
^z---On V" L' kl~riet description of purpose of the vessel, as Air Tank. Alter Cooler. Jacketed Cooker. etc. State conventw of each part.)
'.t c'trltf t
thal 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.
Date c.
196.
Sirgncd Scn l-y*_ :ip-rt t M=,.n iif~cturer r
c rtl,,,*te of Auttra.. tton I:spmres...-!,
." rL-31.--1 6 9 C:EIfI FICATE 01".'11l01 IN' I'EC'1IIO VESSEL MADE BY S:iM_*1ipOatJ---
C-lo.=p at W
coilsii I. the undersigned, holding a vklid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or tI-c S:ate or Proince
"; a=!:!n and employed byD-Pt Of t'tr" t",*'
-or 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 lurer has constructed this pressure vessel in accordance with the applicable secttons of the ASME Boiler and Pressure Vessel Code.
B) sigring this certllcate neither -the Inspector nor his employer makes any warranty, expressed or implied, concerning the pressure vessel described in thts minufacturer's data report. Furthermore, neither the Inspector nor his employer shall be hable tn an) manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
D.te 2'- 7 1968 V11____
41:4
-___ Commissions JIM-..LB92J.i Inspectors Stinature Nat'1 iosrO or State and No.
CERTIF:I" VI E OF FIEIEL)
ASSEMBILY IN'WECTION 1, the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the Slzate or Pro'tnce and employed by of have compared the statements in this manufacturer's data report with the described pressure vessel and state that parts referred to as data items not included in the certificate of shop inspection have been inspected by me and that to the best of my knowledge and belief the manufacturer has constructed and assembled this pressure vessel in accordance with the applicable sections of the ASME Boiler and Pressure Vessel Code. The described vessel %,as inspected and subjected to a hydrostatic test of psi.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the pressure vessel described in this n anufacturer's data report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a lose of any kind arising from or connected with this insp*ection.
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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
We Energies nanme 6610 Nuclear Road Two Rivers, WI 54241
- 4.
Identification of System address Reactor Coolant Date October Sheet:
I of Unit:
1 WO 9942120 21,2002 Repair/Replacement Organization P 0 No, Job No Etc Type Code Symbol Stamp N/A Authotization No.
Expiration Date N/A N/A 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 Owner or Owners Designee, Title ISI Coordinator Date t,
f PBF-7050 Reviston 21 12u2/U2 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 SiMt 7 11 1 I
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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
We Energies name 6610 Nuclear Road Two Rivers, WI 54241 Date Sheet:
October 21, 2002 1
of I
Unit:
1 WO 9941998 Repair/Replacement Organization P.O. No, Job No. Etc Type Code Symbol Stamp N//j L,
7 Authorization No.
Expiration Date N/A N/A address
- 4.
Identification of System:
- 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 Signed o
_e__Designee,-ide Owner or Owner's Designee, Ttfle
/
-f PBF-7050 Revision 2 12/02/02 SEM7 11 1 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
t*SsICr7OL VErsa, I P 6./f
- 0. SS D
FORM& N-1AA
"..FCUES P\\A IWOTFUNUCLU.A2
\\ SSLS
(,Q
,1&'Alternlatce)a 2c 10o ile (TI r-.kr Lr ýco...pletnly
-Lop 7.A ed Vae-se!s G' A,- required by the P~oaisicrns offthe.~IE'Code t(riles zid 0~:e Nal~onail fzt~-
- r'~ss.
Mrnuftctuýet by
'--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 1.re S8r.l (S8t & SttN SLA-302B*
ý Mtr+/-.
rg 2
- 4.
Ok~.
Shl 8O5.505-Th 6
cc""-
3 6 6 1i:
Sh Ml:'oer:al...
.-:Y...........
T....
.. ~...
- t.
hk..
- z.
Allow...... In. DiC-i1..
t......
t9
!n Lcng:b.. 2........
l find & 5Spec. No )
(l.1in. of tr.-ce specified)
Oe-13c S. Seams Long dtt..
E T.
o e
~cec.........
(if Class 0)
Girth B.t ld
.H. T.
yes R.
3 R.....
....... No. of Courses......
0....
- 6. Hleads- (;,)
Material 3kOŽ
- 0 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
~~~~~~~~...
rT.
i.oa
/
if~~~~~~~~
~~~~
r.r.
bot.s.......Ž52.Ab
(
A4.Ohrfutr (Material. Spec. NIo., 7.5., Size. Namrber)
(Describe or A ttachb'.p:
1 XrM)~
- 7. Constructed fo£hap im ac.......
H fl, Tes operating presz.2...... 21j
..... PSI. at nlax. cetup..2 5902 in_
at; tepTf2 F
e~-
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 13353 2l3-2.
2 Renfnrce'rent HowF Outlet. Drain)
Nunbcr Diazr. a: Si,,e Type Materj:.1 Thtck-iess Materialt11c (P
........... 59
... ~,
~ i>;uJK~~ "A41ah bS'.'h
.::MJS.
Z~17..
9 10.Insecton
.ariho'cs, 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
fl h r~.
2 L.~
-U
.i m.--
'$r 1....................
)~.............
SP............v4
ýLL..
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 z
'J`.
~
Certificate of Authorization Expires L.
7i.?z.r...........
in_!1Lau.-Vj()J Dasigo infomation on fle at The OF DESIGN!
abr~
Strss nalsisreprtefile at B~C~
t~~
.~.
ýeBLs
~
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.'
0s
.hxir S.B
.£ I
of
'Th-d
!c.'7ff-:
~
ive inspected the p~estuv:e vessel dnscrtbed in tHis n.:-n_'2!a:Ur~r's data re.-orx or
/. el 4
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 a r 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
- 1.
Owner Nuclear Management Corporation 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
We Energies name 6610 Nuclear Road Two Riveis, WI 54241 address
- 4.
Identification of System.
Residual Heat Removal Date Octc Sheet:
1 Unit:
1 WO 9937845 ober 22, 2002 of 1
Repair/Replacement Organization P.O No., Job No Etc Type Code Symbol Stamp N/A Authorization No.
Expiration Date N/A N/A
- 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 Name of Manufacturer Board Other Removed or Stamped Component Manufacturer Serial No No Identification Built Installed (Yes or No)
RH-00700 Darling Valve N/A N/A RH-700 Unknown Corrected No Co.
RH-0700 Cap Unknown NIA N/A None Unknown Installed No
- 7.
Description of Work:
Replaced capped end of the leak off line due to minor leakage.
- 8.
Tests Conducted-Hydrostatic El Pneumatic Dl Nominal Operating Pressure Z
Exempt L
Other 11 Pressure 2260 psi Test Temp.
546 OF System Leakage Test
- 9.
Remarks RR 2002-0093 eAt 03406*.
PBF-7050 Revision 2 12/02/02 I
SEM 7 11 1 AppllLable ioanuracturer's Data Reprs to oc attac e CERTIFICATE OF COMPLIANCE I certify that the statements made in the iepoit ate 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 ISI Coordinator Date uv,1Ivr ul
lick 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 Owrner's Report during the period September 25, 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 Conmnissions 1%VI-100128 Inspector's Signature National Boai d, State, Province, and Endorsements Date:
J 7
0%&nerorV'A11e15 CSIý-IICC.
I C j6iý6 t
f Signed J,...*/'
Z..
Z -
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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By:
Welding Services Inc.
name 2225 Skyland Ct.
Norcross, GA 30071 address
- 4.
Identification of System:
Safety Injection Date October 31, 2002 Sheet:
1 of 1
Unit:
1 WO 0212624, 0212683, 0212695 Repair/Replacement Organization P.O. No, Job No Etc.
Type Code Symbol Stamp NR Authorization No.
Expiration Date NR-69 11/07/2004 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)
T-034A Delta Southern 41035-67-1 N/A T-34A 1967 Corrected Yes Co.
nozzles
- 7.
8.
9.
Description of Work:
Modified nozzles to remove indications on the inside surface.
Tests Conducted:
Hydrostatic El Pneumatic Ml Nominal Operating Pressure 0
Exempt El Other El Pressure 735 psi Test Temp.
Ambient
- F System Leakage Test Remarks RR 2002-0094, 2002-0100, 2002-0102, 2002-0105 PBF-7050 Revision 2 12/02/02 SEM 7 11.1 nppiciiuic LVk411U14L1u1;I
.JaLa.sLIu, Appllhcabe MVanIuI ct;Ur l ttta ep.Ult o s 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 ISI Coordinator Date Signed fl*.-re nr fluSre6 fl....
nee 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..
S* w**
- T m
owner or Ownees Desi-ee Title L7 1-2 &,, 53 f
/
FORM NR-1 REPORT OF REPAIR F-MODIFICATION F_
OR INSTALLATION OF REPLACEMENT(S)
[
TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Job N
.3214 Wpldmna Services Inc.
- 1.
Work performed by rdinr nn*nltin' PO no. lob no. etcIc
- 2.
3
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
- 10.
- 11.
12 CERTIFICATE OF INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the state of Province of s,,. ns' and employed by Ms 13 C -,
of have inspected the repair, modification or replacement descnbed in this report on C'j?
'3,
.19 Z C0 2.
, and state that, to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied. conceming the repair, modification or replacement descnbed in this report Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind 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 Ti fom.ayb.otand.ro..e.aioa
- or 01 e an r*~
i iii...
t=...
.vn*
Pnr~~ Ar, ni,'.,
Nn5m-8 O
422 NB-8!
Rew 6 (address)
Owner Nuclear Management Company, LLC (name) 6590 Nuclear Road. Two Rivers WI. 54241 (address)
Name, address & identification of nuclear power plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers WI. 54241 System Safety Injection System a: Component repaired, modified or replaced Repair b: Name of manufacturer Delta Southern Company c: Identifying nos.
41035-67-1 N/A WI U009976 1-T34A 1967 (rrmr s senal no )
(Nat I Bd No) purisoctional no (biner)
(year built) d: Construction Code Section III. 1967 Edition N/A N/A N/A (editon)
(addenda)
(Code Case(s)j (Code Cass)
Section XI 1998 Edition Through 2000 N/A (edition)
(addenda)
(Code Case(s)j Applicable edition of ASME Code Section XI 1998 Edition Through 2000 N/A under which repairs, modifications, or replacements were made (edition)
(addenda)
[Code Case(s Applicable edition of Construction Code Section III 1992 No NIA under which repairs. modifications, or replacements were made (Code) (edition) (addenda) [Code Case(s)l Design responsibilities Nuclear Management Company, LLC Tests conducted: hydrostatic pneumatic design pressure = pressure By Others psi Description of work: Machined existing nozzles "A" and reattached piping in accordance to customer provided design and (use of additional sneet(s) or sketchtes) is acceptaole if properly identilied) calculations Reference No. PBCH-01Q-301 Remarks. CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items descnbed above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition Certificate of Authonzation No NR-69 to use the "NR" stamp expires November 7 19 2004 Date October 3 2002 Name Welding Services Inc Signed Site QA Manager (Reoair Oroanization) (Authorized Reoresentatlvebl (Title) Job No 32142 frecair o-anization's P 0 no job no, etc ) (name) This form may be obtained from The National Bsoardof OTBoiler and P'ressure vessel In-.pecto, av...,v, -P I
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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivets, WI 54241 3 Woik Performed By: Welding Ser ices Inc. name 2225 Skyland Ct. Norcross, GA 30071 Date October 9, 2002 Sheet-I of 1 Unit: 1 WO 0212602, 0212615, 0212696, 0212682 Repair/Replacement Organization P 0 No, Job No Etc Type Code Symbol Stamp NR Authorization No. Expiration Date NR-69 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 PBF-7050 Revision 2 12/02/02 tO)wner or Ow,,net's Des,,nice. Title ] SEI7 I1 1 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 "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 Siý(nature National Board, State, Province, and Endorsements Date: .d/?z't /.; ZCtE3 T
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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By: We Energies name 6610 Nuclear Road Two Rivers, WI 54241 Date October 5, 20 Sheet: 1 of I Unit: 1 WO 0212611 Repair/Replacement Organization P.O. No, Job No Etc Type Code Symbol Stamp N/A Authorization No. Expiration Date N/A N/A 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 Description of Work: Rewelded support PS-1 which was cut to remove RV shroud. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pr Other Eli Pressure psi Test Ten essure El Exempt LIp. 0 V. n-t- 'PP '2flf2-09.Qf n4 fl?, ^-.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 ,')amr Chv n,'ne' fl)e*1e-iee_ Titde PBF-7050 Revision 2 12/02/02 ISI Coordinator Date SEM 7.11.1
- 7.
8. 0F 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. 2! Commissions WI-100128 Inspector's 4nature National Board, State, Province, and Endorsements Date: ,7,4, 6, zev. }02 115 /2-4; 1L.- 5 1 5,-----r6w--eesDesi-ee Tide
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 700 First Street, Hudson, WI 54016 2 Plant Point Beach Nucleat Plant 6610 Nuclear Road, Two Rivers, WI 54241 3 Work Performed By: We Energies name 6610 Nuclear Road Two Rivers, WI 54241 address
- 4.
Identification of System: Main Steam Date October 28, 2 Sheet. I of I Unit: 1 WO 0212621 002 Repaii/Replacement Oiganization P 0 No, Job No Etc. Type Code Symbol Stamp N/A Authorization No. Expiiation Date N/A N/A 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 Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No No Identification Built Installed (Yes or No) MS-00218 Velan Inc None None MS-218 1999 Removed/ Yes Installed Piping Unknown None None None Unknown Removed/ No Installed
- 7.
Description of Work: Replacement of valve, immediate piping and elbow.
- 8.
Tests Conducted: Hydrostatic n] Pneumatic Fl1 Nominal Operating Pressure 0 Exempt I Other El Pressure 1000 psi Test Temp 547 OF
- 9.
Remarks RR 2002-0097 Signed 2-- Owieror Owneifs Designee, Title ISI Coordinator Date 11/72 &) PBF-7050 Revision 2 12/02/02 Applicable Manufacturers uata Report, to e ata,, 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 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid comnu*ssion 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 28. 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Ownei'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 National Board, State, Province, and Endorsements Date"-/. 's/S 1 gna ur SENt 7 11 1 Date-
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
- 4. Model No., Seri~es No., or T'ype: GATE NI!-.
name and addrm') Drawing P1-76600-NOI Rev F CHNT N/A
- 5. ASM-E Code, Secti.on 111, DiN
- 6.
Pump or valve VALVE
- 7. Material: Body, SA-1O5,CS (a)
Cart. Holder's Serial No. (b) Nat I1 Board No. N/A ission 1: 1989 NONE 1 X/A (edition) (addenda date) (class) lCode Ciast no !Nom~inal lnlelt size 2 Outlet size 2 (iti.) (in ) Bonne tSA-105, CS Disk SA-351,CFEM Bolta-ng SA-194. (c) Body Serial No. H/C:tiFD RFD HF-D FrD HFD HFL) HFD_ (d) Bonnet Serial Mo. H/C: C-B, c-B c-B C-B C-B C-B C-B 211 (a) No. H/:86Z 86Z 86 Z .'upplemnenta inrorm~non in fmnO ofim sai.keichmi urdran~io m3% be U'ed pro%)dnJ (111 su sS1~I.)~ff~t~
- nie, tr~
on ihi, V~jtl RCPpitt is included on cacb sheet. (3) each shect is numbcrtd 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 p .4 BIEST COPY AVAILAB1-LE 2 I a . P01 .V I .. 991121-2 991121-3 -~*991121-6
- !A-193,37,
FORM NPV-I (Back - Pg. 2 of 2 ) Certificate Holder's Serial No. 99112!
- 6. Design conditions
- 9. Cold working pressure
- 10. Hydrostatic test 1975 psi 100
- F or valve pressure class (pressure)
(temperature) 1975 psi at IC0'F 3000 psi. Disk differential tcst pressure 2200 psi
- 11. Remarks:
MATERIALS H-ET ASME SECTION II EDITION: 1989 ADDENDA: NONE 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 M21t or em%. x rid no. z Ii (1) For manually operated valves only. V', 5r-P " VAIk'i 3E S00 (1) 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 U M MO M jg'l 1'11111ý6'1 1ýý Iiii'll PA4 Si&
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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By: Crane Nuclear nnme 2825 Cobb Internation Blvd. Kennesaw, GA 30152 Date Sheet Unit: I WO 9937372 September 30, 2002 1 of I Repair Organization P0 No,Job No Etc Type Code Symbol Stamp N/A Authorization No. Expiration Date N/A N/A 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 Name of Manufacturer Board Other Year or Stamped Component Manufacturer Serial No No Identification Built Replacement (Yes or No)
CC-00763A Crosby 51032-N/A CC-763A Unknown Replacement No 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. O__ F None
- 9.
RemarKs 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 ISI Coordinator Date Signed ? r,-,1A! o'X PBF-7050 Revision 1 05/17/02 /./ C)ýL ) ) 3 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 September 26, 2002 to September 30, 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. Furthemiore, 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-f-6441-Commissions WI-100128 Inspector's Signature National Board, State, Province, and Endorsements Date: -- //,?c? SEM 7 11 1 lu"I'*VI /-UUL-U I UU micror Nne
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 700 First Street, Hudson, WI 54016 2 Plant Point Beach Nucleai Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By: We Energies name 6610 Nuclear Road Two Rivers, WI 54241 Date Oct Sheet: I Unit: 1 WO 9918412 Ober 21, 2002 of 1 Repatr/Replacement Organtzatton P 0 No, Job No Etc Type Code Symbol Stamp N/A Authorization No. Expiration Date N/A N/A address 4 Identification of System: Main Steam Bech Spec 6118-N-87 5 (a) Applicable Construction Code B31 JL 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 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 Ohuer or ON& nc's Designee. Tatle ISI Coordinator Date PBF-7050 Revision 2 12/02/02 1/ /,12 e-6,i
- /
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 SEM 7 11 I
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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241 3 Work Performed By: We Energies name 6610 Nuclear Road Two Rivers, WI 54241 address 4 Identification of System Incore Flux Mapping Date October 22, Sheet: 1 of I Unit: 1 WO 9942381 ?002 Repair/Replacement Organization P 0 No, Job No Etc Type Code Symbol Stamp N/A Authorization No. Expiration Date N/A N/A 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 Name of S, -t,,nnnon T r I Name of M *nil fact"llirer" Manufacturer Serial No National Board No Other Identification Year Built Corrected, Removed or Installed ASME Code Stamped (Yes or No) FM-Thimbles N/A N/A N/A N/A Unknown Removed No FM-Thimbles Swagelock N/A N/A N/A Unknown Installed No
- 7.
Description of Work: Replacement of union fittings due to degradation.
- 8.
Tests Conducted: Hydrostatic El Pneumatic El Nominal C Other El Pressure psi None D D I LU.AlJ A I.J n PBF-7050 Revision 2 12/02/02 )perating Pressure [:I Exempt [9 Test Temp. OF SEM 7 11.1 Atpplicable M*anufacturer s 1,ata e~lpui:,ts c attache 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 ISI Coordinator Date Signed 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 Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 1, 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 S .(.rCommissions WI-100128 Inspector's Sigyiture National Board, State, Province, and Endorsements Date: it A ý.
- i.
I t, _Z_
- 9.
Remarks L Z2,1,, e, 5
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 t-r ISI Coordinator Date Z///C/() 0Anr O w iiefs Designece, Title 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 Revision 2 12/02/02 SE.N17111
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 700 First Street, Hudson, WI 54016
- 2.
Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241
- 3.
Work Performed By: We Energies name 6610 Nuclear Road Two Rivers, WI 54241 Date Sheet: Unit: 1 WO 0212972 October 18, 2002 2 of 2 Repair/Replacement Organization P 0 No., Job No Etc Type Code Symbol Stamp N/A Authorization No. Expiration Date N/A 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 PBF-7050a Re% tsloo 2 12'02/02 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 SPI' 7 1 1 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 700 Fust Stieet, Hudson, %VI 54016 2 Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241 3 Work Performed By: Crane Movats namne 2825 Cobb Inteinational Blvd Kennesaw, GA 30152 Date September 2 Sheet I of 1 7, 2002 Unit: 1 WO 0207001 Repair/Replacement Organization P 0 No, Job No Etc Type Code Symbol Stamp VR Authotization No. Expiation Date 475 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 Other nI Pressure 2250
- 9.
Remarks nal Operating Pressure 0 Exemrpt psi Test Temp. 547 IT-230, 1-PT-RCS-1 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 PBF-7050 Revision 2 12/02/02 OF oF / 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. I q _e-,-3 SEM 7 11 1 n%% n r or Owners Dcsi ee Title}}