Text

2004 Inservice Inspection (ISI) Summary Report
	ML050620242
Person / Time
Site:	Kewaunee
Issue date:	02/24/2005
From:	Lambert C; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NRC-05-023
	Download: ML050620242 (213)
	v • d • e

Commtied to N iM) Kewaunee Nuclear Power Plant Operated by Nuclear Management Company, LLC February 24, 2005 NRC-05-023 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Kewaunee Nuclear Power Plant Docket 50-305 License No. DPR-43 2004 Inservice Inspection (ISI) Summary Report As required by American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI; Code of Federal Regulation 10CFR50.55a and Wisconsin Administrative Code Department of Commerce, Subchapter V: Chapter Comm 41.55 (3), various ISI examinations were performed as part of the 2004 Refueling Outage at the Kewaunee Nuclear Power Plant (KNPP). The outage took place from October 9, 2004 through December 4, 2004. This letter transmits the Inservice Inspection Summary Report as required by paragraph IWA-6230 of Section XI.

Two separate ASME Section XI inservice examination programs are implemented at KNPP. One program is for pressure retaining piping/vessel and component supports, and the other program is for the metal containment. The 2004 Refueling Outage Inservice Inspections were used to meet the requirements of three distinct inspection program intervals as listed:

a. 3rd Inspection year of the 3rd Period of the 3rd Interval for Class 1, Class 2, and Class 3 Components - Inspections were performed to the examination requirements of ASME Boiler and Pressure Vessel Code, Section Xl, 1989 Edition with implementation in accordance with the Kewaunee Nuclear Power Plant Third Ten-Year Inservice Inspection (ISI) Program 1994-2004.

b. 1st Inspection year of the 3rd Period of the 1st Interval for Class MC Components -- Inspections were performed to the examination requirements of ASME Boiler and Pressure Vessel Code,Section XI, 1992 Edition 1992 Addenda with implementation in accordance with the Kewaunee Nuclear Power Plant First Ten-Year Inservice Inspection (ISI) Class MC Program 1996-2006.

N490 Highway 42 . Kewaunee, Wisconsin 54216-9511 Telephone: 920.388.2560

Document Control Desk Page 2

c. 1st Inspection year of the 1st Period of the 4th Interval for Class 1, Class 2, and Class 3 Components -- Inspections were performed to the examination requirements of ASME Boiler and Pressure Vessel Code, Section Xl, 1998 Edition 2000 Addenda with implementation in accordance with the Kewaunee Nuclear Power Plant Fourth Ten-Year Inservice Inspection (ISI) Program 2004-2014.

The following examinations and tests were performed for Class 1, Class 2, and Class 3 Components and their supports:

Preservice Examination of Replacement Reactor Vessel Closure Head Control Rod Drive Mechanisms

Reactor Vessel: Flange to Shell Weld, Circumferential Shell Welds, Circumferential Head Welds, Nozzle To Shell Welds, Nozzle Inside Radius Sections, Integrally Welded Attachments and Nozzle To Safe End Butt Welds

Reactor Vessel Closure Head Studs, Nuts, Washers and Threads in Flange

Pressurizer Circumferential Shell Welds, Longitudinal Shell Welds and Nozzle Inside Radius Sections

Steam Generator: Tube Sheet to Head Weld, Primary Nozzle Inside Radius Section, Integrally Welded Attachment, Feedwater Nozzle To Shell Weld and Feedwater Nozzle Inside Radius Section

Reactor Coolant Pump Main Flange Bolting and No. 1 Seal Housing Bolting

Residual Heat Removal Heat Exchanger Shell Circumferential Weld and Integrally Welded Attachment

Charging Pump Pulsation Dampener Head Circumferential Weld

Regenerative Heat Exchanger Head and Tube Sheet to Shell Circumferential Welds

Class 1 Valve Bodies

Class 1 Piping Integrally Welded Attachments

Class I and Class 2 Piping Welds

Preservice Examination of Class 2 Piping Welds

Class 2 Safety Injection Pump Integrally Welded Attachments

Class 2 Piping Integrally Welded Attachments

Class 1, Class 2, and Class 3 Piping and Component Supports and Hangers

Class 1 and Class 2 Steam Generator Primary Manway Bolting, Pressurizer Manway Bolting, Flange Bolting and Valve Bonnet Bolting

Class 3 Piping and Component Integrally Welded Attachments

Class 1 System Leakage Test

Class 2 and Class 3 System Leakage Tests

Document Control Desk Page 3 The following items were examined for the Class MC Reactor Building Containment Vessel:

Accessible Surface Areas

Longitudinal and Circumferential Welds

Sleeve To Bellow Welds

Flange Welds and Dissimilar Metal Welds

Seals, Gaskets and Moisture Barriers

Bolted Connections

Airlocks

Pressure Retaining Components In addition, the following examinations were performed in excess of ASME Boiler and Pressure Vessel Code,Section XI, 1998 Editions 2000 Addenda requirements and included the following:

1. Portions of the service water system were radiographed for wall loss, pits, nodules, and sand, mud or other sediments.

2. Balance of plant piping subject to erosion/corrosion was examined by radiographic, ultrasonic, and visual techniques.

3. Nuclear Regulatory Commission Bulletin 88-09 Eddy Current Of Reactor Vessel Thimble Tubes.

Enclosed is a copy of the following documentation that summarizes the Inservice Inspection activities and results relative to the Kewaunee Nuclear Power Plant 2004 Refueling Outage.

1. Summary of Recordable Indications (Rls) and Disposition (Enclosure 1)

2. Summary of Class 1 and Class 2 Repair/Replacement Activities of Components 1 Inch in Diameter or Smaller (Enclosure 2)

3. Form NIS-1 Owners Report for Inservice Inspections of Class 1, Class 2, and Class 3 Components for Third Ten-Year Interval (Enclosure 3)

4. Form NIS-1 Owner's Report for Inservice Inspections of Reactor Vessel Ten-Year Examinations for Third Ten-Year Interval (Enclosure 4)

5. Form NIS-1 Owner's Report for Inservice Inspections of Class 1, Class 2, and Class 3 Components for Fourth Ten-Year Interval (Enclosure 5)

6. Form NIS-1 Owner's Report for Inservice Inspections of Reactor Vessel Examinations for Fourth Ten-Year Interval (Enclosure 6)

Document Control Desk Page 4

7. Form NIS-1 Owner's Report for Preservice Inspections of Replacement Reactor Vessel Closure Head (Enclosure 7)

8. Form NIS-1 Owner's Report for Inservice Inspections for Class MC Components (Enclosure 8)

9. Form NIS-2 Owner's Report for Repair/Replacement Activities (41 Total)

(Enclosure 9)

10. Examination Summary for Class 1, Class 2, and Class 3 Inservice Inspection Program for Third Ten-Year Interval (Enclosure 10)

11. Examination Summary for Reactor Vessel Inservice Inspection Program for Third Ten-Year Interval (Enclosure 11)

12. Examination Summary for Class 1, Class 2, and Class 3 Inservice Inspection Program for Fourth Ten-Year Interval (Enclosure 12)

13. Examination Summary for Reactor Vessel Inservice Inspection Program for Fourth Ten-Year Interval (Enclosure 13)

14. Examination Summary for Preservice Inspection of Replacement Reactor Vessel Closure Head (Enclosure 14)

15. Examination Summary for Inservice Inspection Class MC Program (Enclosure 15)

16. Examination Summary for Eddy Current of Reactor Vessel Thimble Tubes (Enclosure 16) 17.Summary of Examinations That Were Limited by Geometric, Metallurgical, or Design/Access Restrictions and Associated Data Sheets (62 Total)

(Enclosure 17)

The final reports for each of these examinations are on file in the Quality Assurance/Quality Control Records Vault at the Kewaunee Nuclear Power Plant.

Document Control Desk Page 5 The next refueling outage at the Kewaunee Nuclear Power Plant is tentatively scheduled for spring 2006. Please address questions regarding this submittal to Mr. Phillip Bukes, (920) 388-8572.

~0 Craig ert Site Vice President, Kewaunee Nuclear Power Plant Nuclear Management Company, LLC Enclosures (17) cc: Administrator, Region ll, USNRC w/o enclosures Resident Inspector, Kewaunee, USNRC w/o enclosures

ENCLOSURE 1

SUMMARY

OF RECORDABLE INDICATIONS (Rls) AND DISPOSITION DESCRIPTION TYPE OR LOCATION OF METHOD NO. OF Rls RECORDABLE INDICATION (RI)

1. Reactor Vessel Outlet Nozzle To Shell Welds Volumetric (UT) 15 Indications

2. Reactor Vessel Inlet Nozzle To Shell Welds Volumetric (UT) 7 Indications

3. Reactor Vessel Safety Injection Nozzle To Volumetric (UT) 4 Indications Shell Welds

4. Reactor Vessel Bottom Head Circumferential Volumetric (UT) 1 Indication Weld

5. 4" Safety Injection Nozzle To Safe End Weld Surface (PT) 1 Weld

6. Component and Piping Supports and Visual (VT-3) 12 Supports; Hangers; Valve Bonnet Bolting 5 Valves

7. System Leakage Pressure Tests Visual (VT-2) 56 Items

8. Reactor Building Containment Vessel General Visual 10 Plates and VT-3

9. Reactor Building Containment Vessel General Visual 1 Airlock Personnel Airlock and VT-3

10. Reactor Building Containment Vessel VT-3 1 Gasket Personnel Airlock

11. Reactor Building Containment Vessel VT-1 1 Swing Bolt Equipment Door Page 1 of 3

Dispositioning of Class 1, Class 2, and Class 3 indications has been completed in accordance with the rules of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, 1989 Edition for Third Ten-Year Interval examinations, ASME Boiler and Pressure Vessel Code, Section Xl, 1998 Edition 2000 Addenda for Fourth Ten-Year Interval examinations, and ASME Boiler and Pressure Vessel Code, Section Xl, 1992 Edition 1992 Addenda for Class MC Components.

Applicable codes, standards, and engineering criteria were used to disposition indications associated with the non-code-required examinations. Recordable Indications for Class 1, Class 2, Class 3, and Class MC have been dispositioned as summarized below:

1. Reactor Vessel Outlet Nozzle To Shell Welds RV-W7 and RV-W1 0 during Remote Ultrasonic Examinations revealed a total of 15 separate Indications (10 on RV-W7 and 5 on RV-W10). These indications were evaluated to ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition 2000 Addenda Acceptance Standards Table IWB-3512-1 and were Code Allowable.

2. Reactor Vessel Inlet Nozzle To Shell Welds RV-W6 and RV-W9 during Remote Ultrasonic Examinations revealed a total of 7 separate Indications (5 on RV-W6 and 2 on RV-W9). These indications were evaluated to ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition Acceptance Standards Table IWB-3512-1 and were Code Allowable.

3. Reactor Vessel Safety Injection Nozzle To Shell Welds RV-W8 and RV-W1 1 during Remote Ultrasonic Examinations revealed a total of 4 separate Indications (3 on RV-W8 and 1 on RV-W1 1). These indications were evaluated to ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition Acceptance Standards Table IWB-3512-1 and were Code Allowable.

4. Reactor Vessel Bottom Head Circumferential Weld RV-W5 during Remote Ultrasonic Examinations revealed I Indication. This indication was evaluated to ASME Boiler and Pressure Vessel Code, Section Xl, 1989 Edition Acceptance Standards Table IWB-3510-1 and was Code Allowable.

5. A 0.0625" Long Curvilinear Indication (previously recorded in spring 1995) was recorded on the 4" Safety Injection Nozzle To Safe End Butt Weld Sl-W54DM during performance of Liquid Penetrant Examinations. This Curvilinear Indication was Acceptable per ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition 2000 Addenda Table IWB-3514-2.

6. Visual (VT-3) Indications recorded on Component and Piping Supports and Hangers (12 Supports) and Valve Bonnet Bolting (5 Valves) were: (1) Evaluated and Accepted or (2) Repaired, Reexamined and Accepted by KNPP Maintenance, Quality Control, Engineering or Inservice Inspection Personnel, and reviewed by the Authorized Nuclear Inservice Inspector.

Page 2 of 3

7. Visual (VT-2) Indications recorded during System Leakage Pressure Tests (56 Items) were: (1) Evaluated and Accepted or (2) Repaired, Reexamined and Accepted by KNPP Maintenance, Quality Control, Engineering or Inservice Inspection Personnel, and reviewed by the Authorized Nuclear Inservice Inspector.

8.a. General Visual and VT-3 Indication consisting of a slight inward bulge on Plate 74 and Plate 75 was recorded. This slight inward bulge was first recorded in fall 2001.

The slight inward bulge was evaluated by Engineering and Accepted under Kewaunee Nuclear Power Plant Specification TS-1 052, Addenda No.4, Item No.19 Section 10.3 - Shell Tolerance.

8.b. General Visual and VT-3 Indications consisting of previously identified surface rust on Plate 64, Plate 65, Plate 66, Plate 67, and on the Plates for Penetration No.

37EN, Penetration No. 38EN and Penetration No.38ES. This surface rust was removed, the Containment Building Ultrasonically examined to verify wall thickness, repainted, and General Visual and VT-3 examined under Work Order 03-006430.

8.c. General Visual and VT-3 Indication consisting of a scab type indication 3" x 4" located on Plate 158. This scab type indication was Accepted by Engineering as a Preservice Surface Imperfection.

9. General Visual and VT-3 Indications consisting of Caulking pulling away and or cracking between the concrete floor and the Personnel Airlock. These Indications were Accepted by Engineering for continued Service with a recommendation to repair and replace the caulking. Work Order 04-013198 was initiated.

10. VT-3 Indication consisting of a gasket starting to peel away on the Personnel Airlock. The Personnel Airlock Gasket was replaced under Work Order 04-013165, VT-3 reexamined, and Accepted.

11. VT-1 Indication consisting of a missing cotter pin on the swing bolt of the Equipment Door. The missing Cotter Pin was replaced.

Page 3 of 3

ENCLOSURE 2

SUMMARY

OF CLASS I AND CLASS 2 REPAIR/REPLACEMENT ACTIVITIES OF COMPONENTS 1 INCH IN DIAMETER OR SMALLER The following summarizes the repairs and replacements performed following the 2003 Refueling Outage and during the 2004 Refueling outage by grinding, buffing, filing, cutting, or welding on the Class 1 and Class 2 pressure boundary. These repairs and replacements are in addition to those itemized on the enclosed Forms "NIS-2 Owner's Report for Repair/Replacement Activity".

COMPONENT CLASS REFERENCE REPAIR/REPLACEMENT METHOD 1" Replacement I XK-100-10 Welding in Replacement 1" Piping Reactor Vessel Closure Head Reactor Vessel Level Instrumentation Line 1" Replacement 1 XK-100-10 Welding in Replacement 1" Piping Reactor Vessel Closure Head Vent Line 3/4" Valve PR-52 1 XK-1 00-10 Welding in Replacement Valve 3/8" Valve RC-412 I XK-100-44 Welding in Replacement Valve 3/8" Valve RC-422 I XK-100-44 Welding in Replacement Valve Page 1 of 1

ENCLOSURE 3 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS OF CLASS 1, CLASS 2, AND CLASS 3 COMPONENTS FOR THIRD TEN-YEAR INTERVAL 2 pages follow

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO. 1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED -

MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Reactor Vessel RV Combustion CE69202 U11480 21010 Engineering Class 1 Piping Texas Pipe Bending

FORM NIS-1 (Back)

8. Examination Dates: October 5, 2004 to December 4, 2004

9. Inspection Period Identification: 3rd

10. Inspection Interval Identification: 3rd

11. Applicable Edition of Section XI: 1989 Addenda: None

12. Date/Revision of Inspection Plan: June 23, 2003 Revision 3

13. Abstract of Examinations and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. Reference Tab C

14. Abstract of Results of Examinations and Tests. Reference Tab B and Tab F

15. Abstract of Corrective Measures. Reference Tab B and Tab F 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): 4kb Expiration Date: 6Y/1 Date: Poig/ .g- 20 CS'* Signec1: £4J. S/'P1-t, ,eRy:

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 StateorProvinceof AesSs.d and employed by oA4f.rrota 5 nd'er.iCr. of AP, A D 7-. have inspected the components described in this Owner's Report during the period Ctareee6c 7 co q to ijece.... r A e , 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 inspe tion.

A Commissions ,v.d7-,VI ws looet v A/Ia , A

' Inspecbr's Signature National Board, State. Province, and Endotiernents Date: ,f6 ?

F 20 05 I/

ENCLOSURE 4 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS OF REACTOR VESSEL TEN-YEAR EXAMINATIONS FOR THIRD TEN-YEAR INTERVAL 2 pages follow

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF T}IE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO.1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED -

MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Reactor Vessel RV Combustion CE69202 U11480 21010 Engineering Reactor Vessel Westinghouse RCRIUI Internals Class 1 Piping Texas Pipe Bending

FORM NIS-1 (Back)

8. Examination Dates: October 5, 2004 to December 4, 2004

9. Inspection Period Identification: 3rd

10. Inspection Interval Identification: 3rd

11. Applicable Edition of Section XI: 1989 Addenda: None

12. Date/Revision of Inspection Plan: June 23, 2003 Revision 3

13. Abstract of Examinations and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. Reference Tab C

14. Abstract of Results of Examinations and Tests. Reference Tab B and Tab F

15. Abstract of Corrective Measures. Reference Tab B and Tab F Utilization of ASME Boiler and Pressure Vessel Code Section XI Code Case: N-648-1 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): Expiration Date: .,s/4~

Date: As! .P-. 20 ao Signed: w cse&/c By:

Owner CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of J and employed by SrA 4Ddo .#C .rr-oor of f /XrfoFe C r. have inspected the components described in this Owner's Report during the period cc rvi r- S. 2'ai to bee, ,. Y, zo.m , and state thatto the bestofmyknowledgeand belief, the Ownerhas 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.

_____ , #Commissions MV3 77V/ Sis /co7, I N,X5 A n Signature s National Board. State, Province, and Endofsements Date: -6 20 OS, I(

ENCLOSURE 5 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS OF CLASS 1, CLASS 2, AND CLASS 3 COMPONENTS FOR FOURTH TEN-YEAR INTERVAL 11 pages follow

Page 1 of 10 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO. 1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED -

MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Reactor Vessel RV Combustion CE69202 U11480 21010 Engineering Replacement Reactor Mitsubishi Heavy B-VH-N06 U11480 5845 Vessel Closure Head Industries Pressurizer PZR Westinghouse 1151 U11402 68-23 Steam Generator SG- Westinghouse/ 1141/0202 U11400 68-28/151 1A Ansaldo Energia Milano Steam Generator SG- Westinghouse/ 114210201 U11401 68-29/150 1B Ansaldo Energia Milano Excess Letdown Heat Sentry 3996-5E U11407 364 Exchanger AHEL-1A Excess Letdown Heat Sentry 3996-6E U11408 365 Exchanger AHEL-1B Class 1 Piping Texas Pipe Bending Reactor Coolant Westinghouse IA-1-618J871-Pump RCP-1A GO1 Reactor Coolant Westinghouse IB-2-618J871-Pump RCP-1B G02

Page 2 of 10 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO. 1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED -

MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Residual Heat Joseph Oat and 1817-IE U11046 344 Exchanger Sons AHRSI-1A Residual Heat Joseph Oat and 1817-1F U11424 345 Exchanger Sons AHRS2-1B Charging Pump Greer Hydraulics GNI-1848 Pulsation Dampener APD-1A Charging Pump Greer Hydraulics GNI-1846 Pulsation Dampener APD-1B Charging Pump Greer Hydraulics GNI-1847 Pulsation Dampener APD-1C Seal Water Heat Atlas 734 U11404 596 Exchanger AHSW Volume Control Tank Joseph Oat and 1787-1C U11425 376 VCT Sons Regenerative Heat Joseph Oat and 1831-13 U11409 413 Exchanger ARG Sons U11410 414 U11411 415

Page 3 of 10 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF TIlE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO.1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED -

MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Letdown Heat Exchanger AHLD Atlas 1206 U11405 1031 Seal Water Injection Commercial 101072 1172 Filter AFSI-1A Filters Seal Water Injection Commercial 101073 1173 Filter AFSI-1B Filters Reactor Coolant AMF Cuno 121 2616 Filter AFRC Seal Water Filter AMF Cuno 123 2618 AFSW Class 2 Piping Texas Pipe Bending Charging Pump Ajax Iron Works 6578 APCH-1A Charging Pump Ajax Iron Works 6576 APCH-1B Charging Pump Ajax Iron Works 6577 APCH-1C Charging Pump Greer Hydraulics GH1-10234 568 APCH-1A Suction Stabilizer

Page 4 of 10 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF TIlE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO. 1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED -

MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Charging Pump Greer Hydraulics GH1-10235 569 APCH-lB Suction Stablizer Charging Pump Greer Hydraulics GH1-10236 570 APCH-1C Suction Stablizer Residual Heat Byron Jackson 681N0277 Removal Pump APRH1-1A Residual Heat Byron Jackson 681N0276 Removal Pump APRH2-1B Refueling Water General American . C-8297/1969 Storage Tank Transportation Company Diesel Generator ITT Standard 750797-01-2 AHDG-1A Cooling Corp. &

Water Exchangers (2) 750797-01-3 Diesel Generator ITT Standard 750797-01-1 AHDG-1B Cooling Corp. &

Water Exchangers (2) 750797-01-4

Page 5 of 10 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO.1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED -

MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Auxiliary Feedwater Pacific Pump 46573 Pump APFM-1A Motor Driven Auxiliary Feedwater Pacific Pump 46574 Pump APFM-1B Motor Driven Auxiliary Feedwater Pacific Pump 46575 Pump APFT Turbine Driven Reactor Coolant Perfex 723701-1 4014 Pump RCPC-1A Corporation Lube Oil Cooler Reactor Coolant Perfex 723701-2 4015 Pump RCPC-1B Lube Corporation Oil Cooler Class 3 Piping Texas Pipe Bending Containment Fan Joy GF14402 Cooler AHCF-1A Manufacturing and American Air Filter

Page 6 of 10 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO. 1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED -

MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Containment Fan Joy GF14399 Cooler AHCF-1B Manufacturing and American Air Filter Containment Fan Joy GF14401 Cooler AHCF-1C Manufacturing and American Air Filter Containment Fan Joy GF14400 Cooler AHCF-1D Manufacturing and American Air Filter Safety Injection Pump Bingham Pump 290696 APSI-IA Safety Injection Pump Bingham Pump 290697 APSI-IB Safety Injection Pump Flow Serve 21414 Lube Oil Cooler AHSC-1A Safety Injection Pump Borg Warner S-96635 Lube Oil Cooler AHSC-1B

Page 7 of 10 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO. 1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED -

MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Safety Injection Pump Borg Warner 854030:854030 Heat Exchangers (2)

AHSC-1A Safety Injection Pump Borg Warner 854030:854030 Heat Exchangers (2)

AHSC-1B Residual Heat Flowserve 03LEX607100/04 Removal Pump AHRHRP-1A Shaft Seal Heat Exchanger Residual Heat Flowserve 03LEX607100/01 Removal Pump AHRHRP-1B Shaft Seal Heat Exchanger Accumulator Tank Wyatt H-5645-69 U11397 ACC-1A Accumulator Tank Wyatt H-5644-69. U11398 ACC-1B Containment Spray Ingersoll Rand 0670.74 Pump APCS-1A

Page 8 of 10 FORM NIS-1 OWNNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF TIlE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO. 1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED -

MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Containment Spray Ingersoll Rand 0670-75 Pump APCS-1B Containment Spray Hellinow 49486938 Pump APCS-1A Gland Seal Cooler Containment Spray Hellinow 6080694 Pump APCS-1B Gland Seal Cooler Component Cooling Ingersoll Dresser 0600009 Pump APCC-1A Pump Flow Serv.

Component Cooling Ingersoll Dresser 0600010 Pump APCC-IB Pump Flow Serv.

Service Water Pump Worthington VTP27737 APSW-IA1 Pump Service Water Pump Worthington 75 TU-1719-1 APSW-1A2 Pump Service Water Pump Worthington VTP27736 APSW-1B1 Pump Service Water Pump Worthington VTP27738 APSW-1B2 Pump

Page 9 of 10 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO. 1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED -

MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Spent Fuel Pool Heat Struther Wells 1-68-06-1519 U11445 ---

Exchanger AHSF Main Steam Moisture Wright Austin 6230 X.R. 6008 Separator Spent Fuel Pool Pump Gould Pumps 786A519.1 APSF-IA Spent Fuel Pool Pump Gould Pumps 786A519.2 APSF-1B Service Water Pump S.P. Kinney 2278 Strainer ASSW-1A1 Engineers Service Water Pump S.P. Kinney 2279 Strainer ASSW-1A2 Engineers Service Water Pump S.P. Kinney 2280 Strainer ASSW-1B1 Engineers Service Water Pump S.P. Kinney 2281 Strainer ASSW-1B2 Engineers Component Cooling Engineers and S-26125 U39499 3269 Heat Exchanger Fabricators Co.

AHCC1-lA

Page 10 of 10 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO. 1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED-MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Component Cooling Engineers and S-26126 U39500 3270 Heat Exchanger Fabricators AHCC2-1B Component Cooling Sharpsville Steel 714 U11421 714 Surge Tank ATCS Control Room Air Trane Company KlH202002 Conditioning Unit 1A Coil Control Room Air Trane Company K1H202003 Conditioning Unit 1B Coil Control Room Air ITT Bell and Gossett Conditioning Expansion Tank 1A Control Room Air ITT Bell and Gossett 116013 Conditioning Expansion Tank 1B

FORM NIS-1 (Back)

8. Examination Dates: July 27, 2004 to December 4, 2004

9. Inspection Period Identification: 1st

10. Inspection Interval Identification: 4th

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

12. Date/Revision of Inspection Plan: June 16,2004 Original

13. Abstract of Examinations and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. Reference Tab C

14. Abstract of Results of Examinations and Tests. Reference Tab B and Tab F

15. Abstract of Corrective Measures. Reference Tab B and Tab F Utilization of ASME Boiler and Pressure Vessel Code Section XI Code Case: N-490, N-498-4 And N-566-1.

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): /

Expiration Date: .

Date: ,,1,e4l f 20 cs- Signed: 6sc^,o A AL&By:

Owner CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State orProvince of 4hse-vgsAt, and employed by #// aeo Sree4m BLter- #7dcr of

/,eAr.r a6 Cr. have inspected the components described in this Owner's Report during the period DRAW 77.7Zoo to fdoei. qr gHoyt , 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.

with__h______ Commissions IVS 7VI/ Ak/ O0 2 I' Z. . X 5. X4 X Inector's Signature National Board, State, Province, and Endorsernents Date: H o,, 9 20 o-*

I

ENCLOSURE 6 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS OF REACTOR VESSEL EXAMINATIONS FOR FOURTH TEN-YEAR INTERVAL 2 pages follow

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF TIlE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO. 1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED -

MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Reactor Vessel RV Combustion CE69202 U11480 21010 Engineering Class 1 Piping Texas Pipe Bending

FORM NIS-1 (Back)

8. Examination Dates: July 27, 2004 to December 4, 2004

9. Inspection Period Identification: 1st

10. Inspection Interval Identification: 4th

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

12. Date/Revision of Inspection Plan: June 16, 2004 Original

13. Abstract of Examinations and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. Reference Tab C

14. Abstract of Results of Examinations and Tests. Reference Tab B and Tab F

15. Abstract of Corrective Measures. Reference Tab B and Tab F Utilization of ASME Boiler and Pressure Vessel Code Section XI Code Case: N-490, N-498-4 And N-566-1.

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): A/// Expiration Date: __k_ _

Date: n4&^v' &- 20 Signed: *1,kw' 5;jss;f'v6 By: 2e-,OJ--

Owner CERTIFICATE OF INSERVICE INSPECTION L,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the StateorProvinceof /JC0) JA andemployedby 1ff 14.' er. e.8c- of

AArrfA*, Cr. have inspected the components described in this Owner's Report during the period to we? . tO--,?/ ,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.

____ Commissions Ac3 '77,/ w4s lob-Y' t.A'.4.s.A I fpctor's Signature National Board, State. Province, and Endorsements Date: j -'. 9 20 05'

/

ENCLOSURE 7 FORM NIS-1 OWNER'S REPORT FOR PRESERVICE INSPECTIONS OF REPLACEMENT REACTOR VESSEL CLOSURE HEAD 2 pages follow

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO. 1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED -

MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Replacement Reactor Mitsubishi Heavy B-VH-N06 U11480 5845 Vessel Closure Head Industries

FORM NIS-1 (Back)

8. Examination Dates: May 13, 2004 to May 21, 2004

9. Inspection Period Identification: 1st

10. Inspection Interval Identification: 4th

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

12. Date/Revision of Inspection Plan: June 16,2004 Original

13. Abstract of Examinations and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. Reference Tab C

14. Abstract of Results of Examinations and Tests. Reference Tab B and Tab F

15. Abstract of Corrective Measures. Reference Tab B and Tab F 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): tj I Expiration Date: - -

Date: T?& 1s 3So 20 Signed: uBy: W-a Ad; iS_

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 StateorProvinceof W,.xeo and employed by irxeoAej B PA$at,r of

//irrdia C

have inspected the components described in this Owner's Report during the period

",wy /s3, Zoe# to ,qyr 2/. & oe' ,and state that to the best of myknowledge 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 inpection.

_ Commissions /Va f ezis /0e2y" r,4 ers, A Insp~tOr's Signature National Board, State. Pfovince. and Endorsements Date: t 2005

ENCLOSURE 8 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS FOR CLASS MC COMPONENTS 2 pages follow

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. OWNER - WISCONSIN PUBLIC SERVICE CORPORATION, 700 NORTH ADAMS, P.O. BOX 19001, GREEN BAY, WISCONSIN 54307- 9001

2. PLANT - KEWAUNEE, N490 HIGHWAY 42, KEWAUNEE, WISCONSIN 54216-9511

3. PLANT UNIT - NO. 1

4. OWNER CERTIFICATE OF AUTHORIZATION - N/A

5. COMMERCIAL SERVICE DATE - JUNE 16,1974

6. NATIONAL BOARD NUMBER FOR UNIT - N/A

7. COMPONENTS INSPECTED -

MANUFACTURER COMPONENT OR MANUFACTURER OR INSTALLER STATE OR NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. PROVINCE NO. BOARD NO.

Reactor Building Chicago Bridge C4454 U11423 --

Containment Vessel and Iron Company Personnel Airlock Chicago Bridge C4454 U11423 --

and Iron Company

FORM NIS-1 (Back)

8. Examination Dates: October 9, 2004 to December 4, 2004

9. Inspection Period Identification: 3rd

10. Inspection Interval Identification: 1st

11. Applicable Edition of Section XI: 1992 Addenda: 1992

12. Date/Revision of Inspection Plan: July 21, 2003 Revision 2

13. Abstract of Examinations and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. Reference Tab C

14. Abstract of Results of Examinations and Tests. Reference Tab B and Tab F

15. Abstract of Corrective Measures. Reference Tab B and Tab F Utilization of ASME Boiler and Pressure Vessel Code Section XI Code Case N-604.

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): A// Expiration Date: __/_ _

Date: r6?4wwv g- 20_cs Signed: ef'iBy: _ IIsA Owner CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of a),SC4.J5 /' and employed by 6 j/1'G -a.ftr.

i' of WAr*4k) CYr. have inspected the components described in this Owner's Report during the period O6feoXr 9, iotf to ae.-.,a- . wo ' , 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 inspect!

_____ 6 - Commissions ," -V./ 4h'5 {ola Z-V r Ag s. _4 Ingfector's Signature National Board. State. Province.and Endorsements Date: r 9 20 OS

/

ENCLOSURE 9 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITIES (41 TOTAL) 82 pages follow

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

1. Owner Wisconsin Public Service Corporation Date 12/17/2004 700 North Adams P.O.Box 19001 Green Say. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 96-210660

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 34 Class 2 RESIDUAL HEAT REMOVAL Expiration Date NA

5. (a) Applicable Construction Code B31.1-1967 (c) Applicable Section Xl Code Case NA (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped RHR-9A CRANE VALVE CO. 16 NA ACO1O-009 1972 CORRECTED N

7. Description of Work CORRECT BODY TO BONNET LEAK BY SEAL WELDING BODY TO BONNET ON CLASS 2 RESIDUAL HEAT REMOVAL SYSTEM 8" VALVE RHR-9A.

8. Tests conducted Hydrostatic 1 Pneumatic [1 Nominal Operating Pressure [I Exempt [

Other LJ Pressure 472 psi Test Temp. 231 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturers Data Reports to be Attached

/

i

NIS-2 (Back)

Sheet 2 of 2 Date: 12/17/2004 Name of Component: RHR-9A Work Order Number 96-210660 CERTIFICATE OF COMPLIANCE I certify that the statements made In the report are correct and that this CORRECTED conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed I at4 fr Zm4fC. 2u 4 Date 3,20 O5 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In this Owner's Report during the periodA!a D 3 to N1,0@0and 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 the ASME Code, Section Xl.

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.

Jet_ _ Commissions NB7741, 1,N,IS,A WIS 100024 Inspector's Signature National Board, State, Province, and Endorsements Date , co' ,20 OSau j 7 a

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

1. Owner Wisconsin Public Service Corporation Date 4/20/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2 Unit No, 1

2. Plant Kewaunee Nuclear Power Plant N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 02-017647

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 06 Class 2 MAIN STEAM AND STEAM DUMP Expiration Date NA

5. (a) Applicable Construction Code B31.1-1967 Code Case NA (b)Applicable Edition of Section Xi Utilized for Repairs or Replacements 1989

6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Name of Name of Manufacturer National Other Year Replaced, or Code Component Manuracturer Serial No. Board No. ID Built Replacement Stamped SD-3A FISHER CONTROLS CO. 4950741 NA SD022-001 1969 REPLACED N

7. Description of Work REPLACED VALVE SEAT. VALVE STEM ASSEMBLY. PACKING AND GASKETS FOR CLASS 2 MAIN AUXILIARY STEAM AND STEAM DUMP SYSTEM 6 VALVE SD-3A.

8. Tests conducted Hydrostatic 17J Pneumatic E1 Nominal Operating Pressure El Exempt LI Other n Pressure 780 psi Test Temp. 518 deg. F

9. Remarks NOT APPLICABLE Applicable Manufacturers Data Reports to be Attached

)

NIS-2 (Back)

Sheet 2 of 2 Date: 4/2012004 Name of Component: SD-3A Work Order Number: 02-017647 Certificate of Compliance We Certify that the statements made In the report are correct and this REPLACED conforms to the rules of the ASME Code Section Xi. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 7 'Po o-a C. Date ,200 5 Owner or Owners Designee, Title Certificate of INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In the Owners Report during the period ?, C 3 to 8 , oand state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owners Report In accordance with the requirements of the 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 Owners 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 5 4 PAL.. Commissions NB7741. I, N, IS, A WIS 100024 Inspectors Signature National Board, State, Province, and Endorsements Date.} l I20 03X

) V a

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

1. Owner Wisconsin Public Service Corporation Date 12/20/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet I of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee, WI 54216-9511 Work Order 01-007185

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 23 Class 2 CONTAINMENT SPRAY Expiration Date NA

5. (a) Applicable Construction Code B16.5-1967 (c) Applicable Section Xl Code Case NA (b)Applicable Edition of Section Xi Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Mlanufacturer Serial No. Board No. ID Built Installed Stamped RHR-400A CRANE COMPANY NF NA ICS006-005 1970 CORRECTED N

7. Description of Work CORRECTED CLASS 2 CONTAINMENT SPRAY SYSTEM 6 VALVE RHR-400A DISC TO SEAT GALLING BY REPLACING DISC.

8. Tests conducted Hydrostatic Pneumatic Nominal Operating Pressure Exempt L Other Li Pressure 170 psi Test Temp. 85 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturers Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 12/20/2004 Name of Component: RHR-400A Work Order Number: 014007185 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this CORRECTED cmonforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 7 . flA4bT/ , )°--ite , Date 3 20 °5 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I. the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In this Owner's Report during the periodmL& 7.0 3 tokd ID, D5and 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 the ASME Code. Section Xl.

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 u_ _ Commissions NB7741, 1, N, IS, A WIS 100024 Inspectors Signature National Board, State, Province, and Endorsements Date II ,20 orS

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

1. Owner Wisconsin Public Service Corporation Date 11/24/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-002757

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street, Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 23 Class 2 CONTAINMENT SPRAY Expiration Date NA

5. (a) Applicable Construction Code B16.5-1967 (c) Applicable Section XI Code Case NA (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Nameof Nameof Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped ICS-7A CRANE VALVE COMPANY NF NA ICS007-001 1970 INSTALLED N

7. Description of Work REPLACE CLASS 2 INTERNAL CONTAINMENT SPRAY SYSTEM 6 VALVE ICS-7A AND 3- 6 BUTT WELDS DUE TO SEAT LEAKAGE.

8. Tests conducted Hydrostatic El Pneumatic D Nominal Operating Pressure p3 Exempt L Other Pressure 270 psi Test Temp. 80 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturers Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 1112412004 Name of Component: ICS-7A Work Order Number: 03-002757 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this INSTALLED conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed C GoD ftA4, Date 6,q3y -20 , ° 5-Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described in this Owner's Report during the period 2 0 3 tog Cowhand 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 the 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 NB7741, 1,N. IS, A WIS 100024 lnspeoes Signature National Board, State, Province, and Endorsements Date 9_,,, L ,20 D So Dat .2 0

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

1. Owner Wisconsin Public Service Corporation Date 12/17/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet I of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-002879

3. Work Performed By Nuclear Management Comoany. LLC Type Code Sym. Stamp NA 700 First Street, Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 35 Class 2 CHEMICAL AND VOLUME CONTROL Expiration Date NA

5. (a) Applicable Construction Code B31.1-1967 (c) Applicable Section XI Code Case NA (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped CVC-200C VELAN VALVE CORP. NF NA CS035-001 1968 CORRECTED N

7. Description of Work CORRECT CLASS 2 CHEMICAL AND VOLUME CONTROL SYSTEM 3" VALVE CVC-200C DUE TO DIFFICULTY IN OPERATING BY REPLACING VALVE STEM. VALVE STEM BUSHING AND PACKING.

8. Tests conducted Hydrostatic Pneumatic [1 Nominal Operating Pressure F3 Exempt s Other Pressure 2235 psi Test Temp. 112 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturers Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 12117/2004 Name of Component: CVC-200C Work Order Number. 03-002879 CERTIFICATE OF COMPLIANCE I certify that the statements made In the report are correct and that this CORRECTED conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 7°=! Anow Date UL3 ,20 .2 05-Q5 If I 7 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In this Owneres Report during the period 0 to 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 the 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 Owners 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.

an, 'lA ., Commissions NB7741, I, N, IS, A WIS 100024 National Board, State, Province, and Endorsements Inspect s Signature Date ut- II .20 CSo Da-e 2

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

1. Owner Wisconsin Public Service Corporation Date 9/912003 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet I of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-005164

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 31 Class 3 COMPONENT COOLING Expiration Date NA

5. (a) Applicable Construction Code B31.1*1967 Code Case N-416-2 (b)Applicable Edition of Section XI Utilized for Repairs or Replacements 1989

6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Name of Name of Manufacturer National Other Year Replaced, or Code Component Manufacturer Serial No. Board No. ID Built Replacement Stamped APCC-1B NUCLEAR MANAGEMENT NA NA NA 2003 REPLACEMENT N RECIRC. LINE COMPANY

7. Description of Work INSTALL CLASS 3 COMPONENT COOLING WATER SYSTEM RECIRCULATION LINE TO COMPONENT COOLING PUMP lB. INCLUDES 3" AND 3/4" PIPING. 3" VALVE CC-22A. 3" VALVE CC-23B AND 3/4" VALVE CC-11150.

8. Tests conducted Hydrostatic [] Pneumatic g Nominal Operating Pressure p Exempt [E Other [] Pressure 143 psi Test Temp. 91.4 deg. F

9. Remarks UTILIZATION OF ASME BOILER AND PRESSURE VESSEL CODE SECTION XI: CODE CASE N-416-2. NOMINAL OPERATING PRESSURE AND TEMPERATURES: SUCTION: 23 PSIG: TEMPERATURE: 103 DEGREES F: DISCHARGE: 143 PSIG: TEMPERATURE: 91.4 DGREES F.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 919/2003 Name of Component: APOC-1B RECIRC. LINE Work Order Number: 03-005164 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 NA Certificate of Authorization No. NA Expiration Date NA Signed 4 Ifi I*AO Date 1. 3 - 20 05 V

Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described In the Owners Report during the periodF7>-3 toga i0,I0S 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 the 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_ _Commissions NB7741, I, N, IS, A WIS 100024 Inspec or's Signature National Board, State. Province, and Endorsements DateA-~G II ,20 t) 5 V ,. 1-

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

1. Owner Wisconsin Public Service Corporation Date 9/9/2003 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2 Unit No. 1

2. Plant Kewaunee Nuclear Power Plant N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-005165

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 31 Class 3 COMPONENT COOLING Expiration Date NA

5. (a)Applicable Construction Code B31.1-1967 Code Case N-416-2 (b) Applicable Edition of Section Xi Utilized for Repairs or Replacements 1989

6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Name of Name of Manufacturer National Other Year Replaced, or Code Component Manufacturer Serial No. Board No. ID Built Replacement Stamped APCC-1A NUCLEAR MANAGEMENT NA NA NA 2003 REPLACEMENT N RECIRC. LINE COMPANY

7. Description of Work INSTALL CLASS 3 COMPONENT COOLING WATER SYSTEM RECIRCULATION LINE TO COMPONENT COOLING WATER PUMP 1A. INCLUDES X AND 3/4" PIPING. 3" VALVE CC-21A . 3VALVE CC-24B AND 3/4 VALVE CC-11149.

8. Tests conducted Hydrostatic n Pneumatic 2 Nominal Operating Pressure El Exempt n Other Eli Pressure 143 Psi I Test Temp. 91 deg. F I

9. Remarks UTILIZATION OF ASME BOILER AND PRSSURE VESSEL CODE SECTION XI: CODE CASE N-416-2. NOMINAL OPERATING PRESSURE AND TEMPERATURES: SUCTION: 23 PSIG: TEMPERATURE: 103 DEGREES F: DISCHARGE: 143 PSIG:

TEMPERATURE: 91 DEGREES F.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 9/9/2003 Name of Component: APCC-1A RECIRC. LINE Work Order Number: 03-005165 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 Xl. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed M A of Ic fDt V

Date L)Mma3 ,20 5-Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In the Owner's Report during the period % 1,? i 3 to 9jrIS Wand state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the 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.

AL 2 # - Commissions NB7741, I, N,IS,A WIS 100024 V V National Board, State, Province, and Endorsements Inspectors Signature Date /I .20 OR1

,20

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

1. Ovner Wisconsin Public Service Corporation Date 11/27/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2 Unit No. 1

2. Plant Kewaunee Nuclear Power Plant N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-005192

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 23 Class 2 CONTAINMENT SPRAY Expiration Date NA

5. (a) Applicable Construction Code B16.5-1967 (c) Applicable Section XI Code Case NA (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped ICS-201 FISHER CONTROLS 4950737 NA ICS013-002 1972 CORRECTED N INTERNATIONAL

7. Description of Work CORRECT CLASS 2 CONTAINMENT SPRAY SYSTEM 2 VALVE ICS-201 SEAT LEAKAGE BY LAPPING VALVE.

8. Tests conducted Hydrostatic 1I Pneumatic 1 INominal 01)erating Pressure E3 Exempt E Other E1I Pressure 270 psi Test Temp. 80 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

'N NIS-2 (Back)

Sheet 2 of 2 Date: 11/27/2004 Name of Component: ICS-201 Work Order Number. 03-005192 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this CORRECTED conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed &O6wWtD Date q 3 ,20 Qi Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In this Owner's Report during the period '7,0 to 9 C 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 the ASME Code, Section Xl.

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 NB7741, 1,N. IS, A WIS 100024 Inspectors Signature National Board, State, Province, and Endorsements Da I 20 °S V ai

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

1. Owner Wisconsin Public Service Corporation Date 12/20/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-005299

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA 4.1dentification of System 34 Class 1 RESIDUAL HEAT REMOVAL Expiration Date NA

5. (a) Applicable Construction Code B31.1-1967 (c) Applicable Section Xl Code Case NA (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer SerIal No. Board No. ID Built Installed Stamped RHR-2B VELAN VALVE NF NA AC104.004 1972 CORRECTED N CORPORATION

7. Description of Work CORRECT BY SEAL WELDING BODY TO BONNET CLASS 1 RESIDUAL HEAT REMOVAL SYSTEM 8" VALVE RHR-2B DUE TO EVIDENCE OF LEAKAGE.

8. Tests conducted Hydrostatic n Pneumatic L1 I Nominal Op)erating Pressure M Exempt U Other LII Pressure 472 psi Test Temp. 244 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached II

NIS-2 (Back)

Sheet 2 of 2 Date: 12/2012004 Name of Component: RHR-2B Work Order Number: 03.005299 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this CORRECTED conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed iiwwd4 6'. Wt J o Date 3 ,20 C5 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described Inthis Owner's Report during the period.A7Z0P3 togs Ic.Gand state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described inthis Owner's Report Inaccordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described Inthis Owners 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 NB7741, I, N. IS, A WIS 100024 National Board, State, Province, and Endorsements Dat e1 1 i.20a , v _

e d' '

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

1. Owner Wisconsin Public Service Corporation Date 11118/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-005301

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 34 Class 1 RESIDUAL HEAT REMOVAL Expiration Date NA

5. (a) Applicable Construction Code B31.1-1967 (c) Applicable Section Xl Code Case NA (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component M~Ianufacturer Serial No. Board No. ID Built Installed Stamped RHR-1A VELAN VALVE NF NA AC104-001 1972 CORRECTED N CORPORATION

7. Description of Work SEAL WELD BODY TO BONNET ON CLASS 1 RESIDUAL HEAT REMOVAL SYSTEM 8" VALVE RHR-1A AND REPLACE 16 VALVE BONNET STUDS AND 16 VALVE BONNET NUTS DUE TO EVIDENCE OF LEAKAGE.

8. Tests conducted Hydrostatic [j Pneumatic j1 Nominal Operating Pressure E3 Exempt [

Other LI Pressure 150 psi Test Temp. 95 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturers Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 11/18/2004 Name of Component: RHR-1 A Work Order Number 03-005301 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this CORRECTED conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed W4 0 C. tvo, ?%}1}°,, &I1 Date . 3 ,20 05

'I Owner or Owner's Designee, Tie 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 Inspection and Insurance Company of CT have inspected the components described In this Owner's Report during the perioddZ7 0 3 to( c 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 the 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 ,_ _ Commissions NB7741, I, N, IS, A WIS 100024 Inspecfrs Signature National Board, State, Province, and Endorsements Date A t .20 0S C./ j

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

1. Owner Wisconsin Public Service Corcoration Date 12/20/2004 700 North Adams P.O.Box 19001 Green Bay, WI 54307-9001 Sheet I of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-005420

3. Work Performed By Nuclear Management Comrany. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 35 Class 2 CHEMICAL AND VOLUME CONTROL Expiration Date NA

5. (a) Applicable Construction Code B31.1-1967 (c) Applicable Section Xl Code Case NA (b)Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Mlanufacturer Serial No. Board No. ID Built Installed Stamped 1

CVC-3 GRINNELL FIRE NF NA CS036-001 1973 INSTALLED N PROTECTION SYSTEMS

7. Description of Work REPLACE BONNET ASSEMBLY AND DIAPHRAGM ON CLASS 2 CHEMICAL AND VOLUME CONTROL SYSTEM 4 VALVE CVC-3.

8. Tests conducted Hydrostatic _LI Pneumatic [_J Nominal Operating Pressure [E3 Exempt []

Other [l Pressure 25 psi Test Temp. 112 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached I

NIS-2 (Back)

Sheet 2 of 2 Date: 12/20/2004 Name of Component: CVC-3 Work Order Number: 034005420 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this INSTALLED conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 7 /vC~f42IiOtwm'iDate .20 05 Owner or Owner's Designee, Tite 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 Inspection and Insurance Company of CT have inspected the components described in this Owner's Report during the periodA A7 0 to +/-I a)°.

vO'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 the ASME Code, Section Xl.

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.

AL' Commissions NB7741, 1,N. IS, A WIS 100024 Inspegor's Signature National Board, State, Province, and Endorsements ta .20 'S' U a

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

1. Owner Wisconsin Public Service Cormoration Date 11127/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-005446

3. Work Performed By Nuclear Management ComDany. LLC Type Code Sym. Stamp NA 700 First Street, Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 23 Class 2 CONTAINMENT SPRAY Expiration Date NA

5. (a) Applicable Construction Code ASME SECTION III (c) Applicable Section XI Code Case NA (b) Applicable Edition of Section Xi Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ED Built Installed Stamped ICS-3A TRW MISSION D3245 NA ICS003-001 2004 INSTALLED N MANUFACTURING

7. Description of Work INSTALL NEW CLASS 2 CONTAINMENT SPRAY SYSTEM 8" VALVE ICS-3A DUE TO SEAT LEAKAGE.

8. Tests conducted Hydrostatic [] Pneumatic [1 Nominal Operating Pressure El Exempt []

Other [ Pressure 270 psi Test Temp. 80 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

)

NIS-2 (Back)

Sheet 2 of 2 Date: 11/27/2004 Name of Component: ICS-3A Work Order Number: 03-005446 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this INSTALLED conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed l JAl epAX) PA ril4"&Wnw. Date 6dhM3 ,20 oi-Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I. the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In this Owner's Report during the period% til O3 to( 1°#5,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 the ASME Code, Section Xl.

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.

L4 v X Commissions NB7741, I. N. IS, A WIS 100024 Inspectors gnature National Board, State, Province, and Endorsements Date L 1/ .20

,20 C S'

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

1. Owner Wisconsin Public Service Corporation Date 10/17/2003 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-006434

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 31 Class 3 COMPONENT COOLING Expiration Date NA

5. (a) Applicable Construction Code B31.1-1967 Code Case N-416-2 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989

6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Name of Name of Manufacturer National Other Year Replaced, or Code Component Manufacturer Serial No. Board No. ID Built Replacement Stamped APCC-1A NUCLEAR MANAGEMENT NA NA NA 2003 REPLACEMENT N RECIRC. LINE COMPANY

7. Description of Work INSTALL CLASS 3 COMPONENT COOLING WATER SYSTEM RECIRCULATION LINE TO COMPONENT COOLING WATER PUMP 1A. INCLUDES 3".1 AND 3/4 PIPING. VALVES AND FLANGES.

8. Tests conducted Hydrostatic [1 Pneumatic 1I Nominal Operating Pressure =V Exempt U Other U1 Pressure 143 psi Test Temp. 88 deg. F

9. Remarks UTILIZATION OF ASME BOILER AND PRESSURE VESSEL CODE SECTION XI: CODE CASE N-416-2.

Applicable Manufacturers Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 10/17/2003 Name of Component: APCC-1A RECIRC. LINE Work Order Number: 03-006434 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 Xl. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 7°AgC6e i >e4&go DP2 Date 3pN 4 , - 20 05-Owner or Owner's Designee, Title V.

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 Inspection and Insurance Company of CT have Inspected the components described In the Owner's Report during the perio 2o . to( 1DOS 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 the ASME Code, Section Xl.

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 N87741, I, N, IS, A WIS 100024 InspectoUSignature National Board, State, Province, and Endorsements Date A /I .20 L5 .

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

1. Owner Wisconsin Public Service Corporation Date 10/17/2003 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2 Unit No. 1

2. Plant Kewaunee Nuclear Power Plant N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-006434

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 31 Class 3 COMPONENT COOLING Expiration Date NA

5. (a) Applicable Construction Code B31.1-1967 Code Case N-416-2 (b) Applicable Edition of Section Xi Utilized for Repairs or Replacements 1989

6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Name of Name of Manufacturer National Other Year Replaced, or Code Component Mlanuracturer Serial No. Board No. ID Built Replacement Stamped APCC-1B NUCLEAR MANAGEMENT NA NA NA 2003 REPLACEMENT N RECIRC. LINE COMPANY

7. Description of Work INSTALL CLASS 3 COMPONENT COOLING WATER SYSTEM RECIRCULATION LINE TO COMPONENT COOLING WATER PUMP 18. INCLUDES 3". 1" AND 3/4" PIPING. VALVES AND FLANGES.

8. Tests conducted Hydrostatic [] Pneumatic L Nominal Operating Pressure p3 Exempt El Other 1I Pressure 142 ps I Test Temp. 89 deg. F

9. Remarks UTILIZATION OF ASME BOILER AND PRESSURE VESSEL CODE SECTION XI: CODE CASE N-416-2.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 10/17/2003 Name of Component: APCC-1B RECIRC. LINE Work Order Number: 03-006434 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 NA Certificate of Authorization No. NA Expiration Date NA Signed 7 L} Date 20 QL.

.1m Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described inthe Owner's Report during the period 7 tOl3 Ito 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 Inaccordance with the requirements of the ASME Code, Section Xl.

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.

A G oCommissions N87741. I, N, IS,A WIS 100024 Inspecto Signature National Board, State, Province, and Endorsements Date_/ 1 .20 0*Z<

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

1. Owner Wisconsin Public Service Corporation Date 3/29/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 21of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-009898

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 35 Class 2 CHEMICAL AND VOLUME CONTROL Expiration Date NA

5. (a) Applicable Construction Code SEC.lI1 CL2-1980 ADD Code Case NA (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989

6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Name of Name of Manufacturer National Other Year Replaced, or Code Component Manufacturer Serial No. Board No. ID Built Replacement Stamped APSS-1A GREER HYDRAULICS GH1-1 0234 568 162-935 1981 REPAIRED Y

7. Description of Work REBUILD CLASS 2 CHEMICAL AND VOLUME CONTROL SYSTEM CHARGING PUMP lA SUCTION STABILIZER CHARGE VALVE ASSEMBLY.

8. Tests conducted Hydrostatic 2 Pneumatic D Nominal Operating Pressure [E Exempt g Other [] Pressure 24 psi Test Temp. 113 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 3/2912004 Name of Component: APSS-1A Work Order Number: 03-009898 Certificate of Compliance We Certify that the statements made In the report are correct and this REPAIRED conforms to the rules of the ASME Code Section XI. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 7A 4vC 4 6Wiif4A Date ,20 Q5 Owner or Owner's Designee. Title Certificate of INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described in the Owners Report during the period917&0,P3 toll 1°, 5,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 the ASME Code, Section Xl.

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 NB7741, I, N, IS, A WIS 100024 Inspectorswignature National Board, State, Province, and Endorsements Date 1,2 D

£7

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

1. Owner Wisconsin Public Service Comoration Date 10/3112004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet I of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-011274

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 36 Class 1 REACTOR COOLANT Expiration Date NA

5. (a)Applicable Construction Code B31.1.1967 (c) Applicable Section Xl Code Case NA (b)Applicable Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Nameof Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ]ID Built Installed Stamped RTD-H2 ITT GRINNELL VALVE NA NA NA 1967 CORRECTED N COMPANY

7. Description of Work CORRECT BY ADJUSTING HYDRAULIC SNUBBER LENGTH ON CLASS 1 REACTOR COOLANT SYSTEM 2' HYDRAULIC SNUBBER RTD-H2.

8. Tests conducted Hydrostatic El Pneumatic [1 Nominal Operating Pressure J Exempt ELI Other Pressure psi Test Temp. deg. F

9. Remarks NOT APLICABLE.

Applicable Manufacturers Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 10131/2004 Name of Component: RTD-H2 Work Order Number 03-011274 CERTIFICATE OF COMPLIANCE I certify that the statements made In the report are correct and that this CORRECTED conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed J 11Mv 0UnVA Date a .20 05 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described In this Owners Report during the period" I 03 tlo 11D0o* 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 the 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 Owners 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.

JL GCommissions NB7741, I, N, IS,A WIS 100024 Inspect rs Signature National Board, State, Province, and Endorsements

) Date 9 7.20 0o5

)

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

1. Owner Wisconsin Public Service Corporation Date 12/20/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-011276

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 31 Class 3 COMPONENT COOLING Expiration Date NA

5. (a) Applicable Construction Code B16.34-1977 (c) Applicable Section XI Code Case N-416-2 (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped SW-1400-1 ROCKWELL CD310 NA AC123-002 1986 INSTALLED N INTERNATIONAL

7. Description of Work REPLACE CLASS 3 COMPONENT COOLING WATER SYSTEM 2' VALVE SW-1400-1 AND 2- PIPING SOCKET WELDS (t13 TOTAL).

8. Tests conducted Hydrostatic LI Pneumatic D Nominal Operating Pressure Exemptxe li Other LI Pressure 102 psi Test Temp. 52 deg. F

9. Remarks UTILIZATION OF ASME BOILER AND PRESSURE VESSEL CODE SECTION XI: CODE CASE N-416-2.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 12/20/2004 Name of Component: SW-1 400-1 Work Order Number: 03-011276 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this INSTALLED conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed C. &U J Date .320 05 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described in this Owners Report during the periodN&i2 3 to`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 the 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..-...Commissions NB7741. 1,N, IS, A WIS 100024 Inspecto Signature National Board, State, Province, and Endorsements Date /I .20 0 a.

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

1. Owner Wisconsin Public Service Corooration Date 12/20/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-011276

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 31 Class 3 COMPONENT COOLING Expiration Date NA

5. (a) Applicable Construction Code B16.34-1977 (c) Applicable Section Xl Code Case N-416-2 (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped swi 400-5 ROCKWELL CD317 NA AC123-001 1986 INSTALLED N INTERNATIONAL

7. Description of Work REPLACE CLASS 3 COMPONENT COOLING WATER SYSTEM 2' VALVE SW-1400-5 AND 2' PIPING SOCKET WELDS (2 TOTAL).

8. Tests conducted Hydrostatic Li Pneumatic Nominal Operating Pressure p1 Exempt El Other 11 Pressure 102 psi Test Temp. 52 deg. F

9. Remarks UTILIZATION OF ASME BOILER AND PRESSURE VESSEL CODE SECTION XI CODE CASE N-416-2.

Applicable Manufacturers Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 12/20/2004 Name of Component: SW-1400-5 Work Order Number 03-011276 CERTIFICATE OF COMPLIANCE I certify that the statements made In the report are correct and that this INSTALLED conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed / e14Jg l LI bC~ i70' &WflPLJ Date , 20 05 Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In this Owner's Report during the periodbk7 03 to~s 10r05and 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 the 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 NB7741, I, N. IS, A WIS 100024 Inspectoys Signature National Board, State, Province, and Endorsements Date II ,20 O So' as U

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

1. Owner Wisconsin Public Service Corporation Date 12/3/2004 700 North Adams P.O. Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2 Unit No. I

2. Plant Kewaunee Nuclear Power Plant N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-012220

3. Work Performed By Nuclear Manacement Comranv. LLC Type Code Sym. Stamp NA 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 05A Class 2 FEEDWATER Expiration Date NA

5. (a) Applicable Construction Code B31.1-1967 (c) Applicable Section Xi Code Case NA (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped FW-13A ATWOOD & MORRILL CO., _ NF NA F008-001 1972 CORRECTED N INC.

7. Description of Work OPEN FOR INSPECTION CLASS 2 FEEDWATER SYSTEM 16" VALVE FW-13A INCLUDING REPLACING SEAL RING. COVER. RING. 4 BONNET STUDS AND 4 BONNET NUTS.

8. Tests conducted Hydrostatic [] Pneumatic n INominal Operating Pressure pa Exempt Other E] Pressure 1005 psi Test Temp. 545 deg.F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached i

NIS-2 (Back)

Sheet 2 of 2 Date: 12/3/2004 Name of Component: FW-13A Work Order Number: 03-012220 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this CORRECTED conforms to the requirements of the ASME Code,Section XI.

Type Code Symboi Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 7L4C6. Go fOr go Date t4 3 20 05 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described in this Owner's Report during the period>?Z0 3. togsL +/-m1c, A`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 the 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.

FLEW,__ _ __ Commissions NB7741. I, N. IS, A WIS 100024 a lnspectokSignature National Board, State, Province, and Endorsements Date , Il ,20 V<S (a

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

1. Owner Wisconsin Public Service Corporation Date 12/20/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet I of 2 Unit No. I

2. Plant Kewaunee Nuclear Power Plant N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-012432

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 34 Class 2 RESIDUAL HEAT REMOVAL Expiration Date NA

5. (a) Applicable Construction Code NA (c) Applicable Section Xi Code Case NA (b)Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped APRH2-1 B BRYON JACKSON 681 N0276 NA 00128 1970 CORRECTED N

7. Description of Work OVERHAUL CLASS 2 RESIDUAL HEAT REMOVAL SYSTEM RESIDUAL HEAT REMOVAL PUMP lB.

8. Tests conducted Hydrostatic n Pneumatic E1 INominal 01)erating Pressure 3 Exempt [

Other 1I Pressure 472 psi Test Temp. 231 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturers Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 12/20/2004 Name of Component: APRH2-1B Work Order Number. 03-012432 CERTIFICATE OF COMPLIANCE I certify that the statements made In the report are correct and that this CORRECTED conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 7P!w eA4ua) Date ,20 05 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described in this Owner's Report during the period%,-2 7..D3- 1togor- I Sr`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 the 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.

p < Commissions NB7741, I, N. IS, A WIS 100024 Ins SNational Board, State, Province, and Endorsements Date .20 S

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

1. Owner Wisconsin Public Service Corporation Date 11128/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2 Unit No. 1

2. Plant Kewaunee Nuclear Power Plant N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-012495

3. Work Performed By Nuclear Management Comeany. LLC Type Code Sym. Stamp NA 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 36 Class 1 REACTOR COOLANT Expiration Date NA

5. (a) Applicable Construction Code ASME 111-1968 (c) Applicable Section XI Code Case NA (b)Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped I R3 PR-3A CROSBY, ASHTON GAGE NF NA RC008-001 1972 CORRECTED N COMPANY

7. Description of Work REMOVE CLASS 1 REACTOR COOLANT SYSTEM 6 VALVE PR-3A FOR SET POINT TESTING.

8. Tests conducted Hydrostatic [1: Pneumatic g Nominal Operating Pressure E] Exempt n3 Other j1 Pressure psi Test Temp. deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 11/28/2004 Name of Component: PR-3A Work Order Number: 03-012495 CERTIFICATE OF COMPLIANCE I certify that the statements made In the report are correct and that this CORRECTED conforms to the requirements of the ASME Code.Section XI.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed p e&CW; ' Date 4 Dl 3 .20 0 5 Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In this Owner's Report during the periodN.,gc- tq" Io*'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 the 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 NB7741, I, N, IS, A WIS 100024 I VU Inspector's Signature National Board, State, Province, and Endorsements Date At .20 VS" C,;

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

1. Owner Wisconsin Public Service Corporation Date 11/2812004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-012637

3. Work Performed By Nuclear Management Comoanv. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 36 Class 1 REACTOR COOLANT Expiration Date NA

5. (a) Applicable Construction Code ASME II -1968 (c) Applicable Section XI Code Case NA (b)Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. I1 Built Installed Stamped PR-3A CROSBY, ASHTON GAGE NF NA RC008-001 1972 CORRECTED N COMPANY

7. Description of Work REINSTALL FOLLOWING SET POINT TESTING CLASS 1 REACTOR COOLANT SYSTEM 6 VALVE PR-3A.

8. Tests conducted Hydrostatic [] Pneumatic 1 1Nominal Operating Pressure M Exempt Other [] Pressure 2240 psi Test Temp. 546 deg.F

9. Remarks NOT APPLICABLE.

Applicable Manufacturers Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 11/28/2004 Name of Component: PR-3A Work Order Number 03-012637 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this CORRECTED conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed C. J &ff4ft Date 4. 3 20 05 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In this Owner's Report during the period J 07,3 to<9lootoand 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 the 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.

go _ _ _ _ _ Commissions NB7741, ainlBad I, N,IS,ttPoicadEdreet A WIS 100024 E. f~o' Sintr UV Inspoor's Signature National Board, State, Province, and Endorsements Date 9 // ,20 Go1 (J O

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

1. Owner Wisconsin Public Service Corporation Date 11/27/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 03-014216

3. Work Performed By Nuclear Management Comnany. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 36 Class 1 REACTOR COOLANT Expiration Date NA

5. (a)Applicable Construction Code SEC. 111-2000 ADD. (c) Applicable Section Xi Code Case NA (b)Applicable Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identificafion of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped i

RRVCH MITSUBISHI HEAVY B-VH-N06 5845 00033 2004 INSTALLED Y INDUSTRIES

7. Description of Work REPLACE CLASS I REACTOR COOLANT SYSTEM REACTOR VESSEL CLOSURE HEAD.

8. Tests conducted Hydrostatic _ Pneumatic 2 Nominal Operating Pressure El Exempt _

Other 1 Pressure 2240 psi Test Temp. 547 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturers Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 11/27/2004 Name of Component: RRVCH Work Order Number: 03-014216 CERTIFICATE OF COMPLIANCE I certify that the statements made In the report are correct and that this INSTALLED conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed e4 C Iflie1 ( A Date Hi .20o Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In this Owner's Report during the perioedtc,&1,t1. to 9a lt ,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 the ASME Code, Section Xl.

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__ _ _ _ _ __*_* Commissions NB7741, I, N. IS, A WIS 100024 Inspector's Signature National Board, State, Province, and Endorsements l)

Date A . I ,20 O5S Qa

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

1. Owner Wisconsin Public Service Corporation Date 12/20/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-000158

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 35 Class 2 CHEMICAL AND VOLUME CONTROL Expiration Date NA

5. (a) Applicable Construction Code B31.1-1967 (c) Applicable Section XI Code Case NA (b)Applicable Edition of Section Xi Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped CVC-40 CROSBY VALVE & GAGE 51036 M2 NA CS015-001 1971 CORRECTED N CO.

7. Description of Work REMOVE FOR SETPOINT TESTING CLASS 2 CHEMICAL AND VOLUME SYSTEM 3 VALVE CVC-40.

8. Tests conducted Hydrostatic [1 Pneumatic [1 Nominal Operating Pressure E Exempt f:J Other f Pressure 19 psi Test Temp. 81 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 12/20/2004 Name of Component: CVC-40 Work Order Number: 04-000158 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this CORRECTED conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 7°,NfAlfrl 6 f I& e Date - m 2) ,20 05

'I 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 or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In this Owners Report during the periodT Z °3 to° 1JO vv.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 the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, conceming 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 NB7741, I, N. IS, A WIS 100024 Inspectes Signature National Board, State, Province, and Endorsements Date ,, // .20 05s' L/ 6

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT

1. As Required by the Provisions of the ASME Code Section XI

1. Owner Wisconsin Public Service Cormoration Date 1/22/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307.9001 Sheet I of 2 Unit No. I

2. Plant Kewaunee Nuclear Power Plant N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-000303

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 23 Class 2 CONTAINMENT SPRAY Expiration Date NA

5. (a)Applicable Construction Code B31.1-1967 Code Case NA (b)Applicable Edition of Section XI Utilized for Repairs or Replacements 1989

6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Name of Name of Manufacturer National Other Year Replaced, or Code Component Manufacturer Serial No. Board No. ID Built Replacement Stamped ICS-H8 ITT GRINNELL VALVE CO. NA NA NA 1971 REPAIRED N

7. Description of Work REPAIR CLASS 2 INTERNAL CONTAINMENT SPRAY SYSTEM 6 HYDRAULIC SNUBBER ICS-H8 DUE TO OIL LEAK.

8. Tests conducted Hydrostatic ,3 Pneumatic L Nominal Operating Pressure U Exempt I'm Other F1 Pressure psi Test Temp. deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 1/22/2004 Name of Component: ICS-H8 Work Order Number: 04-000303 Certificate of Compliance We Certify that the statements made in the report are correct and this REPAIRED conforms to the rules of the ASME Code Section Xl. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed J LDate 6wC/4J11V&? 3 .20 Q3 Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION I. the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described In the Owners Report during the period i ,7O3 to ~nd state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described inthis Owners Report Inaccordance with the requirements of the ASME Code,Section XI.

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

__ Commissions NB7741, I, N, IS, A WIS 100024 Inspectors Signature National Board, State, Province, and Endorsements Date / ,20 0S .

U a.

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

1. Owner Wisconsin Public Service Corporation Date 11,1 5/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. I N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-000332

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NI 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 36 Class 1 REACTOR COOLANT Expiration Date NA

5. (a) Applicable Construction Code ASME III CLASS A (c) Applicable Section XI Code Case NA (b) Applicabie Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped RV WESTINGHOUSE RCRIUI N/A 00033 1970 INSTALLED N INTERNALS

7. Description of Work REPLACE CLASS 1 REACTOR VESSEL UPPER INTERNALS GUIDE TUBE SPLIT PINS

8. Tests conducted Hydrostatic l1i Pneumatic El Nominal Operating Pressure Li Exempt El Other go Pressure psi Test Temp. deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 11/1512004 Name of Component: RV INTERNALS Work Order Number 04*000332 CERTIFICATE OF COMPLIANCE I certify that the statements made In the report are correct and that this INSTALLED conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Certificate of Authorization No. NA Expiration Date NA Signed A 4m4 , C.,}fi 6wV D Date 3 ,20 CLS5 O U U Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In this Owner's Report during the periodsd. 17 0 3 too a O5and 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 the ASME Code, Section Xl.

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 Owners 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.

,t... < s Commissions NB7741, I, N, IS, A WIS 100024 Inspectors Signature National Board, State, Province, and Endorsements DateeI / ,20 If 5 I

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

1. Owner Wisconsin Public Service Corporation Date 6/1/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2 Unit No. 1

2. Plant Kewaunee Nuclear Power Plant N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-01441

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 35 Class g CHEMICAL AND VOLUME CONTROL Expiration Date NA

5. (a) Applicable Construction Code ASME IlIl CLASS C Code Case NA (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 1989

6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Name of Name of Manufacturer National Other Year Replaced, or Code Component Manufacturer Serial No. Board No. ID Built Replacement Stamped AHLD (CLASS ATLAS 1206 1031 00060 1970 REPLACEMENT Y 2)

7. Description of Work REPLACE CLASS 2 LETDOWN HEAT EXCHANGER FLANGE STUDS (3) AND FLANGE NUTS (6) DUE TO EVIDENCE OF LEAKAGE

8. Tests conducted Hydrostatic n Pneumatic n Nominal Operating Pressure [23 Exempt n Other [n Pressure 250 psiI Test Temp. 280 deg.F

9. Remarks NOMINAL OPERATING PRESSURE: CLASS 2 CHEMICAL AND VOLUME CONTROL SYSTEM: TEST PRESSURE 250 PSIG.

TEST TEMPERATURE: 280 DEGREES F.: CLASS 3 CONPONENT COOLING WATER SYSTEM: TEST PRESSURE: 140 PSIG:

TEST TEMPEARTURE: 95 DEGREES F.

Applicable Manufacturers Data Reports to be Attached

NIS.2 (Back)

Sheet 2 of 2 Date: 61112004 Name of Component: AHLD (CLASS 2)

Work Order Number: 04-01441 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 NA Certificate of Authorization No. NA Expiration Date NA Signed 7°4 ,6 JWL942L k G Date 612 Z3 ,20 0 5 O v V Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In the Owner's Report during the periodtv7 u toa( ,OS 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 the ASME Code, Section Xl.

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.

X G Commissions NB7741, I, N, IS, A WIS 100024 U Inspecto/s Signature National Board, State, Province, and Endorsements Date Vz ,.- it .20 0 S-U 0

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

1. Owner Wisconsin Public Service Cormoration Date 12/8/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet I of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-008484

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 35 Class 2 CHEMICAL AND VOLUME CONTROL Expiration Date NA

5. (a) Applicable Construction Code B16.34-SEC. 111-1982 (c) Applicable Section Xl Code Case NA (b) Applicable Edition of Section Xi Used for RepairlReplacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ED Built Installed Stamped CVC-5C KEROTEST MFG CORP AJ 03-7 NA CS002-015 1986 INSTALLED N

7. Description of Work REPLACE CLASS 2 CHEMICAL AND VOLUME CONTROL SYSTEM 2 VALVE CVC-5C AND 2-2" SOCKET WELDS.

8. Tests conducted Hydrostatic [] Pneumatic Nominal Operating Pressure I' Exempt 1]

Other [] Pressure 2235 psi Test Temp. 112 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 12/8/2004 Name of Component: CVC-5C Work Order Number: 04-008484 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this INSTALLED conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 79i40. Cut 7° l)2%

i J 610 Date .20 Q Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described In this Owner's Report during the period~&os70 3 to.,, .iow 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 the 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 Owners 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 NB77411, I,N. IS, A WIS 100024 Inspectops Signature National Board, State, Province, and Endorsements Date ite/ __dS

)

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

1. Owner Wisconsin Public Service Corporation Date 11/27/2004 700 North Adams P.O.Box 19001 Green Bay, WI 54307-9001 Sheet I of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. I N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-011815

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 36 Class 1 REACTOR COOLANT Expiration Date NA

5. (a)Applicable Construction Code 616.5 (c) Applicable Section XI Code Case NA (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped LD-2 MASONELIAN H46695-2 NA RC011-001 1970 CORRECTED N INTERNATIONAL INC.

7. Description of Work CORRECT CLASS 1 REACTOR COOLANT SYSTEM 2 VALVE LD-2 DUE TO VALVE CLOSING PROBLEMS BY REPLACING VALVE STEM AND GASKET PACKING.

8. Tests conducted Hydrostatic [1 Pneumatic 1 Nominal Operating Pressure F3 Exempt s Other [1 Pressure 2240 psi Test Temp. 547 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 1112712004 Name of Component: LD-2 Work Order Number 04-011815 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are corfect and that this CORRECTED conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 7"P42i U 6i0J - Date .20 O5 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I. the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described In this Owner's Report during the period" 7 o.3 t5 nd 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 the 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 NB7741, I, N, IS, A WIS 100024 Inspectd s Signature National Board, State, Province, and Endorsements Date A (/ .20 5S U V

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

1. Owner Wisconsin Public Service Corporation Date 11/12/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-011819

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 35 Class 1 CHEMICAL AND VOLUME CONTROL Expiration Date NA

5. (a)Applicable Construction Code 831.1.1967 (c) Applicable Section XI Code Case NA (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped RCVC-H36 GRINNELL NF NA NA 1967 CORRECTED N

7. Description of Work CORRECT CLASS 1 CHEMICAL AND VOLUME CONTROL SYSTEM 2 HYDRAULIC SNUBBER RCVC-H36 DUE TO MISALIGNMENT.

8. Tests conducted Hydrostatic [] Pneumatic _ Nominal Operating Pressure 1 Exempt sx Other n Pressure psi Test Temp. deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached I

NIS-2 (Back)

Sheet 2 of 2 Date: 11/12/2004 Name of Component: RCVC-H36 Work Order Number: 04-011819 CERTIFICATE OF COMPLIANCE I certify that the statements made In the report are correct and that this CORRECTED conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed . 134z JlCUOO '0 V Date 4.ng .20 0 j Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described in this Owners Report during the period> 1 °. 3, toFe10.J osand state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Ownees Report in accordance with the requirements of the ASME Code, Section Xl.

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 Owners 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 cCommissions NB7741, I, N. IS, A WIS 100024 Inspe s Signature National Board, State, Province, and Endorsements Date_ _ _ I_ _ .20 0o C' 0

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

1. Owner Wisconsin Public Service Corporation Date 12/17/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet I of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-011827

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 34 Class 2 RESIDUAL HEAT REMOVAL Expiration Date NA

5. (a)Applicable Construction Code B31.1-1967 (c) Applicable Section Xl Code Case NA (b) Applicable Edition of Section Xi Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped RHR-8B FISHER CONTINENTAL 141551 NA AC012-002 1972 CORRECTED N

7. Description of Work CORRECT BODY TO BONNET LEAK ON CLASS 2 RESIDUAL HEAT REMOVAL SYSTEM 8' VALVE RHR-8B INCLUDING REPLACING 12 STUDS AND 24 NUTS ON VALVE BONNET FLANGES.

8. Tests conducted Hydrostatic [1j Pneumatic [ Nominal Operating Pressure M Exempt []

Other [1 Pressure 472 psi Test Temp. 231 deg. F

9. Remarks NOT APPLICABLE Applicable Manufacturer's Data Reports to be Attached

)

NIS-2 (Back)

Sheet 2 of 2 Date: 12/17/2004 Name of Component: RHR-8B Work Order Number: 04-011827 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this CORRECTED conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 6'Me. rl"vtW O

%J wv O.J Date 6,14 3 ,20 0Q5 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I. the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described in this Owner's Report during the period 1 4c'l 1, 3 to to. : o S 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 the 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 NB7741, I, N, IS, A WIS 100024 V f National Board, State, Province, and Endorsements Inspector's Signature Date IteI 2/ 'P r

.20

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

1. Owner Wisconsin Public Service Corporation Date 11110/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 044011838

3. Work Performed By Nuclear Management Comoany. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 35 Class 2 CHEMICAL AND VOLUME CONTROL Expiration Date NA

5. (a)Applicable Construction Code B31.1 (c) Applicable Section XI Code Case NA (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped CVC-H115 ITTGRINNELL VALVE NF NIA NA 1975 CORRECTED N COMPANY

7. Description of Work LOCATE APPARENT MISSING NUT ON CLASS 2 CHEMICAL AND VOLUME CONTROL SYSTEM SUPPORT CVC-H1 15 BY REMOVING PAINT AND GROUTING.

8. Tests conducted Hydrostatic [ Pneumatic Li Nominal Operating Pressure U Exempt El Other Pressure psi Test Temp. deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturers Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 11/10/2004 Name of Component: CVC-H115 Work Order Number 04-011838 CERTIFICATE OF COMPLIANCE I certify that the statements made In the report are correct and that this CORRECTED conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed '. b2,74= 6Arm~z°/V Date 3 ,20 Q Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described in this Owners Report during the periodlc 7,..3 to 9 e.&kA5and 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 the 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 Owners 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.

_______.__X ____-.__ Commissions NB7741, 1,N, IS, A WIS 100024 Inspectors Signature National Board, State, Province, and Endorsements Date A- :q 11 ,20 oS Ua

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

1. Owner Wisconsin Public Service Corporation Date 11/1512004 700 North Adams P.O.Box 19001 Green BaV. WI 54307-9001 Sheet I of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-011856

3. Work Performed By Nuclear Management Comnany. LLC Type Code Sym. Stamp NA 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 34 Class 2 RESIDUAL HEAT REMOVAL Expiration Date NA

5. (a) Applicable Construction Code 631.1-1967 (c) Applicable Section XI Code Case NA (b) Applicable Edition of Section XI Used for Repalr/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped RHR-H1OH ITTGRINNELLVALVECO. NF NA NA 1967 CORRECTED N

7. Description of Work CORRECT CLASS 2 RESIDUAL HEAT REMOVAL SYSTEM B' HYDRAULIC SNUBBER RHR-H10H DUE TO EVIDENCE OF LEAKAGE FROM THE VALVE ASSEMBLY.

8. Tests conducted Hydrostatic L Pneumatic LI Nominal Operating Pressure n Exempt n3 Other [] Pressure psi Test Temp. deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturers Data Reports to be Attached

-I NIS-2 (Back)

Sheet 2 of 2 Date: 11/15/2004 Name of Component: RHR-H10H Work Order Number. 04-011856 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this CORRECTED conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 3 ,200Q5

."Date Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described in this Owner's Report during the period"7, 0 3 - togs-Jo;% 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 the ASME Code, Section Xl.

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 NB7741, I. N, IS, A WIS 100024 I C/ National Board, State, Province, and Endorsements Inspector's Signature Date Il I2t ,20 C S-

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

1. Owner Wisconsin Public Service Corporation Date 11/18/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-011872

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 34 Class I RESIDUAL HEAT REMOVAL Expiration Date NA

5. (a)Applicable Construction Code B31.1-1967 (c) Applicable Section Xi Code Case NA (b) Applicable Edition of Section Xi Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped RHR-1B VELAN VALVE NF NA AC104-003 1972 CORRECTED N CORPORATION

7. Description of Work SEAL WELD BODY TO BONNET ON CLASS 1 RESIDUAL HEAT REMOVAL SYSTEM 8 VALVE RHR-1 B DUE TO EVIDENCE OF LEAKAGE.

8. Tests conducted Hydrostatic Pneumatic Nominal Operating Pressure E Exempt I Other Pressure 150 psi Test Temp. 95 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturers Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 11/18/2004 Name of Component: RHR-1 B Work Order Number 04-01 1872 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this CORRECTED conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed f4 14& &I JITIW T Ot O Date 3 ,20 Q5 Owner or Owner's Designee, Titie 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 Inspection and Insurance Company of CT have inspected the components described Inthis Owner's Reportduringthe periodkm. P7.3 to9llv2,A* Dand 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 the ASME Code, Section Xl.

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_ _ _ _ _ Commissions NB7741, I, N. IS, A WIS 100024 Inspecto Signature National Board, State, Province, and Endorsements Date a / .20 OS'

\ a

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

1. Owner Wisconsin Public Service Comoration Date 12/17/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-011964

3. Work Performed By Nuclear Management Company. LILC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 36 Class I REACTOR COOLANT Expiration Date NA

5. (a) Applicable Construction Code NA (c) Applicable Section Xl Code Case NA (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped RCP-1A WESTINGHOUSE 1.618J871-G01 NA 00037 1970 CORRECTED N

7. Description of Work RETENSION CLASS 1 CHEMICAL AND VOLUME CONTOL SYSTEM REACTOR COOLANT PUMP 1A MAIN FLANGE BOLTS.

8. Tests conducted Hydrostatic LI Pneumatic' Nominal Operating Pressure LI Exempt li Other U Pressure psi Test Temp. deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturers Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 12117/2004 Name of Component: RCP-1 A Work Order Number 04-011964 CERTIFICATE OF COMPLIANCE I certify that the statements made In the report are correct and that this CORRECTED conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed Date ,20 Ci Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have Inspected the components described In this Owner's Report during the peri i to 1 2IDSv e. 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 the 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.

Ace GCommissions

_ __ NB7741, I, N, IS, A WIS 100024 Inspector's Signature National Board, State, Province, and Endorsements Date(I 20 _ OSLO

% aJ

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

1. Owner Wisconsin Public Service Corporation Date 11/12/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2 Unit No. 1

2. Plant Kewaunee Nuclear Power Plant N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-011972

3. Work Performed By Nuclear Management Comoanv. LLC Type Code Sym. Stamp NA 700 First Street. Hudson. Wisconsin 54016 Authorization No. NA

4. Identification of System 33 Class 2 SAFETY INJECTION Expiration Date NA

5. (a)Applicable Construction Code B31.1-1967 (c) Applicable Section XI Code Case NA (b)Applicable Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of - Name of Manufacturer National Other Year Removed, or Code Component Alanufacturer Serial No. Board No. ID Built Installed Stamped RSI-H100 ITT GRINNELL VALVE CO. NA NA NA 1967 CORRECTED N

7. Description of Work CORRECT CLASS 2 SAFETY INJECTION SYSTEM 2" HYDRAULIC SNUBBER RSI-HIOO DUE TO FAILED FUNCTIONAL TEST.

8. Tests conducted Hydrostatic 1j] Pneumatic Eli Nominal Operating Pressure 1 Exempt px Other n Pressure psi Test Temp. deg. F

9. Remarks NOT APPLICABLE Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 11/12/2004 Name of Component: RSI-H100 Work Order Number 04-011972 CERTIFICATE OF COMPLIANCE I certify that the statements made In the report are correct and that this CORRECTED conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed iX >L, 4. 6U?1L4 Date ,200.5 Owner or Owners Designee. Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described In this Owner's Report during the period% .. A ?7 .3 togs 1z0PS., 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 the ASME Code, Section Xl.

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.

_ 2v4- sCommissions NB7741, I, N. IS, A WIS 100024 Insper's Signature National Board, State, Province, and Endorsements Date A, II 20

,20 0 S'

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

1. Owner Wisconsin Public Service Corporation Date 11/18/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet I of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-012022

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 33 Class 2 SAFETY INJECTION Expiration Date NA

5. (a) Applicable Construction Code B31.1-1967 (c) Applicable Section Xi Code Case NA (b) Applicable Edition of Section XI Used for Repair/Reptacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped RSI-H83 ITT GRINNELL VALVE CO. NA NA NA 1967 CORRECTED N

7. Description of Work CORRECT CLASS 2 SAFETY INJECTION SYSTEM 2 HYDRAULIC SNUBBER RSI-H83 DUE TO LEAKING BLEED RATE THREAD SEALS.

8. Tests conducted Hydrostatic [1 Pneumatic [ Nominal Operating Pressure LI Exempt E3 Other 1I Pressure psi Test Temp. deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached l

NIS-2 (Back)

Sheet 2 of 2 Date: 11/18/2004 Name of Component: RSI-H83 Work Order Number 04-012022 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this CORRECTED conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 'R% e. & J Jv Date v ,20 05 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described In this Owners Report during the periodiod&5,g to 9 0 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 the ASME Code, Section Xl.

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 NB7741, I, N. IS, A WIS 100024 Inspectoras Signature National Board, State, Province, and Endorsements Date+/-A L~.L .20 05 V I a

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

1. Owner Wisconsin Public Service Corooration Date 11/15/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-012030

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 34 Class . RESIDUAL HEAT REMOVAL Expiration Date NA

5. (a)Applicable Construction Code B31.1-1967 (c) Applicable Section XI Code Case NA (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped RRHR-H2 ITT GRINNELL VALVE NA NA NA 1967 CORRECTED N COMPANY

7. Description of Work CORRECT CLASS 2 RESIDUAL HEAT REMOVAL SYSTEM 8" SUPPORT RRHR-H2 DUE TO HANGER ROD NOT BEING IN TENSION.

8. Tests conducted Hydrostatic n Pneumatic Cl Nominal Operating Pressure LI Exempt [

Other 1I Pressure psi Test Temp. deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturers Data Reports to be Attached

)

NIS-2 (Back)

Sheet 2 of 2 Date: 11/15/2004 Name of Component: RRHR-H2 Work Order Number 04-012030 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this CORRECTED conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed °ZvDate!-3 ,20 05 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described in this Owner's Report during the period~sM . 03 toF!- j~,

l and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, Section Xl.

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 NB7741, 1,N, IS, A WIS 100024 Inspeclo/r's Signature National Board, State, Province, and Endorsements Date a te-I2 ,20 Oslo

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

1. Owner Wisconsin Public Service Cormoration Date 11/27/2004 700 North Adams P.O.Box 19001 Green Bay, WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-013265

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street, Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 36 Class 1 REACTOR COOLANT Expiration Date NA

5. (a)Applicable Construction Code B31.1-1967 (c) Applicable Section XI Code Case NA (b) Applicable Edition of Section Xl Used for Repalr/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped FE-459 VICKERY SIMMS INC. NF NA 27040 1970 INSTALLED N

7. Description of Work REPLACE 8 STUDS AND 16 NUTS ON CLASS 1 REACTOR COOLANT SYSTEM 3' FLANGE FE-459.

8. Tests conducted Hydrostatic j] Pneumatic [] Nominal Operating Pressure AI Exempt []

Other [1 Pressure 2240 psiI Test Temp. 547 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 11/27/2004 Name of Component: FE-459 Work Order Number: 04-013265 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this INSTALLED conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed /etia.-6. Date 3 .2005 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described In this Owner's Report during the periodsm2&LL-to19 low oSAand 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 the 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___ _ _ _<_ _ Commissions NB7741, I, N. IS, A WIS 100024 Inspect s Signature National Board, State, Province, and Endorsements Date d ,020 O d-' 0

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

1. Owner Wisconsin Public Service Corporation Date 12/3/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet I of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-013710

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 05A Class 2 FEEDWATER Expiration Date NA

5. (a)Applicable Construction Code B31.1-1967 (c) Applicable Section Xl Code Case NA (b)Applicable Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

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

_l FW-13A ATWOOD & MORRILL CO., NF NA F008-001 1972 CORRECTED N INC.

7. Description of Work CORRECT CLASS 2 FEEDWATER SYSTEM 16 VALVE FW-13A DUE TO LEAKAGE PAST THE BONNET SEAL RING.

8. Tests conducted Hydrostatic 2 Pneumatic n Nominal OFperating Pressure plI Exempt n Other Li Pressure 1005 psi Test Temp. 545 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 12/3/2004 Name of Component: FW-13A Work Order Number. 04-013710 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are corfect and that this CORRECTED conforms to the requirements of the ASME Code, Section Xi.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed , 3 20 Q(L5

.Date Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described in this Owner's Report during the period ods.1,L todA 2kr and state that lonn to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the 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 Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this Inspection.

A Gor Commissions NB7741.1,N, IS,A WIS100024 Inspec-ors Signature National Board, State, Province, and Endorsements Date A 1l20 Or a~

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

1. Owner Wisconsin Public Service Corporation Date 1212/2004 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Sheet 1 of 2

2. Plant Kewaunee Nuclear Power Plant Unit No. 1 N490 HWY 42 Kewaunee. WI 54216-9511 Work Order 04-014115

3. Work Performed By Nuclear Management Company. LLC Type Code Sym. Stamp NA 700 First Street. Hudson, Wisconsin 54016 Authorization No. NA

4. Identification of System 35 Class I CHEMICAL AND VOLUME CONTROL Expiration Date NA

5. (a) Applicable Construction Code B31.1-1967 (c) Applicable Section XI Code Case NA (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 1998 Edition 2000 Addenda

6. Identification of Components Corrected, ASME Name of Name of Manufacturer National Other Year Removed, or Code Component Manufacturer Serial No. Board No. ID Built Installed Stamped CVC-206A KEROTEST NF NA CS100-004 1973 CORRECTED N MANUFACTURING CORP.

7. Description of Work TORQUE AND SEAL WELD BODY TO BONNET ON CLASS 1 CHEMICAL AND VOLUME CONTROL SYSTEM 2" VALVE CVC-206A DUE TO ACTIVE LEAKAGE.

8. Tests conducted Hydrostatic ] Pneumatic J1 Nominal Operating Pressure 1`J Exempt :l Other [] Pressure 2235 psi Test Temp. 112 deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back)

Sheet 2 of 2 Date: 12/2/2004 Name of Component: CVC-206A Work Order Number: 04-014115 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this CORRECTED conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed A C A4 Date .20 Q5 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Insurance Company of CT have inspected the components described in this Owner's Report during the period.i,,0A toho-%,,0, 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 the 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 NB7741, I, N, IS, A WIS 100024 Inspector's Signature National Board, State, Province, and Endorsements Date IIl20 CY

ENCLOSURE 10 EXAMINATION

SUMMARY

FOR CLASS 1, CLASS 2, AND CLASS 3 INSERVICE INSPECTION PROGRAM FOR THIRD TEN-YEAR INTERVAL 2 pages follow

KEWAUNEE NUCLEAR POWER PLANT 3RD INTERVAL: 3RD PERIOD: 3RD OUTAGE 2004 EXAMINATION

SUMMARY

INTRODUCTION An Inservice Inspection (ISI) Program was performed at the Kewaunee Nuclear Power Plant from October 5, 2004 through December 4, 2004 (Closing of GI following Refueling Outage) by Kewaunee Nuclear Power Plant and Lambert, MacGill, and Thomas, Inc.(LMT) examination personnel.

Examinations were performed to satisfy the requirements of:

ASME Boiler and Pressure Vessel Code Section XI 1989 Edition The Inservice Inspection Program Plan located under Tab C was prepared by Kewaunee Nuclear Power Plant for the 3rd Interval: 3rd Period: 3rd Outage as identified in the Kewaunee Nuclear Power Plant Third 10-Year Inservice Inspection (ISI) Program 1994- 2004.

Examinations during this Refueling Outage were performed to complete the 3rd Interval: 3rd Period Examination Requirements of ASME Boiler and Pressure Vessel Code Section XI 1989 Edition and Kewaunee Nuclear Power Plant Third 10-Year Inservice Inspection (ISI) Program 1994-2004.

The following items were examined:

Reactor Vessel Threads in Flange

Reactor Vessel Nozzle To Safe End Butt Welds

Reactor Vessel Supports EXAMINATIONS The examinations performed were in accordance with an approved Inservice Inspection Program Plan located under Tab C of the final report. Examination Procedures were approved prior to the start of examinations and certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory.

Page 1 of 2

Some of the arrangements and details of the Kewaunee Nuclear Power Plant Components and Piping Systems were designed and fabricated before ASME Boiler and Pressure Vessel Code Section X1 Code requirements were established. Examinations performed were intended to examine 100% of the required surface or volume. In some cases, examinations were limited by geometric, metallurgical or design/access restrictions. In each case, the occurrence and cause of the limitation was documented. In all cases the maximum amount achievable was examined.

Witnessing and surveillance of the examinations were conducted by: United States Nuclear Regulatory Commission and Hartford Steam Boiler Inspection and Insurance Company of CT.

RESULTS Examinations resulted in No Recordable Indications being noted on the basis of procedure recording criteria, which are generally more restrictive than specified ASME Boiler and Pressure Vessel Code Section X1 Acceptance Standards.

SUMMARY

An Inservice Inspection Program Plan was performed at the Kewaunee Nuclear Power Plant from October 5, 2004 through December 4, 2004 (Closing of GI following Refueling Outage) as scheduled in the Kewaunee Nuclear Power Plant Third 10-Year Inservice Inspection (ISI)

Program 1994-2004 to complete examinations for the 3rd Interval; 3rd Period. There were No Recordable Indications noted.

7°Xt.( asLOOg Phillip E. Bukes Date Engineering Programs Inservice Inspection Program Owner Page 2 of 2

ENCLOSURE 11 EXAMINATION

SUMMARY

FOR REACTOR VESSEL INSERVICE INSPECTION PROGRAM FOR THIRD TEN-YEAR INTERVAL 5 pages follow

KEWAUNEE UNIT 1 NUCLEAR POWER PLANT INTERVAL 3, PERIOD 3, OUTAGE 3 REACTOR VESSEL EXAMINATION EXAMINATION

SUMMARY

November 13, 2004 Introduction The Kewaunee Unit 1 reactor vessel was examined by WesDyne International in connection with the Westinghouse Electric Company, Nuclear Services Division from November 8, 2004 through November 12, 2004. Examinations were governed by the Kewaunee Unit 1 Plant Technical Specifications, ASME Boiler and Pressure Vessel Code,Section XI and Section V, 1989 Edition, no Addenda and 1995 Edition, 1996 Addenda as modified by 10CFR50.55a(b)(2)(xiv, xv, and xvi) and the Examination Program Plan, Revision 2 as submitted to and approved by Nuclear Management Company.

All automated ultrasonic examinations (implementation of Appendix VII were conducted in accordance with the ASME Code,Section XI, 1995 Edition with 1996 Addenda as modified by IOCFR 50.55a(b)(2)(xiv, xv and xvi). Examination scan plans were prepared under the direct supervision of a qualified examiner according to the requirements of procedures PDI-ISI-254 Rev. 5, FC 01, PDI-ISI-254-NZ Rev. 0, PDI-ISI-254-SE Rev. 1,PDI-ISI-254-SI-NZ Rev. 0 and PDI-ISI-254-SI-SE Rev. 1 PDQS Rev. 2.

Automated ultrasonic examinations of the vessel flange to upper shell weld, shell circumferential welds, the lower shell to lower head weld, the lower head weld torus to dollar plate weld, and nozzle to shell welds of the safety injection nozzle and primary inlet nozzles, from the vessel ID were performed in accordance with procedure PDI-ISI-254 Rev. 5, FC 01.

Automated ultrasonic examinations of the inlet nozzle-to-shell welds from the nozzle bore were performed in accordance with procedure PDI-ISI-254-NZ Rev. 0.

Automated ultrasonic examinations of the of the inlet nozzle to safe end welds from the nozzle bore were performed in accordance with procedure PDI-ISI-254-SE Rev. 1.

Page I of 5

Automated ultrasonic examinations of the safety injection nozzle-to-shell welds from the nozzle bore were performed in accordance with procedure PDI-ISI-254-SI-NZ Rev. 0.

Automated ultrasonic examinations of the of the safety injection nozzle to safe end weld @ 108.50 from the nozzle bore was performed in accordance with procedure PDI-ISI-254-SI-SE Rev. I PDQS Rev 2.

Supplemental automated eddy current examinations of the primary inlet nozzle to safe-end welds from the nozzle bore, where necessary, were performed in accordance with procedure WDI-STD-146 Rev 3 to supplement the parallel scans of the ultrasonic examination limitations.

Manual ultrasonic examinations of the flange to shell weld were conducted in accordance to procedure WDI-SSP-073 Rev. 1Field Change 1.

Visual examination of the safety injection, and primary inlet and outlet nozzle inner radius areas were conducted in lieu of volumetric examination in accordance with Procedure NEP No.15.29, Rev. 0 which references the 1989 Edition of the ASME Code,Section XI and Code Case N-648-1.

The reactor vessel interior, the reactor vessel interior and components within and beyond the beltline, and the reactor vessel removable core support structure were examined in accordance with Procedure NEP No. 15.29, Rev 0 which references the 1989 Edition of the ASME Code,Section XI.

Code Examinations Instructions for calibrations, examinations and assessment of recorded data are contained in the applicable procedures and considered as an integral part of these procedures is the Examination Program Plan; Revision 2 (EPP). The program plan is a plant specific document detailing the calibration blocks, beam angles, arrangement of transducers on the various end-effectors and scaled drawings depicting the reactor vessel section profiles and scanning paths. The scanning paths depicted in the technique drawings served as input data for the vessel solid models generated for the SUPREEM robot motion control software.

Examinations were conducted completely by the contact technique using two WesDyne PARAGON multi-channel data acquisition systems, one interfaced to each SUPREEM robot and scanning platform.

Page 2 of 5

All examinations were conducted to the maximum extent practical with the access provided and within the limitation of component geometry.

All shell welds were examined from the vessel ID with 450 transducers. Scanning was performed both parallel and perpendicular to each weld. The scan index increment was 0.5".

Nozzle to shell welds were examined from the vessel ID with 450 transducers. Scanning was performed both parallel and perpendicular to each weld. The scan index increment was 0.5".

Shell weld, flange to shell weld and nozzle-to-shell weld examinations, conducted from the vessel ID, were performed according to the qualified Appendix VIII procedures which required the use of 45° dual element and single element transducers for volumes of metal from the clad base-metal interface to a depth of 0.6 "t" and 450 shear transducers for depths from 0.6 "t" to the OD surface. Scanning was conducted normal to and parallel to the exam volume at less than 5.5 inches per second with four directional interrogation performed wherever possible Nozzle to shell welds were also examined from within the nozzle bores using an axial-radial examination approach using 5, 25, 35, 40 and 50 degree L wave single element transducers. Nozzle to shell weld scans from the nozzle bore were performed using increments along the bore surface to produce an effective index size in the examination area of interest of 0.25".

Ultrasonic detection scans for the Inlet nozzle to safe-end welds were examined from the ID surface using 70° L- wave transducers applied four-directionally. This exam interrogated the inner 1/3 thickness volume. Axial scans were performed at a 0.25" increment and the circumferential scans were conducted at a 0.080" incremental distance. Eddy Current examinations were also employed to examine inner surfaces of the dissimilar metal welds and the adjacent examination volumes where ID geometry presented a limitation to the detection of axial flaws as defined in the PDQS for the qualified Appendix VIII technique.

All data was digitally recorded from baseline to 100% full screen height and assessed off-line by PDI qualified Level m or Level II examiners having certification attachments issued by PDI relative to procedures PDI-ISI-254, Rev 5, FC 01, PDI-ISI-254-NZ, Rev 0, PDIS-ISI-254-SI-NZ, Rev. 0, PDI-ISI-254-SE, Rev 1, and PDI-ISI-254-SI-SE Rev. I PDQS Rev. 2.

Page 3 of 5

Examination Results Automated ultrasonic examinations of the Kewaunee Unit 1 reactor vessel yielded a total of 12 recorded indications. Flaw bounding measurements for these indications were performed in accordance with Procedures PDI-ISI-254 Rev. 5 FC 01, PDI-ISI-254-NZ Rev. 0 and PDI-ISI-254-SI-NZ Rev. 0, by qualified examiners. All recorded indications were assessed in terms of the criteria in the ASME Code Section XI, 1989 Edition, no Addenda, Article IWB-3000, Par. 1WB-3500; and were found to be within the allowable limits specified with no further evaluation required.

Supplemental eddy current examinations of the inlet nozzle to safe-end welds from the nozzle bore revealed no indications.

Manual examination of the flange to shell weld revealed no indications.

Remote visual examinations of the safety injection and primary inlet nozzle inner radius areas (VT-1) resulted in no recorded indications.

Remote visual examinations of the reactor vessel interior and components (VT-3) resulted in one recordable indication. Reference CAP No. 23818 and OBD 103 which details the evaluation.

Remote visual examination of the reactor vessel removable core support structure/core barrel revealed no indications.

All required examinations were completed per the Kewaunee Unit 1 Reactor Vessel Examination Program Plan.

Examination Limitations Following is a description of the weld examinations where the coverage was limited to less than 90%.

RV-WI - Reactor Vessel Shell to Flange Weld Due to the flange configuration 100% examination coverage was not achieved. Calculations for coverages were calculated using single sided coverage as well as two sided coverage. The breakdowns of each method can be found in Tab I of this report.

Page 4 of 5

RV-W4 - Reactor Vessel Shell to Bottom Head Due to the core support lugs 100% examination coverage was not achieved. Calculations for coverages were calculated using single sided coverage as well as two sided coverage. The breakdowns of each method can be found in Tab I of this report.

RV-W8 & WI I Safety Injection Nozzle to Shell Due to the nozzle protrusion, 100% of the examination was not achieved. Calculations for coverages were calculated using single sided coverage as well as two sided coverage. If single sided coverage is used the examination becomes more than 90% completed. The breakdowns of each method can be found in Tab I of this report.

RC-W26DM & RC-W58DM Nozzle to Safe End Weld The primary inlet Nozzle to Safe-end welds are limited in examination coverage for the detection of axial flaws (circumferential scans), as per the PDI issued PDQS document, due to the ID configurations involved with conducting examinations from the inner surfaces of piping. Areas of identified limitations were fully examined by supplemental Eddy Current techniques.

Da ItMoreau Wvel mI Page 5 of 5

ENCLOSURE 12 EXAMINATION

SUMMARY

FOR CLASS 1, CLASS 2, AND CLASS 3 INSERVICE INSPECTION PROGRAM FOR FOURTH TEN-YEAR INTERVAL 4 pages follow

KEWAUNEE NUCLEAR POWER PLANT 4TH INTERVAL: 1ST PERIOD: 1ST OUTAGE 2004 EXAMINATION

SUMMARY

INTRODUCTION An Inservice Inspection (ISI) Program (Scheduled and Augmented) was performed at the Kewaunee Nuclear Power Plant from July 27, 2004 through August 24, 2004 (Non Refueling Outage) and October 4, 2004 through December 4, 2004 (Closing of GI following Refueling Outage) by Kewaunee Nuclear Power Plant and Lambert, MacGill, and Thomas, Inc.(LMT) examination personnel.

Examinations were performed to satisfy the requirements of:

ASME Boiler and Pressure Vessel Code Section XI 1998 Edition 2000 Addenda

United States Nuclear Regulatory Commission Generic Letter 88-05 " Boric Acid Corrosion of Carbon Steel Reactor Coolant Boundary Components in PWR Plants"

United States Nuclear Regulatory Commission Bulletin 2003-02 "Leakage From Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity" The Inservice Inspection Program Plan and Augmented Inspection Program Plan located under Tab C was prepared by Kewaunee Nuclear Power Plant for the 4th Interval: 1st Period: 1st Outage as identified in the Kewaunee Nuclear Power Plant Fourth 10-Year Inservice Inspection (ISI) Program 2004 - 2014. Examinations during this Refueling Outage were performed to commence the 4th Interval: 1st Period Examination Requirements of ASME Boiler and Pressure Vessel Code Section XI 1998 Edition 2000 Addenda and Kewaunee Nuclear Power Plant Fourth 10-Year Inservice Inspection (ISI) Program 2004-2014.

The following items were examined:

Reactor Vessel Closure Head Studs, Nuts, Washers and Threads in Flange

Pressurizer Circumferential and Longitudinal Welds and Nozzle Inside Radius Sections

Steam Generator: Tube Sheet to Head Weld, Primary Nozzle Inside Radius Section, Integrally Welded Attachment, Feedwater Nozzle To Shell Weld and Feedwater Nozzle Inside Radius Section

Reactor Coolant Pump Main Flange Bolting and No. 1 Seal Housing Bolting

Residual Heat Exchanger Shell Circumferential Weld and Integrally Welded Attachment Page 1 of 4

Charging Pump Pulsation Dampener Head Circumferential Weld

Regenerative Heat Exchanger Head and Tube Sheet To Shell Circumferential Welds

Class 1 Valve Bodies

Class 1 Piping Integrally Welded Attachments

Class 1 and Class 2 Piping Welds

Preservice Examination of Class 2 Piping Welds

Class 2 Safety Injection Pump Welded Attachments

Class 2 Piping Integrally Welded Attachments

Class 1, Class 2 and Class 3 Piping and Component Supports and Hangers

Class 1 and Class 2 Steam Generator Primary Manway Bolting, Pressurizer Manway Bolting, Flange Bolting and Valve Bonnet Bolting

Class 3 Piping and Component Integrally Welded Attachments

Class 1 System Leakage Test

Class 2 and Class 3 System Leakage Tests EXAMINATIONS The examinations performed were in accordance with an approved Inservice Inspection Program Plan located under Tab C of the final report. Examination Procedures were approved prior to the start of examinations and certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory.

Some of the arrangements and details of the Kewaunee Nuclear Power Plant Components and Piping Systems were designed and fabricated before ASME Boiler and Pressure Vessel Code Section XI Code requirements were established. Examinations performed were intended to examine 100% of the required surface or volume. In some cases, examinations were limited by geometric, metallurgical or design/access restrictions. In each case, the occurrence and cause of the limitation was documented. In all cases the maximum amount achievable was examined.

Witnessing and surveillance of the examinations were conducted by personnel from: Nuclear Regulatory Commission and Hartford Steam Boiler Inspection and Insurance Company of CT.

RESULTS Examinations resulted with the following Recordable Indications being noted on the basis of procedure recording criteria, which are generally more restrictive than specified ASME Boiler and Pressure Vessel Code Section XI Acceptance Standards.

Page 2 of 4

Recordable Indications detected during the 2004 Refueling Outage are listed in Table I with a brief summary following. Specific data relative to all Recordable Indications and their dispositions by either corrective measures, acceptance by ASME Boiler and Pressure Vessel Code Section XI 1998 Edition through 2000 Addenda Acceptance Criteria, Repair or Replacement or Evaluation are located in Tab F of the Final Report TABLE 1 TYPE OR LOCATION OF RECORDABLE INDICATION (RI) METHOD NO. OF RI'S

4" Safety Injection Nozzle To Safe End Weld Surface (PT) 1 Weld

Component and Piping Supports and Hangers Visual (VT-3) 12 Supports

Valve Bonnet Bolting Visual (VT-3) 5 Valves

System Leakage Pressure Tests Visual (VT-2) 56 Items

1. A 0.0625" Long Curvilinear Indication (previously recorded in Spring 1995) was recorded on the 4" Safety Injection Nozzle To Safe End Butt Weld SI-W54DM during performance of Liquid Penetrant Examination. This Curvilinear Indication was Acceptable per ASME Boiler and Pressure Vessel Code Section XI 1998 Edition 2000 Addenda Table IWB-3514-2.

2. Visual (VT-3) Indications recorded on Component and Piping Supports and Hangers (12 Supports) and Valve Bonnet Bolting (5 Valves) were: (1) Evaluated and Accepted or (2)

Repaired, Reexamined and Accepted by: Kewaunee Nuclear Power Plant - Maintenance, Quality Control, Engineering or Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.

3. Visual (VT-2) Indications recorded during System Leakage Pressure Tests (56 Items) were:

(1) Evaluated and Accepted or (2) Repaired, Reexamined and Accepted by: Kewaunee Nuclear Power Plant Maintenance, Quality Control, Engineering or Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.

Page 3 of 4

SUMMARY

An Inservice Inspection Program Plan was performed at the Kewaunee Nuclear Power Plant from July 27, 2004 through August 24, 2004 (Non Refueling Outage) and October 4, 2004 through December 4, 2004 (Closing of GI following Refueling Outage). Examinations were performed as scheduled in the Kewaunee Nuclear Power Plant Fourth 10-Year Inservice Inspection (ISI) Program 2004 -2014 to commence examinations for the 4th Interval; 1st Period.

A total of 74 Recordable Indications were detected. All Recordable Indications were corrected or accepted by ASME Boiler and Pressure Vessel Code Section XI 1998 Edition 2000 Addenda Acceptance Criteria, Repair/Replacement or Evaluation.

Phillip . Bukes Date Engineering Programs Inservice Inspection Program Owner Page 4 of 4

ENCLOSURE 13 EXAMINATION

SUMMARY

FOR REACTOR VESSEL INSERVICE INSPECTION PROGRAM FOR FOURTH TEN-YEAR INTERVAL 4 pages follow

KEWAUNEE UNIT 1 NUCLEAR POWER PLANT INTERVAL 4, PERIOD 1, OUTAGE 1 REACTOR VESSEL EXAMINATION EXAMINATION

SUMMARY

November 13, 2004 Introduction The Kewaunee Unit 1 reactor vessel was examined by WesDyne International in connection with the Westinghouse Electric Company, Nuclear Services Division from November 8, 2004 through November 12, 2004. Examinations were governed by the Kewaunee Unit 1 Plant Technical Specifications, ASME Boiler and Pressure Vessel Code,Section XI and Section V, 1998 Edition, 2000 Addenda, as modified by IOCFR50.55a(b)(2)(xiv, xv, and xvi) and the Examination Program Plan, Revision 2 as submitted to and approved by Nuclear Management Company.

All automated ultrasonic examinations (implementation of Appendix VII) were conducted in accordance with the ASME Code,Section XI, 1998 Edition with 2000 Addenda as modified by 10CFR 50.55a(b)(2)(xiv, xv and xvi). Examination scan plans were prepared under the direct supervision of a qualified examiner according to the requirements of procedures PDI-ISI-254 Rev. 5, FC 01, PDI-ISI-254-NZ Rev. 0, and PDI-ISI-254-SE Rev. 1, and PDI-ISI-254-SI-SE Rev. 1 PDQS Rev. 2.

Automated ultrasonic examinations of the vessel nozzle to shell welds of the primary outlet nozzles, from the vessel ID were performed in accordance with procedure PDI-ISI-254 Rev. 5, FC 01.

Automated ultrasonic examinations of the primary outlet nozzle-to-shell welds from the nozzle bore were performed in accordance with procedure PDI-ISI-254-NZ Rev. 0.

Automated ultrasonic examinations of the outlet nozzle to safe end welds from the nozzle bore were performed in accordance with procedure PDI-ISI-254-SE Rev. 1.

Automated ultrasonic examinations of the of the safety injection nozzle to safe end weld @ 288.5°from the nozzle bore was performed in accordance with procedure PDI-ISI-254-SI-SE Rev. 1 PDQS Rev. 2.

Page I of 4

Supplemental automated eddy current examinations of the primary outlet nozzle to safe-end welds from the nozzle bore, where necessary, were performed in accordance with procedure WDI-STD-146 Rev 3 to supplement the parallel scans of the ultrasonic examination limitations.

Manual ultrasonic examinations of the flange to shell weld were conducted in accordance to procedure WDI-SSP-073 Rev. 1 Field Change 1.

Visual examination of the primary outlet nozzle inner radius areas were conducted in lieu of volumetric examination in accordance with Procedure NEP-15.29, Rev. A which references the 1998 Edition, 2000 Addenda of the ASME Code,Section XI and Code Case N-648-1.

Code Examinations Instructions for calibrations, examinations and assessment of recorded data are contained in the applicable procedures and considered as an integral part of these procedures is the Examination Program Plan, Revision 2 (EPP). The program plan is a plant specific document detailing the calibration blocks, beam angles, arrangement of transducers on the various end-effectors and scaled drawings depicting the reactor vessel section profiles and scanning paths. The scanning paths depicted in the technique drawings served as input data for the vessel solid models generated for the SUPREEM robot motion control software.

Examinations were conducted completely by the contact technique using two WesDyne PARAGON multi-channel data acquisition systems, one interfaced to each SUPREEM robot and scanning platform.

All examinations were conducted to the maximum extent practical with the access provided and within the limitation of component geometry.

Nozzle to shell welds were examined from the vessel ID with 450 transducers. Scanning was performed both parallel and perpendicular to each weld. The scan index increment was 0.5".

Nozzle-to-shell weld examinations, conducted from the vessel ID, were performed according to the qualified Appendix VIII procedures which required the use of 45° dual element and single element transducers for volumes of metal from the clad base-metal interface to a depth of 0.6 "t" and 45° shear transducers for depths from 0.6 "t"to the OD surface. Scanning was conducted normal to and parallel to the exam volume at less than 5.5 inches per second with four directional interrogation performed wherever possible Page 2 of 4

Nozzle to shell welds were also examined from within the nozzle bores using an axial-radial examination approach using 5, 25, 35, 40 and 50 degree L wave single element transducers. Nozzle to shell weld scans from the nozzle bore were performed using increments along the bore surface to produce an effective index size in the examination area of interest of 0.25".

Ultrasonic detection scans for the outlet nozzle to safe-end welds were examined from the ID surface using 70° L- wave transducers applied four-directionally. This exam interrogated the inner 1/3 thickness volume. Axial scans were performed at a 0.25" increment and the circumferential scans were conducted at a 0.080" incremental distance. Eddy Current and Enhanced Visual techniques were also employed to examine inner surfaces of the dissimilar metal welds and the adjacent examination volumes where ID geometry presented a limitation to the detection of axial flaws as defined in the PDQS for the qualified Appendix VIII technique.

All data was digitally recorded from baseline to 100% full screen height and assessed off-line by PDI qualified Level III or Level II examiners having certification attachments issued by PDI relative to procedures PDI-ISI-254, Rev 5, FC 01, PDI-ISI-254-NZ, Rev 0, PDI-ISI-254-SE, Rev 1, and PDI-ISI-254-SI-SE Rev. 1 PDQS Rev.2.

Examination Results Automated ultrasonic examinations of the Kewaunee Unit 1 reactor vessel yielded a total of 15 recorded indications. Flaw bounding measurements for these indications were performed in accordance with procedures PDI-ISI-254-NZ Rev. 0, by qualified examiners. All recorded indications were assessed in terns of the criteria in the ASME Code Section Xl, 1998 Edition, 2000 Addenda, Article IWB-3000, Par. IWB-3500; and were found to be within the allowable limits specified with no further evaluation required.

Supplemental eddy current examinations of the outlet nozzle to safe-end welds from the nozzle bore revealed no indications.

Manual examination of the flange to shell weld revealed no indications.

Remote visual examinations of the primary outlet nozzle inner radius areas (VT-1) resulted in no recorded indications.

Page 3 of 4

All required examinations were completed per the Kewaunee Unit I Reactor Vessel Examination Program Plan.

Examination Limitations Following is a description of the weld examinations where the coverage was limited to less than 90%.

RV-W7 and RV-WI0 Outlet Nozzle to Shell Weld Due to the nozzle protrusion and vessel saddle geometry along the vessel interior, 100% of the examination was not achieved. The parallel, or TAN scans, were severely limited due to these conditions, which prevented the examination sled from indexing across the weld and heat affected zone.

The breakdowns of each method can be found in Tab I of this report.

RC-WIDM & RC-W30DM Nozzle to Safe End Weld The primary outlet Nozzle to Safe-end welds are limited in examination coverage for the detection of axial flaws (circumferential scans), as per the PDI issued PDQS document, due to the ID configurations involved with conducting examinations from the inner surfaces of piping. Areas of identified limitations were fully examined by supplemental Eddy Current techniques.

Iel mMO Page 4 of 4

ENCLOSURE 14 EXAMINATION

SUMMARY

FOR PRESERVICE INSPECTION OF REPLACEMENT REACTOR VESSEL CLOSURE HEAD 2 pages follow

KEWAUNEE NUCLEAR POWER PLANT REPLACEMENT REACTOR VESSEL CLOSURE HEAD PRESERVICE INSPECTION EXAMINATION

SUMMARY

4TH INTERVAL: 1ST PERIOD: 1ST OUTAGE 2004 INTRODUCTION A Preservice Inspection (PSI) was preformed on the Replacement Reactor Vessel Closure Head at the Mitsubishi, Kobe, Japan facility from May 13, 2004 through May 21, 2004 by WESDYNE International examination personnel.

Examinations were performed to satisfy the requirements of:

ASME Boiler and Pressure Vessel Code Section XI 1998 Edition up to and including 2000 Addenda The Preservice Inspection Program Plan located under Tab C was prepared by Kewaunee Nuclear Power Plant for the 4th Interval: 1st Period: 1st Outage as identified in the Kewaunee Nuclear Power Plant Fourth 10-Year Inservice Inspection (ISI) Program 2004-2014.

The following items were examined:

Replacement Reactor Vessel Closure Head Control Rod Drive Mechanisms EXAMINATIONS The examinations performed were in accordance with an approved Preservice Inspection Program Plan located under Tab C of the final report. Examination Procedures were approved prior to the start of examinations and certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory.

Witnessing and surveillance of the examinations were conducted by: Hartford Steam Boiler Inspection and Insurance Co. of CT.

Page 1 of 2

RESULTS Ultrasonic and Surface Examinations resulted in No Valid Flaw Indications being noted on the basis of procedure recording criteria, which are generally more restrictive than specified ASME Boiler and Pressure Vessel Code Section XI Acceptance Standards. Ultrasonic Reflectors due to Root Geometry and Beam Redirection were recorded and classified as Acceptable Non Valid Flaw Indications. Radiographs were reviewed to verify weld root configuration.

ADDITIONAL INFORMATION Prior to installation at the Kewaunee Nuclear Power Plant on November 15, 2004 Inservice Inspection Personnel attempted to perform a preliminary examination of the Replacement Reactor Vessel Closure Head Bare Metal at the Control Rod Drive Mechanisms (29), Spare Control Rod Drive Mechanisms (4), 3 Core Exit Thermocouples Assemblies and the 2 - 1" Vent Line locations. This preliminary examination was intended to identify any restrictions that would limit future visual examination of 100% of the Reactor Vessel Closure Head Bare Metal through the Shroud Access Ports (4) and corresponding Insulation Access Ports.

However, it was discovered that only one (1) of the four (4) Access Ports through both the Shroud and Insulation was available for the required future Visual Examinations. This information was documented in CAP 024082 and Work Request 04-003485 was generated to resolve this accessibility restriction during the Spring 2006 Refueling outage. Reference Tab E.

SUMMARY

A Preservice Inspection Program for the Replacement Reactor Vessel Closure Head was performed at the Mitsubishi, Kobe, Japan facility from May 13, 2004 through May 21, 2004 Examinations were performed as scheduled in the Kewaunee Nuclear Power Plant Fourth 10-Year Inservice Inspection (ISI) Program 2004-2014. There were No Recordable Indications noted for the requirements of ASME Boiler and Pressure Vessel Code Section XI 1998 Edition 2000 Addenda.

d~d4. z o o05 Phillip E. Bukes Date Engineering Programs Inservice Inspection Program Owner Page 2 of 2

ENCLOSURE 15 EXAMINATION

SUMMARY

FOR INSERVICE INSPECTION CLASS MC PROGRAM 3 pages follow

KEWAUNEE NUCLEAR POWER PLANT 1ST INTERVAL: 3RD PERIOD: 1ST OUTAGE 2004 EXAMINATION

SUMMARY

INTRODUCTION An Inservice Inspection (ISI) Program for the Class MC Reactor Building Containment Vessel was performed at the Kewaunee Nuclear Power Plant from October 9, 2004 through December 4, 2004 (Closing of GI following Refueling Outage) by Kewaunee Nuclear Power Plant and Lambert, MacGill and Thomas Inc. examination personnel.

Examinations were performed to satisfy the requirements of:

ASME Boiler and Pressure Vessel Code Section XI 1992 Edition up to and including 1992 Addenda The Inservice Inspection Program Plan located under Tab C was prepared by Kewaunee Nuclear Power Plant for the 1st Interval: 3rd Period:lst Outage as identified in the Kewaunee Nuclear Power Plant First 10-Year Inservice Inspection (ISI) Program 1996-2006.

The following items were examined for the Class MC Reactor Building Containment Vessel:

Accessible Surface Areas

Longitudinal Welds and Circumferential Welds

Sleeve To Bellows Welds

Flange Welds and Dissimilar Metal Welds

Seals, Gaskets and Moisture Barriers

Bolted Connections

Airlocks

Pressure Retaining Components EXAMINATIONS The examinations performed were in accordance with an approved Inservice Inspection Program Plan located under Tab C of the final report. Examination Procedures were approved prior to the start of examinations and certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory.

Page 1 of 3

Some of the arrangements and details of the Kewaunee Nuclear Power Plant Components and Piping Systems were designed and fabricated before ASME Boiler and Pressure Vessel Code Section XI Code requirements were established. Examinations performed were intended to examine 100% of the required surface or volume. In some cases, examinations were limited by geometric, metallurgical or design/access restrictions. In each case, the occurrence and cause of the limitation was documented. In all cases the maximum amount achievable was examined.

Witnessing and surveillance of the examinations were conducted by: Hartford Steam Boiler Inspection and Insurance Company of CT.

RESULTS Examinations resulted with the following Recordable Indications being noted on the basis of procedure recording criteria, which are generally more restrictive than specified ASME Boiler and Pressure Vessel Code Section XI Acceptance Standards.

Recordable Indications detected during the 2004 Refueling Outage are listed in Table 1 with a brief summary following. Specific data relative to all Recordable Indications and their dispositions by either corrective measures or acceptance by ASME Boiler and Pressure Vessel Code Section XI 1992 Edition up to and including 1992 Addenda Acceptance Criteria, Repair/Replacement or Evaluation are located in Tab F of the Final Report.

TABLE 1 TYPE OR LOCATION OF RECORDABLE INDICATION (RI) METHOD NO. OF RIPS Reactor Building Containment Vessel General Visual and VT-3 10 Plates Reactor Building Containment Vessel General Visual and VT-3 1 Airlock Personnel Airlock Reactor Building Containment Vessel VT-3 1 Gasket Personnel Airlock Reactor Building Containment Vessel VT-1 1 Swing Equipment Door Bolt Page 2 of 3

1. General Visual and VT-3 Indication consisting of a slight inward bulge on Plate 74 and Plate 75 was recorded. This slight inward bulge was first recorded in Fall 2001. The slight inward bulge was evaluated by Engineering and Accepted under Kewaunee Nuclear Power Plant Specification TS-1052, Addenda No.4, Item No.19 Section 10.3 -

Shell Tolerance.

2. General Visual and VT-3 Indications consisting of previously identified surface rust on Plate 64, Plate 65, Plate 66, Plate 67, and on the Plates for Penetration No. 37EN, Penetration No. 38EN and Penetration No. 38ES. This surface rust was removed, the Containment Building Ultrasonically examined to verify wall thickness, repainted and General Visual and VT-3 Examined under Work Order 03-006430.

3. General Visual and VT-3 Indication consisting of a scab type indication 3" x 4" located on Plate 158. This scab type indication was Accepted by Engineering as a Preservice Surface Imperfection.

4. General Visual and VT-3 Indications consisting of Caulking pulling away and or cracking between the concrete floor and the Personnel Airlock. These Indications were Accepted by Engineering for continued Service with a recommendation to repair and replace the caulking. Work Order 04-013198 was initiated.

5. VT-3 Indication consisting of a gasket starting to peel away on the Personnel Airlock.

The Personnel Airlock Gasket was replaced under Work Order 04-013165.

6. VT-1 Indication consisting of a missing cotter pin on the swing bolt of the Equipment Door. The missing Cotter Pin was replaced.

SUMMARY

An Inservice Inspection Program for the Class MC Reactor Building Containment Vessel was performed at the Kewaunee Nuclear Power Plant from October 9, 2004 through December 4, 2004 (Closing of G1 following Refueling Outage). Examinations were performed as scheduled in the Kewaunee Nuclear Power Plant First 10-Year Inservice Inspection (ISI) Program 1996-2006. A total of 13 Recordable Indications were detected. All Recordable Indications were Corrected or Accepted by: ASME Boiler and Pressure Vessel Code Section XI 1992 Edition up to and including 1992 Addenda Acceptance Criteria, Evaluation or Kewaunee Nuclear Power Plant Technical Specifications.

Phillip Bukes Date Engineering Programs Inservice Inspection Program Owner Page3of 3

ENCLOSURE 16 EXAMINATION

SUMMARY

FOR EDDY CURRENT OF REACTOR VESSEL THIMBLE TUBES 1 page follows

Summary of Incore Flux Thimble Tube Eddy Current Inspection During the Fall 2004 KNPP outage, the incore flux thimble tubes were eddy current inspected. The final results show essentially no degradation growth as compared to the previous inspection which was performed during the 2000 outage. Inspections of the thimble tubes are required per response to NRC Bulletin 88-09.

The following table shows the results of the 2004 eddy current examination compared to the results found during the previous examination.

Number of Thimbles Wear () 2000 2004 0-19 8 9 20-29 8 7 30-39 9 7 40-49 10 12 50-59 0 0 Note: one thimble is capped, therefore was not inspected. Values are of wear scars at the current lower nozzles only - repositioned scars have not changed in size since repositioning. Lower nozzle wear is only degradation mechanism.

Many flaw values have changed slightly due to better eddy current testing technology and more applicable use of eddy current standards (as recommended in WCAP 12866).

All damage is in the form of external wear located at the lower nozzle of the reactor fuel assemblies. Wear was not detected at any other locations (other than old wear marks of which have been repositioned during previous outages) along the thimble tubes, nor was there evidence of internal damage, cracking, or pitting. The wear at the lower nozzle is due to vibration of the tubes and does not appear to be significantly growing.

WCAP 12866 was used to assist in the evaluation of the eddy current results. The evaluation consisted of using a supplied regression equation obtained from comparing the 2000 data to the 2004 data to calculate predicted tube wear growth. The conclusion from the evaluation was that current wear growth is at a minimum and wear is not expected to exceed repair criteria within the next 5 years of service time.

The thimbles will be eddy current tested within 5 years, currently scheduled for KR-30, per NRC Bulletin 88-09 KNPP response.

~/ 01- D3-bA'o Brent Dunn / Date HX Eddy Current Program Owner

ENCLOSURE 17

SUMMARY

OF EXAMINATIONS THAT WERE LIMITED BY GEOMETRIC, METALLURGICAL, OR DESIGNIACCESS RESTRICTIONS AND ASSOCIATED DATA SHEETS (62 TOTAL) 65 pages follow

SUMMARY

OF EXAMINATIONS THAT WERE LIMITED BY GEOMETRIC, METALLURGICAL, OR DESIGN/ACCESS RESTRICTIONS 2004

SUMMARY

OF LIMITATIONS FOR 3RD OUTAGE, 3RD PERIOD, 3RD INTERVAL INSERVICE INSPECTION Year Component Method of % Recorded as Not Year Identification Examination Examined and Limitation Reactor vessel shell to flange 25.56% single side coverage 2004 weld weld RV-W1vese UT 46.98% two direction coverage:

Shell to flange configuration 2004 Reactor vessel lower shell to UT 13.86% two direction coverage:

head lowerweld RV-W4 4 lower core supports Reactor vessel inlet nozzle to 7.56%: Safety injection and 2004 Rell w shell weld elRV-W6 inlet UT inlet nozzlenozzle protrusion saddle geometryand 2004 Reactor nozzle tovessel safety shell weld injection RV-W8 UT 9.96%: Safety injection nozzle protrusion Reactor vessel inlet nozzle to 7.56%: Safety injection and 2004 Rell w shell weld elRV-W9nozzle inlet UT inlet nozzle protrusion saddle geometryand Reactor vessel safety injection U11.69% (two sided coverage) 2004 nozzle to shell weld RV-Win1 UT safety injection nozzle

_____ ___________________ __________protrusion

2004

SUMMARY

OF LIMITATIONS FOR 1ST OUTAGE, 1ST PERIOD, 4TH INTERVAL INSERVICE INSPECTION Component Method of % Recorded as Not Year Identification Examination Examined and Limitation 2004 Reactor vessel outlet nozzle to UT 22.66%: Nozzle protrusion and shell weld RV-W7 vessel saddle geometry 2004 Reactor vessel outlet nozzle to UT 22.66%: Nozzle protrusion and shell weld RV-W1O U vessel saddle geometry Pressurizer circumferential 4.6%: 4 - 2.5" x 2.5" welded 2004 weld P-W3 UT pads Less than 2%: 4 - welded lugs 2004 weld P-W5 UT - 2.5" x 2.5" and 2 - 3/4" drain w P lines Replacement steam generator 6.3%: Integrally welded 2004 1A nozzle inside radius UT attachment section SG-IR25 Replacement steam generator 24.6%: Integrally welded 2004 lA integrally welded MT attachment configuration

_____attachment SG-1 A-23A ____________________

Residual heat exchanger 1A 71.72%: Integrally welded 2004 shell circumferential weld UT attachments and nozzle AHRS1 -Wi configurations Residual head exchanger 1A 20.7%: Integrally welded 2004 integrally welded attachment PT attachment configuration

_ __ AHRSI-SW 1 _ _ _ _ _ _ _ _ _ _ _

Regenerative heat exchanger 2004 tube sheet to shell weld UT 16%: Rigid support clamp ARG-W10 Charging pump pulsation 2004 dampener APD-1 A head UT 15%: Welded name plate circumferential weld APD-1A-W1 Safety injection pump 1A 14.6%: Integrally welded 2004 integrally welded attachment MT attachment configuration 2004_ APSI-1 A-Si MTatac ___________rtio Safety injection pump 1A 14.6%: Integrally welded 2004 integrally welded attachment MT attachment configuration Safety injection pump 1B 14.6%: Integrally welded 2004 integrally welded attachment MT attachment configuration APSI-1 B-S2 2004 Circumferential weld PS-W44 UT 9.1%: Elbow intradose on 3" pressurizer spray 2004 Circumferential weld PS-W48 UT 8.65%: Elbow intradose on 3" pressurizer spray 2004 Circumferential weld Sl-W429 UT 50%: Valve to pipe on 6" safety injection configuration

2004

SUMMARY

OF LIMITATIONS FOR 1ST OUTAGE, 1ST PERIOD, 4TH INTERVAL

_INbtKVILt IMblM; I 1UN tLCUN I INUItU)

Year Component Method of % Recorded as Not Identification Examination Examined and Limitation 2004 Circumferential weld SI-W234 UT 9.1%: Elbow intradose on 3" safety injection 2004 Circumferential weld SI-W262 UT 9.1%: Elbow Intradose on 3" safety injection_______________

2004 Integrally welded attachment PT 4.2%: Welded I.D. plate SI-H17A on 3" safety injection 2004 Circumferential weld RC-W60 UT 50%: Branch nozzle on 6" reactor coolant configuration 2004 Circumferential weld SI-W283 UT 9.1%: Elbow Intradose on 3" safety injection ______________

2004 Circumferential weld Sl-W284 UT 9.1%: Elbow intradose on 3" safety injection 2004 Circumferential weld Sl-W51 UT 13.33%: 6" x 4" reducer on 6" safety injection configuration Circumferential nozzle to safe 50%: Safe end to elbow 2004 end weld PR-W27 on 6" UT configuration pressurizer relief Integrally welded attachment 8.0%: Configuration of 2004 CS-H7 on 8" containment PT integrally welded attachment

-spray Circumferential weld 50%: Elbow to valve 2004 ICS-Wl 80 on 6" containment UT configuration spray configuration Circumferential weld 50%: Valve to pipe 2004 ICS-W181 on 6" containment UT configuration spray configuration Circumferential weld 2004 ICS-W103 on 6" containment UT 9.3%: Welded l.D. plate spray Circumferential weld 50%: Valve to pipe 2004 RHR-W419 on 6" residual UT configuration heat removal 2004 Circumferential weld FW-W61 UT 1.8%: Adjacent branch on 16" feedwater connection configuration 2004 Circumferential weld FW-W61 MT 3.6%: Adjacent branch on 16" feedwater connection configuration Circumferential branch 2004 connection weld RC-W22BC UT 50%: Branch connection on 6" reactor coolant configuration

.1 REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Kewaunee Unit _

WELD NO. RV-W1 COMPONENT Shell to Flange Weld LIMITATIONS: NO L YES [I 74.44 % Complete (Single Sided Coverage)

See Coverage Breakdown Sheet RESULTS NO. OF INDICATIONS N/A NI X STATUS N/A RI EXAM DOCUMENTATION INDICATION DOCUMENTATION ETI PARAGON ANALYSIS LOG =ASSESSMENT SHEET

[flPARAGON ACQUISITION LOG [ PARAGON HARD COPY EKISCAN PRINT OUT =OTHER (Specify) 07ICOVERAGE BREAKDOWN Comments:. See figures 1 and 2 for limitations Analyst / u Date: e

R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Kewaunee WesDyne WELD NO. RV-W1 International COMPONENT Shell to Flange Weld BEAM ANGLE BREAK DOWN 5Ser4 SINGLE SIDE igl BE. DIETO. COVERAGE 5LDa rmSa u BEAM DIRECTION 45 Shear 45 L Single 45 L Dual From Seal Surf.

WELD VOLUME WELD (VOLUME WELD VOLUME WELD (VOLUME Perpendicular 100.00 100.00 88.93 54.55 0.00 26.05 100.00 91.00 Parallel 100.00 57.64 100.00 57.64 100.00 57.64 AVERAGE 89.41 75.28 45.92 95.50 Comments: .

Coverage estimates for the shell PDI Exam are based on single side coverage.

Combined Perp. 70.07 A, Combined Para. 78.82 Combined Average 74.44 Analyst /f Date -44.... 'I

"-I I-

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Kewaunee Unit _

WELD NO. RV-Wl COMPONENT Shell to Flange Weld LIMITATIONS: NO Em YES [X3 53.02 % Complete (Two Directions)

See Coverage Breakdown Sheet RESULTS NO. OF INDICATIONS N/A NI X STATUS N/A RI EXAM DOCUMENTATION INDICATION DOCUMENTATION mX PARAGON ANALYSIS LOG E]ASSESSMENT SHEET

[II PARAGON ACQUISITION LOG = PARAGON HARD COPY EKI SCAN PRINT OUT =OTHER (Specify) 111COVERAGE BREAKDOWN Comments: See figures 1 and 2 for limitations Analyst i> Date: i';'1

R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Kewaunee WesDyne WELD NO. RV-W1 International COMPONENT Shell to Flange Weld BEAM ANGLE BREAK DOWN TWO DIRECTIONAL COVERAGE BEAM DIRECTION 45 Shear 45 L Single 45 L Dual From Seal Surf.

WELD lVOLUME -WELD lVOLUME WELD IVOLUME WELD iVOLUME Perpendicular 0.00 0.00 0.00 3.78 0.00 22.92 100.00 91.00 Parallel 100.00 57.64 100.00 57.64 100.00 57.64 AVERAGE 39.41 40.35 45.14 95.50 Comments: Coverage estimates for the shell PDI Exam are based on 2 directional coverage.

Combined Perp. 27.21 _f Combined Para. 78.82 Combined Average 53.02 Analyst s

?A lJI Date

-21.44 1 Top Parallel 5 Top Perp

) Bott Parallel Bott Perp 65.91 RV-WI Figure 1

.1

.25 Figure 2 RV-Wi

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Kewaunee Unit 1 WELD NO. RV-W4 COMPONENT Lower Shell to Lower Head LIMITATIONS: NO f[X YES j 90.82 % Complete (One Direction)

See Coverage Breakdown Sheet RESULTS NO. OF INDICATIONS N/A NI X STATUS N/A RI _ _ _

EXAM DOCUMENTATION INDICATION DOCUMENTATION EKI PARAGON ANALYSIS LOG FEIASSESSMENT SHEET W73 PARAGON ACQUISITION LOG = PARAGON HARD COPY IIZ SCAN PRINT OUT E=OTHER (Specify) 3JCOVERAGE BREAKDOWN Comments: See figure 1 for limitations Analyst Date: J"/1

R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Kewaunee WesDyne WELD NO. RV-W4 International COMPONENT Lower Shell to Lower Head BEAM ANGLE BREAK DOWN ONE DIRECTIONAL COVERAGE BEAM DIRECTION 45 Shear 45 L Single 45 L Dual I

_ WELD (VOLUME WELD (VOLUMEj WELD VOLUMEl WELD IVOLUME Perpendicular 100.00 100.00 83.56 88.35 79.45 86.04 Parallel 100.00 92.55 100.00 92.55 79.45 87.86 _ _

AVERAGE 98.14 91.12 83.20 Comments: Coverage estimates for the shell PDI exam are based on I directional coverage.

Combined Perp. 89.57 ,/ Combined Para. 92.07 Combined Average 90.82 Analyst /___ AI- ,

Date i/djk)UJ/

(I Cy /

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Kewaunee Unit i WELD NO. RV-W4 COMPONENT Lower Shell to Lower Head LIMITATIONS: NO Fl YES z 86.14 % Complete (Two Directions)

See Coverage Breakdown Sheet RESULTS NO. OF INDICATIONS N/A NI X STATUS N/A RI EXAM DOCUMENTATION INDICATION DOCUMENTATION KIxPARAGON ANALYSIS LOG FLASSESSMENT SHEET W7XPARAGON ACQUISITION LOG =PARAGON HARD COPY TUSCAN PRINT OUT =OTHER (Specify)

EZICOVERAGE BREAKDOWN Comments: See figure 1 for limitations Ans -

. S lAnalyst / // r Date: 1 g/

R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Kewaunee WesDyne WELD NO. RV-W4 International COMPONENT Lower Shell to Lower Head BEAM ANGLE BREAK DOWN TWO DIRECTIONAL COVERAGE BEAM DIRECTION 45 Shear WELD VOLUME ELD 45 L Single VOLUME WVE 45 L Dual OLUME

( WELD IVOLUME Perpendicular 79.45 80.58 79.45 79.53 79.45 82.74 Parallel 100.00 92.55 100.00 92.55 79.45 87.86 AVERAGE 88.15 87.88 82.38 Comments: Coverage estimates for the shell PDI exam are based on 2 directional coverage.

Combined Perp. 80.20 Combined Para. 92.07 Combined Average 86.14 Mini, t,;

Analyst yr1 Date ///1 :-/';'

1:Y ..

LI/

RV-W4 3* TOP PERP 80.5 BOTT PARALLEL RV--W5 68' Figure 1

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Kewaunee Unit 1 WELD NO. RV-W6 COMPONENT Inlet Nozzle to Shell @ 328.50 LIMITATIONS: NO jIg YES [TJ 92.44 % Complete See Coverage Breakdown Sheet See Figures 1 & 2 RESULTS NO. OF INDICATIONS 5 NI STATUS Code Allowable RI X EXAM DOCUMENTATION INDICATION DOCUMENTATION E7i PARAGON ANALYSIS LOG [R]ASSESSMENT SHEET 3PARAGON ACQUISITION LOG EKII PARAGON HARD COPY 3xI SCAN PRINT OUT =OTHER (Specify)

WCOVERAGE BREAKDOWN Comments:

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular.

and the Tan Scan (parallel). Limitation is due to the Safety Injection nozzle, outlet protrusion, and Nozzle Saddle geometry on the inner surface of the reactor vessel limiting the required scan path.

Analyst V Date:

R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Kewaunee WesDyne WELD NO. RV-W6 International COMPONENT Inlet Nozzle to Shell @ 328.50 BEAM ANGLE BREAK DOWN BEAM DIRECTION 45 Shear 45 L Single 45 L Dual Combined Bore/Star WELD I VOLUME WELD I VOLUME WELD I VOLUME WELD ! VOLUME TAN Scan Parallel 88.87 82.46 100.00 90.81 100.00 100.00 Combined Bore&Star Perpendicular I___89.37 93.03 AVERAGE 85.66 95.40 100.00 91.20 Comments: Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Limitation is due to the Safety Injection nozzle, outlet protrusion, and Nozzle Saddle geometry on the inner surface of the reactor vessel limiting the required scan path.

Combined Perp. 91.20 Combined Para. 93.69 Combined Average 92.44 Analyst /-.} , '-- Date / / /, /

Y-II U--

3I Inlet Outl et Noz z) e Nlozzl e 1.59-vVyly-MIM'Iffiffft ROMMM" Inlet Nozzle Star Scan Limitation due to SI Nozzle and Outlet Nozzle Protrusion (Nozzle Boss)

Figure 1 RV-W6 I

lI 0

Limitation clue to salodle geometry For bore star andl tan scans Figure 2 RV-W6

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Kewaunee Unit I WELD NO. RV-W8 COMPONENT Safety Injection Noz-Shell @108.5° LIMITATIONS: NO [] YES [X] 90.04 %Complete (single sided coverage)

See Coverage Breakdown Sheet RESULTS NO. OF INDICATIONS 3 NI STATUS Code Allowable RI X EXAM DOCUMENTATION INDICATION DOCUMENTATION 3-iJ PARAGON ANALYSIS LOG REKASSESSMENT SHEET 3KIIPARAGON ACQUISITION LOG LKI PARAGON HARD COPY 3Fl SCAN PRINT OUT CIOTHER (Specify)

Fl COVERAGE BREAKDOWN Comments:

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular.

and the Tan Scan (parallel). Figure 1 depicts the limitation.

Analyst lDate: /1 : 6Y

- - l--I R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Kewaunee WesDyne WELD NO. RV-W8 International COMPONENT Safety Injection Noz-Shell @108.5' BEAM ANGLE BREAK DOWN SINGLE SIDED COVERAGE BEAM DIRECTION 45 Shear 45 L Single 45 L Dual Combined Bore/Star WELD T VOLUME WELD VOLUME WELD VOLUME WELD [VOLUME TAN Scan . lll ___

Parallel 100.00 51.00 100.00 65.36 100.00l 64.11 l }_ _

Combined Bore&Star Perpendicular 100.00 100.00 AVERAGE 75.50 82.68 82.06 100.00 Comments: Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, . _

and the Tan Scan (parallel). Figure 1 depicts the limitation.

Combined Perp. 100.00 Combined Para. 80.08 Combined Average 90.04 Analyst XCR.-/-'I-DateDate/I/

r- -,

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Kewaunee Unit I WELD NO. RV-W8 COMPONENT Safety Injection Noz-Shell @108.5° LIMITATIONS: NO :] YES X 90.04 %Complete (two sided coverage)

See Coverage Breakdown Sheet RESULTS NO. OF INDICATIONS 3 NI STATUS Code Allowable RI X EXAM DOCUMENTATION INDICATION DOCUMENTATION FX1J PARAGON ANALYSIS LOG REIIASSESSMENT SHEET 3PARAGON ACQUISITION LOG WIPARAGON HARD COPY EXiJSCAN PRINT OUT =OTHER (Specify)

WICOVERAGE BREAKDOWN Comments:

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular.

and the Tan Scan (parallel). Figure 1 depicts the limitation.

Analyst . Date: e

R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Kewaunee WesDyne WELD NO. RV-W8 International COMPONENT Safety Injection Noz-Shell @108.50 BEAM ANGLE BREAK DOWN TWO SIDED COVERAGE BEAM DIRECTION 45 Shear 45 L Single 45 L Dual l Combined Bore/Star WELD I VOLUME WELD VOLUME WELD l VOLUME _WELD I VOLUME TAN Scan _____

Parallel 100.00 51.00 100.00 65.36 100.00 64.11 Combined Bore&Star Perpendicular 100.00 100.00 AVERAGE 75.50 82.68 82.06 100.00 Comments: Coveragecalculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Figure 1 depicts the limitation.

Combined Perp. 100.00 Combined Para. 80.08 Combined Average 90.04 Analyst 'I

'4--.

.Date // / 3 ( ' -

i7 '

Figure 1 Tan/Star Coverage IMlustration of the Safety Injection Nozzle Protrusion Linitation

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Kewaunee Unit 1 WELD NO. RV-W9 COMPONENT Inlet Nozzle to Shell @ 148.50 LIMITATIONS: NO CZ YES EJ 92.44 % Complete See Coverage Breakdown Sheet See Figures 1 & 2 RESULTS NO. OF INDICATIONS 2 NI STATUS Code Allowable RI X EXAM DOCUMENTATION INDICATION DOCUMENTATION EXl PARAGON ANALYSIS LOG WEASSESSMENT SHEET EI PARAGON ACQUISITION LOG EX PARAGON HARD COPY EEJ SCAN PRINT OUT =OTHER (Specify)

EKI COVERAGE BREAKDOWN Comments:

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Limitation is due to the Safety Injection nozzle, outlet protrusion, and Nozzle Saddle geometry on the inner surface of the reactor vessel limiting the required scan path.

Analyst X Date:

R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Kewaunee WesDyne WELD NO. RV-W9 International COMPONENT Inlet Nozzle to Shell @ 148.50 BEAM ANGLE BREAK DOWN BEAM DIRECTION [ 45 Shear 45 L'Single [ 45 L Dual [Combined Bore/Star WELD VOLUME WELD VOLUME VOLUM VOLUME WELD VOLUME TAN Scan I

Parallel 88.87 82.46 100.00 90.81 100.00 100.00 Combined Bore&Star Perpendicular 89.37 93.03 AVERAGE 85.66 95.40 100.00 91.20 Comments: Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Limitation is due to the Safety Injection nozzle, outlet protrusion, and Nozzle Saddle geometry on the inner surface of the reactor vessel limiting the required scan path.

I Combined Perp. 91.20 Combined Para. 93.69 Combined Average 92.44 Analyst Hi} 1 /C Date /I '/ . I

(-I

. -.1 .--

3I -fInlet Outl et Noz z) e Nozzle 131..5 9-s-1000walmr MOM==

Inlet Nozzle Star Scan Limitation due to SI Nozzle and Outlet Nozzle Protrusion (Nozzle Boss)

Figure 1 RV-W9

0 Lirmi+/-ation ldue to sacoldte geometry F or bore star and tan scans Figure 2 RV-W9

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Kewaunee Unit I WELD NO. RV-WI I COMPONENT Safety Injection Noz-Shell @288.5° LIMITATIONS: NO C YES FTJ 88.31 %Complete (two sided coverage)

See Coverage Breakdown Sheet RESULTS NO. OF INDICATIONS 1 NI STATUS Code Allowable RI X EXAM DOCUMENTATION INDICATION DOCUMENTATION EllPARAGON ANALYSIS LOG [REAASSESSMENT SHEET E[lPARAGON ACQUISITION LOG El PARAGON HARD COPY M SCAN PRINT OUT =I] OTHER (Specify)

[El COVERAGE BREAKDOWN Comments:

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular.

and the Tan Scan (parallel). Figure 1 depicts the limitation.

Analyst ;.x7fZ. . Date: 11)3

R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Kewaunee WesDyne WELD NO. RV-WI 1 International COMPONENT Safety Injection Noz-Shell @288.50 BEAM ANGLE BREAK DOWN TWO SIDED COVERAGE BEAM DIRECTION 45 Shear 45 L Single l 45 L Dual Combined Bore/Star N WELD VOLUME WELD l VOLUME l WELD VOLUME WELD VOLUME TAN Scan Parallel 100.00 51.00 100.00 65.36 100.00 64.11 Combined Bore&Star Perpendicular 100.00 93.09 AVERAGE 75.50 82.68 82.06 96.54 Comments: Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Figure 1 depicts the limitation.

Combined Perp. 96.54 Combined Para.

80.08 Combined Average 88.31 Analyst i "ti./ A ' Date

/1

_~~~ I i

I

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Kewaunee Unit 1 WELD NO. RV-W11 COMPONENT Safety Injection Noz-Shell @288.50 LIMITATIONS: NO [ YES Ed 90.04 % Complete (single sided coverage)

See Coverage Breakdown Sheet RESULTS NO. OF INDICATIONS 1 NI STATUS Code Allowable Ri X EXAM DOCUMENTATION INDICATION DOCUMENTATION FIIZI PARAGON ANALYSIS LOG - XWASSESSMENT SHEET rnPARAGON ACQUISITION LOG EJPARAGON HARD COPY

[X]SCAN PRINT OUT =OTHER (Specify)

[K]COVERAGE BREAKDOWN Comments:

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Figure 1 depicts the limitation.

Analyst,, &'5 Date:

R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Kewaunee WesDyne WELD NO. RV-W1 1 International COMPONENT Safety Injection Noz-Shell @288.50 BEAM ANGLE BREAK DOWN SINGLE SIDED COVERAGE BEAM DIRECTION 45 Shear 45 L Single 45 L Dual Combined Bore/Star

WELD jVOLUME WELD VOLUME WELD VOLUME WELD l VOLUME TAN Scan Parallel 100.00 51.00 100.00 65.36 100.00 64.11 Combined Bore&Star _

Perpendicular _-= _ 100.00 100.00 AVERAGE 75.50 82.68 82.06 100.00 Comments: Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Figure1 depicts the limitation.

Combined Perp. 100.00 Combined Para. 80.08 Combined Average 90.04 Analyst /A" A Date )/'./b6-/

' J '

43o sheQt zone &

RV-Wi1 Figure 1 Tan/Star Coverage Illustration of the Safety Injection Nozzle Protrusion Limitation

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Kewaunee Unit 1 WELD NO. RV-W7 COMPONENT Outlet Nozzle to Shell @ 28.5° LIMITATIONS: NO D YES 3 77.34 % Complete See Coverage Breakdown Sheet RESULTS NO. OF INDICATIONS 10 NI STATUS Code Allowable RI X EXAM DOCUMENTATION INDICATION DOCUMENTATION

[K] PARAGON ANALYSIS LOG WEASSESSMENT SHEET 3TIPARAGON ACQUISITION LOG [XI] PARAGON HARD COPY EIl SCAN PRINT OUT [ OTHER (Specify)

WECOVERAGE BREAKDOWN Comments:

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Limitation is due to the outlet protrusion and saddle geometry of the nozzle along the inside surface. See Figure 1 Analyst vt,,_z ' Date:

I/;

R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Kewaunee WesDyne WELD NO. RV-W7 International COMPONENT Outlet Nozzle to Shell @ 28.50 BEAM ANGLE BREAK DOWN BEAM DIRECTION 45 Shear 45 L Single 45 L Dual Combined Bore/Star WELD [ VOLUME WELD VOLUME WELD I VOLUME WELD I VOLUME TAN Scan Parallel 51.97 28.52 58.93 56.90 67.27 69.79 Combined Bore&Star Perpendicular _99.68 I__ 98.57 AVERAGE 40.24 57.91 68.53 99.12 Comments: Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Limitation is due to the outlet protrusion and saddle geometry of the nozzle along the inside surface. See Figure 1 Combined Perp. 99.12 N Combined Para. 55.56 Combined Average 77.34 I

Anal AnlDate > /.'

(

Limitation: Noz2,1e protrusion and vessel sadcdle geometry Figure 1 RV-W7

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME Kewaunee Unit 1 WELD NO. RV-W10 COMPONENT Outlet Nozzle to Shell @ 208.5° LIMITATIONS: NO U YES TJ 77.34 % Complete .

See Coverage Breakdown Sheet RESULTS NO. OF INDICATIONS 5 NI STATUS Code Allowable RI X EXAM DOCUMENTATION INDICATION DOCUMENTATION LKI PARAGON ANALYSIS LOG EIASSESSMENT SHEET LKI PARAGON ACQUISITION LOG Fl PARAGON HARD COPY LKISCAN PRINT OUT E] OTHER (Specify)

WCOVERAGE BREAKDOWN Comments:

Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Limitation is due to the outlet protrusion and saddle geometry of the nozzle along the inside surface. See Figure 1 A

Analyst .-- Date: / ISk,

R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME Kewaunee WesDyne WELD NO. RV-W10 International COMPONENT Outlet Nozzle to Shell @ 208.50 BEAM ANGLE BREAK DOWN BEAM DIRECTION 45 Shear l 45 L Single 45 L Dual Combined Bore/Star WELDIVOLUME l_WELD lVOLUMEjWELD JVLUME WELD VOLUME T A N S can _ l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Parallel 51.97 28.52 58.93 56.90 67.27 69.79 Combined Bore&Star Perpendicular 99.68 98.57 AVERAGE 40.24 57.91 68.53 99.12 Comments: Coverage calculation is based on the Bore and Star scan (combined) as perpendicular, and the Tan Scan (parallel). Limitation is due to the outlet protrusion and saddle geometry of the nozzle along the inside surface. See Figure I Combined Perp. 99.12 -

Combined Para. 55.56 Combined Average 77.34 C11 Analyst I t ?~

Date At;/ 'if/l

Limqitationl: Nozzle protrusion anld vessel sacddle geometry Figure 1 RV-W1O

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: PRr5SUVR Z PZ, DRAWING NO.: M- 120 -

COMPONENT IDENTIFICATION: P-w3 - PROCEDURE: OPjK. 0i REVISION:

ULTRASONIC: X LIQUID PENETRANT: MAGNETIC PARTICLE: VISUAL:

EXAMINER: ARLxji I iT DATE: II/g/o/

LEVEL EXAMINER: Tosl A&iS4jt 117 DATE: :tt /OA /

LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

SCAN 5 & 2 LIMITED TO 92.5" OF REQUIRED EXAMINATION LENGTH (97.0"),

DUE TO 4,2.6" x 2.5" WELDED PADS.

PERCENTAGE OF REDUCED EXAMINATION CODE COVERAGE: 4.6 %

KEWAUNEE NUCLEAR 7

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DA TE : & JE Z I , 2 O '

POWER PLANT REVIEW:4 ki t.AW4:&°Z_

AUTHORIZED NUCLEAR . A-,

INSERVICE INSPECTOR REVIEW: .ge DATE:_________

WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: Peessoeozoe DRAWING NO.:. tm- 12.o 0 COMPONENT IDENTIFICATION: P-ws5 PROCEDURE: NerP-1S0' REVISION: B ULTRASONIC: Y LIQUID PENETRANT: __ MAGNETIC PARTICLE: __ VISUAL:

EXAMINER: A4Le, iJscas e( - DATE: llp2zhotq LEVEL EXAMINER: 1 O t oualyJS H i - DATE: I Dz2q faos 7I LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

REDUCED EXAMINATION COVERAGE LESS THAN 2%

4 LUGS 2 112" X 21/2" 3 FROM CENTERLINE OF WELD.

(2) 3/4" DRAIN LINES 7" FROM CENTERLINE OF WELD.

KEWAUNEE NUCLEAR RS a POWER PLANT REVIEW: i dt 9 6. /4Ufi- DATE____ _,.

AUTHORIZED NUCLEAR % 4 _

INSERVICE INSPECTOR REVIEW: ___________ A d DATE: _______

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: R6PLA J&1..,J1 6TAM &Pe4DRS SC,- (A xmt 9CSG-- IB DRAWING NO.: M-IZol PROCEDURE: ELP- .4&'4 lREVISION:

COMPONENT IDENTIFICATION: l R2* fB ULTRASONIC: X LIQUID PENETRANT:__ MAGNETIC PARTICLE:___ VISUAL: _ _

EXAMINER: ARgLrz/ *JS-rj6 at Jr DATE: t c2{710q t LEVEL EXAMINER: sod WNStl(eQUW-- 4, i, --- a DATE: Jo/2.7 /aq

'l LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

EXAM NATION LIMITED DUE TO CONFIGURATION OF COMPONENT SUPPORT. PERCENTAGE OD REDUCED COVERAGE: 6.3% .

KEWAUNEE NUCLEAR / -

POWER PLANT REVIEW: fft4 . DATE: VJoV( 400Y AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: -_

D ______ DATE:______

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: RE6?LA CEfASES Sr-A/4/ 6,A6ENhAWqf S6 - 1/4 ANZ) 56-/B DRAWING NO.: 1S - /2,/

COMPONENT IDENTIFICATION: S& -/A -2 JA PROCEDURE: ,VAEP-/fia7 REVISION: A ULTRASONIC:.. LIQUID PENETRANT: MAGNETIC PARTICLE: X VISUAL:

EXAMINER: TOJi WAM1/3uA' ,, P_ -

z T77 LEVEL DATE: // D Y EXAMINER: 1/A DATE: N/A LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

EXAMINATION LIMITED DUE TO CONFIGURATION OF COMPONENT SUPPORT PERCENTAGE OF REDUCED EXAMINATION CODE COVERAGE: 24.6%

KEWAUNEE NUCLEAR by, POWER PLANT REVIEW:- - p& 7ArYAJ DATE:: ANw.30 AUTHORIZED NUCLEAR )X e INSERVICE INSPECTOR REVIEW: - B DATE: . -0

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: 9*</aZ..1A2 S~'E.4 r t4A'q

, (/ -/A e-DRAWINGNO.: A/- /2v7 COMPONENT IDENTIFICATION: AP9f,/ - WI PROCEDURE:W/EP /d/ REVISION: A ULTRASONIC: X.-.. LIQUID PENETRANT:.- MAGNETIC PARTICLE:.. VISUAL:

EXAMINER:. '4ov'/ i~ ° m- DATE: L0 -L9 0- Y LEVEL EXAMINER: _Joa Wv. f 4 A 'v &-' , DATE: /'// E/0 P-

.1LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

NO SCAN 5, SCAN227. 8 LIMITED TO ACCESSIBLEAREA OF DOWNSTREAM SIDE OF WELD ONLY, DUETOHEAT EXCHANGER SUPPORTS & NOZZLE CONFIGURATIONS.

CODE REQUIRED EXAMINATION VOLUME: 25.34 sqJn. /VOLUME OBTAINED 7.181 sq.in.

REDUCED EXAMI NATION CO DEC OVERAGE: 71.72%

KEWAUNEE NUCLEAR POWER PLANT REVIEW: ag DATE: 6-d&hk-3 20L AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW DATE:________

WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEMORCOMPONENT: RKS/1vAL iH-EA-r Ex>cl/-AA/(.Eks AHrsl-IA.AIIAHRSz- 18 DRAWING NO.: M 7 COMPONENT IDENTIFICATION: AMRS I- SW/ PROCEDURE: /NEP-/ht/gREVISION: A ULTRASONIC:___ LIQUID PENETRANT: X MAGNETIC PARTICLE: __ VISUAL:

EXAMINER:.T A..Lp.. tJ (I ,Q 7-r DATE: I/oA/q/o d1 LEVEL EXAMINER: N/A I DATE: ZA LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

EXAMINATION LIMITED DUE TO CONFIGURATION OF SUPPORT.

PERCENTAGE OF REDUCED EXAMINATION CODE COVERAGE: 20.7%

KEWAUNEE NUCLEAR n.4 4pJ POWER PLANT REVIEW:- fre dX& 7 & aJ DATE: -O-O,3aY AUTHORIZED NUCLEAR i IINSERVICE INSPECTOR REVIEW: - FI7t DATE: /I'e V

. .0

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: Heeew e-,ec iHA-vet7c Age, DRAWING NO.: M 1 aS2 COMPONENT IDENTIFICATION: ARO -lWI PROCEDURE: glep -ir tU REVISION: A ULTRASONIC: . LIQUID PENETRANT: _ MAGNETIC PARTICLE: _ VISUAL:

EXAMINER:_ DATE: /e /z7/o'-<

LEVEL EXAMINER: AJA DATE: iJA LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

SCAN 2 LIMITED TO WELD PLUS 0.70" BASE METAL (SCAN AREA) DUE TO RIGID SUPPORT CLAMP.

DECf12JTAf'Ir: n% RPfUtCED FYAMINATION COVERAGE: 16%

KEWAUNEE NUCLEAR .0 2J/a,i&1f3.;o0v DAT POWER PLANT REVIEW:'-1~-t//) £o. f(w4' ______

AUTHORIZED NUCLEAR D z . L INSERVICE INSPECTOR REVIEW: 57r, / DATE: /_________

WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: tLrg 9 imnq 7r 2IsJorndampener A4P-i4

- 0 -4 l DRAWING NO.: M - 141q COMPONENT IDENTIFICATION: Il VI.2a PROCEDURE: S-6J*. A REVISION:

ULTRASONIC: LIQUID PENETRANT: __ MAGNETIC PARTICLE: __ VISUAL:

EXAMINER: ,OLI/lS a nLthe fg4l- LEVEL zi::c DATE:

EXAMINER: tJo0s0e _ a -/-rrA DATE: /.) - //- C) 4 LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

Welded name plate located approximately 3116" downstream from centerline of weld APD-1A-1.

3.0" X 5 3/16" welded name plate limits 0 degree long. ,45 and 60 degree shear wave coverage.

Percentage of Reduced Examination Code Coverage: 8.5%.

Percentage of Reduced Examination Procedural Coverage: 15%.

KEWAUNEE NUCLEAR /, .

POWER PLANT REVIEW:. .cja_ DATE: 002 AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: _ DATE:_________

WISCONSIN PUBLIC SERVICE CORPORATION RV ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEMORCOMPONENT: Ste-.v1Ifc.4; v 4, APSLIA AdA APS'- 1 3 DRAWING NO.: M 1707 _

A Psx- ImA I COMPONENT IDENTIFICATION: Aisix. iA-s PROCEDURE: NEP-mO7 REVISION: A ULTRASONIC: __ LIQUID PENETRANT:___ MAGNETIC PARTICLE: X VISUAL:

EXAMINER- Eiohb,. By11...

%J 7 Jr DATE: mt)-l5-oq LEVEL EXAMINER: a°'.

G.eCube;se *z? DATE: - Jot

/

LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

Exanination limited due to configuration of support.

Limitation Length: 6" Reduced exanination Code Coverage 14.6i KEWAUNEE NUCLEAR POWER PLANT REVIEW:

X

, C:, Av DATE:_____ 5 _;c_

AUTHORIZED NUCLEAR I.NSERVICE INSPECTOR REVIEW: apt DATE: __________

WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: -

l-Sca.e. 7*-0O PgeMj4e,-Z _

DRAWING NO.: Is m _- 7+ - I COMPONENT IDENTIFICATION: PC-W ' PROCEDURE: MEP -ss Wy REVISION:a4f& &o ULTRASONIC: X LIQUID PENETRANT:_ MAGNETIC PARTICLE: _ VISUAL:

EXAMINER: 'Top la1s-haoaj DATE: Io /2 - /2 "'i 7- LEVEL EXAMINER: Lc.mt- acowA'e- lll&rtz"l -- -p DATE: I D 27 Aaa LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

SCAN 2 LIM ITED TO 7.0" OF REQUIRED 11.0" CIRCUMFERENCE DUE TO CONFIGURATION OF ELBOW INTRADOSE.

PERCENrAGE OF REDUCED EXAMINATIONCOVERAGE :9.1%

HitS 4 KEWAUNEE NUCLEAR POWER PLANT REVIEW: a /s /AIC DATE: 6A&a8oo0 AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW:_ /o -a PkTC /

DATE:.

-- Iv

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT - ----

2u 0 0 -

-'A.5 - .. I- f DRAWING NO.: ascim-8 S4

-1 -1 COMPONENT IDENTIFICATION: Ps. Iqs PROCEDURE: A1e- -/sIf REVISION:-&.U"6e ULTRASONIC: X LIQUID PENETRANT:.. MAGNETIC PARTICLE:__ VISUAL:

EXAMINER: Ar WwAS&4tj DATE: (0/27 /2oc/

LEVEL EXAMINER: LoweLL acttsj DATE: I /I7 /2 oo LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

SCAN 2 LI ITED TO 9.0" OF REQUIRED 11.0" CIRCUMFERENCE DUE TO CONFIGURATION OF ELBOW INTRADOSE.

PERCENTAGE OF REDUCED EXAMINATION COVERAGE: 8.65%

' P _W48 KEWAUNEE NUCLEAR POWER PLANT REVIEW: ____ __

- - ____ _ DATE: (9eA .28A04o '

I I AUTHORIZED NUCLEAR D d INSERVICE INSPECTOR REVIEW: 7- AT DATE: . ~L . ~O

,.-J

WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND

-VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT:!4A-rr" Ie4-i AS-ncwPs acjnetAc,?,Poj DRAWING NO.: I51m-933 COMPONENT IDENTIFICATION: 5i1 wf29 PROCEDURE: WEP- 'S.41. REVISION:LnePzAe ULTRASONIC: X< LIQUID PENETRANT-... MAGNETIC PARTICLE:__ VISUAL:

EXAMINER: U&IU'/nR raid DATE:

LEVEL EXAMINER: DATE: A14 7 LEVEL 'I SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

EXAMINATION LIMITED TO SINGLE SIDE ACCESS ONLY, DUE TO VALVE TO PIPE CONFIGURATION. -

KEWAUNEE NUCLEAR POWER PLANT REVIEW: _ 77&; t4 DATE: N,9 1 a (oy AUTHORIZED NUCLEAR X --I v INSERVICE INSPECTOR REVIEW: -_ DATE: Y-u U

WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: fA 7 ,/JTG6/v-V Pv'r D/rCT A'//(

j 0 RIFIV 290 DRAWING NO.: ]*f -g3//-/

COMPONENT IDENTIFICATION: S f W23 v. PROCEDURE:A1,5/6</ REVISION: R ULTRASONIC: X LIQUID PENETRANT: _ MAGNETIC PARTICLE: VISUAL: -

EXAMINER: u,7 i Ad DATE: -t -2 3 -01 9F LEVEL EXAMINER: /ozae-/) o ay DATE: /6 -$.-6 LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

AXIAL EXAMINATION (SCAN 215 ) ON ELBOW SIDE OF WELD LIMITED TO 7.0" OF 11.0" CIRCUMFERENCE DUE TO INTRADOSE OF ELBOW.

PERCENTAGE OF REDUCED EXAMINATION CODE COVERAGE: 9.1%

-TYPICAL FOR SI-W234, SI-W262, SI-W283, AND SI-W284.

KEWAUNEE NUCLEAR ,4)LpJ POWER PLANT REVIEW: ran . &h.) DATE: octAd45_ a 00 q AUTHORIZED NUCLEAR IINSERVICE INSPECTOR REVIEW: DATE: __-___ _

WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: >AMUCK /A//6A'71,ok, PO,"9f l/fc/_P ycP5a P4' W/ ws-z-

/?

DRAWING NO.: .7s.7,- - 9? 5'-2 COMPONENT IDENTIFICATION: S / - W, 62 PROCEDURE: /1'6P-? /REVISION: 3 ULTRASONIC: X LIQUID PENETRANT:__ MAGNETIC PARTICLE:__ VISUAL:

EXAMINER: Jo > (i=-4, -z7- DATE: -2 - Y at V LEVEL EXAMINER: Lai BonIe-LEVEL DATE: /I -)-e SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

AXIAL EXAMINATION (SCAN 215 ) ON ELBOW SIDE OF WELD LIMITED TO 7.0" OF 11.0" CIRCUMFERENCE DUE TO INTRADOSE OF ELBOW.

PERCENTAGE OF REDUCED EXAMINATION CODE COVERAGE: 9.1%

-TYPICAL FOR St-W234, SI-W262, Sl-W283, AND SI-W284.

KEWAUNEE NUCLEAR Ro POWER PLANT REVIEW: by DATE: O'fi> a5s -Ioo AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: 249- 7~4f/L DATE: /1 -IV/

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT:g'5h 1 LwIdo+;' PomLp.s D0,5C4. PUpjw- h f- . 2SN R4. r DRAWING NO.: ZSXM-43q.I-COMPONENT IDENTIFICATION: §ST-81J7 PROCEDURE: NEP-)5. O0 REVISION: A ULTRASONIC:__ LIQUID PENETRANT: X MAGNETIC PARTICLE:.. VISUAL:

EXAMINER: 3obbtA Lwi.der s DATE: LO 13-01

-d LEVEL EXAMINER: JS&,AY T CuRRA, 'U,2;I,10'-J IX DATE: /o-13-0Y 6' vWO LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

Examination limited due to welded l.D. plate.

Limitation Area: 1.0 sq. Inch Reduiced Eraminntinn Codne Cnveraan 4.20/.

KEWAUNEE NUCLEAR /1 / &W I POWER PLANT REVIEW: 7 . e *& DATE:fUI AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: 4---

m L/ .0 DATE: _______

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: S- Nrbn, tlmar Hen. .X$? 7 Amirg aJ ei21 aw Zs DRAWING NO.: 5In/m - wb eqAu COMPONENTIDENTIFICATION: PL4- 1z0 PROCEDURE: NAMP .1*A REVISION: Ad 44&nf ULTRASONIC: LIQUID PENETRANT: __ MAGNETIC PARTICLE: __ VISUAL: _

EXAMINER: /`inhtal I Ot L~- LVEL

~LEVEL DATE:

EXAMINER: A1L" sC1-Zee te --0, n7 -- DATE: )/_-Vo

/ LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

EXAMINATION LIMITED TO UPSTREAM WELD AND BASE METAL ONLY, DUE TO BRANCH CONNECTION CONFIGURATION.

PERCENTAGE OF REDUCED EXAMINATION CODE COVERAGE: 50%

KEWAUNEE NUCLEAR POWER PLANT REVIEW: - i &7 DATE: IOml 14H.aOO AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: - __ DATE:______ _lo__

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEMORCOMPONENT: 5/ -AleeA' 61Y7r Av4o.L 2OA/ 72) A!a7-Yr A4/Z)

DRAWING NO.: /*//1- 9 ?6 COMPONENT IDENTIFICATION: 5/-W2gRI S/- W)AP PROCEDURE:4z- /DC -/ REVISION: B?

ULTRASONIC: s< LIQUID PENETRANT: __ MAGNETIC PARTICLE:___ VISUAL:

EXAMINER: J74- - ra., . , _ _ .,Z DATE: /z2 -3 a ?

LEVEL EXAMINER: gods/}j ;04 A oP nhc. DATE: I6-c42-0`

LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

AXIAL EXAMINATION (SCAN 215 ) ON ELBOW SIDE OF WELD LIMITED TO 7.0" OF 11.0" CIRCUMFERENCE DUE TO INTRADOSE OF ELBOW.

PERCENTAGE OF REDUCED EXAMINATION CODE COVERAGE: 9.1%

-TYPICAL FOR SI-W234, SI-W262, SI-W283, AND SI-W284.

KEWAUNEE NUCLEAR POWER PLANT REVIEW:

R rat - DATE: _c_______o_

AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW:.' : I "

DATE:__________

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEMORCOMPONENT: A 0a /

tQ 4g ., i e7h ooie'.hn DRAWING NO.: LSA - >

- 99 .q)

COMPONENT IDENTIFICATION: !X- VJ 61 PROCEDURE:_NF/§?-/e'Y/REVlSlON: ?

ULTRASONIC: LIQUID PENETRANT: MAGNETIC PARTICLE: VISUAL:

EXAMINER: L'W&II Rnl;iJiAe- 4 qxx a t )- DATE: /4-0y LEVEL EXAMINER: Ay-L-U J-p"v--c!'Q if DATE: 1-t 20-oq 0 -LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

i i

eCAUI MT1NLIMITED DUETO OONFGtFCUiAT1OF REDUCE t GrAN2 LIM TEOTO 11Z FPOULIDOWNSTREIdELOD 7E.

CODEREUIRED EXAUVOLUWE: iaomsq.li.

REnuCFDconERMU ERAED eMiVOLUME: t.C2&q.l. 13.31%

VOLUME NOT EXAMINE V E EXAMINED KEWAUNEE NUCLEAR

DAE POWER PLANT REVIEW: 7___ ____DATE: ad________

AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: / ' "3 DATE:__________

WISCONSIN PUBLIC SERVICE CORPORATION IREV ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: Reat- &.Wka- >mePresrza, 4 a to.t pwz -

DRAWING NO.: 1J/,' - pyo-COMPONENT IDENTIFICATION.:N- g1a7 PROCEDURE: j'/ft?-Jqi . REVISION: ,k.A ULTRASONIC: X LIQUID PENETRANT:-. MAGNETIC PARTICLE:__ VISUAL:

FXlkAMINFrP-W^AI\fllE5CI1.,

a/nlol 1/l DATE: //-6-64' LEVEL EXAMINER: DATE: V1/4

&, LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

EXAMINATION LIMITED TO SINGLE SIDE ACCESS ONLY, DUE TO SAFE END TO ELBOW CONFIGURATION.

PERCENTAGE OF REDUCED EXAMINATION CODE COVERAGE: 50%

_7 I i '

KEWAUNEE NUCLEAR POWER PLANT REVIEW: 6.AA., DATE: N4twe £.; OO'J AUTHORIZED NUCLEAR X m- .

JNSERVICE INSPECTOR REVIEW: A I DATE: /"- -o

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: eAotrw.'r SfeEVs P Sate ,/G DRAWING NO.: Ism- 9.o -1 COMPONENT IDENTIFICATION: e-S147 PROCEDURE: pePg-lKd'l REVISION: A ULTRASONIC:__ LIQUID PENETRANT: X MAGNETIC PARTICLE:__ VISUAL:

EXAMINER: &AL J.Ji g4 LEVE DATE: 11-2Y LEVEL EXAMINER: ,A4v; 6. c;AASi is DATE: //-2 -C*f1 LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

EXAMINATION LIMITED DUE TO WELDED ATTACHMENT.

PERCENTAGE OF REDUCED EXAMINATION CODE COVERAGE: 8.0%

_ . .s A. '.

KEWAUNEE NUCLEAR ,

POWER PLANT REVIEW: r2%& C AAn c DATE: Nn ao 00 AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: Ads,________ _ DATE: _-_-______

WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: COdrArWlM/vE,.iS.PRAY PUMP IA OS, e Pa26 7sO PAl. 29q DRAWING NO.: isrM-qsvI COMPONENT IDENTIFICATION: ICS-'wi PROCEDURE: REVISION:

REVPSION:

ULTRASONIC: X LIQUID PENETRANT: - MAGNETIC PARTICLE: VISUAL: _

EXAMINER: So_0 ," 'g4 v6 be Byn 4 DATE: LL.A.ad-o

, LEVEL EXAMINER: DATE: //-o4 LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

EXAMINATION LIMITED TO SINGLE SIDE ACCESS, DUE TO ELBOWTO VALVE CONFIGURATION PERCENTAG.E OF REDUCED EXAMINATION COVFRAGF: 50%

KEWAUNEE NUCLEAR _O POWER PLANT REVIEW: /-d 4 6. i d-4

- DATE: /\ .WbqY AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: 4___________ ___._ DATE: II '-

(/ - . l

I WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: covlA4ME/r-14pRqAY Pump jA DiScH P/PvIi& T7 PA. ZcIAI DRAWING NO.: XSr94-COMPONENT IDENTIFICATION: ZC-S - W/

1 I PROCEDURE: N'-?- J. I REVISION: a ULTRASONIC: < LIQUID PENETRANT: MAGNETIC PARTICLE: VISUAL:

EXAMINER: ; \ v- ;Z* - DATE: I/-eu-04' LEVEL EXAMINER: Russo,/I Eoan 64 DATE: 'I-.'-O*

-LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

EXAMINATION LIMITED TO SINGLE SIDE ACCESS, DUE TO VALVE TO PIPE CONFIGURATION PERCENTAGE OF REDUCED EXAMINATION COVERAGE: 50%

KEWAUNEE NUCLEAR POWER PLANT REVIEW: / t- DATE: tQ 9oY AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: eAdd DATE: d'-5!-Oy'

I WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: &nhn;hneon er~y Ap lB ; 9 pnt -A"ae . A?

II ' .J DRAWING NO.: /rSlr- 5A COMPONENT IDENTIFICATION: M i/D 6 PROCEDURE: At-.As . REVISION: _ _

Up v ULTRASONIC: &.LIQUID PENETRANT: ___MAGNETIC PARTICLE:____ VISUAL: ___

EXAMINER: /ZAiuy//

i , BoLbn _ K;lygv/I DATE: I1-6-01 LEVEL EXAMINER: I)iXvia C-.-9#d/;* A m DATE:

LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

EXAMINATION LIMITED DUE TO WELDED IDENTIFICATION PLATE.

PERCENTAGE OF REDUCED EXAMINATION CODE COVERAGE: 9.3%

KEWAUNEE NUCLEAR 7( 5 DATE: b.OY q AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: __________ A p DATE:_________

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: RWRQ- 1:;sa firLZ4, fDii; Ad aw8 Oppa-%... f5s DRAWING NO.: )fi/Y1 -91J)

COMPONENT IDENTIFICATION: RR - AL9 PROCEDURE: A8a- /d. / REVISION: eB, U LI S ULTRASONIC: LIQUID PENETRANT:____ MAGNETIC PARTICLE:____ VISUAL: ___

EXAMINER: R -~ I Z~ŽU1?I2~J- DATE: /-'t4 LEVEL EXAMINER: 0,4t"' 6.

4./ go DATE: _______

LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

EXAMINATION LIMITED TO SINGLE SIDE ACCESS ONLY, DUE TO VALVE TO PIPE CONFIGURATION.

PERCENTAGE OF REDUCED EXAMINATION CODE COVERAGE: 50%

KEWAUNEE NUCLEARLER Xw POWER PLANT REVIEW: 7 DATE: I0/ 7.;odv AUTHORIZED NUCLEAR X INSERVICE INSPECTOR REVIEW: A " ' DATE:________

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: -EEbWATEK Ro(A AN pfoI~ELL -ro SrM ax1 h5 DRAWING NO.: ISIM- 9 -11 COMPONENT IDENTIFICATION: 4VI- LAu PROCEDURE: tlJ- 15.. REVISION: B ULTRASONIC: Y LIQUID PENETRANT: MAGNETIC PARTICLE:__ VISUAL:__

EXAMINER: AugL~ lwsaj (lL94F ff- DATE: 10/Jg/oq LEVEL EXAMINER: rotLWASPIL T7-' DATE: 18/91 LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

NO EXAMINATIONPERFORMED ON DOWNSTREAM SIDE OF WELD DUE TO CONFIGURATION OF B RANCH CONNECTION. AREA OF LIM ITATION :4.0 sq. In.

REDUCED EXAMINATION CODE COVERAGE: 1.8%

NOTE: 60 DEGREE EXAMINATION WOULD NOT REDUCE AREA OF LIMITATION KEWAUNEE NUCLEAR /) 1 1A X POWER PLANT REVIEW: 7--i .° DATE:aOA, AUTHORIZED NUCLEAR DA TE INSERVICE INSPECTOR REVIEW: - / X'i DATE: "e"'

WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: 14 fe, re 4wercl EL.L fo ST/\ Ad IS DRAWING NO.: IE(TM-'97/

COMPONENT IDENTIFICATION: rlJ- Litol PROCEDURE: NEPI15.07 REVISION: X ULTRASONIC: _ LIQUID PENETRANT:__.__MAGNETIC PARTICLE: X VISUAL:

EXAMINER: Boi. watesr DATE: lo-18-o0 LEVEL EXAMINER: a.d, edA A ... DATE: /a-10-e-s LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

NO EXAMINATION PERFORMED ON DOWNSTREAM SIDE OF WELD DUE TO CONFIGURATION OF BRANCH CONNECTION. AREA OF LIMITATION.: 4.0 sq. in.

REDUCED EXAMINATION CODE COVERAGE: 3.6%

w2 KEWAUNEE NUCLEAR POWER PLANT REVIEW: 7 ° e C. ; DATE: oth ,8o C1 a

AUTHORIZED NUCLEAR / DAT I'NSERVICE -INSPECTOR REVIEW: Ad 7DATE: /Pt °Y

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: A0-814.-r aloolan f ')~P ina I-)

{o e& 14 DRAWING NO.: JS)M - / 7DO COMPONENT IDENTIFICATION: if! - L2iC d PROCEDURE: _L5P-/16.92REVISION: 4 ULTRASONIC: LIQUID PENETRANT: __ MAGNETIC PARTICLE:__ VISUAL:

EXAMINER: o,) e ns- DATE:

LEVEL EXAMINER: Antxon iEf tjsZj 6?Lzc(L AL DATE: l/-d_____

91 LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

EXAMINATION LIMITED TOUPSTREAMSIDE OFVWELD AND BASE METALONLY DUE TO CONFIGURATION OF BRANCH CONNECTION.

PERCENTAGE OF REDUCED EXAMINATION CODE COVERAGE: 50.00%

B.1 KEWAUNEE NUCLEAR POWER PLANT REVIEW: rtv- DATE: Nae3,J oy AUTHORIZED NUCLEAR A INSERVICE INSPECTOR REVIEW: / F DATE: "3"Y

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