NLS2007013, Inservice Inspection Summary Report

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Inservice Inspection Summary Report
ML070570138
Person / Time
Site: Cooper Entergy icon.png
Issue date: 02/20/2007
From: Fleming P
Nebraska Public Power District (NPPD)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2007013
Download: ML070570138 (99)
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Text

{{#Wiki_filter:N Nebraska Public Power District NLS2007013 Always there when you need us February 20, 2007 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Inservice Inspection Summary Report Cooper Nuclear Station NRC Docket No. 50-298, DPR-46 The purpose of this letter is to provide to the Nuclear Regulatory Commission the Inservice Inspection (ISI) Summary Report for the Fall 2006 Refueling Outage at Cooper Nuclear Station (CNS). This report is submitted in accordance with the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI. Enclosure 1 provides the Owner's Reports for Inservice Inspections, and Repairs or Replacements. Certain non-ASME Section XI augmented ISI results are also included. Should you have any questions regarding this matter, please contact me at (402) 825-2774. Si erey PaulV.F 1n Licensing ger /wv Enclosure cc: Regional Administrator w/enclosure USNRC Region IV Senior Resident Inspector w/enclosure USNRC - CNS Cooper Project Manager w/enclosure USNRC - NRR Project Directorate IV-I NPG Distribution w/o enclosure CNS Records w/enclosure COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 .404q Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com

ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS@ ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS@ Correspondence Number: NLS2007013 The following table identifies those actions committed to by Nebraska Public Power District (NPPD) in this document. Any other actions discussed in the submittal represent intended or planned actions by NPPD. They are described for information only and are not regulatory commitments. Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments. COMMITMENT COMMITTED DATE COMMITMENT NUMBER OR OUTAGE None f f t I 4 4 4 4 4 4 PROCEDURE 0.42 REVISION 20 PAGE 19 OF 26

NLS2007013 Enclosure Enclosure 1 ASME B&PV Code, Section XI, Summary Report

ASME B&PV Code, Section XI, Summary Report Cooper Nuclear Station Refueling Outage RE23, Fall 2006 Table of Contents

1. Abstract of Examinations, Results, and Corrective Measures ................................ 3 Pages
2. NIS-1 Forms and Summary Tables RE22-EXT NIS-1 Form (Remainder of Third Interval ISI Inspections) ............... 2 Pages Attachment 1 Inservice Inspection Report ................................................ 5 Pages RE23 NIS-1 Form (Start of Fourth Interval) .................................................. 2 Pages Attachment 1, Inservice Inspection Report ................................................ 56 Pages RE 23 IW E N IS-1 Form ....................................................................... 2 Pages Attachment 1, Inservice Inspection Report ................................................ 3 Pages
3. NIS-2 Forms and Summary Tables NIS-2 Form/Summary Table (End of Third Interval) ..................................... 3 Pages NIS-2 (Beginning of Fourth Interval) ...................................................... 4 Pages
4. NED C 05-001, R evision 1...................................................................... 15 Pages

Abstract of Examinations, Tests, Results, and Corrective Measures Introduction This report documents the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, Inservice Inspection (ISI) Examinations, and Repair or Replacements performed from February 19, 2005 to November 22, 2006 that corresponds with the end of Refueling Outage 23 (RE23) at Cooper Nuclear Station (CNS). CNS completed the Third ISI Interval for Class 1, 2 and 3 components on February 28, 2006. However, for four (4) component examinations that are credited to the Third ISI Interval, the interval was extended to include Refueling Outage 23 (RE23) in accordance with IWA-2430(d). For the other examinations, RE23 is the first outage of the first period in the Fourth ISI Interval for Class 1, 2 and 3 components that started on March 1, 2006. RE23 is the first outage of the third period in the First Interval for Class MC containment inspections. Examinations, repairs, and replacements were performed to the applicable requirements of the ASME B&PV Code, Section XI as delineated on the attached NIS-1 and NIS-2 forms. Three NIS- 1 forms are included to encompass examinations for: a) the end of the Third ISI Interval (including the 4 examinations for which the interval was extended), b) the beginning of the Fourth ISI Interval, and c) the third period of the First IWE Interval for Class MC components. Two NIS-2 forms are included to encompass repairs and replacements covering: a) the end of the Third ISI Interval, and b) the beginning of the Fourth ISI Interval. The Core Shroud is considered a Class 1 "core support structure" in the CNS ISI Program and is therefore subject to to the visual examination requirements for Category B-N-2, Item B 13.40 components per Table IWB-2500-1. A flaw on the outside surface of the shroud was identifed in RE23 requiring analysis per IWB-3142.4 to accept the flaw for continued operation. IWB-3144 requires analyses of examination results as required by IWB-3142.4 to be submitted to the NRC. Therefore, CNS Calculation NEDC 05-001, Revision 1 is included in this enclosure for information. The vendor-supplied attachments with proprietary information have not been included, but are available upon request. Examinations ASME Section XI Class 1, 2, and 3 Components The examinations of ASME Code Class 1, 2, and 3 components performed during and prior to RE23 are provided in the NIS-1 summary tables. For those examinations that were conducted as part of the third period of the Third IS Interval, the examinations were performed in accordance with ASME Section XI 1989 Edition No Addenda and ASME Section XI Risk-Informed. Those examinations that were conducted as part of the first period of the Fourth ISI Interval, the examinations were performed in accordance with ASME Section XI 2001 Edition 2003 Addenda. See Attachment 1 to the RE22-EXT NIS-I and RE23 NIS-I Forms for details.

Containment The containment inservice inspection program implements the examinations schedule of the primary containment pressure boundary in accordance with ASME Section XI, 1992 Edition, 1992 Addenda. The examinations were credited to the third period of the First IWE Interval for Class MC components. See Attachment 1 to the RE23 IWE NIS-1 Form for details. Pressure Testing The Class 1 system leakage test was performed to test the primary coolant system boundary, Code Category BP, and the Class 2 portion of the Control Rod Drive system boundary credited to the Fourth 10 Year ISI Interval. The vessel flange seal leak detection system was pressure tested with the refueling cavity flooded as permitted by Relief Request PR-04. See Attachment 1 to the RE23 NIS-1 Form for details. Code Category C-H ten (10) year pressure tests were performed and credited to the third period of the Third 10 Year Interval for the Residual Heat Removal, High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling systems. Code Category D-B ten (10) year pressure tests were performed on the Service Water system and secondary HPCI supply piping from the Condensate storage tanks. See Attachment 1 to the RE22-EXT NIS-1 Form for details. Owner-Elected and Augmented Examinations Owner-elected component examinations were performed and credited to the Boiling Water Reactor Vessel Internals Project (BWRVIP) and to General Electric Service Information Letters. The Owner-elected examinations included ultrasonic and visual examinations as required by the CNS Vessel Internals Program that implements the recommendations by BWRVIP and other industry operating experiences. Component examinations were also credited to NUREG-0619, CNS Management directives, etc. The augmented examinations included visual examinations of the four (4) Feedwater nozzles and ultrasonic examinations of Class 3 Reactor Equipment Cooling system welds. See Attachment 1 to the RE23 NIS-1 Form for details. Snubber Inspection Program The CNS Snubber Inspection Program implements examination and testing based on Relief Request RI-13. The CNS snubber population consists of two-hundred and eight (208) safety-related snubbers that require periodic visual examination, functional testing, and service life monitoring and seal replacement. The 10% sample consisted of twenty-two (22) snubbers which were functionally tested this cycle. Snubbers were removed and replaced as part of the service life monitoring program. The snubbers that were replaced with new snubbers are listed on the summary attachment table of the NIS-2 form.

Repairs or Replacements The ASME Section XI repairs or replacements are as summarized in the Form NIS-2 Owner's Report and summary table.

Page 1 of 2 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS (As required by the Provisions of the ASME Code Rules)

1. Owner Nebraska Public Power District 1414 15th St. Columbus, NE 68602 (Name and Address of Owner)
2. Plant Cooper Nuclear Station, 72676 648A Avenue, PO Box 98, Brownville, NE 68321-0098 (Name and Address of Plant)
3. Plant Unit 1 4. Owner Certificate of Authorization (if required) N/A
5. Commercial Service Date 07/01/1974 6. National Board Number for Unit N/A
7. Components Inspected Component or Manufacturer or Manufacturer or Installer State or Province National Board No.

Appurtenance Installer Serial No. No. Piping, Pumps, Valves, and N/A N/A N/A N/A Supports Reactor Pressure Vessel / Combustion Engineering C.E.66106 / C.E.66206 N/A 20762 Vessel Head Containment Chicago Bridge and Iron C-4448 N/A N/A I + + I I +/- I 

                                                                           +/-                                 +                               1 I                                           +/-                                 A-                              I It                                                                          f+/-

(*) SEE "ATTACHMENT 1" FOR APPLICABLE INFORMATION Note: Supplemental sheets in form of lists, sketches, or drawings maybe used, provided (1) size is 8-1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top ofthis form. This form (E00029) may be obtained from the ASME Order Dept., 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300

Page 2 of 2 FORM NIS-1 (Back)

8. Examination Dates 2/19/2005 to 11/22/2006
9. Inspection Period Identification: Period 3, 11/01/2002 to 02/28/2006
10. Inspection Interval Identification: Interval 3, 03/01/1996 to 02/28/2006
11. Applicable Edition of Section XI 1989 Addenda None
12. Date/Revision of Inspection Plan: 10/16/2006
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.

See Attachment 1

14. Abstract of Results of Examinations and Tests.

See Attachment 1

15. Abstract of Corrective Measures.

See Attachment 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) N/A Expiration Date Date - / , Signed Nebraska Public Power District By Vasant N. Bhardwaj/ I Owner " CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska and employed by Hartford Steam Boiler Inspection and Insurance Co. of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period o -- 1 9 --05s to - ao , 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. Todd Ward/ Commissions A$)I4'S') /P-A* " /o lot 

                          ,upector's Signature                                                          National Board, State, Province, and Endorsements Date           c           --O7

(*) SEE "ATTACHMENT 1" FOR APPLICABLE INFORMATION

Monday, February 12, 2007 Page 1 of 5 : Inservice Inspection Report, Interval 3, Period 3, RE22-EXT

1. Owner, Address: Nebraska Public Power District 1414 15th St. Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72676 648A Avenue, PO Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Exam Credit: PSI Equal: 13
--- ------.C ategory: ----B-G -2... Equal:      .1.0.............................

Item No.: B7.80 Equal: 10 Summary No.: Component ID: Class: System: Component Description B7.80.06-31 CRD-BG2-06-31 1 CRD CRD Housing Flange Bolting Eight (8) Total Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4442572 VT-1 PSI-F06-001 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description B7.80.10-15 CRD-BG2-10-15 1 CRD CRD Housing Flange Bolting Eight (8) Total Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4451679 VT-1 PSI-F06-002 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description B7.80.10-27 CRD-BG2-10-27 1 CRD CRD Housing Flange Bolting Eight (8) Total Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4451780 VT-1 PSI-F06-003 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description B7.80.10-35 CRD-BG2-10-35 1 CRD CRD Housing Flange Bolting Eight (8) Total Work Order Exam Method ReporNo. Results Code Case Comments / Corrective Measures 4451781 VT-1 PSI-F06-004 Accept Summary No.: Component ID: Class: System: Component Description B7.80.14-19 CRD-BG2-14-19 1 CRD CRD Housing Flange Bolting Eight (8) Total Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4451782 VT-1 PSI-F06-005 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description B7.80.18-11 CRD-BG2-18-11 1 CRD CRD Housing Flange Bolting Eight (8) Total Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4451783 VT-1 PSI-F06-006 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description B7.80.18-19 CRD-BG2-18-19 1 CRD CRD Housing Flange Bolting Eight (8) Total Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4451785 VT-1 PSI-F06-007 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description B7.80.22-47 CRD-BG2-22-47 1 CRD CRD Housing Flange Bolting Eight (8) Total Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4451787 VT-1 PSI-F06-008 Accept N/A Examination SAT.

Monday, February 12, 2007 Page 2 of 5 : Inservice Inspection Report, Interval 3, Period 3, RE22-EXT

1. Owner, Address: Nebraska Public Power District 1414 15th St. Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72676 648A Avenue, PO Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321 -0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description B7.80.46-31 CRD-BG2-46-31 1 CRD CRD Housing Flange Bolting Eight (8) Total Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4451791 VT-1 PSI-F06-009 Accept N/A Examination SAT.

Summary No.: Component ID: Class: system: Component Description B7.80.50-27 CRD-BG2-50-27 1 CRD CRD Housing Flange Bolting Eight (8) Total Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4451793 VT-1 PSI-F06-010 Accept N/A Examination SAT. Category: D-A Equal: 1 Item No.: D1.30 Equal: 1 Summary No.: Component ID: Class: System: Component Description D1.30.0004 SW-PD-A1 3 SW Pump Support Integrally Welded AttAchment Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4368343 VT-1 PSI-F06-012 Accept N/A Examination SAT Category: F-A Equal: 2 Item No.: F11.40.B Equal: 2 Summary No.: Component ID: Class: System: Component Description F11.40.B.0017 SW-BPD-S1 3 SW Booster Pump Support Work Order Exam Method Report No. Results Code Case Comments i Corrective Measures 4345743 VT-3 PSI-F06-013 Accept N/A Examination SAT. Summary No.: Component ID: Class: SStem: Component Description F1.40.B.0021 SW-PD-S1 3 SW Main Pump Support Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4368343 VT-3 PSI-F06-011 Accept N/A Examination SAT. Exam Credit: Sec.XI Equal: 22 Category: B-N-2 Equal: 2 Item No.: B13.40 Equal: 2 ' Summary No.: Component ID: Class: System: Component Description B13.40.0004 SHRD-UPCLYASEM@0>180 1 NB Core Shroud Assembley Upper Cylinder, Accessible surfaces from top of Shroud (steam dam) to H7 Weld area 0 to 180 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448817 VT-3 VT-F06-180 Accept N/A Examination SAT. Examination credited to 3rd ISI Interval. Examination performed to the 2001, 2003 Addenda using Code Case N-686 but reconciled to the 1989 Edition as referenced in Section 5 of the AREVA RE23 IWI Outage Report. Accessible areas were examined. See Section 3, Tab 5 of AREVA IWI Outage Report.

Monday, February 12, 2007 Page 3 of 5 : Inservice Inspection Report, Interval 3, Period 3, RE22-EXT

1. Owner, Address: Nebraska Public Power District 1414 15th St. Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72676 648A Avenue, PO Box 98, Brownville, 5. Owner Certificate of Authorization (if Required): N/A NE 68321 -0098
3. Plant Unit: 1 6. National Certificate of Authorization (IfRequired): N/A Summary No.: Component ID: Class: System: Component Description B13.40.0005 SHRD-UPCLYASEM@180>360 1 NB Core Shroud Assembley Upper Cylinder, Accessible surfaces from top of Shroud (steam dam) to H7 Weld area 180 to 360 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 VT-3 VT-F06-181 Accept N/A Examination SAT. Examination credited to 3rd ISI Interval. Examination performed to the 2001, 2003 Addenda using Code Case N-686 but reconciled to the 1989 Edition as referenced in Section 5 of the AREVA RE23 IWI Outage Report. Accessible areas were examined. An indication was identified between jet pumps 18 and 19 and documented per AREVA indication notification form INF#CNS-RFO-23-05 and CNS Condition Report CR-CNS-2006-08297. Indication was evaluated per NEDC 05-001, Rev 1 as acceptable for continued operation. See Section 3, Tab 5 of AREVA IWI Outage Report.

Category: C-H Equal: 14 Item No.: C7.20 Equal: 2 Summary No.: Component ID: Class: System: Component Description C7.20.RHR-A.PV.SHT01 RHR-A.PV.PRB.SHT 2 RHR Pressure Vessels, Pressure Retaining Boundary System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4361267 VT-2 6.1RHR.501-3301 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWC-5222 and CNS Surveillance Procedure 6.1RHR.501 Summary No.: Component ID: Class: System: Component Description C7.20.RHR-B.PV.SHT01 RHR-B.PV.PRB.SHT 2 RHR Pressure Vessels, Pressure Retaining Boundary System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4401009 VT-2 6.2RHR.501-3301 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWC-5222 and CNS Surveillance Procedure 6.2RHR.501 Item No.: C7.40 Equal: 4 Summary No.: Component ID: Class: System: Component Description C7.40.HPCI.PIPE.SHT01 HPCI.PIPE.PRB.SHT 2 HPCI Piping, Pressure Retaining Boundary System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4361098 VT-2 6.HPCI.501-3301 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWC-5222 and CNS Surveillance Procedure 6.HPCI.501 Summary No.: Component ID: Class: System: Component Description C7.40.RCIC.PIPE.SHT01 RCIC.PIPE.PRB.SHT 2 RCIC Piping, Pressure Retaining Boundary System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4373693 VT-2 6.RCIC.501-3301 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWC-5222 and CNS Surveillance Procedure 6.RCIC.501 Summary No.: Component ID: Class: System: Component Description C7.40.RHR-A.PIPE.SHT01 RHR-A.PIPE.PRB.SHT 2 RHR Piping, Pressure Retaining Boundary System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4361267 VT-2 6.1RHR.501-3302 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWC-5222 and CNS Surveillance Procedure 6.1RHR.501 Summary No.: Component ID: Class: System: Component Description C7.40.RHR-B.PIPE.SHTO1 RHR-B.PIPE.PRB.SHT 2 RHR Piping, Pressure Retaining Boundary System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4401009 VT-2 6.2RHR.501-3302 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWC-5222 and CNS Surveillance Procedure 6.2RHR.501

Monday, February 12, 2007 Page 4of 5 : Inservice Inspection Report, Interval 3, Period 3, RE22-EXT

1. Owner, Address: Nebraska Public Power District 1414 15th St. Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72676 648A Avenue, PO Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Item No.: C7_.60 Equal1: 4 Summary No.: Component ID: Class: System: Component Description C7.60.HPCI.PUMP.SHT01 HPCI.PUMP.PRB.SHT 2 HPCI Pumps, Pressure Retaining Boundary System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4361098 VT-2 6.HPCI.501-3302 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWC-5222 and CNS Surveillance Procedure 6.HPCI.501 Summary No.: Component ID: Class: System: Component Description C7.60.RCIC.PUMP.SHT01 RCIC.PUMP.PRB.SHT 2 RCIC Pumps, Pressure Retaining Boundary System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4373693 VT-2 6.RCIC.501.3302 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWC-5222 and CNS Surveillance Procedure 6.RCIC.501 Summary No.: Component ID: Class: System: Component Description C7.60.RHR-A.PUMP.SHT01 RHR-A.PUMP.PRB.SHT 2 RHR Pumps, Pressure Retaining Boundary System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4361267 VT-2 6.1RHR.501-3303 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWC-5222 and CNS Surveillance Procedure 6.1RHR.501 Summary No.: Component ID: Class: System: Component Description C7.60.RHR-B.PUMP.SHT01 RHR-B.PUMP.PRB.SHT 2 RHR Pumps, Pressure Retaining Boundary System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4401009 VT-2 6.2RHR.501.3303 Accept N-498-4 110 Year Pressure Test SAT in accordance with IWC-5222 and Code Case N-498-4.

Item No.: C7.80 Equal: 4 Summary No.: Component ID: Class: System: Component Description C7.80.HPCI.VALVE.SHT01 HPCI.VALVE.PRB.SHT 2 HPCI Valves, Pressure Retaining Boundary System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4361098 VT-2 6.HPCI.501-3303 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWC-5222 and CNS Surveillance Procedure 6.HPCI.501. Summary No.: Component ID: Class: System: Component Description C7.80.RCIC.VALVE.SHT01 RCIC.VALVE.PRB.SHT 2 RCIC Valves, Pressure Retaining Boundary System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4373693 VT-2 6.RCIC.501-3303 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWC-5222 and CNS Surveillance Procedure 6.RCIC.501 Summary No.: Component ID: Class: System: Component Description C7.80.RHR-A.VALVE.SHT01 RHR-A.VALVE.PRB.SHT 2 RHR Valves, Pressure Retaining Boundary System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4361267 VT-2 6.1RHR.501-3304 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWC-5222 and CNS Surveillance Procedure 6.1RHR.501. Summary No.: Component ID: Class: System: Component Description C7.80.RHR-B.VALVE.SHT01 RHR-B.VALVE.PRB.SHT 2 RHR Valves, Pressure Retaining Boundary, System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4401009 VT-2 6.2RHR.501-3304 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWC-5222 and CNS Surveillance Procedure 6.2RHR.501

Monday, February 12, 2007 Page 5 of 5 : Inservice Inspection Report, Interval 3, Period 3, RE22-EXT

1. Owner, Address: Nebraska Public Power District 1414 15th St. Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72676 648A Avenue, PO Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Category: 0-B Equal: 4 Item No.: D2.1O0 Equal: 4 Summary No.: Component ID: Class: System: Component Description D2.10.ECS.PRC.SHT01 ECSTK.HPCI.PRB.SHT 3 CM Emergency Condensate Storage Tanks A and B Pressure Retaining Boundaries, System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4361098 VT-2 6.HPCI.501-3304 Accept Summary No.: Component ID: Class: System: Component Description D2.10.HPCI.PRC.SHT01 HPCI.SUPPLY.ECS.PRB.SHT 3 HPCI HPCI Supply Piping From Emergency Condensate Storage Pressure Retaining Boundaries, System, Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4361098 VT-2 6.HPCI.501-3305 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWD-5222 and CNS Surveillance Procedure 6.HPCI.501.

Summary No.: Component ID: Class: System: Component Description D2.10.SW-A.PRC.SHT01 SW-A.PRB.SHT 3 SW Service Water Loop A Pressure Retaining Boundaries, System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4401061 VT-2 6.1SW.501-3301 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWD-5222 and CNS Surveillance Procedure 6.HPCI.501. Summary No.: Component ID: Class: System: Component Description D2.10.SW-B.PRC.SHT01 SW-B.PRB.SHT 3 SW Service Water Loop B Pressure Retaining Boundaries, System Hydrostatic Test Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4361219 VT-2 6.2SW.501-3301 Accept N-498-4 10 Year Pressure Test SAT in accordance with IWD-5222 and CNS Surveillance Procedure 6.2SW..501 Category: F-A Equal: 2 Item No.: F1.40.A Equal: 2 Summary No.: Component ID: Class: System: Component Description F1.40.A.0020 RPV-STB-2A 1 NB Reactor Vessel Stabilizer Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448891 VT-3 VT-F06-169 Accept N/A Examination SAT. Examination credited to the 3rd Interval ISI Program. Examination was performed to the 2001 Edition, 2003 Addenda and reconciled to the 1989 Edition of ASME Section Xl as documented on the data sheet. See AREVA RE23 Manual ISI Report. Summary No.: Component ID: Class: System: Component Description Fl.40.A.0021 RPV-STB-3A 1 NB Reactor Vessel Stabilizer Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448891 VT-3 VT-F06-182 Accept N/A Examination SAT. Examination credited to the 3rd Interval ISI Program. Examination was performed to the 2001 Edition, 2003 Addenda and reconciled to the 1989 Edition of ASME Section XI as documented on the data sheet. See AREVA RE23 Manual ISI Report.

Page 1 of 2 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS (As required by the Provisions of the ASME Code Rules)

1. Owner Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 (Name and Address of Owner)
2. Plant Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, NE 68321-0098 (Name and Address of Plant)
3. Plant Unit 1 4. Owner Certificate of Authorization (if required) N/A
5. Commercial Service Date 07/01/1974 6. National Board Number for Unit N/A
7. Components Inspected Component or Manufacturer or Manufacturer or Installer State or Province National Board No.

Appurtenance Installer Serial No. No. Pping, Pumps, Supports, and N/A N/A N/A N/A Valves Reactor Vessel / Vessel Head Combustion Engineering C.E.66106 / C.E.66206 N/A 20762 Containment Chicageo Bridge and Iron C-4448 N/A N/A F I I I. F I I F F 1 1 F F I -I F t 1 1 F F -I I I-F -l I F F I I F t 1 1 F (*) SEE "ATTACHMENT 1" FOR APPLICABLE INFORMATION Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top ofthis form. This form (E00029) may be obtained from the ASME Order Dept., 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300

Page 2 of 2 FORM NIS-1 (Back)

8. Examination Dates 3/1/2006 to 11/22/2006
9. Inspection Period Identification: Period 1, 03/01/2006 to 06/30/2009
10. Inspection Interval Identification: Interval 4, 03/01/2006 to 02/29/2016
11. Applicable Edition of Section XI 2001 Addenda 2003
12. Date/Revision of Inspection Plan: 12/4/2006 Revision 0.2
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.

See Attachment 1

14. Abstract of Results of Examinations and Tests.

See Attachment 1

15. Abstract of Corrective Measures.

See Attachment 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) N/A Expiration Date Date .2/ o Signed Nebraska Public Power District By Vasant N. Bhardwaj/ Owner ,K 2//?L7 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 Nebraska and employed by Hartford Steam Boiler Inspection and Insurance Co. of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 0 ;L_ 1 -as- - 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 inany manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Todd Ward/ Commissions 

                            *nspector's Signure                                                        National Board, State, Province, and Endorsements Date       O) - q -0 )

(*) SEE "ATTACHMENT V"FOR APPLICABLE INFORMATION

Monday, February 12, 2007 Page 1 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Exam Credit: PSI Equal : 10 Category: B-G-2 Equal: 1 Item No.: B7.50 Equal: 1 Summary No.: Component ID: Class: System: Component Description B7.50.0011 MSD-BG2-31 1 MS Main Run Pipe Flange to Valve Flange Bolting Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4446762 VT-1 PSI-F06-015 Accept Category: F-A Equal: 8 Item No.: F1.20.A Equal: 2 Summary No.: Component ID: Class: System: Component Description F1.20.A.0066 PVH-104B 2 PNC Sway Strut Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4534069 VT-3 PSI-F06-021 Accept N-686 Examination SAT.

Summary No.: Component ID: Class: System: Component Description F1.20.A.0071 PVS-1B&R 2 PNC Sway Strut Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4533334 VT-3 PSI-F06-022 Accept N-686 Examination SAT. 

 .............. --t-e_

_m 

                           - -__o--.. .... -         ..............................--

Item No.: F1.20.13 Equal: 5 Summary No.: Component ID: Class: System: Component Description F1.20.D.0024 RHS-30B 2 RHR Hydraulic Snubber, Fig.200, one (1) of two (2) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4443492 VT-3 PSI-F06-017 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description F1.20.D.0026 RHS-37 2 RHR Hydraulic Snubber, Fig.201 Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4443342 VT-3 PSI-F06-016 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description F1.20.D.0027 RHS-40 2 RHR Hydraulic Snubber, Fig.201 Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4443493 VT-3 PSI-F06-018 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description F1.20.D.0030 RHS-43 2 RHR Hydraulic Snubber, Fig.201 Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4443490 VT-3 PSI-FO6-019 Accept N/A Examination SAT.

Monday, February 12, 2007 Page 2 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description F1.20.D.0044 RHS-80 2
  • RHR Hydraulic Snubber, Fig.200 Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4443487 VT-3 PSI-F06-020 Accept N/A 01/16/2007 Item No.: F1.40.8 Equal: 1 Summary No.: Component ID: Class: System: Component Description F1.40.B.0014 SW-BPA-S1 3 SW Booster Pump Support Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4529307 VT-3 PSI-F06-014 Accept N/A Examination SAT.

Category: R-A Equal: 1 Item No.: R 1.20-6 Equal: I Summary No.: Component ID: Class: System: Component Description 89.21.0029.RI MSDR-BJ-72R2 1 MSDR Pipe to Valve Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4426440 MT MT-F06-006 Accept N-460 Examination SAT. See AREVA RE23 Manual ISI Outage Report. Exam Credit: Sec.XI Equal: 90 Category: B-G-2 Equal: 5 Item No.: B7.50 Equal: 4 Summary No.: Component ID: Class: System: Component Description B7.50.0004 MSB-BG2-16 1 MS Main Run Pipe Flange to Valve Flange Bolting Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448890 VT-i VT-F06-080 Accept N-686 Examination SAT. See AREVA RE23 Manual ISI Outage Report. Summary No.: Component ID: Class: System: Component Description B7.50.0005 MSB-BG2-21 1 MS Main Run Pipe Flange to Valve Flange Bolting Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448890 VT-i VT-F06-087 Accept N-686 Examination SAT. See AREVA RE23 Manual ISIOutage Report. Summary No.: Component ID: Class: System: Component Description 87.50.0006 MSC-BG2-19 1 MvS Main Run Pipe Flange to Valve Flange Bolting Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448890 VT-i VT-F06-1 18 Accept N-686 Examination SAT. See AREVA RE23 Manual ISI Outage Report. Summary No.: Component ID: Class: System: Component Description B7.50.0007 MSC-BG2-24 1 MS Main Run Pipe Flange to Valve Flange Bolting Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448890 VT-11 VT-F06-117 Accept N-686 Examination SAT. See AREVA RE23 Manual ISI Outage Report.

Monday, February 12, 2007 Page 3 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Item No.: B7.70 Equal: 1 Summary No.: Component ID: Class: System: Component Description B7.70.0008 MS-AO-86A 1 MS Valve Body Bolting Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448890 VT-1 VT--F06-168 Accept N-686 Examination SAT. See AREVA RE23 Manual ISI Outage Report.

Category: B-K Equal: 3 Item No.: B10.20 Equal: 3 Summary No.: Component ID: Class: System: Component Description B10.20.0043 FWB-BK1-8 1 RF Lugs Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448888 MT MT-F06-003 Accept N-460 Examination SAT. See AREVA RE23 Manual ISI Outage Report. Summary No.: Component ID: Class: System: Component Description B10.20.0030 PSA-BKI-19 1 MS Lugs (4 total 1 1/2 x 1 3/4 x 1 3/4 inches) Work Order Exam Method ReportNo. Results Code Case Comments I Corrective Measures 4448889 MT MT-F06-004 Accept N-460 Examination SAT. See AREVA RE23 Manual ISI Outage Report. Summary No.: Component ID: Class: System: Component Description B10.20.0060 RHC-BK1-24 1 RHR Stanchion Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448892 MT MT-F06-005 Accept N-460 Examination SAT. See AREVA RE23 Manual ISI Outage Report. Category: B-M-2 Equal: 1 Item No.: B12.50 Equal: 1 Summary No.: Component ID: Class: System: Component Description B12.50.0036 RHR-MO-25A-BM2 1 RHR Valve Body Internal Surfaces Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4534360 VT-3 VE-F06-013 Accept N-686 Examination SAT. Category: B-N-1 Equal: 1 Item No.: 613.10 Equal: 1 Summary No.: Component ID: Class: System: Component Description B13.10.0004 VES-INTER@180>360 1 NB RPV Interior Surfaces (One Half RPV Accessible Areas) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 VT-3 VT-F06-232 Accept N-686 Examination SAT. Examined Interior Surfaces 180-270 and 270-360; Access limited to areas above Shroud Flange. See Section 3, Tab 6 of AREVA RE23 IVl Outage Report.

Monday, February 12, 2007 Page 4 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Category: B-N-2 Equal: 51 Item No.: B13.30 Equal: 12 Summary No.: Component ID: Class: System: Component Description B13.30.0001 CSA-BKTATTWLDS@150 1 CS Core Spray A Internal Piping Bracket Attachment Welds to RPV at 150 Degrees Azimnth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 VT-3 VT-F06-136 Accept N-686 Examination SAT. VT-3 and EVT-1 (BWRVIP-18-A) obtained 100% coverage. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report.

Summary No.: Component ID: Class: System: Component Description B13.30.0002 CSA-BKTATTWLDS@30 1 CS Core Spray A Internal Piping Bracket Attachment Welds to RPV at 30 Degrees Azimnth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448881 VT-3 VT-F06-138 Accept N-686 Examination SAT. VT-3 and EVT-1 (BWRVIP-18-A) obtained 100% coverage. See Section 3, Tab 1 of AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0003 CSB-BKTATTWLDS@210 1 CS Core Spray B Internal Piping Bracket Attachment Welds to RPV at 210 Degrees Azimnth Work Order Exam Method Report No. Results Code Case Comments /Corrective Measures 4448881 VT-3 VT-F06-140 Accept N-686 Examination SAT. VT-3 and EVT-1 (BWRVIP-18-A) obtained 100% coverage. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0004 CSB-BKTATTWLDS@330 1 CS Core Spray B Internal Piping Bracket Atachment Welds to RPV at 330 Degrees Azimnth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448881 VT-3 VT-F06-142 Accept N-686 Examination SAT. VT-3 and EVT-1 (BWRVIP-18-A) obtained 100% coverage. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0005 FW-ASPRBKT-ATTWLDS@5 1 RF Feedwater Sparger Bracket Attachment Welds at 5 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 VT-3 VT-F06-121 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. VT-3 and EVT-1 (BWRVIP-48-A) exams limited to 75% coverage due to interference of Feedwater Spargers. See Section 3, Tab 8 of the AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0006 FW-ASPRBKT-ATTWLDS@85 1 RF Feedwater Sparger Bracket Attachment at 85 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 VT-3 VT-F06-123 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. VT-3 and EVT-1 (BWRVIP-48-A) exams limited to 75% coverage due to interference of Feedwater Spargers. See Section 3, Tab 8 of the AREVA RE23 IVVI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0007 FW-BSPRBKT-ATTWLDS@175 1 RF Feedwater Sparger Bracket Attachment Welds at 175 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 VT-3 VT-F06-170 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. VT-3 exam limited to 90% and EVT-1 (BWRVIP-48-A) exam limited to 70% coverage due to Guide Rod interference. See Section 3, Tab 8 of the AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 5 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description B13.30.0008 FW-BSPRBKT-ATTWLDS@95 1 RF Feedwater Sparger Bracket Attachment at 95 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 VT-3 VT-F06-172 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. 100% coverage for VT-3, 75%

coverage for EVT-1 (BWRVIP-48-A). See Section 3, Tab 8 of the AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0009 FW-CSPRBKT-ATTWLDS@185 1 RF Feedwater Sparger Bracket Attachment Welds at 185 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448817 VT-3 VT-F06-174 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. VT-3 obtained 100% coverage. EVT-1 (BWRVIP-48-A) obtained 75% coveage, limited by configuration and Guide Rod interference. See Section 3, Tab 8 of the AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0010 FW-CSPRBKT-ATTWLDS@265 1 RF Feedwater Sparger Bracket Attachment Welds at 265 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 VT-3 VT-F06-176 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. VT-3 exam limited to 75% due to interference of Feedwater Sparger. EVT-1 (BWRVIP-48-A) was limited to 75% due to interference of Feedwater Sparger and Cattle Chute above. See Section 3, Tab 8 of the AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0011 FW-DSPRBKT-ATTWLDS@275 1 RF Feedwater Sparger Bracket Attachment Welds at 275 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 VT-3 VT-F06-178 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. VT-3 and EVT-1 (BWRVIP-48-A) exams limited to 60% due to interference of Feedwater Sparger and Cattle Chute above. See Section 3, Tab 8 of the AREVA RE23 IVV Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0012 FW-DSPRBKT-ATTWLDS@355 1 RF Feedwater Sparger Bracket Attachment Welds at 355 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 VT-3 VT-F06-125 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. Exam limited due to interference of Feedwater Sparger. Both VT-3 and EVT-1 (BWRVIP-48-A) limited to 75% coverage. See Section 3, Tab 8 of the AREVA RE23 IWI Outage Report. 

...............              B13.40 Item No.:-------         Equal: 39 Summary No.:                   Component ID:                      Class:   System:   Component Description B13.40.0001                    CORE-PLATE                           1         NB     Core Plate Assembly, Accessible surfaces including Rim Hold-Down Bolts (Total of 72, Critical Number 36)

Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4452896 VT-3 VT-F06-301 Accept N-686 Examination SAT. Examined core plate at CRD locations as made accessible. CR locations are as follows: 06-19, 06-35, 10-11, 10-35, 14-35, 18-11, 18-15, 22-31, 30-11, 30-35, 30-39, 34-15, 34-43, 38-19, 42-11, 42-19, 42-27, 42-35. See Section 3, Tab 7 of the AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.GT06-19 CRGT-(06-19) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-280 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 6 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description B13.40.GT06-35 CRGT-(06-35) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments i Corrective Measures 4452896 VT-3 VT-F06-257 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report.

Summary No.: Component ID: Class: System: Component Description B13.40.GT10-11 CRGT-(10-11) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-281 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.GT1O-35 CRGT-(10-35) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4452896 VT-3 VT-F06-258 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.GT14-35 CRGT-(14-35) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-282 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.GT18-11 CRGT-(18-11) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-283 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.GT18-15 CRGT-(18-15) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-259 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.GT22-31 CRGT-(22-31) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-284 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IVl Outage Report.

Monday, February 12, 2007 Page 7 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (IfRequired): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (IfRequired): N/A Summary No.: Component ID: Class: System: Component Description B13.40.GT30-11 CRGT-(30-11) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-285 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. FME (Small Debris) Located on Core Plate in NW corner of cell. Item Removed, Ref. CR-CNS-2006-8675. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report.

Summary No.: Component ID: Class: System: Component Description B13.40.GT30-35 CRGT-(30-35) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-260 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.GT30-39 CRGT-(30-39) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-261 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.GT34-15 CRGT-(34-15) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-262 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.GT34-43 CRGT-(34-43) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-263 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.GT38-19 CRGT-(38-19) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-286 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.GT42-11 CRGT-(42-1 1) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-287 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 8 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description B13.40.GT42-19 CRGT-(42-19) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-264 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report.

Summary No.: Component ID: Class: System: Component Description B13.40.GT42-27 CRGT-(42-27) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-265 Accept N-686 Examination SAT. Examine the Core Plate area around the Guide Tube, CRGT-1, Guide Tube and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.GT42-35 CRGT-(42-35) 1 NB Control Rod Guide Tube Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-266 Accept N-686 Examination SAT. Examined the Core Plate area around the Guide Tube, Guide Tube for Debris and Uncoupling Pin position. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.OF06-19 OFSC-(06-19) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-288 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.OF06-35 OFSC-(06-35) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-229 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.OF10-1 1 OFSC-(10-1 1) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-289 Accept N686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IVVI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.OF1O-35 OFSC-(10-35) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-290 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.OF14-35 OFSC-(14-35) 1 NB Four Lobed Oriflced Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-291 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 9 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (IfRequired): N/A Summary No.: Component ID: Class: System: Component Description B13.40.OF18-11 OFSC-(18-11) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-292 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report.

Summary No.: Component ID: Class: System: Component Description B13.40.OF18-15 OFSC-(18-15) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-293 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IVVI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.0F22-31 OFSC-(22-31) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-294 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.OF30-11 OFSC-(30-11) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4452896 VT-3 VT-F06-295 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.OF30-35 OFSC-(30-35) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-267 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.OF30-39 OFSC-(30-39) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-268 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.OF34-15 OFSC-(34-15) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4452896 VT-3 VT-F06-269 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.OF34-43 OFSC-(34-43) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-270 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 10 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description B13.40.OF38-19 OFSC-(38-19) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-296 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IVl Outage Report.

Summary No.: Component ID: Class: System: Component Description B13.40.0F42-111 OFSC-(42-1 1) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-297 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 WIl Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.OF42-19 OFSC-(42-19) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-230 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.OF42-27 OFSC-(42-27) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4452896 VT-3 VT-F06-231 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.OF42-35 OFSC-(42-35) 1 NB Four Lobed Orificed Fuel Support Casting Assembly Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4452896 VT-3 VT-F06-271 Accept N-686 Examination SAT. Examine FSC exterior surfaces including flow holes and tack welds. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.40.0006 TPGD-ASEM 1 NB Top Guide Assembly consisting of grid beams, rim welds, rim pins,wedges Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448819 VT-3 VT-F06-300 Accept N-686 Examination SAT. Examined top guide at CRD locations as made accessible. CR locations are as follows: 06-19, 06-35, 10-11, 10-35,14-35,18-11,18-15, 22-31, 30-11, 30-35, 30-39, 34-15, 34-43, 38-19, 42-11, 42-19, 42-27, 42-35. See Section 3, Tab 7 of the AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description 1I340 0007 TPGD-HRDWARE 1 NB Top Guide Assembly Hardware and Rim Weld (Hold Down Latches and Horizontal Alignment Pins at 0, 90, 180, and 270 degree azimuth) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448819 VT-3 VT-F06-129 Accept N-686 Examination SAT. Examined accessible areas of the Top Guide including the Rim, Hold downs, Rim Bolts and Lattice Structure from 0 to 3600. See Section 3, Tab 9 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 11 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Category: B-O Equal: 2 Item No.: B14.10 Equal: 2 Summary No.: Component ID: Class: System: Component Description B14.10.02-27-1 CRD-02-27-1 1 CRD Peripheral Control Rod Drive Housing to Flange weld Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448893 PT PT-F06-002 Accept N-460 Examination SAT. See AREVA RE23 Manual ISI Outage Report.

Summary No.: Component ID: Class: System: Component Description B14.10.02-31-1 CRD-02-31-1 1 CRD Peripheral Control Rod Drive Housing to Flange weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448893 PT PT-F06-001 Accept N-460 Examination SAT. See AREVA RE23 Manual ISI Outage Report. Category: B-P Equal: 2 Item No.: B15.10 Equal: 2 Summary No.: Component ID: Class: System: Component Description B15.10.PRC.SLT01 PRC.CLS1 1 NB All Pressure Retaining Components, System Leakage Test Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4429682 VT-2 6.MISC.502-4101 Accept N/A Examination SAT Summary No.: Component ID: Class: System: Component Description B15.10.PRC.SLT02 VS.HD.FLGSEL.LEK.DETEC 1 NB Pressure Retaining Component, Reactor Pressure Vessel, RPV Flange Seal Leak Detection System, System Leakage Test Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4446598 VT-2 PM10606-F06-01 Accept N-498-4 Examination SAT. " Category: C-A Equal: 1

  • Item No.: C1.20 Equal: 1 Summary No.: Component ID: Class: System: Component Description Cl .20.0001 RHR-CA-1A 2 RHR Top Head to Shell Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448896 Manual UT UT-F06-097 Accept N-460 Examination SAT. See AREVA RE23 Manual ISI Outage Report.

4448896 Manual UT UT-F06-096 Accept 4448896 Manual UT UT-F06-095 Accept 4448896 Manual UT UT-F06-098 Accept

  • Category: C-C Equal: 2 Item No.:
 -----------------------------     C3.20         Equal: 2 Summary No.:                       Component ID:                               Class: System:     Component Description C3.20.0022                         HPID-CC-5                                     2         HPCI   Stachion Work Order      Exam Method           Report No.       Results    Code Case     Comments / Corrective Measures 4448894             MT             MT-F06-001        Accept        N-460      Examination SAT. See AREVA RE23 Manual ISI Outage Report.

Monday, February 12, 2007 Page 12 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description C3.20.0034 PSA-CE1-1 2 MS Stanchion Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448895 MT MT-F06-002 Accept N-460 Examination SAT. See AREVA RE23 Manual ISI Outage Report.
  • Category: C-H Equal: 1

.. Item No.: C7.10 Equal: I Summary No.: Component ID: Class: System: Component Description C7.10.PRC.CRD.SLT01 PRC.CLS2.CRD 2 CRD Pressure Retaining Components, CRD System Leakage Test Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4429682 VT-2 6.MISC.502-4402 Accept N-686 Examination SAT. Category: F-A Equal: 12 Item No.: FI.10.C Equal: 3 Summary No.: Component ID: Class: System: Component Description F1.10.C.0021 MSH-134 1 MS Constant Support Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448889 VT-3 VT-F06-302 Reject N-686 Examination SAT based on review of support setting against acceptance criteria in CNS Procedure 7.2.57. See AREVA RE23 Manual ISI Outage Report. Evaluation Acceptable Evaluation Comments: Examination SAT Summary No.: Component ID: Class: System: Component Description F1.10.C.0042 RFH-70 1 RF Constant Support Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448888 VT-3 VT-F06-026 Accept N-686 Examination SAT. See AREVA RE23 Manual ISI Outage Report. Summary No.: Component ID: Class: System: Component Description F1.10.C.0047 RFH-73 1 RF Constant Support Trapeze Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448888 VT-3 VT-F06-027 Accept N-686 Examination SAT. See AREVA RE23 Manual ISI Outage Report. Item No.: F1.20.A Equal: 3 Summary No.: Component ID: Class: System: Component Description F1.20.A.0018 HPH-6 2 HPCI Stanchion Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448894 VT-3 VT-F06-003 Accept N-686 Examination SAT. See AREVA RE23 Manual ISI Outage Report. Summary No.: Component ID: Class: System: Component Description F1.20.A.0019 HPH-6A 2 HPCI Rod Hanger Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448894 VT-3 VT-F06-004 Reject N-686 Examination SAT based on attached Civil Engineering evaluation. See AREVA RE23 Manual ISI Outage Report. Evaluation Acceptable Evaluation Comments: CR-CNS-2006-07790 was written to document the indication but administratively closed following evaluation by Civil Engineering concluding a condition did not exist. Therefore, examination SAT.

Monday, February 12, 2007 Page 13 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (IfRequired): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (IfRequired): N/A Summary No.: Component ID: Class: System: Component Description F1.20.A.0046 MSH-157A 2 MS Sway Strut Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448894 VT-3 VT-F06-024 Reject N-686 Engineering review has determined that the configuration discrepancy meets the acceptance standards of IWF-3410, therefore the examination is SAT. See AREVA RE23 Manual ISI Outage Report.

Evaluation Acceptable Evaluation Comments: Based on engineering evaluation, the recordable indication meets the Acceptance Standards of IWF-3410 therefore this examination is SAT. Item No.: F1.20.B Equal: 1 Summary No.: Component ID: Class: System: Component Description F1.20.B.0017 RFH-41 2 HPCI Rigid Brace Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448894 VT-3 VT-F06-005 Accept N-686 Examination SAT. See AREVA RE23 Manual ISI Outage Report. Item No.: F1.20.C Equal: 1 Summary No.: Component ID: Class: System: Component Description F1.20.C.0028 MSH-109 2 MS Variable Spring Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448895 VT-3 VTr-F06-025 Reject N-686 Examination SAT. Spring Can setting within tolerance as allowed by procedure. See AREVA RE23 Manual ISI Outage Report. Evaluation Acceptable Evaluation Comments: Examination SAT. Item No.: F1.40.A Equal: 2 Summary No.: Component ID: Class: System: Component Description F1.40.A.0019 RPV-STB-1A 1 NB Reactor Vessel Stabilizer Work Order Exam Method Reoort No. Results Code Case Comments I Corrective Measures 4448891 VT-3 VT-F06-119 Accept N-686 Examination SAT. See AREVA RE23 Manual ISI Outage Report. Summary No.: Component ID: Class: System: Component Description F1.40.A.0022 RPV-STB-4A 1 NB Reactor Vessel Stabilizer Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448891 VT-3 VT-F06-120 Accept N-686 Examination SAT. See AREVA RE23 Manual ISI Outage Report. Item No.: F1.40.B Equal: 2 Summary No.: Component ID: Class: System: Component Description Fl.40.B.0003 HPCI-BP-S1 2 HPCI Booster Pump Support Work Order Exam Method ReportNo. Results Code Case Comments I Corrective Measures 4448894 VT-3 VT-F06-006 Accept N-686 Examination SAT. See AREVA RE23 Manual ISI Outage Report. Summary No.: Component ID: Class: System: Component Description F1.40.8.0004 HPCI-MP-S1 2 HPCI Main Pump Support Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448894 VT-3 VT-F06-007 Accept N-686 Examination SAT. See AREVA RE23 Manual ISI Outage Report.

Monday, February 12, 2007 Page 14 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (IfRequired): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (IfRequired): N/A Category: R-A Equal: 9 Item No.: R1.11-5 Equal: 1 Summary No.: Component ID: Class: System: Component Description C5.51.0269.RI HPEX-CF-10 2 MS Pipe to Cap Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448894 Manual UT UT-F06-109 Accept N-460 Examination SAT.

4448894 Manual UT UT-F06-108 Accept Item No.: R1.20-4 Equal: 8 Summary No.: Component ID: Class: System: Component Description B9.11.0206.RI FWD-BJ-24x 1 RF Pipe to Elbow Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448888 Manual UT UT-F06-112 Accept N-460 Examination SAT. See AREVA RE23 Manual ISI Outage Report. 4448888 Manual UT UT-F06-113 Accept Summary No.: Component ID: Class: System: Component Description B9.11.0207.RI FWD-BJ-25 1 RF Elbow to Pipe Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448888 Manual UT UT-F06-1 11 Accept N-460 Examination SAT. See AREVA RE23 Manual ISI Outage Report. 4448888 Manual UT UT-F06-1 10 Accept Summary No.: Component ID: Class: System: Component Description B9.11.0044.RI MSA-BJ-35x 1 MS Pipe to Elbow Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448889 Manual UT UT-F06-116 Accept N-460 Examination SAT. 4448889 Manual UT UT-F06-117 Accept Summary No.: Component ID: Class: System: Component Description B9.11.0045.RI MSA-BJ-36x 1 MS Elbow to Pipe Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448889 Manual UT UT-F06-114 Accept N-460 Examination SAT. See AREVA RE23 Manual ISI Outage Report. 4448889 Manual UT UT-F06-115 Accept Summary No.: Component ID: Class: System: Component Description B9.11.0064.RI MSB-BJ-28x 1 MS Pipe to Elbow Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448889 Manual UT UT-F06-119 Accept N-460 Examinaiton SAT. See AREVA RE23 Manual ISI Outage Report. 4448889 Manual UT UT-F06-118 Accept

Monday, February 12, 2007 Page 15 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description B9.11.0093.RI MSC-BJ-35x 1 MS Elbow to Pipe Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448889 Manual UT UT-F06-122 Accept N-460 Examination SAT. See AREVA RE23 Manual ISI Outage Report.

4448889 Manual UT UT-F06-123 Accept Summary No.: Component ID: Class: System: Component Description B9.11.0119.RI MSD-BJ-39x 1 MS Pipe to Elbow Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448889 Manual UT UT-F06-125 Accept N-460 Examination SAT. See AREVA RE23 Manual ISI Outage Report. 4448889 Manual UT UT-F06-124 Accept Summary No.: Component ID: Class: System: Component Description B9.11.0121.RI MSD-BJ-40x 1 MS Elbow to Pipe Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448889 Manual UT UT-F06-121 Accept N-460 Examination SAT. See AREVA RE23 Manual ISI Outage Report. 4448889 Manual UT UT-F06-120 Accept Exam Credit: VIP Equal: 212 Category: B-N-2 Equal: 12 Item No.: B13.30 Equal: 12 Summary No.: Component ID: Class: System: Component Description B13.30,0001 CSA-BKTATTWLDS@150 1 CS Core Spray A Internal Piping Bracket Attachment Welds to RPV at 150 Degrees Azimnth Work Order Exam Method ReportNo. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-137 Accept N-686 Examination SAT. VT-3 and EVT-1 (BWRVIP-18-A) obtained 100% coverage. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0002 CSA-BKTATTWLDS@30 1 CS Core Spray A Internal Piping Bracket Attachment Welds to RPV at 30 Degrees Azimnth Work Order Exam Method Report No. Results Code Case Comments ) Corrective Measures 4448881 EVT-1 VT-F06-139 Accept N-686 Examination SAT. VT-3 and EVT-1 (BWRVIP-18-A) obtained 100% coverage. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0003 CSB-BKTATTWLDS@210 1 CS Core Spray B Internal Piping Bracket Attachment Welds to RPV at 210 Degrees Azimnth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448881 EVT-1 VT-F06-141 Accept N-686 Examination SAT. VT-3 and EVT-1 (BWRVIP-18-A) obtained 100% coverage. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 16 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description B13.30.0004 CSB-BKTATTWLDS@330 1 CS Core Spray B Internal Piping Bracket Atachment Welds to RPV at 330 Degrees Azimnth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448881 EVT-1I VT-F06-143 Accept N-686 Examination SAT. VT-3 and EVT-1 (BWRVIP-18-A) obtained 100% coverage. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report.

Summary No.: Component ID: Class: SVstem: Component Description B13.30.0005 FW-ASPRBKT-ATTWLDS@5 1 RF Feedwater Sparger Bracket Attachment Welds at 5 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 EVT-1 VT-F06-122 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. VT-3 and EVT-1 (BWRVIP-48-A) exams limited to 75% coverage due to interference of Feedwater Spargers. See Section 3, Tab 8 of the AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0006 FW-ASPRBKT-ATTWLDS@85 1 RF Feedwater Sparger Bracket Attachment at 85 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 EVT-1 VT-F06-124 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. VT-3 and EVT-1 (BWRVIP-48-A) exams limited to 75% coverage due to interference of Feedwater Spargers. See Section 3, Tab 8 of the AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0007 FW-BSPRBKT-ATTWLDS@175 1 RF Feedwater Sparger Bracket Attachment Welds at 175 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 EVT-1 VT-F06-171 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. VT-3 exam limited to 90% and EVT-1 (BWRVIP-48-A) exam limited to 70% coverage due to Guide Rod interference. See Section 3, Tab 8 of the AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0008 FW-BSPRBKT-ATTWLDS@95 1 RF Feedwater Sparger Bracket Attachment at 95 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 EVT-1 VT-F06-173 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. 100% coverage for VT-3, 75% coverage for EVT-1 (BWRVIP-48-A). See Section 3, Tab 8 of the AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0009 FW-CSPRBKT-ATTWLDS@185 1 RF Feedwater Sparger Bracket Attachment Welds at 185 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 EVT-1 VT-F06-175 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. VT-3 obtained 100% coverage. EVT-1 (BWRVIP-48-A) obtained 75% coveage, limited by configuration and Guide Rod interference. See Section 3, Tab 8 of the AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0010 FW-CSPRBKT-ATTWLDS@265 1 RF Feedwater Sparger Bracket Attachment Welds at 265 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448817 EVT-1 VT-F06-177 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. VT-3 exam limited to 75% due to interference of Feedwater Sparger. EVT-1 (BWRVIP-48-A) was limited to 75% due to interference of Feedwater Sparger and Cattle Chute above. See Section 3, Tab 8 of the AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 17 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description B13.30.0011 FW-DSPRBKT-ATTWLDS@275 1 RF Feedwater Sparger Bracket Attachment Welds at 275 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 EVT-1 VT-F06-179 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. VT-3 and EVT-1 (BWRVIP-48-A) exams limited to 60% due to interference of Feedwater Sparger and Cattle Chute above.

See Section 3, Tab 8 of the AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description B13.30.0012 FW-DSPRBKT-ATTWLDS@355 1 RF Feedwater Sparger Bracket Attachment Welds at 355 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448817 EVT-1 VT-F06-126 Accept N-686 Examination SAT. Bracket to Vessel attachment weld. Exam limited due to interference of Feedwater Sparger. Both VT-3 and EVT-1 (BWRVIP-48-A) limited to 75% coverage. See Section 3, Tab 8 of the AREVA RE23 IWI Outage Report. Category: R-A Equal: 1 Item No.: R1.20-4 Equal: I Summary No.: Component ID: Class: System: Component Description B5.20.0005.RI SLC-BJ-1 1 SLC Safe-End to RPV Partial Penetration Nozzle Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 6.MISC.502 EVT-2 VE-F06-014 Accept N-686 Examination SAT. Category: V112.13 Equal: 2 Item No.: SIL462 Equal: 2 Summary No.: Component ID: Class: System: Component Description S462.SSAHC.0 SSAHC-0 N/A NB Core Shroud Access Hole Cover to Core Shroud Support Plate Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448883 EVT-1 VT-F06-255 Accept SIL 462 Examination SAT to SIL 462. See Section 3, Tab 5 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description S462.SSACH.180 SSAHC-180 N/A NB Core Shroud Access Hole Cover to Core Shroud Support Plate Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448883 EVT-1 VT-F06-256 Accept SIL 462 Examination SAT to SIL 462. See Section 3, Tab 5 of AREVA RE23 IWI Outage Report. Category: V112.15 Equal: 78 t............... 

                 .em.No..: -------..   .L474     Equ.al1:-3 3-----------------------------

Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH1H.23 STMDRY-DRCHWLD-1 H@23 N/A NB Steam Dryer Drain Channnel Weld One (1) Horizontal at 23 degree azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-036 Accept N-686, Examination SAT to SIL 474. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. SIL-474

Monday, February 12, 2007 Page 18 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH1VL.23 STMDRY-DRCHWLD-1VL@23 N/A NB Steam Dryer Drain Channnel Weld One (1) Vertical Left Side at 23 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-i VT-F06-037 Accept N-686, Examination SAT to SIL 474. Previously recorded indication (# 1) - 65" down from upper SIL-474 Support Ring; No change from previous examination. Indication was previously evaluated per EE01-127, Rev 1 as acceptable. See Section 3, Tab 4 of AREVA RE23 IVl Outage Report for data and RFO-23 Steam Dryer Report, Figure 1.

Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH1VR.23 STMDRY-DRCHWLD-1VR@23 N/A NB Steam Dryer Drain Channnel Weld One (1) Vertical Right Side at 23 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-038 Accept N-686, Examination SAT to SIL 474. Previously recorded Nonrelevant indication (#2): Area of SIL-474 corrosion - 65" down from upper Support Ring. Also noted minor cracking associated with Indication #4. No Change from previous examination. Indications were previously evaluated per EE-1-127, Rev 1 as acceptable. See Section 3, Tab 4 of AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH2H.40 STMDRY-DRCHWLD-2H@40 N/A NB Steam Dryer Drain Channnel Weld Two (2) Horizontal at 40 degree azimuth Work Order Exam Method ReportNo. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-039 Accept N-686, Examination SAT to SIL 474. See Section 3, Tab 4 of AREVA IVl Outage Report. SIL-474 Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH2VL.40 STMDRY-DRCHWLD-2VL@40 N/A NB Steam Dryer Drain Channnel Weld Two (2) Vertical Left Side at 40 degrees azimuth Work Order Exam Method ReporNo. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-040 Accept N-686, Examination SAT to SIL 474. Indication noted on bottom toe of skirt Horiz weld. Indication SIL-474 identified as Indication #6 on Figure 1 of Steam Dryer Report. See AREVA RE23 IWI Outage Report, INF # CNS-RFO-23-02 and CNS Condition Report CR-CNS-2006-7881. Indication evaluated as acceptable. Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH2VR.40 STMDRY-DRCHWLD-2VR@40 N/A NB Steam Dryer Drain Channnel Weld Two (2) Vertical Right Side at 40 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-041 Accept N-686, Examination SAT to SIL 474. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. SIL-474 Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH3H.140 STMDRY-DRCHWLD-3H@140 N/A NB Steam Dryer Drain Channnel Weld Three (3) Horizontal at 140 degree azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-042 Accept N-686, Examination SAT to SIL 474. Minor scaling & corrosion products noted on both sides of the SIL-474 weld. See Section 3, Tab 4 of AREVA RE23 IVl Outage Report.

Monday, February 12, 2007 Page 19 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH3VL.140 STMDRY-DRCHWLD-3VL@140 N/A NB Steam Dryer Drain Channnel Weld Three (3) Vertical Left Side at 140 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-I VT-F06-043 Accept N-686, Examination SAT to SIL 474. Minor scaling & corrosion products noted on both sides of the SIL-474 weld. See Section 3, Tab 4 of AREVA RE23 IVl Outage Report.

Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH3VR.140 STMDRY-DRCHWLD-3VR@140 N/A NB Steam Dryer Drain Channnel Weld Three (3) Vertical Right Side at 140 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-044 Accept N-686, Examination SAT to SIL 474. Minor scaling &corrosion products noted on both sides of the SIL-474 weld. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH4H.158 STMDRY-DRCHWLD-4H@158 N/A NB Steam Dryer Drain Channnel Weld Four (4) Horizontal at 158 degree azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-I VT-F06-045 Accept N-686, Examination SAT to SIL 474. Minor scaling &corrosion products noted on both sides of the SIL-474 weld. See Section 3, Tab 4 of AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH4VL.158 STMDRY-DRCHWLD-4VL@158 N/A NB Steam Dryer Drain Channnel Weld Four (4) Vertical Left Side at 158 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1i VT-F06-046 Accept N-686, Examination SAT to SIL 474. Minor scaling &corrosion products noted on both sides of the SIL-474 weld. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH4VR.158 STMDRY-DRCHWLD-4VR@158 N/A NB Steam Dryer Drain Channnel Weld Four (4) Vertical Right Side at 158 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-047 Accept N-686, Examination SAT to SIL 474. Minor scaling &corrosion products noted on both sides of the SIL-474 weld. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH5H.193 STMDRY-DRCHWLD-5H@193 N/A NB Steam Dryer Drain Channnel Weld Five (5) Horizontal at 193 degree azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-048 Accept N-686, Examination SAT to SIL 474. Minor scaling &corrosion products noted on both sides of the SIL-474 weld. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH5VL.193 STMDRY-DRCHWLD-5VL@193 N/A NB Steam Dryer Drain Channnel Weld Five (5) Vertical Left side at 193 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-049 Accept N-686, Examination SAT to SIL 474. Previously recorded Nonrelevant Indication - 65" down from SIL-474 upper Support Ring; Ref. EE-01-127 Rev.i. Indication identified as Indication #5 on Figure 1 of Steam Dryer Report.See Section 3, Tab 4 of AREVA RE23 IVl Outage Report.

Monday, February 12, 2007 Page 20 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH5VR.193 STMDRY-DRCHWLD-5VR@193 N/A NB Steam Dryer Drain Channnel Weld Five (5) Vertical Right Side at 193 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-050 Accept N-686, Examination SAT to SIL 474. Minor scaling & corrosion products noted on both sides of the SIL-474 weld. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report.

Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH6H.220 STMDRY-DRCHWLD-6H@220 N/A NB Steam Dryer Drain Channnel Weld Six (6) Horizontal at 220 degree azimuth Work Order Exam Method Report No. Results Code Case Comments!/Corrective Measures 4448816 VT-1 VT-F06-051 Accept N-686, Examination SAT to SIL474. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. SIL-474 Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH6VL.220 STMDRY-DRCHWLD-6VL@220 N/A NB Steam Dryer Drain Channnel Weld Six (6) Vertical Left Side at 220 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-052 Accept N-686, Examination SAT to SIL 474. Minor scaling & corrosion products noted on both sides of the SIL-474 weld. Nonrelevant line of Dark corrosion product located on Drain channel about 1/2 way down. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH6VR.220 STMDRY-DRCHWLD-6VR@220 N/A NB Steam Dryer Drain Channnel Weld Six (6) Vertical Right Side at 220 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-053 Accept N-686, Examination SAT to SIL 474. Minor scaling & corrosion products noted on both sides of the SIL-474 weld. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH7H.310 STMDRY-DRCHWLD-7H@310 N/A NB Steam Dryer Drain Channnel Weld Seven Horizontal at 310 degree azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-054 Accept N-686, Examination SAT to SIL 474. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. SIL-474 Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH7VL.310 STMDRY-DRCHWLD-7VL@310 N/A NB Steam Dryer Drain Channnel Weld Seven (7) Vertical Left Side at 310 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-055 Accept N-686, Examination SAT to SIL 474. Minor scaling & corrosion products noted on both sides of the SIL-474 weld. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH7VR.310 STMDRY-DRCHWLD-7VR@310 N/A NB Steam Dryer Drain Channnel Weld Seven (7) Vertical Right Sideat 310 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-056 Accept N-686, Examination SAT to SIL 474. Minor scaling & corrosion products noted on both sides of the SIL-474 weld. See Section 3, Tab 4 of AREVA RE23 IVV Outage Report.

Monday, February 12, 2007 Page 21 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH8H.347 STMDRY-DRCHWLD-8H@347 N/A NB Steam Dryer Drain Channnel Weld Eight (8) Horizontal at 347 degree azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-057 Accept N-686, Examination SAT to SIL 474. See Section 3, Tab 4 of AREVA RE23 IVl Outage Report.

SIL-474 Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH8VL.347 STMDRY-DRCHWLD-8VL@347 N/A NB Steam Dryer Drain Channnel Weld Eight (8) Vertical Left Side at 347 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-058 Accept N-686, Examination SAT to SIL 474. Minor scaling & corrosion products noted on both sides of the SIL-474 weld. See Section 3, Tab 4 of AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDY.DRCH8VR.347 STMDRY-DRCHWLD-8VR@347 N/A NB Steam Dryer Drain Channnel Weld Eight (8) Vertical Right Side at 347 dgrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-059 Accept N-686, Examination SAT to SIL 474. Minor scaling & corrosion products noted on both sides of the SIL-474 weld. See Section 3, Tab 4 of AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDYSKT.1-2 STMDRY-SKT-BTWDC1-2 N/A NB Steam Dryer Skirt Area between Drain Channels 1 and 2, 23 to 40 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-061 Accept N-686, Examination SAT to SIL 474. Water marks, crud lines, deposits, and scale. No change in SIL-474 the non relevant indications. See Section 3, Tab 4 of AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDYSKT.2-3 STMDRY-SKT-BTWDC2-3 N/A NB Steam Dryer Skirt Area between Drain Channels 2 and 3, 40 to 140 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-062 Accept N-686, Examination SAT to SIL 474. Water marks, crud lines, deposits, and scale. No change in SIL-474 the non relevant indications. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDYSKT.3-4 STMDRY-SKT-BTWDC3-4 N/A NB Steam Dryer Skirt Area between Drain Channels 3 and 4, 140 to 158 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-i VT-F06-063 Accept N-686, Examination SAT to SIL 474. Water marks, crud lines, deposits, and scale. No change in SIL-474 the non relevant indications. See Section 3, Tab 4 of AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDYSKT.4-5 STMDRY-SKT-BTWDC4-5 N/A NB Steam Dryer Skirt Area between Drain Channels 4-5, 158 to 193 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-064 Accept N-686, Examination SAT to SIL 474. Water marks, crud lines, deposits, and scale. No change in SIL-474 the non relevant indications. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 22 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description S474.STMDYSKT.5-6 STMDRY-SKT-BTWDC5-6 N/A NB Steam Dryer Skirt Area between Drain Channels 5 and 6, 193 to 220 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-065 Accept N-686, Examination SAT to SIL 474. Water marks, crud lines, deposits, and scale. No change in SIL-474 the non relevant indications. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report.

Summary No.: Component ID: Class: System: Component Description S474.STMDYSKT.6-7 STMDRY-SKT-BTWDC6-7 N/A NB Steam Dryer Skirt Area between Drain Channel 6 and 7, 220 to 310 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-066 Accept N-686, Examination SAT TO SIL 474. Scaling & corrosion products noted on the skirt consistent SIL-474 with previous outages. Nonrelevant Crud line located at 63" below the Upper Support Ring and 11.75 "from the 300° Drain Pipe. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report, INF-CNS-RFO-23-03. Condition documented in CNS Condition Report CR-CNS-2006-07953 but dispositioned as acceptable. Summary No.: Component ID: Class: System: Component Description S474.STMDYSKT.7-8 STMDRY-SKT-BTWDC7-8 N/A NB Steam Dryer Skirt Area between Drain Channel 7 and 8, 310 to 347 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-067 Accept N-686, Examination SAT to SIL 474. Water marks, crud lines, deposits, and scale. No change in SIL-474 the non relevant indications. See Section 3, Tab 4 of AREVA.RE23 Outage Report. Summary No.: Component ID: Class: System: Component Description S474.STMDYSKT.8-1 STMDRY-SKT-BTWDC8-1 N/A NB Steam Dryer Skirt Area between Drain Channel 8 and 1, 347 to 23 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-068 Accept N-686, Examination SAT to SIL 474. Water marks, crud lines, deposits, and scale. Previously SIL-474 recorded indications (# 3 & 4) - 36" down from upper Support Ring; Ref. EE-01-127 Rev. 1, No change in the non relevant indications. See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. Item No.: V139.H Equal: 4 Summary No.: Component ID: Class: System: Component Description V139.SD.90B1 .H001 SD-90B1-H1 N/A NB Steam Dryer Slanted Hood Outer Dryer Bank 1 Hood Lower Horizontal Weld Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-I VT-F06-071 Accept N-686, Examination SAT to BWRVIP-139. Non-relevant stain noted. See Section 3, Tab 4 of the BWRVIP139 AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.90B1 .H002 SD-90B1-H2 N/A NB Steam Dryer Slanted Hood Outer Dryer Bank 1 Hood Upper Horizontal Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-072 Accept N-686, Examination SAT to BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI Outage BWRVIP139 Report.

Monday, February 12, 2007 Page 23 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321 -0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Item No.: V139.HS Equal: 4 Summary No.: Component ID: Class: System: Component Description V139.SD.270B5A.HS003 SD-270B5-HS-A1 N/A NB Steam Dryer Slanted Hood Outer Dryer Bank 5 Hood Vertical Stiffener Plate Weld Exterior Location Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-073 Accept N-686, Examination SAT to BWRVIP-139. Non-relevant stains and scratches noted. See Section 3, BWRVIP139 Tab 4 of the AREVA RE23 IWI Outage Report.

Summary No.: Component ID: Class: System: Component Description V139.SD.270B5A.HS004 SD-270B5-HS-A2 N/A NB Steam Dryer Slanted Hood Outer Dryer Bank 5 Hood Vertical Stiffener Plate Weld Exterior Location Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-I VT-F06-074 Accept N-686, Examination SAT to BWRVIP-139. Non-relevant stains and scratches noted. See Section 3, BWRVIP139 Tab 4 of the AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.90B1E.HS001 SD-90B1-HS-E1 N/A NB Steam Dryer Slanted Hood Outer Dryer Bank 1 Hood Vertical Stiffener Plate Weld Exterior Location Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-I VT-F06-075 Accept N-686, Examination SAT to BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI Outage BWRVIP139 Report. Summary No.: Component ID: Class: System: Component Description V139.SD.90B1E.HS002 SD-90B1-HS-E2 N/A NB Steam Dryer Slanted Hood Outer Dryer Bank 1 Hood Vertical Stiffener Plate Weld Exterior Location Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-076 Accept N-686, Examination SAT to BWRVIP-139. Non-relevant flaking crud line about 5" long. See BWRVIP139 Section 3, Tab 4 of the AREVA RE23 IWI Outage Report. Item No.: V139.LR Equal: 4 Summary No.: Component ID: Class: System: Component Description V139.SD.LR.R002 SD-LR145 N/A NB Steam Dryer Slanted Hood Lifting Rod Assembley and Attchment Welds at 145 degress azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-077 Accept N-686, Examination SAT to BWRVIP-139. An indication was identifed on a tack weld between the BWRVIP139 lifting rod and lug. The indication is documented in CNS Condition Report CR-CNS-2006-07863 and evaluated as acceptable. See AREVA INF# CNS-RFO-23-01 in Section 2, Tab 2 of the AREVA RE23 IWI Outage Report for details and Section 3, Tab 4 for examination results. Indication was identified as Indication #7 in Figure 1 of the Steam Dryer Report also located in Tab 4. Summary No.: Component ID: Class: System: Component Description V139.SD.LR.R003 SD-LR215 N/A NB Steam Dryer Slanted Hood Lifting Rod Assembley and Attachment Welds at 139 degress azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-078 Accept N-686, Examination SAT to BWRVIP-139. See Section 3, Tab 4 of AREVA RE23 IWI Outage BWRVIP139 Report.

Monday, February 12, 2007 Page 24 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321 -0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V139.SD.LR.R004 SD-LR325 N/A NB Steam Dryer Slanted Hood Lifting Rod Assembley and attchment Welds at 325 degress azimuth consisting of attachment welds and tack welds Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-079 Accept N-686, Examination SAT to BWRVIP-139. See Section 3, Tab 4 of AREVA RE23 IWI Outage BWRVIP139 Report.

Summary No.: Component ID: Class: System: Component Description V139.SD.LR.RO01 SD-LR35 N/A NB Steam Dryer Slanted Hood Lifting Rod Assembley and Attachment Welds at 35 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-i VT-F06-081 Accept N-686, Examination SAT to BWRVIP-139. Nonrelevant indication noted in the center of the lifting BWRVIP139 Rod bracket due to a lap on the seam weld in the bracket. See Section 3, Tab 4 of the AREVA RE23 IWI Outage Report. Item No.: V139.R Equal: 2 Summary No.: Component ID: Class: System: Component Description V139.SD.270B5.R002 SD-270B5-R1 N/A NB Steam Dryer Slanted Hood Outer Dryer Bank 5 Cover Plate to Support Ring Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-082 Accept N-686, Examination SAT to BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI Outage BWRVIP139 Report. Summary No.: Component ID: Class: System: Component Description V139.SD.90B1.RO01 SD-90B1-R1 N/A NB Steam Dryer Slanted Hood Outer Dryer Bank 1 Cover Plate to Support Ring Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-i VT-F06-083 Accept N-686, Examination SAT to BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI Outage BWRVIP139 Report. Item No.: V139.SR Equal: 1 Summary No.: Component ID: Class: System: Component Description V139.SD.UPSP.RO01 SD-UPSUPRING N/A NB Steam Dryer Slanted Hood Upper Support Ring Assembley Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-084 Accept N-686, Examination SAT to BWRVIP-139. Scale and normal wear on Dryer Support Brackets was BWRVIP139 noted. See Section 3, Tab 4 of AREVA RE23 IVl Outage Report. Item No.: V139.TB Equal: 10 Summary No.: Component ID: Class: System: Component Description V139.SD.B2B1 .TBO10 SD-B2B1-TB10 N/A NB Steam Dryer Slanted Hood Top of Dryer Bank 2 to Top of Bank 1 Tie Bar Welds (180 degree end, east end) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-085 Accept N-686, Examination SAT to BWRVIP-139.. See Section 3, Tab 4 of the AREVA RE23 IWI Outage BWRVIP139 Report.

Monday, February 12, 2007 Page 25 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V139.SD.B2B1 .TB009 SD-B2B1-TB9 N/A NB Steam Dryer Slanted Hood Top of Dryer Bank 2 to Top of Bank 1 Tie Bar Welds (0 degree end, west end)

Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-086 Accept N-686, Examination SAT to BWRVIP-139. Non-relevant indication identified on a non-structural BWRVIP139 tack weld outside the examination area. The indication is documented in INF-CNS-RO 04 in Section 2, Tab 2 of the AREVA RE23 IWI Outage Report. See Section 3, Tab 4 of the AREVA RE23 IWI Outage Report for examination results. Summary No.: Component ID: Class: System: Component Description V139.SD.B3B2.TBOO6 SD-B3B2-TB6 N/A NB Steam Dryer Slanted Hood Top of Dryer Bank 3 to Top of Bank 2 Tie Bar Welds (0 degree end, west end) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-088 Accept N-686, Examination SAT to BWRVIP-139. Bar is slightly bent but considered non-relevant. See BWRVIP139 Section 3, Tab 4 of the AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.B3B2.TB007 SD-B3B2-TB7 N/A NB Steam Dryer Slanted Hood Top of Dryer Bank 4 to Top of Bank 3 Tie Bar Welds (center tie bar) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-089 Accept N-686, Examination SAT to BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI Outage BWRVIP139 Report. Summary No.: Component ID: Class: System: Component Description V139.SD.B3B2.TBOO8 SD-B3B2-TB8 N/A NB Steam Dryer Slanted Hood Top of Dryer Bank 3 to Top of Bank 2 Tie Bar Welds (180 degree end, east end) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-090 Accept N-686, Examination SAT to BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI Outage BWRVIP139 Report. Summary No.: Component ID: Class: System: Component Description V139.SD.B4B3.TB003 SD-B4B3-TB3 N/A NB Steam Dryer Slanted Hood Top of Dryer Bank 4 to Top of Bank 3 Tie Bar Welds (0 degree end, west end) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-091 Accept N-686, Examination SAT to BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI Outage BWRVIP139 Report. Summary No.: Component ID: Class: System: Component Description V139.SD.B4B3.TB004 SD-B4B3-TB4 N/A NB Steam Dryer Slanted Hood Top of Dryer Bank 4 to Top of Bank 3 Tie Bar Welds (center tie bar) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-i VT-F06-092 Accept N-686, Examination SAT to BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IVVI Outage BWRVIP139 Report. Summary No.: Component ID: Class: System: Component Description V139.SD.B4B3.TB005 SD-B4B3-TB5 N/A NB Steam Dryer Slanted Hood Top of Dryer Bank 4 to Top of Bank 3 Tie Bar Welds (180 degree end, east end) Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-093 Accept N-686, Examination SAT to BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI Outage BWRVIP139 Report.

Monday, February 12, 2007 Page 26 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V139.SD.B5B4.TB001 SD-B5B4-TBI N/A NB Steam Dryer Slanted Hood Top of Dryer Bank 5 to Top of Bank 4 Tie Bar Welds (0 degree end, west end)

Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-094 Accept N-686, ExExamination SAT to BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI Outage BWRVIP139 Report.. Summary No.: Component ID: Class: System: Component Description V139.SD.B5B4.TB002 SD-B5B4-TB2 N/A NB Steam Dryer Slanted Hood Top of Dryer Bank 5 to Top of Bank 4 Tie Bar Welds (180 degree end, east end) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-095 Accept N-686, Examination SAT to BWRVIP-139. Non-relevant indication identified on a non-structural BWRVIP139 tack weld outside the examination area. The indication is documented in INF-CNS-RO 04 in Section 2, Tab 2 of the AREVA RE23 IVl Outage Report. See Section 3, Tab 4 of the AREVA RE23 IWI Outage Report for examination results. Item No.: V139.V Equal: 20 Summary No.: Component ID: Class: System: Component Description V139.SD.0B1.V001 SD-0B1-V1 N/A NB Steam Dryer Slanted Hood Outer Dryer Bank 1 End Plate Vertical Weld (0 degree side, southwest weld) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-097 Accept N-686, Examination SAT. Reference BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI BWRVIP139 Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.0B1.V002 SD-0B1-V2 N/A NB Steam Dryer Slanted Hood Outer Dryer Bank 1 End Plate Vertical Weld (0 degree side, northwest weld) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-098 Accept N-686, Examination SAT. Reference BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI BWRVIP139 Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.0B2.V005 SD-0B2-V1 N/A NB Steam Dryer Slanted Hood Inner Dryer Bank 2 End Plate Vertical Weld (0 degree side, northwest weld) Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-099 Accept N-686, Examination SAT. Reference BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI BWRVIP139 Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.0B2.V006 SD-0B2-V2 N/A NB Steam Dryer Slanted Hood Inner Dryer Bank 2 End Plate Vertical Weld (0 degree side, northwest weld) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-I VT-F06-100 Accept N-686, Examination SAT. Reference BWRVIP-139. See Seclion 3, Tab 4 of the AREVA RE23 IWI BWRVIP139 Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.0B3.V009 SD-0B3-Vi N/A NB Steam Dryer Slanted Hood Inner Dryer Bank 3 End Plate Vertical Weld (0 degree side, southwest weld) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-101 Accept N-686, Examination SAT. Reference BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI BWRVIP13c9 Outage Report.

Monday, February 12, 2007 Page 27 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V139.SD.0B3.VO10 SD-0B3-V2 N/A NB Steam Dryer Slanted Hood Inner Dryer Bank 3 End Plate Vertical Weld (0 degree side, northwest weld)

Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-102 Accept N-686, Examination SAT. Reference BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI BWRVIP139 Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.0B4.V013 SD-0B4-V1 N/A NB Steam Dryer Slanted Hood Inner Dryer Bank 4 End Plate Vertical Weld (0 degree side, southwest weld) Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-103 Accept N-686, Examination SAT. Scale and corrosion products adjacent to weld. Reference BWRVIP-139. BWRVIP139 See Section 3, Tab 4 of the AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.0B4.V014 SD-0B4-V2 N/A NB Steam Dryer Slanted Hood Inner Dryer Bank 4 End Plate Vertical Weld (0 degree side, northwest weld) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-104 Accept N-686, Examination SAT. Reference BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI BWRVIP139 Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.0B5.V017 SD-0B5-V1 N/A NB Steam Dryer Slanted Hood Inner Dryer Bank 5 End Plate Vertical Weld (0 degree side, southwest weld) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-105 Accept N-686, Examination SAT. Scale and corrosion flaking. Reference BWRVIP-139. See Section 3, BWRVIP139 Tab 4 of the AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.0B5.V018 SD-0B5-V2 N/A NB Steam Dryer Slanted Hood Inner Dryer Bank 5 End Plate Vertical Weld (0 degree side, northwest weld) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-106 Accept N-686, Examination SAT. Scale and corrosion flaking. Reference BWRVIP-139. See Section 3, BWRVIP139 Tab 4 of the AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.180B1 .V003 SD-180B1-V3 N/A NB Steam Dryer Slanted Hood Outer Dryer Bank 1 End Plate Vertical Weld (180 degree, northeast weld) Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-107 Accept N-686, Examination SAT. Scale and corrosion products adjacent to weld. Reference BWRVIP-139. BWRVIP139 See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.180B1.V004 SD-180B1-V4 N/A NB Steam Dryer Slanted Hood Outer Dryer Bank 1 End Plate Vertical Weld (180 degree side, southeast weld) Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-108 Accept N-686, Examination SAT. Scale and corrosion products adjacent to weld. Reference BWRVIP-139. BWRVIP13 9 See Section 3, Tab 4 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 28 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V139.SD.180B2.V007 SD-180B2-V3 N/A NB Steam Dryer Slanted Hood Inner Dryer Bank 2 End Plate Vertical Weld (180 degree side, northeast weld)

Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-I VT-F06-109 Accept N-686, Examination SAT to BWRVIP-139. Previously recorded indication: Nonrelevant indication BWRVIP139 (lap or scale layer) on right side of weld just above the leveling screw. See Section 3, Tab 4 of AREVA RE23 Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.180B2.V008 SD-180B2-V4 N/A NB Steam Dryer Slanted Hood Inner Dryer Bank 2 End Plate Vertical Weld (180 degree side, southeast weld) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT--F06-110 Accept N-686, Examination SAT. Scale and corrosion products adjacent to weld. Reference BWRVIP-139. BWRVIP139 See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.180B3.VO1 1 SD-180B3-V3 N/A NB Steam Dryer Slanted Hood Inner Dryer Bank 3 End Plate Vertical Weld (180 degree side, northeast weld) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448816 VT-1 VT-F06-111 Accept N-686, Examination SAT to BWRVIP-139. See Section 3, Tab 4 of AREVA RE23 IWI Outage BWRVIP139 Report. Summary No.: Component ID: Class: System: Component Description V139.SD.180B3.V012 SD-180B3-V4 N/A NB Steam Dryer Slanted Hood Inner Dryer Bank 3 End Plate Vertical Weld (180 degree side, southeast weld) Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-112 Accept N-686, Examination SAT. Scale and corrosion products adjacent to weld. Reference BWRVIP-139. BWRVIP139 See Section 3, Tab 4 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V139.SD.180B4.VO15 SD-180B4-V3 N/A NB Steam Dryer Slanted Hood Outer Dryer Bank 4 End Plate Vertical Weld (180 degree, northeast weld) Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448816 VT-1 VT-F06-113 Accept N-686, Examination SAT to BWRVIP-139. See Section 3, Tab 4 of the AREVA RE23 IWI Outage BWRVIP139 Report. Category: VIP18 Equal: 78 Item No.: 

-----------------------------   V18.P1         Equal: 2                                .

Summary No.: Component ID: Class: System: Component Description V18.P1.TBJ.90 CS-A-TJB@90-(P1) N/A CS Core Spray Piping Tee Junction Box at 90 degrees azimuth, Thermal Sleeve to Junction Box Weld (hidden) Examine the accessible top and bottom outside surfaces of the Tee Junction Box Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-144 Accept BWRVIP18A Examination SAT. Examined the accessible top and bottom surfaces of the Tee Junction Box. Previously recorded Ind. from 180° - 200° No apparent change from previously recorded Indications. Ref. CNS Condition Report CR-CNS-2006-8668. Previous indication was evaluated as acceptable per NEDC 02-052. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 29 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (IfRequired): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (IfRequired): N/A Summary No.: Component ID: Class: System: Component Description V18.P1.TBJ.270 CS-B-TJB@270-(Pl) N/A CS Core Spray Piping Tee Junction Box at 270 degrees azimuth, Thermal Sleeve to Junction Box Weld (hidden) Examine the accessible top and bottom outside surfaces of the Tee Junction Box Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-225 Accept BWRVIP18A Examination SAT.Examination limited to 75% of all adjacent surfaces due to the proximity of the RPV and the Junction box configuration. Thermal sleeve is welded on the OD.

Nonrelevant scratch mark located adjacent to weld at approx. 45°. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Item No.: V18.P2 Equal: 2 Summary No.: Component ID: Class: System: Component Description V18.P2.A11.90 CS-Al1 @90-(P2) N/A CS Core Spray Piping Tee Junction Box at 90 degrees azimuth, Cover Plate to Junction Box Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-145 Accept BWRVIP18A Examination SAT. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.P2.B11.270 CS-B1 1@270-(P2) N/A CS Core Spray Piping Tee Junction Box at 270 degrees azimuth, Cover Plate to Junction Box Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-226 Accept BWRVIP18A Examination SAT. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. 

        . . . .Item -No.-: - - --V1_8.P3 --- -Equal1: 4 - - - - - - - - - - - - - - -

Summary No.: Component ID: Class: System: Component Description V18.P3.A10.90 CS-Al0@90-(P3) N/A CS Core Spray Piping Tee Junction Box at 90 degrees azimuth, Horizontal Pipe to Junction Box Weld, from Downcomer "C" Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448881 EVT-1 VT-F06-146 Accept BWRVIP18A Examination SAT. Examination limited to 50% due to proximity of the RPV. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.P3.A12.90 CS-A12@90-(P3) N/A CS Core Spray Piping Tee Junction Box at 90 degrese azimuth, Horizontal Pipe to Junction Box Weld, to Downcomer "A" Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-147 Accept BWRVIP18A Examination SAT. Grinding noted on core side of header piping. Exam limited to 50 % due to proximity of the RPV. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.P3.B10.270 CS-BlO@270-(P3) N/A CS Core Spray Piping Tee Junction Box at 270 degrees azimuth, Horizontal Pipe to Junction Box Weld, from Downcomer "B" Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-227 Accept BWRVIP18A Examination SAT. Examination limited to 60% due to proximity of the RPV. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.P3.B12.270 CS-Bl2@270-(P3) N/A CS Core Spray Piping Tee Junction Box at 270 degrees azimuth, Horizontal Pipe to Junction Box Weld, to Downcomer "D" Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-228 Accept BWRVIP18A Examination SAT. Examination limited to 60% due to proximity of the RPV. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 30 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A

" Item No.: V18.P4 Equal: 4 " Summary No.: Component ID: Class: System: Component Description V18.P4d.B3.350 CS-B3@350-(P4d) N/A CS Core Spray Piping, Elbow to Shroud Pipe, off Downcomer "B"at 350 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-148 Accept BWRVIP18A Examination SAT. See Section 3, Tab 1 of AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description V18.P4c.B4.350 CS-B4@350-(P4c) N/A CS Core Spray Piping, Lower Downcomer "B" to Elbow at 350 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-149 Accept BWRVIP18A Examination SAT. Examination limited to 60% due to proximity of the RPV. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.P4b.B8.350 CS-B8@350-(P4b) N/A CS Core Spray Piping, Elbow to Pipe Downcomer "B" at 350 degree azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-150 Accept BWRVIP18A Examination SAT. Examination limited to 70% due to proximity of the RPV. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.P4a.B9.350 CS-B9@350-(P4a) N/A CS Core Spray Piping, Horizontal Pipe to Elbow, off Downcomer "B" at 350 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-151 Accept BWRVIP18A Examination SAT. Examination limited to 50% due to proximity of the RPV and FW spargers. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. 

.             Item No.:    V18.P5      Equal: 4 -

Summary No.: Component ID: Class: System: Component Description V18.P5.A15.10 CS-A15@10-(P5) N/A CS Core Spray Piping, Sliding Sleeve to Upper Downcomer "A" at 10 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-152 Accept BWRVIP18A Examination SAT. Examination limited to 70% due to proximity of the RPV. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.P5.A7.170 CS-A7@170-(P5) N/A CS Core Spray Piping, Sliding Sleeve to Upper Downcomer "C" at 170 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-153 Accept BWRVIP18A Examination SAT. Examination limited to 60% due to proximity of the RPV and Shroud. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.P5.B 15.190 CS-B 15@190-(P5) N/A CS Core Spray Piping, Sliding Sleeve to Upper Downcomer "D" at 190 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-154 Accept BWRVIP18A Examination SAT. Examination limited to 60% due to proximity of the RPV. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 31 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V18.P5.B7.350 CS-B7@350-(P5) N/A CS Core Spray Piping, Sliding Sleeve to Upper Downcomer "B"at 350 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-155 Accept BWRVIP18A Examination SAT. Examination limited to 60% due to proximity of the RPV and shroud. See Section 3, Tab 1 of.AREVA RE23 IWI Outage Report.

Item No.: V18.P6 Equal: 4 Summary No.: Component ID: Class: System: Component Description V18.P6.A16.10 CS-A16@10-(P6) N/A CS Core Spray Piping, Sliding Sleeve Weld to Outer Sleeve, off Downcomer "A"at 10 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-156 Accept BWRVIP18A Examination SAT. Examination limited to 70% due to proximity of the RPV. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.P6.A6.170 CS-A6@170-(P6) N/A CS Core Spray Piping, Sliding Sleeve Weld to Outer Sleeve, off Downcomer "C" at 170 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-157 Accept BWRVIP18A Examination SAT. Examination limited to 60% due to proximity of the RPV and Shroud. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.P6.B16.190 CS-B16@190-(P6) N/A CS Core Spray Piping, Sliding Sleeve Weld to Outer Sleeve, off Downcomer "D"at 190 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-158 Accept BWRVIP18A Examination SAT. Examination limited to 60% due to proximity of the RPV. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.P6.B6.350 CS-B6@350-(P6) N/A CS Core Spray Piping, Sliding Sleeve Weld to Outer Sleeve, off Downcomer "B"at 350 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448881 EVT-1 VT-F06-159 Accept BWRVIP18A Examination SAT. Examination limited to 60% due to proximity of the RPV and shroud. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Item No.: V18.P7 Equal: 4 Summary No.: Component ID: Class: System: Component Description V18.P7.A17.10 CS-A17@10-(P7) N/A CS Core Spray Piping, Outer Sleeve to Lower Downcomer "A"at 10 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-160 Accept BWRVIP18A Examination SAT. Examination limited to 55% due to proximity of the RPV. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.P7.A5.170 CS-A5@170-(P7) N/A CS Core Spray Piping, Outer Sleeve to Lower Downcomer "C" at 170 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-161 Accept BWRVIP18A Examination SAT. Examination limited to 50% due to proximity of the RPV, Shroud and guide rod interference. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 32 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V18.P7.B17.190 CS-B17@190-(P7) N/A CS Core Spray Piping, Outer Sleeve to Lower Downcomer "D" at 190 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-162 Accept BWRVIP18A Examination SAT. Examination limited to 60% due to proximity of the RPV. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report.

Summary No.: Component ID: Class: System: Component Description V18.P7.B5.350 CS-B5@350-(P7) N/A CS Core Spray Piping, Outer Sleeve to Lower Downcomer "B" at 350 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-163 Accept BWRVIP18A Examination SAT. Examination limited to 50% due to proximity of the RPV and shroud. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Item No.: V18.P8 Equal: 8 Summary No.: Component ID: Class: System: Component Description V18.P8b.A1.170 CS-A1@170-(P8b) N/A CS Core Spray Piping Downcomer "C" at 170 degrees azimuth, Collar to Shroud Weld Work Order Exam Method ReportNo. Results Code Case Comments / Corrective Measures 4448882 Remote Auto UT VE-F06-009 Accept BWRVIP18A Examination SAT. EVT-1 examination limited to 90% due to proximity of the downcommer above. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. UT examination reported NRI however was limited to 50% coverage. See Sections 1 and 3 of AREVA RE23 Automated UT Outage Report. 4448882 EVT-1 VT-F06-028 Accept Summary No.: Component ID: Class: System: Component Description V18.P8a.A2.170 CS-A2@170-(P8a) N/A CS Core Spray Piping Downcomer "C" at 170 degrees azimuth, Collar to Shroud Weld Work Order Exam Method Report No. Results Code Case Comments ! Corrective Measures 4448882 Remote Auto UT VE-F06-005 Accept BWRVIP18A Examination SAT. EVT-1 examination limited to 90% due to proximity of the downcommer above. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. UT examination reported NRI however was limited to 50% coverage. See Sections 1 and 3 of AREVA RE23 Automated UT Outage Report. 4448882 EVT-1 VT-F06-029 Accept Summary No.: Component ID: Class: System: Component Description V18.P8a.A20.10 CS-A20@10-(P8a) N/A CS Core Spray Piping Downcomer "A" at 10 degress azimuth, Collar to Shroud Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448882 Remote Auto UT VE-F06-006 Accept BWRVIP18A Examination SAT. EVT-1 examination limited to 90% due to proximity of the downcommer above. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. UT examination reported NRI however was limited to 50% coverage. See Sections 1 and 3 of AREVA RE23 Automated UT Outage Report. 4448882 EVT-1 VT-F06-030 Accept

Monday, February 12, 2007 Page 33 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V18.P8b.A21.10 CS-A21@10-(P8b) N/A CS Core Spray Piping Downcomer "A" at 10 degrees azimuth, Collar to Shroud Weld Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448882 Remote Auto UT VE-F06-010 Accept BWRVIP18A Examination SAT. Ref. EVT-1 exam limited to 90% due to proximity of the downcommer above. No apparent change from prev. recorded Indications at AZ 310 -10. Ref. CNS Condition Report CR-CNS-2006-8668. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. UT examination confirmed the visual indication with no apparent change from UT previous examination however UT was limited to 50%. See Sections 1 and 3 of AREVA RE23 Automated UT Outage Report. Previous indication was evaluated as acceptable per NEDC 98-054.

4448882 EVT-1 VT-F06-031 Accept Summary No.: Component ID: Class: System: Component Description V18.P8b.B1.350 CS-B1 @350-(P8b) N/A CS Core Spray Piping Downcomer "B" at 350 degrees azimuth, Collar to Shroud Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448882 EVT-1 VT-F06-032 Accept BWRVIP18A Examination SAT. EVT-1 examination limited to 90% due to proximity of the downcommer above. See Section 3, Tab 1 of AREVA RE23 IVl Outage Report. UT examination reported NRI however was limited to 50% coverage. See Sections 1 and 3 of AREVA RE23 Automated UT Outage Report. 4448882 Remote Auto UT VE-F06-011 Accept Summary No.: Component ID: Class: System: Component Description V18.P8a.B2.350 CS-B2@350-(P8a) N/A CS Core Spray Piping Downcomer "B" at 350 degrees azimuth, Collar to Shroud Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448882 EVT-1 VT-F06-033 Accept BWRVIP18A Examination SAT. EVT-1 examination limited to 90% due to proximity of the downcommer above. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. UT examination reported NRI however was limited to 50% coverage. See Sections 1 and 3 of AREVA RE23 Automated UT Outage Report. 4448882 Remote Auto UT VE-F06-007 Accept Summary No.: Component ID: Class: System: Component Description V18.P8a.B20.190 CS-B20@190-(P8a) N/A CS Core Spray Piping Downcomer "D" at 190 degrees azimuth, Collar to Shroud Weld Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448882 Remote Auto UT VE-F06-008 Accept BWRVIP18A Examination SAT. Ref. EVT-1 exam limited to 90% due to proximity of the downcommer above. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. UT examination was limited to 50%. An indication previously identified in RE20 by UT did not show any appreciable change. See Sections 1 and 3 of AREVA RE23 Automated UT Outage Report. Previous indication was evaluated as acceptable per NEDC 98-054. 4448882 EVT-1 VT-F06-034 Accept

Monday, February 12, 2007 Page 34 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V18.P8b.B21.190 CS-B21 @190-(P8b) N/A CS Core Spray Piping Downcomer "D" at 190 degrees azimuth, Collar to Shroud Pipe Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448882 Remote Auto UT VE-F06-012 Accept BWRVIP18A Examination SAT. EVT-1 examination limited to 90% due to proximity of the downcommer above. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. UT examination reported NRI however was limited to 50% coverage. See Sections 1 and 3 of AREVA RE23 Automated UT Outage Report.

4448882 EVT-1 VT-F06-035 Accept Item No.: V18.PB Equal: 4 Summary No.: Component ID: Class: System: Component Description V18.PB.A.150 PB-CSA@150 N/A CS Core Spray A Internal Piping Brackets (bracket to RPV Welds Heat-Affected zones on bracket side, bolting, and tack welds to bolting) Downcomer "C" side at 150 degree azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-164 Accept BWRVIP18A Examination SAT. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.PB.A.30 PB-CSA@30 N/A CS Core Spray A Internal Piping Brackets (Includes Attachment Welds to RPV, Heat-Affected zones, and Tack Welds to Bolting) Downcomer "A" side at 30 degree azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448881 EVT-1 VT-F06-165 Accept BWRVIP18A Examination SAT. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.PB.B.210 PB-CSB@210 N/A CS Core Spray B Internal Piping Brackets (Includes Attachment Welds to RPV, Heat-Affected zones, and Tack Welds to Bolting) Downcomer "D" side at 210 degree azimuth Work Order Exam Method ReportNo. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-166 Accept BWRVIP18A Examination SAT. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.PB.B.330 PB-CSB@330 N/A CS Core Spray B Internal Piping Brackets (Includes Attachment Welds to RPV, Heat-Affected zones, and Tack Welds to Bolting) Downcomer "B" side at 330 degree azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448881 EVT-1 VT-F06-167 Accept BWRVIP18A Examination SAT. See Section 3, Tab 1 of AREVA RE23 IWI Outage Report. Item No.: V18.S Equal: 2 Summary No.: Component ID: Class: System: Component Description V18.S.BLX.346 S-BL-XTRW@346 N/A CS Core Spray Sparger "B" Lower, Sparger Pipe to Sparger Pipe, Extra Weld at 346 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 EVT-1 VT-F06-132 Accept BWRVIP18A Examination SAT. This is an additional field weld added during construction. Examination limited to 45% Coverage. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 35 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V18.S.BLX.354 S-BL-XTRW@354 N/A CS CoreSpray Sparger "B" Lower, Sparger Pipe to Sparger Pipe, Extra Weld at 354 degrees azi muth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448880 EVT-1 VT-F06-133 Accept BWRVIP18A Examination SAT. This is an additional field weld added during construction. Examination limited to 50% Coverage. See Section 3, Tab 2 of AREVA RE23 IVl Outage Report.

Item No.: V18.S1 Equal: 4 Summary No.: Component ID: Class: System: Component Description V18.S1.AUTB.10 S1-AU-TB@10 N/A CS Core Spray Sparger "A" Upper Tee Box at 10 degrees azimuth, Cover Plate to Sparger Tee Box Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 EVT-1 VT-F06-234 Accept BWRVIP18A Examination SAT. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.1 .BLTB.350 S1-BL-TB@350 N/A CS Core Spray Sparger "B" Lower Tee Box at 350 degrees azimuth, Cover Plate to Sparger Tee Box Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 EVT-1 VT-F06-134 Accept BWRVIP18A Examination SAT. NRI however, arc strike and scratch were noted. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: Svstem: Component Description V18.1 .CUTB.170 S1-CU-TB@170 N/A CS Core Spray Sparger "C" Upper Tee Box at 170 degrees azimuth, Cover Plate to Sparger Tee Box Weld Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448880 EVT-1 VT-F06-236 Accept BWRVIP18A Examination SAT. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.S1 .DLTB.190 S1-DL-TB@190 N/A CS Core Spray Sparger "D" Lower Tee Box at 190 degrees azimuth, Cover Plate to Sparger Tee Box Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 EVT-1 VT-F06-235 Accept BWRVIP18A Examination SAT. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Item No.: V18.S2 Equal: 8 Summary No.: Component ID: Class: System: Component Description V18.S2.AUTB.12 S2@12-AU-TB@10 N/A CS Core Spray Sparger "A" Upper Tee Box at 10 degrees azimuth, Sparger Pipe to Tee Box Weld at 12 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448880 EVT-1 VT-F06-237 Accept BWRVIP18A Examination SAT. Examination limited to 45% due to proximity of the Shroud and Sparger Nozzles. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.S2.CUTB.168 S2@168-CU-TB@170 N/A CS Core Spray Sparger "C" Upper Tee Box at 170 degrees azimuth, Sparger Pipe to Tee Box Weld at 168 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 EVT-1 VT-F06-238 Accept BWRVIP18A Examination SAT. Examination limited to 45% due to proximity of the Shroud and Sparger Nozzles. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 36 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V18.S2.CUTB.172 $2@172-CU-TB@170 N/A CS Core Spray Sparger "C" Upper Tee Box at 170 degrees azimuth, Sparger Pipe to Tee Box Weld at 172 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 EVT-1 VT-F06-239 Accept BWRVIP18A Examination SAT. Examination limited to 45% due to proximity of the Shroud and Sparger Nozzles. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report.

Summary No.: Component ID: Class: System: Component Description V18.S2.DLTB.188 S2@188-DL-TB@190 N/A CS Core Spray Sparger "D"Lower Tee Box at 190 degrees azimuth, Sparger Pipe to Tee Box Weld at 188 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 EVT-1 VT-F06-240 Accept BWRVIP18A Examination SAT. Examination limited to 40% due to proximity of the Shroud, Sparger Nozzles and Top Guide. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.S2.DLTB.192 S2@192-DL-TB@190 N/A CS Core Spray Sparger "D"Lower Tee Box at 190 degrees azimuth, Sparger Pipe to Tee Box Weld at 192 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448880 EVT-1 VT-F06-241 Accept BWRVIP18A Examination SAT. Examination limited to 40% due to proximity of the Shroud, Sparger Nozzles and Top Guide. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18,S2.BLTB.348 S2@348-BL-TB@350 N/A CS Core Spray Sparger "B"Lower Tee Box at 350 degrees azimuth, Sparger Pipe to Tee Box Weld at 348 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448880 EVT-1 VT-F06-135 Accept BWRVIP18A Examination SAT. Examination limited to 45% due to proximity of the Shroud, Sparger Nozzles, and Top Guide. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.S2.BLTB.352 S2@352-BL-TB@350 N/A CS Core Spray Sparger "B"Lower Tee Box at 350 degrees azimuth, Sparger Pipe to Tee Box Weld at 352 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 EVT-1 VT'-F06-216 Accept BWRVIP18A Examination SAT. Examination limited to 45% due to proximity of the Shroud, Sparger Nozzles and Top Guide. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.S2.AUTB.8 S2@8-AU-TB@10 N/A CS Core Spray Sparger "A"Upper Tee Box at 10 degrees azimuth, Sparger Pipe to Tee Box Weld at 8 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 EVT-1 VT-F06-242 Accept BWRVIP18A Examination SAT. Examination limited to 45% due to proximity of the Shroud and Sparger Nozzles. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Item No.: V18.S3a Equal: 2 Summary No.: Component ID: Class: System: Component Description V18.S3a.BLNSW S3a-BL-NSPW@271>89 N/A CS Core Spray Sparger "B" Lower, Nozzle to Sparger Pipe Welds, all spray nozzles from 89 to 271 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 VT-1 VT-F06-272 Accept BWRVIP18A Examination SAT. Examined the accessible areas of the nozzles and tack welds. Coverage was limited to 50%. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 37 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V18.S3a.DLNSW S3a-DL-NSPW@92>269 N/A CS Core Spray Sparger "D" Lower, Nozzle to Sparger Pipe Welds, all spray nozzles from 92 to 269 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 VT-i VT-F06-273 Accept BWRVIP18A Examination SAT. Examined the accessible areas of the nozzles and tack welds.

Coverage was limited to 50%. See Section 3, Tab 2 of AREVA RE23.IWI Outage Report. Item No.: V18.S3b Equal: 2 Summary No.: Component ID: Class: System: Component Description V18.S3b.BLNOW S3b-BL-NOW@271>89 N/A CS Core Spray Sparger "B" Lower, Nozzle to Orifice Welds, all spray nozzles from 89 to 271 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 VT-1 VT-F06-274 Accept BWRVIP18A Examination SAT. Examined the accessible areas of the nozzles and tack welds. Coverage was limited to 50%. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.S3b.DLNOW S3b-DL-NOW@92>269 N/A CS Core Spray Sparger "D" Lower, Nozzle to Orifice Welds, all spray nozzles from 92 to 269 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 VT-1 VT-F06-275 Accept BWRVIP18A Examination SAT. Examined the accessible areas of the nozzles and tack welds. Coverage was limited to 50%. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Item No.: V18.S3c Equal: 2 Summary No.: Component ID: Class: System: Component Description V18.S3c.BLD.279 S3c-BL-DRSPW@279 N/A CS Core Spray Sparger "B" Lower, Drain to Sparger Pipe Weld at 279 degrees azimuth, Includes Tack Weld on Drain Plug Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 VT-1 VT-F06-276 Accept BWRVIP18A Examination SAT. Examination limited to 50% coverage. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.S3c.BLD.81 S3c-BL-DRSPW@81 N/A CS Core Spray Sparger "B" Lower, Drain to Sparger Pipe Weld at 81 degrees azimuth, Includes Tack Weld on Drain Plug Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448880 VT-1 VT-F06-243 Accept BWRVIP18A Examination SAT. Examination limited to 50% coverage. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Item No.: V18.S4 Equal: 8 Summary No.: Component ID: Class: System: Component Description V18.S4.AUEC.271 S4-AU-ECSPW@271 N/A CS Core Spray Sparger "A" Upper, End Cap to Sparger Pipe Weld at 271 degrees azimuth Assumed to be creviced internally Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448880 EVT-1 VT-F06-217 Accept BWRVIP18A Examination SAT. Examination limited to 50% due to proximity of the Shroud and Sparger brackets. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.S4.AUEC.89 S4-AU-ECSPW@89 N/A CS Core Spray Sparger "A" Upper, End Cap to Sparger Pipe Weld at 89 degrees azimuth Assumed to be creviced internally Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 EVT-1 VT-F06-244 Accept BWRVIP18A Examination SAT. Examination limited to 40% due to proximity of the Shroud and Sparger brackets. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 38 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V18.S4.BLEC.271 S4-BL-ECSPW@271 N/A CS Core Spray Sparger "B"Lower, End Cap to Sparger Pipe Weld at 271 degrees azimuth Assumed to be creviced internally Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 EVT-1 VT-F06-218 Accept BWRVIP18A Examination SAT. Examination limited to 35% due to proximity of the Shroud and Sparger brackets. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report.

Summary No.: Component ID: Class: System: Component Description V18.S4.BLEC.89 S4-BL-ECSPW@89 N/A CS Core Spray Sparger "B"Lower, End Cap to Sparger Pipe Weld at 89 degrees azimuth Assumed to be creviced internally Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 EVT-1 VT-F06-245 Accept BWRVIP18A Examination SAT. Examination limited to 35% due to proximity of the Shroud and Sparger brackets. See Section 3, Tab 2 of AREVA RE23 iWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.S4.CUEC.269 S4-CU-ECSPW@269 N/A CS Core Spray Sparger "C" Upper, End Cap to Sparger Pipe Weld at 269 degrees azimuth Assumed to be creviced internally Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 EVT-1 VT-F06-219 Accept BWRVIP18A Examination SAT. Examination limited to 40% due to proximity of the Shroud and Sparger brackets. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.S4.CUEC.91 S4-CU-ECSPW@91 N/A CS Core Spray Sparger "C" Upper, End Cap to Sparger Pipe Weld at 93 degrees azimuth Assumed to be creviced internally Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448880 EVT-1 VT-F06-246 Accept BWRVIP18A Examination SAT. Examination limited to 40% due to proximity of the Shroud and Sparger brackets. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.S4.DLEC.269 S4-DL-ECSPW@269 N/A CS Core Spray Sparger "D"Lower, End Cap to Sparger Pipe Weld at 269 degrees azimuth Assumed to be creviced internally Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448880 EVT-1 VT-F06-220 Accept BWRVIP18A Examination SAT. Examination limited to 40% due to proximity of the Shroud and Sparger brackets. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.S4.DLEC.91 S4-DL-ECSPW@91 N/A CS Core Spray Sparger "D"Lower, End Cap to Sparger Pipe Weld at 91 degrees azimuth Assumed to be creviced internallyN/A Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 EVT-11 VT-F06-247 Accept BWRVIP18A Examination SAT. Examination limited to 35% due to proximity of the Shroud and Sparger brackets. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Item No.: V18.SB Equal: 14 . Summary No.: Component ID: Class: System: Component Description V18.SB.AUBL.272 SB-AU-BL-SPR@272 N/A CS Core Spray Sparger Bracket at 272 degrees azimuth between CS Sparger "A"Upper and CS Sparger "B" Lower Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448880 VT-1 VT-F06-248 Accept BWRVIP18A Examination SAT. Examination coverage limited to 70%. See Section 3, Tab 2 of AREVA RE23 IVl Outage Report.

Monday, February 12, 2007 Page 39 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V18.SB.AUBL.299 SB-AU-BL-SPR@299 N/A CS Core Spray Sparger Bracket at 299 degrees azimuth between CS Sparger "A" Upper and CS Sparger "B" Lower Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448880 VT-1 VT-F06-249 Accept BWRVIP18A Examination SAT.Examinalion coverage limited to 80%. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report.

Summary No.: Component ID: Class: System: Component Description V18.SB.AUBL.30 SB-AU-BL-SPR@30.5 N/A CS Core Spray Sparger Bracket at 30.5 degrees azimuth between CS Sparger "A" Upper and CS Sparger "B" Lower Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 VT-1 VT-F06-250 Accept BWRVIP18A Examination SAT.Examination coverage limited to 80%. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.SB.AUBL.329 SB-AU-BL-SPR@329.5 N/A CS Core Spray Sparger Bracket at 329.5 degrees azimuth between CS Sparger "A" Upper and CS Sparger "B" Lower Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448880 VT-1 VT-F06-251 Accept BWRVIP18A Examination SAT.Examination coverage limited to 80%. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.SB.AUBL.61 SB-AU-BL-SPR@61 N/A CS Core Spray Sparger Bracket at 61 degrees azimuth between CS Sparger "A" Upper and CS Sparger "B" Lower Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 VT-I VT-F06-252 Accept BWRVIP18A Examination SAT. Examination coverage limited to 80%. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.SB.AUBL.88 SB-AU-BL-SPR@88 N/A CS Core Spray Sparger Bracket at 88 degree azimuth between CS Sparger "A" Upper and CS Sparger "B" Lower Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 VT-1 VT-F06-253 Accept BWRVIP18A Examination SAT. Examination coverage limited to 80%. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.SB.BL.DL.270 SB-BL-DL-SPR@270 N/A CS Core Spray Sparger Bracket at 270 degrees azimuth between CS Sparger "B" Lower and CS Sparger "D" Lower Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 VT-1 VT-F06-221 Accept BWRVIP18A Examination SAT. Examination coverage limited to 65%. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.SB.BLDL.90 SB-BL-DL-SPR@90 N/A CS Core Spray Sparger Bracket at 90 degrees azimuth between CS Sparger "B" Lower and CS Sparger "D" Lower Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448880 VT-1 VT-F06-277 Accept BWRVIP18A Examination SAT. Examination coverage limited to 50%. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 40 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V18.SB.CUDL.119 SB-CU-DL-SPR@1 19 N/A CS Core Spray Sparger Bracket at 119 degrees azimuth betwee CS Sparger "C" Upper and CS Sparger "D"Lower Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448880 VT-1 VT-F06-254 Accept BWRVIP18A Examination SAT. Examination coverage limited to 90%. See Section 3, Tab 2 of AREVA RE23 IVl Outage Report.

Summary No.: Component ID: Class: System: Component Description V18.SB.CUDL.149 SB-CU-DL-SPR@149.5 N/A CS Core Spray Sparger Bracket at 149.5 degrees azimuth betwee CS Sparger "C" Upper and CS Sparger "D"Lower Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 VT-1 VT-F06-278 Accept BWRVIP18A Examination SAT. Examination coverage limited to 90%. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.SB.CUDL.210 SB-CU-DL-SPR@210.5 N/A CS Core Spray Sparger Bracket at 210.5 degrees azimuth betwee CS Sparger "C" Upper and CS Sparger "D"Lower Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 VT-1 VT-F06-222 Accept BWRVIP18A Examination SAT. Examination coverage limited to 90%. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.SB.CUDL.241 SB-CU-DL-SPR@241 N/A CS Core Spray Sparger Bracket at 241 degrees azimuth betwee CS Sparger "C" Upper and CS Sparger "D"Lower Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 VT-1 VT-F06-223 Accept BWRVIP18A Examination SAT. Examination coverage limited to 90%. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.SB.CUDL.268 SB-CU-DL-SPR@268 N/A CS Core Spray Sparger Bracket at 268 degrees azimuth betwee CS Sparger "C" Upper and CS Sparger "D"Lower Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 VT-I VT-F06-224 Accept BWRVIP18A Examination SAT. Examination coverage limited to 90%. See Section 3, Tab 2 of AREVA RE23 lWI Outage Report. Summary No.: Component ID: Class: System: Component Description V18.SB.CUDL.92 SB-CU-DL-SPR@92 N/A CS Core Spray Sparger Bracket at 92 degree azimuth betwee CS Sparger "C" Upper and Sparger "D" Lower Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448880 VT-1 VT-F06-279 Accept BWRVIP18A Examination SAT. Examination coverage limited to 75%. See Section 3, Tab 2 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 41 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Category: VIP26 Equal: 4 Item No.: V26.HLDAS Equal: 2 Summary No.: Component ID: Class: System: Component Description V26.TGHLDNAS.270 TG-HLDWN-ASEM@270 N/A NB Top Guide Hold Down Assembly consisiting of two bolts top and botton and a centeral, spring loaded tensioning locking bolt, which is fillet welded in the locked position at 266 degrees azimuth, 4 degrees counter-clockwise from 180 degrees azimuth.

Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448819 VT-1 VT-F06-130 Accept N-686, Examination SAT. Examined accessible areas of the Hold-Down assembly. This assembly BWRVIP26A can only be seen from the top. Limited exam area due to Top Guide inference. See Section 3, Tab 9 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V26.TGHLDNAS.90 TG-HLDWN-ASEM@90 N/A NB Top Guide Hold Down Assembly consisiting of two bolts top and botton and a centeral, spring loaded tensioning locking bolt, which is fillet welded in the locked position at 86 degrees azimuth, 4 degrees counter-clockwise from 90 degrees azimuth. Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448819 VT-1 VT-F06-131 Accept N-686, Examination SAT. Examined accessible areas of the Hold-Down assembly. This assembly BWRVIP26A can only be seen from the top. Limited exam area due to Top Guide inference. See Section 3, Tab 9 of AREVA RE23 IWI Outage Report. Item No.: V26.HZAPN Equal: 2 Summary No.: Component ID: Class: System: Component Description V26.HZALPN.270 TG-HOZALNPIN-ASEM@270 N/A NB Top Guide Horizontal Aligner Assembly Pins, Sockets, and Welds at 270 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448819 EVT-1 VT-F06-303 Accept BWRVIP26A Examination SAT. Examined accessible areas of the Horizontal Alignment Pin assembly and attachment welds. Access from Core Loc. 02-27 Examined approx. 50% of assembly. Located 3 separate indications as documented in AREVA indication notice form INF-CNS-RFO-23-007. Indicaitons documented in CNS Condition Report CR-CNS-2006-08457 and were evaluated as acceptable. See Section 3, Tab 9 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V26.HZALPN.90 TG-HOZALNPIN-ASEM@90 N/A NB Top Guide Horizontal Aligner Assembly Pins, Sockets, and Welds at 90 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448819 EVT-1 VT-F06-233 Accept BWRVIP26A Examination SAT. Examined accessible areas of the Horizontal Alignment Pin assembly and attachment welds. Access from Core Loc. 50-27 Examined approx. 50% of assembly. Located 3 separate indications as documented in AREVA indication notice form INF-CNS-RFO-23-006. Indications documented in CNS Condition Report CR-CNS-2006-08386 and were evaluated as acceptable. See Section 3, Tab 9 of AREVA RE23 IWI Outage Report. Category: VIP38 Equal: 1 Item No.: V38.SDSPW Equal: 1 Summary No.: Component ID: Class: System: Component Description V38.SRDWLD.H8 SHRD-SUPLTWLD-H8 N/A NB Core Shroud Support Plate Horizontal Circumferential Weld to Shroud Lower Cylinder, 0 to 360 degrees azimuth, including intersections of vertical seam welds Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-185 Accept BWRVIP-38 Examination SAT. See Section 3, Tab 5 in the AREVA RE23 IVl Outage Report for specific locations and coverages between various jet pumps.

Monday, February 12, 2007 Page 42 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Category: VIP41 Equal: 30 Item No.: V41.AD1 Equal: 4 Summary No.: Component ID: Class: System: Component Description V41 .ADi .JP15 AD-1-JP15 N/A NB Jet Pump Adapter Top to Adapter Bottom Weld (Bi-metallic weld)

Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-186 Accept BWRVIP- Examination SAT.Examination limited to 15% due to proximity of the RPV, Shroud and 41, Rev 1 Sensing Line. See Section 3, Tab 3 of AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description V41 .AD1 .JP16 AD-1-JP16 N/A NB Jet Pump Adapter Top to Adapter Bottom Weld (Bi-metallic weld) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-187 Accept BWRVIP- Examination SAT. Examination limited to 15% due to proximity of the RPV, Shroud and 41, Rev 1 Sensing Line. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V41 .AD .JP19 AD-1-JP19 N/A NB Jet Pump Adapter Top to Adapter Bottom Weld (Bi-metallic weld) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-188 Accept BWRVIP- Examination SAT. Examination limited to 40% due to proximity of the RPV, Shroud and 41, Rev 1 Gusset. Summary No.: Component ID: Class: System: Component Description V41 AD1 .JP20 AD-1-JP20 N/A NB Jet Pump Adapter Top to Adapter Bottom Weld (Bi-metallic weld) Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448818 EVT-1 VT-F06-189 Accept BWRVIP- Examination SAT. Examination limited to 20% due to proximity of the RPV, Shroud and 41, Rev 1 Gusset. See Section 3, Tab 3 of AREVA RE23 IVl Outage Report. Item No.: V41.AD2 Equal: 4 Summary No.: Component ID: Class: System: Component Description V41.AD2.JP15 AD-2-JP15 N/A NB Jet Pump Adapter Bottom to Core Shroud Support Plate Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-190 Accept BWRVIP- Examination SAT. Examination limited to 15% due to proximity of the RPV, Shroud, Gusset, 41, Rev 1 and Sensing Line. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V41.AD2.JP16 AD-2-JP16 N/A NB Jet Pump Adapter Bottom to Core Shroud Support Plate Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448818 EVT-1 VT-F06-191 Accept BWRVIP- Examination SAT. Examination limited to 20%. See Section 3, Tab 3 of AREVA RE23 IWI 41, Rev 1 Outage Report. Summary No.: Component ID: Class: System: Component Description V41 .AD2.JP19 AD-2-JP19 N/A NB Jet Pump Adapter Bottom to Core Shroud Support Plate Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-192 Accept BWRVIP- Examination SAT. Examination limited to 40% due to proximity of the RPV, Shroud and 41, Rev 1 Gusset. See Section 3, Tab 3 of AREVA RE23 IVl Outage Report.

Monday, February 12, 2007 Page 43 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98,. Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V41 .AD2.JP20 AD-2-JP20 N/A NB Jet Pump Adapter Bottom to Core Shroud Support Plate Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448818 EVT-1 VT-F06-193 Accept BWRVIP- Examination SAT. Examination limited to 40% due to proximity of the RPV, Shroud and 41, Rev 1 Gusset. See Section 3, Tab 3 of AREVA RE23 IVl Outage Report.

Item No.: V41.AD3a Equal: 4 Summary No.: Component ID: Class: System: Component Description V41 .AD3a.JP15 AD-3a-JP15 N/A NB Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-194 Accept BWRVIP- Examination SAT. Examination limited to 15% due to proximity of the RPV, Shroud, Gusset, 41, Rev 1 and Sensing Line. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V41 .AD3a.JP16 AD-3a-JP16 N/A NB Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-195 Accept BWRVIP- Examination SAT. Examination limited to 15%. See Section 3, Tab 3 of AREVA RE23 IWI 41, Rev 1 Outage Report. Summary No.: Component ID: Class: System: Component Description V41 AD3a.JP19 AD-3a-JP19 N/A NB Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 vTr-F06-196 Accept BWRVIP- Examination SAT. Examination limited to 40% due to proximity of the RPV, Shroud and 41, Rev 1 Gusset. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V41.AD3a.JP20 AD-3a-JP20 N/A NB Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-197 Accept BWRVIP- Examination SAT. Examination limited to 20% due to proximity of the RPV, Shroud and 41, Rev 1 Gusset. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report. Item No.: V41.AD3b Equal: 4 Summary No.: Component ID: Class: System: Component Description V41.AD3b.JP15 AD-3b-JP15 N/A NB Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448818 EVT-1 VT-F06-198 Accept BWRVIP- Examination SAT. Examination limited to 15% due to proximity of the RPV, Shroud and 41, Rev 1 Sensing Line. See Section 3, Tab 3 of AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description V41.AD3b.JP16 AD-3b-JP16 N/A NB Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-199 Accept BWRVIP- Examination SAT. Examination limited to 15%. See Section 3, Tab 3 of AREVA RE23 IVl 41, Rev 1 Outage Report.

Monday, February 12, 2007 Page 44 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V41 .AD3b.JP19 AD-3b-JP19 N/A NB Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-200 Accept BWRVIP- Examination SAT.Examination limited to 40% due to proximity of the RPV, Shroud and 41, Rev 1 Gusset. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report.

Summary No.: Component ID: Class: System: Component Description V41 .AD3b.JP20 AD-3b-JP20 N/A NB Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448818 EVT-1 VT-F06-201 Accept BWRVIP- Examination SAT. Examination limited to 25% due to proximity of the RPV, Shroud and 41, Rev 1 Gusset. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report. Item No.: V41.DF1 Equal: 6 Summary No.: Component ID: Class: System: Component Description V41 .DF1 .JP15 DF-1-JP15 N/A NB Jet Pump Diffuser Collar to Diffuser Shell Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-202 Accept BWRVIP- Examination SAT. Examination limited to 40% due to proximity of the RPV and Shroud. 41, Rev 1 See Section 3, Tab 3 of AREVA RE23 IVl Outage Report. Summary No.: Component ID: Class: System: Component Description V41.DF1.JP16 DF-1-JP16 N/A NB Jet Pump Diffuser Collar to Diffuser Shell Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT--F06-203 Accept BWRVIP- Examination SAT. Examination limited to 40% due to proximity of the RPV and Shroud. 41, Rev 1 See Section 3, Tab 3 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V41.DF1.JP17 DF-1-JP17 N/A NB Jet Pump Diffuser Collar to Diffuser Shell Weld Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448818 EVT-1 VT-F06-204 Accept BWRVIP- Examination SAT. Examination limited to 40% due to proximity of the RPV, Shroud and 41, Rev 1 Sensing Line. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V41 .DF1 .JP18 DF-1-JP18 N/A NB Jet Pump Diffuser Collar to Diffuser Shell Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-205 Accept BWRVIP- Examination SAT. Examination limited to 40% due to proximity of the RPV and Shroud. See 41, Rev 1 Section 3, Tab 3 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V41.DF1.JP19 DF-1-JP19 N/A NB Jet Pump Diffuser Collar to Diffuser Shell Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-206 Accept BWRVIP- Examination SAT. Examination limited to 40% due to proximity of the RPV, Shroud and 41, Rev 1 Sensing Line. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report.

Monday, February 12, 2007 Page 45 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V41 .DF1 .JP20 DF-1-JP20 N/A NB Jet Pump Diffuser Collar to Diffuser Shell Weld Work Order Exam Method Report No. Results Code Case Comments ! Corrective Measures 4448818 EVT-1 VT-F06-207 Accept BWRVIP- Examination SAT. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report.

41, Rev 1 Item No.: V41.DF2 Equal: 4 Summary No.: Component ID: Class: System: Component Description V41 .DF2.JP15 DF-2-JP15 N/A NB Jet Pump Diffuser Shell to Tailpipe Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-208 Accept BWRVIP- Examination SAT.Examination limited to 15% due to proximity of the RPV, Shroud and 41, Rev 1 Sensing line. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: SVstem: Component Description V41 .DF2.JP16 DF-2-JP16 N/A NB Jet Pump Diffuser Shell to Tailpipe Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 v'T-F06-209 Accept BWRVIP- Examination SAT. Examination limited to 15%. See Section 3, Tab 3 of AREVA RE23 IWI 41, Rev 1 Outage Report. Summary No.: Component ID: Class: System: Component Description V41 .DF2.JP19 DF-2-JP19 N/A NB Jet Pump Diffuser Shell to Tailpipe Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-210 Accept BWRVIP- Examination SAT. Examination limited to 40% due to proximity of the RPV, Shroud and 41, Rev 1 Gusset. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report. Summary No.: Component ID: Class: System: Component Description V41 .DF2.JP20 DF-2-JP20 N/A NB Jet Pump Diffuser Shell to Tailpipe Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-211 Accept BWRVIP- Examination SAT. Examination limited to 20% due to proximity of the RPV, Shroud and 41, Rev 1 Gussets. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report. Item No.: V41.RS. Equal: 2 Summary No.: Component ID: Class: SVstem: Component Description V41.RS1 .JP15-16 RS-1-JP15&JP16 N/A NB Recirc Thermal Sleeve to Jet Pump Riser Elbow Weld Work Order Exam Method Report No. Results Code Case Comments ! Corrective Measures 4448818 EVT-1 VT-F06-212 Accept BWRVIP- Examination SAT. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report. 41, Rev 1 Summary No.: Component ID: Class: System: Component Description V41.RS1.JP19-20 RS-1-JP19&JP20 N/A NB Recirc Thermal Sleeve to Jet Pump Riser Elbow Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-213 Accept BWRVIP- Examination SAT. See Section 3, Tab 3 of AREVA RE23 IWI Outage Report. 41, Rev 1

Monday, February 12, 2007 Page 46 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Item No.:

V41.RS2 Equal: 2 Summary No.: Component ID: Class: System: Component Description V41.RS2.JP15-16 RS-2-JP15&JP16 N/A NB Jet Pump Riser Elbow to Riser Pipe Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-214 Accept BWRVIP- Examination SAT. Examination limited to 50%. See Section 3, Tab 3 of AREVA RE23 IVl 41, Rev 1 Outage Report. Summary No.: Component ID: Class: System: Component Description V41 .RS2.JP19-20 RS-2-JP19&JP20 N/A NB Jet Pump Riser Elbow to Riser Pipe Weld Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448818 EVT-1 VT-F06-215 Accept BWRVIP- Examination SAT. Examination limited to 50%. See Section 3, Tab 3 of AREVA RE23 IVVI 41, Rev 1 Outage Report. Category: VIP47 Equal: 2 Item No.: V47.GT2 Equal: 1 Summary No.: Component ID: Class: System: Component Description V47.CRGT2.42-27 CRGT-2-(42-27) N/A NB Control Rod Drive Gudie Tube Assembly Upper Circ Weld Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4452896 EVT-1 VT-F06-298 Accept BWRVIP Examination SAT. See Section 3, Tab 7 of AREVA RE23 IWI Outage Report. A Item No.: V47.GT3 Equal: 1 Summary No.: Component ID: Class: System: Component Description V47.CRGT3.42-27 CRGT-3-(42-27) N/A NB Control Rod Drive Gudie Tube Assembly Lower Circ Weld Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4452896 EVT-1 VT-F06-299 Accept BWRVIP Examination SAT. See Section 3, Tab 7 of AREVA RE23 IVl Outage Report. A Category: VIP76 Equal: 4 Item No.: V76.HCSW Equal: 4 Summary No.: Component ID: Class: System: Component Description V76.SHDWLDH5 CORESHDWLD-H5 N/A NB Core Shroud Horizontal Circumferential Weld including intersections of vertical seam welds Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448815 Remote Auto UT VE-F06-001 Accept BWRVIP-76 Examination SAT. Examination was performed as a two-sided exam with a total coverage of 72.44%. Three indications, one previous, and two new indications were identifed and documented in CNS Condition Report CNS-CR-2006-08462. Previous indication showed no apparent change in length of 2.32". The two new indications were in material not previously scanned in 1995. Indication lengths were 2.32", 2.17" and 1.39" in length. Indications were evaluated as acceptable for another 10 years of service per NEDC 05-001, Rev 1. See AREVA RE23 Automated Ultrasonic Examinations Outage Report. Summary No.: Component ID: Class: System: Component Description V76.SHDWLDH6a CORESHDWLD-H6a N/A NB Core Shroud Horizontal Circumferential Weld including intersections of vertical seam welds Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448815 Remote Auto UT VE-F06-002 Accept BWRVIP-76 Examination SAT. Examination was performed as a two-sided exam with total coverage of 72.44%. One previous indication was identified with no apparent change in length at 2.17". Indications were evaluated as acceptable for 10 more years of service per NEDC 05-001, Rev 1 as acceptable. Reference CNS Condition Report CR-CNS-2006-08462. See AREVA RE23 Automated Ultrasonic Examinations Outage Report.

Monday, February 12, 2007 Page 47 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description V76.SHDWLDH6b CORESHDWLD-H6b N/A NB Core Shroud Horizontal Circumferential Weld including intersections of vertical seam welds Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448815 Remote Auto UT VE-F06-003 Accept BWRVIP-76 Examination SAT. Examination was performed as a two-sided exam with a total coverage of 72.44%. One new indication was identified at 1.86" in length. Indication was analyzed as acceptable for 10 more years of service per NEDC 05-001, Rev 1. Reference CR-CNS-2006-08462. See AREVA RE23 Automated Ultrasonic Examination Report.

Summary No.: Component ID: Class: System: Component Description V76.SHDWLDH7 CORESHDWLD-H7 N/A NB Core Shroud Horizontal Circumferential Weld including intersections of vertical seam welds Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448815 Remote Auto UT VE-F06-004 Accept BWRVIP-76 Examination SAT. Examination was performed as single sided examination due to gusset locations. Total coverage achieved was 53.78%. Two new indications were identified at 2.10" and 2.54" in length. Indications were evaluated as acceptable for another 10 years of service per NEDC 05-001, Rev 1. Reference CNS Condition Report CR-CNS-2006-08462. See AREVA RE23 Automated Ultrasonic Examination Outage Report. Exam Credit: XMAUG Equal: 43 Category: REC Equal: 39 Item No.: Al1.12.37 Equal: 8 Summary No.: Component ID: Class: System: Component Description A11.12.37078 2848-2-W109 3 REC FLANGE TO RED. (PI-449C) Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448948 Manual UT UT-F06-018 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448948 Manual UT UT-F06-017 Accept Summary No.: Component ID: Class: System: Component Description A11.12.37036 2848-2-W110 3 REC (PI-449C) RED. TO FLANGE Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448948 Manual UT UT-F06-002 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448948 Manual UT UT-F06-001 Accept Summary No.: Component ID: Class: System: Component Description A11.12.37052 2848-2-W12 3 REC PIPE TO ELBOW Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448948 Manual UT UT-F06-011 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448948 Manual UT UT-F06-012 Accept

Monday, February 12, 2007 Page 48 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (IfRequired): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description A11.12.37107 2848-2-W40 3 REC PIPE TO ELBOW Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448948 Manual UT UT-F06-009 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report.

4448948 Manual UT UT-F06-010 Accept Summary No.: Component ID: Class: System: Component Description A11.12.37109 2848-2-W42 3 REC FLANGE TO TEE Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448948 Manual UT UT-F06-008 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448948 Manual UT UT-F06-007 Accept Summary No.: Component ID: Class: System: Component Description A 1.12.37110 2848-2-W45 3 REC PIPE TO TEE Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448948 Manual UT UT-F06-006 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448948 Manual UT UT-F06-005 Accept Summary No.: Component ID: Class: System: Component Description A11.12.37112 2848-2-W47 3 REC FLANGE TO ELBOW Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448948 Manual UT UT-F06-004 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448948 Manual UT UT-F06-003 Accept Summary No.: Component ID: Class: System: Component Description Al 1.12.37061 2848-2-WJ 3 REC ELBOW TO VALVE (REC-CV-13CV) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448948 Manual UT UT-F06-015 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448948 Manual UT UT-F06-016 Accept Item No.: A.1.1 2.40 Equal: 7 Summary No.: Component ID: Class: System: Component Description A11.12.40062 2848-9-W22 3 REC PIPE TO PIPE Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448954 Manual UT UT-F06-041 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448954 Manual UT UT-F06-042 Accept

Monday, February 12, 2007 Page 49 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description A11.12.40086 2848-9-W60 3 REC PIPE TO PIPE Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448954 Manual UT UT-F06-037 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report.

4448954 Manual UT UT-F06-038 Accept Summary No.: Component ID: Class: System: Component Description A11.12.40087 2848-9-W61 3 REC PIPE TO ELBOW Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448954 Manual UT UT-F06-036 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448954 Manual UT UT-F06-035 Accept Summary No.: Component ID: Class: System: Component Description Al1.12.40088 2848-9-W62 3 REC ELBOW TO PIPE Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448954 Manual UT UT-F06-034 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448954 Manual UT UT-F06-033 Accept Summary No.: Component ID: Class: System: Component Description Al 1.12.40089 2848-9-W63 3 REC PIPE TO PIPE Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448954 Manual UT UT-F06-031 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. 4448954 Manual UT UT-F06-032 Accept Summary No.: Component ID: Class: System: Component Description Al1.12.40090 2848-9-W64 3 REC PIPE TO TEE Work Order Exam Method Report No. Results Code Case Comments /Corrective Measures 4448954 Manual UT UT-F06-029 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448954 Manual UT UT-F06-030 Accept Summary No.: Component ID: Class: System: Component Description Al1.12.40091 2848-9-W65 3 REC TEE TO 4X3 CONC. REDUCER Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448954 Manual UT UT-F06-028 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448954 Manual UT UT-F06-050 Accept

Monday, February 12, 2007 Page 50 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Item No.: All1.122.41 Equal1: 5 Summary No.: Component ID: Class: System: Component Description Al 1.12.41033 2848-14-W16 3 REC TEE TO 6X4 CONC. REDUCER Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448950 Manual UT UT-F06-100 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report.

4448950 Manual UT UT-F06-099 Accept 4448950 Manual UT UT-F06-101 Accept Summary No.: Component ID: Class: System: Component Description A11.12.41039 2848-14-WB 3 REC ELBOW TO VALVE (REC-MOV-71 1MV) Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448950 Manual UT UT-F06-106 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448950 Manual UT UT-F06-105 Accept 4448950 Manual UT UT-F06-107 Accept Summary No.: Component ID: Class: System: Component Description A11.12.41020 2848-14-WFA 3 REC RED. TEE TO TEE Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448949 Manual UT UT-F06-024 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448949 Manual UT UT-F06-019 Accept 4448949 Manual UT UT-F06-020 Accept 4448949 Manual UT UT-F06-021 Accept 4448949 Manual UT UT-F06-022 Accept 4448949 Manual UT UT-F06-023 Accept Summary No.: Component ID: Class: System: Component Description A11.12.41021 2848-14-WFC 3 REC RED. TEE TO TEE Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448950 Manual UT UT-F06-102 Accept 11.12 Examination performed per the Augmented ISI Program 11.12. See AREVA RE23 Manual ISI Outage Report. 4448950 Manual UT UT-F06-104 Accept 4448950 Manual UT UT-F06-103 Accept

Monday, February 12, 2007 Page 51 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (IfRequired): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (IfRequired): N/A Summary No.: Component ID: Class: System: Component Description Al1.12.41041 2848-14-WH 3 REC VALVE (REC-MOV-714MV) TO RED. TEE Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448949 Manual UT UT-F06-060 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report.

4448949 Manual UT UT-F06-013 Accept 4448949 Manual UT UT-F06-014 Accept 4448949 Manual UT UT-F06-061 Accept Item No.: Al1.12.42 Equal: 3 Summary No.: Component ID: Class: System: Component Description A11.12.42019 2848-15-Wi 3 REC PIPE TO ELBOW (CONTINUED FROM CNS-REC-40) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448954 Manual UT UT-F06-046 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448954 Manual UT UT-F06-045 Accept Summary No.: Component ID: Class: System: Component Description A11.12.42020 2848-15-W2 3 REC ELBOW TO PIPE Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448954 Manual UT UT-F06-044 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448954 Manual UT UT-F06-043 Accept Summary No.: Component ID: Class: System: Component Description A11.12.42030 2848-15-W23 3 REC ELBOW TO PIPE (CONTINUED ON CNS-REC-40) Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448954 Manual UT UT-F06-039 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448954 Manual UT UT-F06-040 Accept Item No.: Equal: Al1.12.48------- 

----------------------------------------               4                               .

Summary No.: Component ID: Class: System: Component Description Al 1.12.48009 2848-54-W12 3 REC PIPE TO ELBOW Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448955 Manual UT UT-F06-083 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448955 Manual UT UT-F06-085 Accept 4448955 Manual UT UT-F06-084 Accept

Monday, February 12, 2007 Page 52 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (IfRequired): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description A11.12.48010 2848-54-W13 3 REC ELBOW TO PIPE Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448955 Manual UT UT-F06-055 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report.

4448955 Manual UT UT-F06-056 Accept 4448955 Manual UT UT-F06-054 Accept Summary No.: Component ID: Class: System: Component Description A11.12.48011 2848-54-W16 3 REC PIPE TO ELBOW Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448955 Manual UT UT-F06-052 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448955 Manual UT UT-F06-053 Accept 4448955 Manual UT UT-F06-051 Accept Summary No.: Component ID: Class: System: Component Description Al 1.12.48012 2848-54-W17 3 REC ELBOW TO FLANGE SOCKET WELD Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448955 Manual UT UT-F06-086 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448955 Manual UT UT-F06-087 Accept 4448955 Manual UT UT-F06-088 Accept Item No.: Al1.12.49 

----------------------------------             Equal: 7 Summary No.:                      Component ID:                               Class: System:     Component Description A11.12.49014                      2848-55-W21                                   3        REC     FLANGE (FLEX HOSE) TO ELBOW Work Order      Exam Method          Report No.       Results    Code Case     Comments / Corrective Measures 4448951         Manual UT          UT-F06-094       Accept        11.12      Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report.

4448951 Manual UT UT-F06-093 Accept 4448951 Manual UT UT-F06-092 Accept

Monday, February 12, 2007 Page 53 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description A11.12.49015 2848-55-W22 3 REC ELBOW TO PIPE Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448951 Manual UT UT-F06-026 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report.

4448951 Manual UT UT-F06-025 Accept 4448951 Manual UT UT-F06-027 Accept Summary No.: Component ID: Class: System: Component Description A11.12.49016 2848-55-W25 3 REC PIPE TO FLANGE Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448951 Manual UT UT-F06-091 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448951 Manual UT UT-F06-089 Accept 4448951 Manual UT UT-F06-090 Accept Summary No.: Component ID: Class: System: Component Description A11.12.49017 2848-55-W28 3 REC PIPE TO FLANGE (FLEX HOSE) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448951 Manual UT UT-F06-078 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448951 Manual UT UT-F06-079 Accept 4448951 Manual UT UT-F06-077 Accept Summary No.: Component ID: Class: System: Component Description A11.12.49018 2848-55-W29 3 REC FLANGE (FLEX HOSE) TO PIPE Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448951 Manual UT UT-F06-082 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448951 Manual UT UT-F06-080 Accept 4448951 Manual UT UT-F06-081 Accept Summary No.: Component ID: Class: System: Component Description A11.12.49006 2848-55-W6 3 REC ELBOW TO FLANGE (FLEX HOSE) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448951 Manual UT UT-F06-064 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448951 Manual UT UT-F06-062 Accept 4448951 Manual UT UT-F06-063 Accept

Monday, February 12, 2007 Page 54 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (IfRequired): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: Svstem: Component Description A11.12.49007 2848-55-W8 3 REC FLANGE TO ELBOW Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448951 Manual UT UT-F06-047 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report.

4448951 Manual UT UT-F06-049 Accept 4448951 Manual UT UT-F06-048 Accept Item No.: Al1.12.51 Equal: 5 Summary No.: Component ID: Class: System: Component Description A11.12.51008 2848-57-W12 3 REC PIPE TO ELBOW Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448953 Manual UT UT-F06-058 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448953 Manual UT UT-F06-059 Accept 4448953 Manual UT UT-F06-057 Accept Summary No.: Component ID: Class: System: Component Description A11.12.51009 2848-57-W14 3 REC ELBOW TO FLANGE Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448953 Manual UT UT-F06-073 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448953 Manual UT UT-F06-075 Accept 4448953 Manual UT UT-F06-074 Accept Summary No.: Component ID: Class: System: Component Description A11.12.51005 2848-57-W6 3 REC PIPE TO FLANGE (FLEX HOSE) Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448953 Manual UT UT-F06-071 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448953 Manual UT UT-F06-070 Accept 4448953 Manual UT UT-F06-072 Accept

Monday, February 12, 2007 Page 55 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description A11.12.51006 2848-57-W7 3 REC FLANGE (FLEX HOSE) TO ELBOW Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448953 Manual UT UT-F06-076 Accept 11.12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report.

4448953 Manual UT UT-F06-069 Accept 4448953 Manual UT UT-F06-068 Accept Summary No.: Component ID: Class: System: Component Description A1. 12.51007 2848-57-W9 3 REC ELBOW TO PIPE Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448953 Manual UT UT-F06-067 Accept 11/12 Examination performed per the Augmented ISI Program Section 11.12. See AREVA RE23 Manual ISI Outage Report. 4448953 Manual UT UT-F06-066 Accept 4448953 Manual UT UT-F06-065 Accept Category: XM11.1 Equal: 4 Item No.: NR.0619.S Equal: 4 Summary No.: Component ID: Class: System: Component Description Al 1.1 .FWSPRA.045 FW-ASparger-45 N/A NB Feedwater Sparger at 45 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 VT-3 VT-F06-183 Accept ' N-686, Examination SAT. Examined accessible areas of FW sparger, nozzles, tee-box, and end NUREG- brackets. See Section 3, TAB 8 of AREVA RE23 IWI Outage Report. 0619 Summary No.: Component ID: Class: System: Component Description A11.1.FWSPRB.135 FW-BSparger-135 N/A NB Feedwater Sparger at 135 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 VT-3 VT-F06-127 Accept N-686, Examination SAT. Examined accessible areas of FW sparger, nozzles, tee-box, and end NUREG- brackets. See Section 3, TAB 8 of AREVA RE23 IWI Outage Report. 0619 Summary No.: Component ID: Class: System: Component Description A11.1 .FWSPRC.225 FW-CSparger-225 N/A NB Feedwater Sparger at 225 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448817 VT-3 VT-F06-184 Accept N-686, Examination SAT. Examined accessible areas of Feedwater Sparger, Nozzles, Tee-Box, NUREG- and End Brackets. See Section 3, TAB 8 of AREVA RE23 IWI Outage Report. 0619 Summary No.: Component ID: Class: System: Component Description Al1.1 .FWSPRD.315 FW-DSparger-315 N/A NB Feedwater Sparger at 315 degrees azimuth Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448817 VT-3 VT'-F06-128 Accept N-686, Examination SAT.Examined accessible areas of Feedwater Sparger, Nozzles, Tee-Box, and NUREG- End Brackets. See Section 3, TAB 8 of AREVA RE23 IWI Outage Report. 0619

Monday, February 12, 2007 Page 56 of 56 : Inservice Inspection Report, Interval 4, Period 1, RE23

1. Owner, Address: Nebraska Public Power District, 1414 15th St., Columbus, NE 68602 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72646 648A Avenue, P.O. Box 98, Brownville, 5. Owner Certificate of Authorization (If Required): N/A NE 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A

Page 1 of2 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS (As required by the Provisions ofthe ASME Code Rules)

1. Owner Nebraska Public Power District 1414 15th St. Columbus, NE 68321 (Name and Address of Owner)
2. Plant Cooper Nuclear Station, 72676 648A, PO Box 98, Brownville, NE 68321-0098 (Name and Address of Plant)
3. Plant Unit 1 4. Owner Certificate of Authorization (if required) N/A
5. Commercial Service Date 07/01/1974 6. National Board Number for Unit N/A
7. Components Inspected Component or Manufacturer or Manufacturer or Installer State or Province National Board No.

Appurtenance Installer Serial No. No. Containment Chicago Bridge and Iron C-4448 N/A None (*) SEE "ATTACHMENT 1" FOR APPLICABLE INFORMATION Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. This form (E00029) may be obtained from the ASME Order Dept., 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300

Page 2 of 2 FORM NIS-1 (Back)

8. Examination Dates 2/19/2005 to 11/22/2006
9. Inspection Period Identification: Period 3, 01/09/2005 to 05/08/2008
10. Inspection Interval Identification: Interval 1, 09/09/1996 to 05/08/2008
11. Applicable Edition of Section XI 1992 Addenda 1992
12. Date/Revision of Inspection Plan: 12/28/2004 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.

See attachment 1

14. Abstract of Results of Examinations and Tests.

See attachment 1

15. Abstract of Corrective Measures.

See attachment 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 ASvE Code, Section XI. Certificate of Authorization No. ( if applicable) N/A Expiration Date Date _ -I-Z 61 /-7 Signed Nebraska Public Power District By Vasant N. Bhardwaj/ Owner 4m6 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board ofBoiler and Pressure Vessel Inspectors and the State or Province of Nebraska and employed by Hartford Steam Boiler Inspection and Insurance Co. of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period o '? 1&ý" to I I- ý- L"t- :* , 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. Todd Ward/ Commissions *)1lI'7 *f*"s' 1 '"/o/cf _-lnspector's Signaiýý National Board, State, Province, and Endorsements Date --_q_-o - (*) SEE "ATTACHMENT 1" FOR APPLICABLE INFORMATION

Monday, February 12, 2007 Page 1 of 3 : Inservice Inspection Report, Interval 1, Period 3, RE23-IWE

1. Owner, Address: Nebraska Public Power District 1414 15th St. Columbus, NE 68321 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72676 648A, PO Box 98, Brownville, NE 5. Owner Certificate of Authorization (If Required): N/A 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Exam Credit: Sec.Xl Equal: 20 Category: E-A Equal: 20 Item No.: E1.12 Equal: 12 Summary No.: Component ID: Class: System: Component Description E1.12.0081 DW-HD MC PC Drywell Head Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4449180 VT-3 VT-F06-001 Accept N/A Examination SAT.

Summary No.: Component ID: Class: System: Component Description E1.12.0082 DW-HD-FLG MC PC Drywell Head Flange Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4449180 VT-3 VT-F06-002 Accept N-686 Examination SAT. N-460 Summary No.: Component ID: Class: System: Component Description E1.12,0083 DW-SH-FLG MC PC Drywell Shell Flange Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4449180 VT-3 VT-F06-304 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description E1. 12.0086 DW-UC MC PC Drywell Upper Cylinder Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448998 VT-3 VT-F06-096 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description E1.12.0090 SIP-1-ATT MC PC Stabilizer Attachment Welds Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448998 VT-3 VT-F06-012 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description E1.12.0091 SIP-2-ATT MC PC Stabilizer Attachment Welds Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448998 VT-3 VT-F06-013 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description E1.12.0092 SIP-3-ATT MC PC Stabilizer Attachment Welds Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448998 VT-3 VT--F06-014 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description E1.12.0093 SIP-4-ATT MC PC Stabilizer Attachment Welds Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448998 VT-3 VT-F06-015 Accept N/A Examination SAT.

Monday, February 12, 2007 Page 2 of 3 : Inservice Inspection Report, Interval 1, Period 3, RE23-IWE

1. Owner, Address: Nebraska Public Power District 1414 15th St. Columbus, NE 68321 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72676 648A, PO Box 98, Brownville, NE 5. Owner Certificate of Authorization (If Required): N/A 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description E1.12.0094 SIP-5-ATT MC PC Stabilizer Attachment Welds Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448998 VT-3 VT-F06-016 Accept N/A Examination SAT.

Summary No.: Component ID: Class: System: Component Description E1.12.0095 SIP-6-ATT MC PC Stabilizer Attachment Welds Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448998 VT-3 VT-F06-017 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description E1.12.0096 SIP-7-ATT MC PC Stabilizer Attachment Welds Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448998 VT-3 VT-F06-018 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description E1.12.0097 SIP-8-ATT MC PC Stabilizer Attachment Welds Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448998 VT-3 VT-F06-019 Accept N/A Examination SAT. Item No.: E1.20 Equal: 8 Summary No.: Component ID: Class: System: Component Description E1.20.0085 X201E-EB MC PC Vent Line Expansion Bellows Bay 10 Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448999 VT-3 VT-F06-011 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description E1.20.0086 X201F-EB MC PC Vent Line Expansion Bellows Bay 12 Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448999 VT-3 VT-F06-010 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description E1.20.0087 X201G-EB MC PC Vent Line Expansion Bellows Bay 14 Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448999 VT-3 VT-F06-009 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description E1.20.0088 X201H-EB MC PC Vent Line Expansion Bellows Bay 16 Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448999 VT-3 VT-F06-008 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description E1.20.0073 X5E-V MC PC Drywell Penetration, Torus Vent Line, Drainage Channels to Bay 10 Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448998 VT-3 VT-F06-020 Accept N/A Examination SAT.

Monday, February 12, 2007 Page 3 of 3 : Inservice Inspection Report, Interval 1, Period 3, RE23-IWE

1. Owner, Address: Nebraska Public Power District 1414 15th St. Columbus, NE 68321 4. Commercial Service Date: 07/01/1974
2. Plant, Address: Cooper Nuclear Station, 72676 648A, PO Box 98, Brownville, NE 5. Owner Certificate of Authorization (If Required): N/A 68321-0098
3. Plant Unit: 1 6. National Certificate of Authorization (If Required): N/A Summary No.: Component ID: Class: System: Component Description E1.20.0075 X5F-V MC PC Drywell Penetration, Torus Vent Line, Drainage Channels to Bay 12 Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448998 VT-3 VT-F06-021 Accept N/A Examination SAT.

Summary No.: Component ID: Class: System: Component Description E1.20.0077 X5G-V MC PC Drywell Penetration, Torus Vent Line, Drainage Channels to Bay 14 Work Order Exam Method Report No. Results Code Case Comments I Corrective Measures 4448998 VT-3 VT-F06-022 Accept N/A Examination SAT. Summary No.: Component ID: Class: System: Component Description E1.20.0079 X5H-V MC PC Drywell Penetration, Torus Vent Line, Drainage Channels to Bay 16 Work Order Exam Method Report No. Results Code Case Comments / Corrective Measures 4448998 VT-3 VT-F06-023 Accept N/A Examination SAT.

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI 1.Owner: Nebraska Public Power District Date: P.O. Box 98 Brownville, Nebraska 68321 Sheet I of 3 2.Plant: Cooper Nuclear Station Unit One P.O. Box 98 Brownville, Nebraska 68321 N/A Repair Orgamization, P.O. No,, Job No.. etc. 3.Work Performed by: NPPD Type Code Symbol Stamp N/A P.O. Box 98 Authorization No. N/A Brownville, Nebraska 68321 Expiration Date N/A

4. Identification of System As shown in the Attached Table
5. (a) Applicable Construction Code As shown in the Attached Table (b) Applicable Edition of Section XI Utilized for Repairs or Replacements:

2001 Edition including 2003 Addenda

6. Identification of Components Repaired or Replaced and Replacement Components: As shown in the Attached Table
7. Description of Work: As shown in the Attached Table
8. Tests Conducted: As shown in the Attached Table
9. Remarks:

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and these repairs and replacements conform to the rules of the ASME Code, Section Xl. Type Code Symbol Stamp N/A Certificate of Authorization No. N/A Expiration Date N/A SignedL-4 ffc. Owner or Owner's kesignee, Title - D X-. tbat~ te 1 /-7Z CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State of Nebraska and Employed by Hartford Steam Boiler Inspection and Insurance Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period February 19, 2005 to November 22, 2006, and state that to the best ofmy knowledge and belief, the Ownerhas 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's Report. Furthermore, neitherthe Inspector nor his employer shall be liable in aC er for anyperson ry or property damage or a loss of any kind arising from or connected with this inspection. __ _ _ __ _ __ _ _ Commissions 41I i3s") N pNIE" /010 

                 ., Inspectors Signature                                                  National Board, State, Province, and Endorsements Date

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI Nebraska Public Power District Cooper Nuclear Station Unit 1, P.O. Box 98, Brownville, Nebraska 68321 WO R/R SYST Name of Mfgr. C Name of Nat'l Description of Applicable Year Repaired ASME Pressure Tests RECORD Component Serial I Manufacturer Board Work Constr. Code Built or Code Conducted, No No. Replaced Stamp Code Cases 4370565 06-013 REC REC-V-20 N/A 3 HENRY PRATT N/A Replaced Valve B31.1 - 1967 1%9 Replaced N/A YES 4451987 06-015 R.HR RHR-RV-14RV N/A 2 Dresser Valve/ N/A Replaced Spoolpiece B31.7- 1969 1969 Replaced N/A YES NPPD including Valve 4456074 06-016 REC REC-V-97 & N/A 3 ANCHOR VALVE N/A Replaced Valves B31.1 -1967 1969 Replaced N/A YES REC-V-98 4443342 06-017 R-IHR RH-S37 N/A 2 ANVIL Intl. N/A Replaced Snubber B31.7- 1969 1969 Replaced N/A N/A 4443487 06-018 RHR RH-S80 N/A 2 ANVIL Intl. N/A Replaced Snubber B31.7 - 1969 1969 Replaced N/A N/A 4443490 06-019 RHR RH-S43 N/A 2 ANVIL Intl. N/A Replaced Snubber B31.7 - 1969 1969 Replaced N/A NIA 4443492 06-020 RHR RH-S30B N/A 2 ANVIL Intl. N/A Replaced Snubber B31.7 - 1969 1969 Replaced N/A N/A 4443493 06-021 R1IR RH-S40 N/A 2 ANVIL Intl. N/A Replaced Snubber B31.7 - 1969 1969 Replaced N/A N/A 4443496 06-022 RI-tR RH-S44A N/A 2 ANVIL Intl. N/A Replaced Snubber B31.7 - 1969 1969 Replaced NIA N/A 4471800 06-023 SW SW-STNR-A N/A 3 ZURN IND. N/A Repaired Inspection Port B31.1 -1967 1969 Repaired N/A YES 

                                                                          & Cover 4476380 06-024  SW    SW-STNR-B       N/A    3  ZURN IND.            N/A   Repaired Inspection Port B31.1 - 1967  1969  Repaired    N/A YES
                                                                          & Cover 4437651 06-025  DG    DG-D-I          N/A    3  Cooper Energy Svcs   N/A   Replaced Flex hose       B3 1.1 - 1967 1969  Replaced    N/A YES 4437652 06-026  DG    DG-D-2          N/A    3  Cooper Energy Svcs   N/A   Replaced Flexhose        B31.1 - 1967  1969  Replaced    N/A YES 7005942 06-027  MS    MS-RV-71 Spare  378    1  TARGET ROCK          N/A   Replaced Bolts           B31.7 - 1969  1969  Replaced    N/A N/A 7005942 06-028  MS    MS-RV-71 Spare  386    I  TARGET ROCK          N/A   Replaced Bolt            B31.1 - 1969  1969  Replaced    N/A N/A 7005942 06-029  MS    MS-RV-71 Spare  387    1  TARGET ROCK          N/A   Replaced Bolt            B31.1 - 1969  1969  Replaced    NIA N/A 4472140 06-030  SW    SW-CV-ARA       N/A    3  GA Industrics        N/A   Replaced Ball            B31.1 - 1967  1969  Replaced    N/A N/A BALL 4472141 06-031  SW    SW-CV-ARB       N/A    3  GA Industries        N/A   Replaced Ball            B31.1 - 1967  1969  Replaced    N/A N/A BALL Page 2 of 3

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI Nebraska Public Power District Cooper Nuclear Station Unit 1, P.O. Box 98, Brownville, Nebraska 68321 WO R/R SYST Name of Mfgr. C Name of Nat'l Description of Applicable Year Repaired ASME Pressure Tests RECORD Component Serial I Manufacturer Board Work Constr. Code Built or Code Conducted, No No. Replaced Stamp Code Cases 4478526 06-032 RHR RHR-Pipe N/A 2 NPPD N/A Install Hydrolazer Taps on B31.7 - 1969 2006 Replaced N/A YES RHR Division 1 4508474 06-034 RHR RHR-Pipe N/A 2 NPPD N/A R/R window in RHR B31.7 - 1969 1969 Repaired N/A YES 4411762 06-035 SW SW-MOV- N/A 3 Control N/A Replaced Disc 131.1 - 1967 1969 Replaced N/A N/A MO89A Components, Inc. 4426440 06-036 MS MS-MOV-MO77 N/A I ANCHOR N/A Replaced Valve B31.7 - 1969 1969 Replaced N/A 6.NISC.502 DARLING 4516272 06-039 SW SW-P-BPA N/A 3 BYRON JACKSON N/A Replaced Pump B31.1 - 1967 1969 Replaced N/A YES 4485647 06-040 RCIC RCIC-RD-S240 N/A 2 BLACK SIVALLS N/A Replaced Rupture Disc B31.7 - 1969 1969 Replaced N/A YES 

                                            & BRYSON, INC.

4483095 06-042 HPIC HPIC-RD-S241 N/A 2 BLACK SIVALLS N/A Replaced Rupture Disc B31.7 - 1969 1969 Replaced N/A YES 

                                            & BRYSON, INC.

4529307 06-046 SW SW-P-BPA NIA 3 BYRON JACJSON N/A Replaced Pump B31.1 -1967 1969 Replaced N/A YES 4533334 06-049 PC PV-S1 B&R N/A 2 NPPD N/A Replaced Support ASME 111, 77 1969 Replaced N/A N/A w/S77 Add. 4534360 06-051 RHR RHR-MOV- N/A 2 ANCHOR VALVE N/A Repaired Valve Bonnet B31.7 - 1969 1969 Repaired N/A YES M025A 4446762 06-052 MS MS-RV-71HRV N/A I TARGET ROCK N/A Replaced studs & nuts B31.7 - 1969 1969 Replaced N/A YES 4403913 06-053 SW SW-CV-36CV & N/A 3 ANCHOR N/A Replaced Discs B31.1-1967 1969 Replaced N/A N/A 

                    -38CV                   DARLING 4534069 06-054  PC   PV-HI04B      N/a    2  NPPD               N/A   Replaced Support           ASME 111,77    1969 Replaced    NIA N/A w/$77 Add.

Page 3 of 3

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI 1.Owner: Nebraska Public Power District Date: P.O. Box 98 Brownville, Nebraska 68321 Sheet 1 of 4 2.Plant: Cooper Nuclear Station Unit One P.O. Box 98 Brownville, Nebraska 68321 N/A Repair Organization. P.O. No., Job No, etc. 3.Work Performed by: NPPD Type Code Symbol Stamp N/A P.O. Box 98 Authorization No. N/A Brownville, Nebraska 68321 Expiration Date N/A

4. Identification of System As shown in the Attached Table
5. (a) Applicable Construction Code As shown in the Attached Table (b) Applicable Edition of Section XI Utilized for Repairs or Replacements:

1989 Edition including 1989 Addenda & 1992 Edition including 1992 Addenda (IWE)

6. Identification of Components Repaired or Replaced and Replacement Components: As shown in the Attached Table
7. Description of Work: As shown in the Attached Table
8. Tests Conducted: As shown in the Attached Table
9. Remarks: Code Cases N-416-1& N-416-2 were used for Repairs and Replacements:

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and these repairs and replacements conform to the rules of the ASME Code, Section XI. Type Code Symbol Stamp N/A Certificate of Authorization No. N/A Expiration Date N/A Sig--d- - Date I(*/o7 Owner or OwneV's Designee, TiWe CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State ofNebraska and Employed by Hartford Steam Boiler Inspection and Insurance Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period February 19, 2005 to November 22, 2006, 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's Report. Furthermore, neitherthe Inspector nor his employer shall be liable in any anr for any person7 perty damage or a loss of any kind arising from or connected with this inspection. 7 ,Commissions t3 iIS*t) NISTA ijj ()lofI ns ector' National Board, State, Province, and Endorsements Date C I -/ 8-0")

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI Nebraska Public Power District Cooper Nuclear Station Unit 1, P.O. Box 98, Brownville, Nebraska 68321 WO RIR SYST Name of Mfgr. C Name of Nat'l Description of Applicable Year Repaired ASME Pressure Tests RECORD Component Serial I Manufacturer Board Work Constr. Code Built or Code Conducted, No No. Replaced Stamp Code Cases 4174359 02-002 SW SW-CV-20CV N/A 3 ANCHOR N/A Replaced valve B31.1 -1967 1969 Replaced N/A 02-057 DARLING 4297703 04-002 HPCI HPCI-V-75 N/A 2 CRANE Valve N/A Replaced Valve & pipe B31.7 - 1969 1969 Replaced N/A 04-006 4349812 04-055 DGI DGI Intercooler N/A 3 Thermal Eng. Int.. N/A Replaced Intercooler B31.1 - 1967 1969 Replaced N/A 04-334 4349813 04-056 DG2 DG2 Intercooler N/A 3 Thermal Eng. Int. N/A Replaced Intercooler B31.1 - 1967 1969 Replaced N/A 04-335 PO 04-079 SW SW-P-BP-Spare 781-C- 3 JOHNSTON PUMP N/A Repaired Worn areas of B31.1 - 1967 1969 Repaired N/A N/A 45000 603 Pump Casing and 41329 machined to obtain fits 4429164 05-029 SW SW-Pipe N/A 3 NPPD N/A Replace Piping B31.1 - 1967 1969 Replaced N/A 05-074 4345743 05-030 SW SW-P-BPD N/A 3 BYRON JACKSON N/A Replaced Pump B31.1 - 1967 1969 Replaced N/A 05-030 4431710 05-031 SW SW-Pipe N/A 3 NPPD N/A Replaced Piping B31.1 - 1967 1969 Replaced N/A 05-086 4368343 05-035 SW SW-P-D 280005/ 3 Johnston Pump Co. N/A Replaced bowl assy. B31.1 - 1967 1969 Replaced N/A 05-019 08 4368343 05-036 SW SW-P-D 280005/ 3 BYRON JACKSON N/A Replaced pump columns B3 1.1- 1967 1969 Replaced N/A 05-019 08 and discharge head 4368343 05-037 SW SW-EXPJ-SWPD N/A 3 GARLOCK N/A Replaced Expansion Joint B31.L - 1967 1969 Replaced N/A 05-019 4368343 05-038 SW SW-CV-13CV N/A 3 Atwood & Morrill N/A Replaced Check Valve B31.1 - 1967 1969 Replaced N/A 05-019 4195503 05-039 SW SW-Rad. Monitor N/A 3 NPPD N/A Repaired SW Pipe B31. I - 1967 1969 Repaired N/A N/A 4421582 05-040 SW SW-STNR-A N/A 3 ZURN IND. N/A Repaired lnsp. Port & B31.1 - 1967 1969 Repaired N/A 05-150 Cover 4421583 05-041 SW SW-STNR-B N/A 3 ZURN IND. N/A Repaired lnsp. Port & B31.1 -1967 1969 Repaired N/A 05-151 Cover P.O. 05-042 SW SW-P-BP-Spare 70495- 3 JOHNSTON PUMP N/A Repaired worn areas of B31.I - 1967 1969 Repaired N/A N/A 45000 C- Pump Casing and 50412 1214528 machined to obtain fits 4438533 05-045 HPCI HPCI-MOV- N/A 2 NOVA Machine N/a Replace Bonnet B31.7 - 1969 1969 Replaced N/A 05-141 14MO Capscrews I I Page 2 of 4

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI Nebraska Public Power District Cooper Nuclear Station Unit 1, P.O. Box 98, Brownville, Nebraska 68321 WO RiR SYST Name of Mfgr. C Name of Nat'l Description of Applicable Year Repaired ASME Pressure Tests RECORD Component Serial I Manufacturer Board Work Constr. Code Built or Code Conducted, No No. Replaced Stamp Code Cases 4442572 05-046 CRD CRD-CRD-{06- N/A I GENERAL N/A Replaced Control Rod 131.7 - 1969 1969 Replaced N/A 6.MISC.502

31) ELECTRIC Drive & Flange Bolts 4451679 05-048 CRD CRD-CRD-(l0- N/A I GENERAL N/A Replaced Control Rod B31.7- 1969 1969 Replaced N/A 6.MISC.502
15) ELECTRIC Drive & Flange Bolts 4451780 05-049 CRD CRD-CRD-(10- N/A I GENERAL N/A Replaced Control Rod B31.7 - 1969 1969 Replaced N/A 6.MISC.502
27) ELECTRIC Drive & Flange Bolts 4451781 05-050 CRD CRD-CRD-(10- N/A I GENERAL N/A Replaced Control Rod B31.7 -1969 1969 Replaced N/A 6.MISC.502
35) ELECTRIC Drive & Flange Bolts 4451782 05-051 CRD CRD-CRD-(14- N/A I GENERAL N/A Replaced Control Rod B31.7- 1969 1969 Replaced N/A 6.MISC.502
19) ELECTRIC Drive & Flange Bolts 4451793 05-052 CRD CRD-CRD-(50- N/A I GENERAL N/A Replaced Control Rod B31.7 - 1969 1969 Replaced N/A 6.MISC.502
27) ELECTRIC Drive & Flange Bolts 4451791 05-054 CRD CRD-CRD-(46- N/A I GENERAL N/A Replaced Control Rod B31.7 - 1969 1969 Replaced N/A 6.MISC.502
31) ELECTRIC Drive & Flange Bolts 4451787 05-057 CRD CRD-CRD-(22- N/A I GENERAL N/A Replaced Control Rod B31.7 - 1969 1969 Replaced N/A 6.MISC.502
47) ELECTRIC Drive & Flange Bolts 4451785 05-058 CRD CRD-CRD-(I 8- N/A I GENERAL N/A Replaced Control Rod B31.7 - 1969 1969 Replaced N/A 6.MISC.502
19) ELECTRIC Drive & Flange Bolts 4451783 05-059 CRD CRD-CRD-(I 8- N/A I GENERAL N/A Replaced Control Rod B31.7 - 1969 1969 Replaced N/A 6.MISC.502 I1) ELECTRIC Drive & Flange Bolts 4457321 05-061 SW SW-STNR-A N/A 3 ZURN Industries N/A Replaced Cover Nuts B31.1 - 1967 1969 Replaced N/A YES 4475302 05-070 SW SW-EXPJ-SWPB N/A 3 GARLOCK N/A Replaced Expansion Joint B31.1 - 1967 1969 Replaced N/A YES and Bolting 4477239 05-073 SW SW-EXPJ-SWPA N/A 3 GARLOCK N/A Rcplaced Expansion Joint B31.1 - 1967 1969 Replaced N/A YES and bolting 4477238 06-001 SW SW-EXPJ-SWPC N/A 3 GARLOCK NIA Replaced Expansion Joint B31. 1 - 1967 1969 Replaced N/A YES 4484087 06-002 RHR RHR-RV-14RV N/A 2 BONNEY FORGE N/A Replaced Flange B31.7-1969 1969 Replaced N/A N-416-2 I___ _ I___

Spare I I I Page 3 of 4

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI Nebraska Public Power District Cooper Nuclear Station Unit 1, P.O. Box 98, Brownville, Nebraska 68321 WO RIR SYST Name of Mfgr. C Name of Nat'l Description of Applicable Year Repaired ASME Pressure Tests RECORD Component Serial I Manufacturer Board Work Constr. Code Built or Code Conducted, No No. Replaced Stamp Code Cases 7005942 06-003 MS MS-RV-71 Spare 378 1 TARGET ROCK N/A Replaced Hex Nuts with 1331.7 - 1969 1969 Replaced N/A N/A Splined Nuts 7005942 06-004 MS MS-RV-71 Spare 386 I TARGET ROCK N/A Replaced Hex Nuts with B31.1 - 1969 1969 Replaced N/A NIA Splined Nuts 06-005 MS MS-RV-71 Spare 387 1 TARGET ROCK N/A Replaced Hex Nuts with B31.7 - 1969 1969 Replaced N/A N/A 7005942 Splined Nuts Page 4 of 4

Page 1 of 15

Title:

Evaluation of Core Shroud Inspection Results Calculation Number: NEDC 05-001 from Refueling Outage 22 (RF022) and Refueling CED/EE Number: EE 05-001 Outage 23 (RF023) Setpoint Change/Part Eval Number: N/A System/Structure: NB / Core Shroud Discipline: Civil]Structural Component: Core Shroud SQAP Requirements Met? [ ] Yes; IX ] N/A Classification: IX] Essential; ] Non-Essential Proprietary Information Included? [XI Yes; [ I No

Description:

The purpose of this calculation is to document the evaluation performed by Structural Integrity (SI) of the results of "Areva's"inspection of the CNS Core Shroud horizontal and vertical welds during RF022 (Jan/Feb 2005) and RF023 (Oct/Nov 2006). The evaluation performed by SI determines if identified cracks are acceptable based on the evaluation criteria specified in EPRI Report TR- 114232, Final Report, Dated November 1999, BWR Vessel and Internals Project BWR Core Shroud Inspection and Flaw Evaluation Guidelines (BWRVIP-76). This evaluation is required by the CNS VIP document and accounts for projected crack growth until the next inspection. Conclusions and Recommendations: The conclusions provided in the SI calculation will be used for determining future core shroud inspection requirements. The evaluation of the coverage obtained for H1 through H4 meets the criteria of BWRVIP-76. These welds will be reinspected within 10 years (good until 2015). The re-evaluation of the H5 through H7 welds using 1995 data was also performed in accordance with the criteria of BWRVIP-76. However, extending the re-examination interval to 12 years for the 1995 data is not addressed in the guideline. Thus a plant specific evaluation was performed under the guidance of BWRVIP-94. The plant specific evaluation shows that extending the reinspection interval for one additional cycle will not compromise the structural integrity of the shroud and will still meet the allowable safety factors used in BWRVIP-76. Therefore, deferring the reinspection of the H5 through H7 welds for one cycle (until RFO 23) is safe. Revision 1 incorporates a second plant-specific flaw evaluation of welds H5 through H7 performed in accordance with the criteria of BWRVIP-76 by SI, again using the 1995 inspection data. This evaluation determines the structural acceptability of these welds for ten additional years (until 2015) or fifteen 18-month operating cycles from 1995 (22.5 years from 1995). Again, since extending the re-examination interval to 20 years for the 1995 data is not addressed in the guideline, a plant specific evaluation was performed under the guidance of BWRVIP-94. The plant specific evaluation shows that extending the reinspection interval for 10 years will not compromise the structural integrity of the shroud and will still meet the allowable safety factors used in BWRVIP-76. However, the extension of the inspection of welds H5-H7 for another 10 years is contrary to Cooper Nuclear Station Vessel Internals Program (VIP), Revision 9, section 12.10.4, which states "Re-inspection shall be every ten (10) years". Revision I also incorporates a third plant-specific flaw evaluation (Attachment 6.4.3) of welds H5 through H7 performed in accordance with the criteria of BWRVIP-76 by Structural Integrity, using 2006 inspection data obtained during RF023. This evaluation determines the structural acceptability of these welds for ten additional years (until 2016). Welds H5 through H7 will be reinspected within 10 years (good until 2016) in accordance to BWRVIP-76. The indication identifed visually ner ASME Section XI will renhuirp successive inspections for the next three Section XI periods. Structural Integrity Perry K. Adelung N/A 4-8-05 / 11-09-06 11-12-06 // Rev. Status Prepared By/Date Reviewed By/Date IDVed By/Date Approved Number By/Date Status Codes

1. Active 4. Superseded or Deleted 7. PRA/PSA
2. Information Only 5. OD/OE Support Only 3- Pending 6. Maintenance Activity Support Only

Page: 2 of 15 NEDC: 05-001 Rev. Number: 1 Nebraska Public Power District DESIGN CALCULATION CROSS-REFERENCE INDEX ITEM REV. PENDING CHANGES NO. DESIGN INPUTS NO. TO DESIGN INPUTS 1 GE Drawing 730E854, Sheet 1 8 None 2 Areva Examination/Inspection N/A None Report (Appendix G of Structural Integrity Associates Calculation Package COOP-20Q-301, Rev. 0) 3 NEDC 95-191 0 None 4 TransWare Enterprises, Inc. 0 None Fluence Report (Appendix H of Structural Integrity Associates Calculation Package COOP-20Q-301, Rev. 0) 5 Willamette Iron & Steel Supply E None for all four sheets Drawing E854, Sheetsl-4 D D C

Page: 3 of 15 NEDC: 05-001 Rev. Number: 1 Nebraska Public Power District DESIGN CALCULATION CROSS-REFERENCE INDEX ITEM NO. AFFECTED DOCUMENTS REV. NUMBER None

Page: 4 of 15 NEDC: 05-001 Rev. Number: 1 The purpose of this form is to assist the Preparer in screening new and revised design calculations to determine potential impacts to procedures and plant operations.1 SCREENING QUESTIONS YES NO UNCERTAIN

1. Does it involve the addition, deletion, or manipulation of a [ ] I []

component or components which could impact a system lineup and/or checklist for valves, power supplies (breakers), process control switches, HVAC dampers, or instruments?

2. Could it impact system operating parameters (e.g., [ I [X] [I temperatures, flow rates, pressures, voltage, or fluid chemistry)?
3. Does it impact equipment operation or response such as [I [XI [ I valve closure time?
4. Does it involve assumptions or necessitate changes to the [ ] [X] []

sequencing of operational steps?

5. Does it transfer an electrical load to a different circuit, or [ ] X] []

impact when electrical loads are added to or removed from the system during an event?

6. Does it influence fuse, breaker, or relay coordination? [] [XJ []
7. Does it have the potential to affect the analyzed [] [X] []

conditions of the environment for any part of the Reactor Building, Containment, or Control Room?

8. Does it affect TS/TS Bases, USAR, or other Licensing [] [X] [I]

Basis documents?

9. Does it affect DCDs? [I [X] [I]
10. Does it have the potential to affect procedures in any way Pq not already mentioned (refer to review checklists in II Procedure EDP-06)? If so, identify:

If all answers are NO, then additional review or assistance is not required. If any answers are YES or UNCERTAIN, then the Preparer shall obtain assistance from the System Engineer and other departments, as appropriate, to determine impacts to procedures and plant operations. Affected documents shall be listed on Attachment 2.

Page: 5 of 15 NEDC: 05-001 Rev. Number: 1 Nebraska Public Power District DESIGN CALCULATIONS SHEET

1. PURPOSE 1.1 General The CNS Vessel Internals Program (VIP) document provides the administrative requirements for the implementation of the BWR Vessel Internals Project administered by EPRI. This program document requires that flaw evaluations are performed for relevant indications.

The purpose of this calculation is to document the evaluation performed by Structural Integrity (SI) of the results of "Areva's" inspection of the CNS Core Shroud horizontal and vertical welds during RF022 (JanlFeb 2005) and RFO 23 (Oct/Nov 2006). The evaluation performed by SI determines if identified cracks are acceptable based on the evaluation criteria specified in EPRI Report TR- 114232, Final Report, Dated November 1999, BWR Vessel and Internals Project BWR Core Shroud Inspection and Flaw Evaluation Guidelines (BWRVIP-76). This evaluation is required by the CNS VIP document and accounts for projected crack growth until the next inspection. Four horizontal (circumferential) welds (H1, H2, H3, and 114) were inspected and one vertical weld was partially inspected during the 2005 refueling outage (RF022) and are subject to this evaluation. This portion of the calculation addresses the acceptability of the Consultant's purpose, assumptions, methodology, conclusions, references, and attachments as required by procedure 3.4.7, Revision 26, step 5.4. A review of a "draft" of the calculation (Attachment 6.4.1) was performed and comments were submitted to SI. Identified comments on the "draft" calculation are noted in the applicable section and were satisfactorily addressed by SI. Revision 1 incorporates a second plant-specific flaw evaluation (Attachment 6.4.2) of welds H5 through H7 performed in accordance with the criteria of BWRVIP-76 by Structural Integrity, again using the 1995 inspection data. This evaluation determines the structural acceptability of these welds for ten additional years (until 2015) or fifteen 18-month operating cycles from 1995 (22.5 years from 1995). A review of a "draft" of the calculation (Attachment 6.4.2) was performed and comments were submitted to SI. Identified comments on the "draft" calculation are noted in the applicable section and were satisfactorily addressed by SI. Only the final document is attached to this calculation. This analysis provides only the technical basis for operation of the shroud for up to

Page: 6 of 15 NEDC: 05-001 Rev. Number: 1 Nebraska Public Power District DESIGN CALCULATIONS SHEET 10 more years beyond RE22 completed in January 2005. This calculation is only an input to the CNS BWRVIP and does not supercede the inspection requirements of the CNS Vessel Internals Program that implements the requirements of the BWRVIP. Revision 1 also incorporates a third plant-specific flaw evaluation (Attachment 6.4.3) of welds H5 through H7 performed in accordance with the criteria of BWRVIP-76 by Structural Integrity, using 2006 inspection data obtained during RF023. This evaluation determines the structural acceptability of these welds for ten additional years (until 2016). This evaluation also determines the structual accpetability of a visual indication detected during an ASME Section XI VT-3 examination of the shroud in accordance to ASME Section XI, 1989 Edition, IWB-3142.4 "Acceptance by Analytical Evaluation". A review of a "draft" of the calculation (Attachment 6.4.3) was performed and comments were submitted to SI. Identified comments on the "draft" calculation are noted in the applicable section and were satisfactorily addressed by SI. Only the final document is attached to this calculation.

1.2 Background

CNS scheduled a re-examination of Core Shroud welds H1 through H7 in RE22. The scope of the examinations was intended to cover 100% of the accessible areas as required by BWRVIP-76, Section 2.2.1. During the outage problems with the inspection tool arose eventually impacting the critical path. A decision was made to reduce the scope of the examinations to cover at least 50% of welds H1 through H4 in general and the previously identified flaws in particular. Welds H5 through 57 were initially re-evaluated using the DLL code for additional cycle of operation. Furthermore, a flaw in horizontal weld H3 was in close proximity to vertical weld V16. The vertical weld was examined for a distance of 12 inches. NEDC 05-001 provides the technical evaluation of the flaws detected during RE22 in Core Shroud welds H1 through H4. It also provides the re-evaluation of welds H5 through H7 using the 1995 data. The evaluation was prepared in accordance with BWRVIP-76 criteria and the DLL Code. The analysis includes various safety margins depending on the controlling loads and the estimated neutron fluence at EOL. The neutron fluence was calculated using the BWRVIP RAMA code. BWRVIP-76 is an accepted industry approach for inspecting and evaluating BWR Core Shrouds. Achieving less than 100% coverage of the accessible areas was not intended, however BWRVIP-94 provides some flexibility for unanticipated problems. The evaluation of the coverage obtained for H1 through H4 meets the criteria of BWRVIP-76. These welds will be reinspected within 10 years.

Page: 7 of 15 NEDC: 05-001 Rev. Number: 1 Nebraska Public Power District DESIGN CALCULATIONS SHEET The re-evaluation of the H5 through H7 welds using 1995 data was also performed in accordance with the criteria of BWRVIP-76. However, extending the re-examination interval to 12 years for the 1995 data is not addressed in the guideline. Thus a plant specific evaluation was performed under the guidance of BWRVIP-94. The plant specific evaluation shows that extending the reinspection interval for one additional cycle will not compromise the structural integrity of the shroud and will still meet the allowable safety factors used in BWRVIP-76. Therefore, deferring the reinspection of the H5 through H7 welds for one cycle is safe. A second plant-specific flaw evaluation of welds H5 through H7 was performed in accordance with the criteria of BWRVIP-76 by SI, again using the 1995 inspection data. This evaluation determines the structural acceptability of these welds for ten additional years (until 2015) or fifteen 18-month operating cycles from 1995 (22.5 years from 1995). Again, since extending the re-examination interval to 20 years for the 1995 data is not addressed in the guideline, a plant specific evaluation was performed under the guidance of BWRVIP-94. The plant specific evaluation shows that extending the reinspection interval for 10 years will not compromise the structural integrity of the shroud and will still meet the allowable safety factors used in BWRVIP-76. However, the extension of the inspection of welds H5-H7 for another 10 years is contrary to Cooper Nuclear Station Vessel Internals Program (VIP), Revision 9, section 12.10.4, which states "Re-inspection shall be every ten (10) years". Revision 1 also incorporates a third plant-specific flaw evaluation (Attachment 6.4.3) of welds H5 through H7 performed in accordance with the criteria of BWRVIP-76 by Structural Integrity, using 2006 inspection data obtained during RF023. This evaluation determines the structural acceptability of these welds for ten additional years (until 2016). Note: No credit for HWC and NMCA has been assumed for operation prior to 2005. NMCA was reapplied prior to the shutdown for RE22 and moderate HWC is assumed to be available for the balance of plant life. 1.3 Review of Contractor Calculation "Purpose" for COOP-20Q-301, Rev. 0 The Contractor's calculation "Purpose" section is acceptable. No changes were required. 1.4 Review of Contractor Calculation "Purpose" for COOP-20Q-302, Rev. 0 SI was requested to add "and BWRVIP-76" to the end of the second sentence in section 3.0 (renumbered in final report to section 4.0). After incorporation of this

Page: 8 of 15 NEDC: 05-001 Rev. Number: 1 Nebraska Public Power District DESIGN CALCULATIONS SHEET comment, the Contractor's "Purpose" section is acceptable. 1.5 Review of Contractor Calculation "Purpose" for COOP-20Q-302, Rev. 1 The Contractor's calculation "Purpose" section is acceptable. No changes were required.

2. ASSUMPTIONS 2.1 Assumptions for this calculation None 2.2 Review of Contractor Calculation "Assumptions"for COOP-20Q-301, Rev. 0 The Contractor's calculation "Assumptions" section is acceptable. No changes were required.

2.3 Review of Contractor Calculation "Assumptions" for COOP-20Q-302, Rev. 0 SI was requested to answer the question "Does BWRVIP require that the uninspected regions be considered completely flawed through wall?"in section 5.0 (renumbered in final report to section 6.0). After addressing this question, the Contractor's "Assumptions" section is acceptable. 2.4 Review of Contractor Calculation "Assumptions" for COOP-20Q-302, Rev. 1 SI was requested to address the following comment(s): 2.4.1 Add an additional assumption: "H7 was examined from one side only. Cracking is not assumed on the uninspected side of the weld." After incorporationlresolution of this comment, the Contractor's "Assumptions" section is acceptable.

3. METHODOLOGY 3.1 Extent of Review This calculation was reviewed to verify that all applicable design inputs were used and incorporated as requested under the Task Authorization to perform the work.

Page: 9 of 15 NEDC: 05-001 Rev. Number: 1 Nebraska Public Power District DESIGN CALCULATIONS SHEET The review did not include any checks of mathematical computations. 3.2 Review of Contractor Calculation "Methodology"for COOP-20Q-301, Rev. 0 The Contractor's calculation "Methodology" section is acceptable. No changes were required.

Page: 10 of 15 NEDC: 05-001 Rev. Number: 1 Nebraska Public Power District DESIGN CALCULATIONS SHEET 3.3 Review of Contractor Calculation "Methodology" for COOP-20Q-302, Rev. 0 SI was requested to address the following comments: 3.3.1 Section 6 (renumbered in final report to section 7), last sentence of the first paragraph: Add period after"...welds" and delete rest of sentence. 3.3.2 Section 6 (renumbered in final report to section 7), Paragraph Number 1 beginning with "For welds H5-H7 ..... " ,add "the other" between "for" and "shroud" in the second sentence. 3.3.3 Table 1, add "(Max Stress)" to "Minimum Calculated Safety Factor" title. In addition, add a superscript "2" for the following note to be added below "Note 1" below the table. "2. For LEFM the maximum stress is listed." 3.3.4 Table 1 add "(Max Allowable Stress)" to "Minimum Required Safety Factor" title. In addition, add a superscript "2" for the above stated note. 3.3.5 Table 1, Should the fluence be shown? 3.3.6 Section 4 (Design Input) (renumbered in final report to section 5), On the ninth bullet, please state the applicable sections of BWVIP-76. Also, on the 1 0 th bullet, please state where in BWRVIP-14 you are using the value of 5 x 105.5 After incorporation of these comments, the Contractor's "Methodology" section is acceptable. 34 Review of Contractor Calculation "Methodology" for COOP-20Q-302, Rev. 1 SI was requested to address the following comment(s): 3.4.1 The paragraph numbered 2. has a weld numbered "Hxx" which is in error. 3.4.2 In Table 2, is the 5 tb line designation of Weld "H5" correct? 3.4.3 Comment on "Editorial note/question: There were no BWRVIP vertical weld inspections performed. This flaw was detected during XI IVVI exams, and was conservatively evaluated as if it were both a circumferential and vertical indication on the adjacent shroud welds. Not sure how to treat this with respect to reinspection using BWRVIP-76 guidelines. Is it OK to say 10 years,

Page: 11 of 15 NEDC: 05-001 Rev. Number: 1 Nebraska Public Power District DESIGN CALCULATIONS SHEET or should it be 6 years consistent with a one-sided exam?": Ten years is acceptable from BWRVIP perspective since not actually on a vertical weld. ASME Section XI will require us to reexamine for 3 successive examinations in the next three periods. After incorporation/resolution of these comments, the Contractor's "Methodology" section is acceptable.

4. CONCLUSIONS 4.1 Review of Contractor Calculation "Conclusions"for COOP-20Q-301, Rev. 0 The Contractor's calculation "Conclusions" section is acceptable. SI was requested to summarize Case #3 (Welds H1-H7, GE Inspection Data, 12-year Evaluation Period) in section 8 of their calculation.

4.2 Review of Contractor Calculation "Conclusions" for COOP-20Q-302, Rev. 0 The Contractor's calculation "Conclusions" section is acceptable. No changes were required. 4.3 Review of Contractor Calculation "Conclusions" for COOP-20Q-302, Rev. 1 SI was requested to address the following comment(s): 4.3.1 Add the following sentence to the last conclusion: "However, since the indication was determined via an ASME Section XI examination, three successive examinations will be required in accordance with IWB-2420." After incorporation/resolution of this comment, the Contractor's "Conclusions" section is acceptable. 4.4 Conclusions The conclusions provided in the SI calculation will be used for determining future core shroud inspection requirements. The evaluation of the coverage obtained for H1 through H4 meets the criteria of BWRVIP-76. These welds will be reinspected within 10 years (good until 2015).

Page: 12 of 15 NEDC: 05-001 Rev. Number: 1 Nebraska Public Power District DESIGN CALCULATIONS SHEET The re-evaluation of the H5 through H7 welds using 1995 data was also performed in accordance with, the criteria of BWRVIP-76. However, extending the re-examination interval to 12 years for the 1995 data is not addressed in the guideline. Thus a plant specific evaluation was performed under the guidance of BWRVIP-94. The plant specific evaluation shows that extending the reinspection interval for one additional cycle will not compromise the structural integrity of the shroud and will still meet the allowable safety factors used in BWRVIP-76. Therefore, deferring the reinspection of the H5 through H7 welds for one cycle (until RF023) is safe. A second plant-specific flaw evaluation of welds H5 through H7 was performed in accordance with the criteria of BWRVIP-76 by SI, again using the 1995 inspection data. This evaluation determines the structural acceptability of these welds for ten additional years (until 2015) or fifteen 18-month operating cycles from 1995 (22.5 years from 1995). Again, since extending the re-examination interval to 20 years for the 1995 data is not addressed in the guideline, a plant specific evaluation was performed under the guidance of BWRVIP-94. The plant specific evaluation shows that extending the reinspection interval for 10 years will not compromise the structural integrity of the shroud and will still meet the allowable safety factors used in BWRVIP-76. However, the extension of the inspection of welds H5-H7 for another 10 years is contrary to Cooper Nuclear Station Vessel Internals Program (VIP), Revision 9, section 12.10.4, which states "Re-inspection shall be every ten (10) years". Revision 1 also incorporates a third plant-specific flaw evaluation (Attachment 6.2.3) of welds H5 through H7 performed in accordance with the criteria of BWRVIP-76 by Structural Integrity, using 2006 inspection data obtained during RF023. This evaluation determines the structural acceptability of these welds for ten additional years (until 2016). Welds H5 through H7 will be volumetrically re-examined within 10 years (good until 2016) in accordance to BWRVIP-

76. The indication identified by VT-3 to ASME Section XL. 1989 Edition, will require visual re-examination for the next three Section XI periods in accordance to 1WB-2420 "Successive Inspections".

Page: 13 of 15 NEDC: 05-001 Rev. Number: 1 Nebraska Public Power District DESIGN CALCULATIONS SHEET The following table summarizes the results of the inspections and evaluations: Summary Data from COOP-20Q-302, Rev. 0 (Re-evaluated for 10 years based on 1995 data) (FOR INFORMATION ONLY) 1-15(1) 76.1 0.7 0.5 8.41E20 SAT - LEFM 10 years H6aM') 73.4 0.5 0.4 3.53E17 SAT - Limit Load 10 years H6b(') 73.4 0 0 1.11E17 SAT - Limit Load 10 years H7(l) 68.6 0 0 <1E17 SAT - Limit Load 10 years Sg~in'Miry,13atad from COOP-402Q-3, Re.1(evlae after RFO 23-ins Ipection? in,20O66)' H5(2) 71.01(4) 4.03 2.86 8.41E20 SAT - LEFM 10 years (2016) H6a(2) 71.0104) 0.55 0.39 3.53E17 SAT - Limit Load 10 years (2016) H6b(2) 71.01(4) 0.47 0.33 1.11E17 SAT - Limit Load 10 years (2016) H7(2) 53.23(') 1.62 0.86 <1E17 SAT - Limit Load 10 years (2016) Vert(3) 100 0.09 0.09 8.42E20 SAT - LEFM 10 years H4-H5 I I I 1_ (2016) (1) Second plant-specific flaw evaluation of welds H5 through H7 (See Attachment 6.4.2) (2) Third plant-specific flaw evaluation of welds H5 through H7 (See Attachment 6.4.3) (3) One sided visual (VT-3) examination per ASME XI; Will require re-examination of the indications identified visually for next 3 successive periods in accordance with IWB-2420, 2001Edition, 2003 Addenda. (4) See assumption, bullet 4 in COOP20Q-302 regarding assumed inspection coverage. (5) Coverages revised to correlate to AREVA examination data sheets

Page: 14 of 15 NEDC: 05-001 Rev. Number: 1 Nebraska Public Power District DESIGN CALCULATIONS SHEET

5. REFERENCES 5.1 Review of Contractor Calculation "References"for COOP-20Q-301, Rev. 0 The Contractor's calculation "References" section is acceptable. SI was requested to include two items listed as References as Appendices to their calculation. These two items were the Areva Examination/Inspection Report and the TransWare Enterprises Report.

5.2 Review of Contractor Calculation "References" for COOP-20Q-302, Rev. 0 The Contractor's calculation "References" section is acceptable. No changes were required. 5.3 Review of Contractor Calculation "References" for COOP-20Q-302, Rev. 1 SI was requested to address the following comment(s): 5.3.1 Add a reference to Willamette Iron & Steel Supply Drawings E854, Sheets 1-4. Add this reference to Section 5.0, Design Input, also. After incorporation/resolution of this comment, the Contractor's "References" section is acceptable. 5.4 References 5.4.1 Cooper Nuclear Station Vessel Internals Program (VIP), Revision 9 5.4.2 EPRI Report TR-114232, Final Report, Dated November 1999, BWR Vessel and Internals Project BWR Core Shroud Inspection and Flaw Evaluation Guidelines (BWRVIP-76) 5.4.3 BWRVIP-94, Program Implementation Guideline 5.4.4 NEDC 95-191 Rev. 0, Evaluation of Core Shroud Inspection Results 5.4.5 EDP-06, Supporting Requirements for Configuration Change Control, Rev. 19 5.4.6 EE 05-001, Rev. 0, Evaluation of Core Shroud Inspection Results from Refueling Outage 22 (RF022) 5.4.7 CR 2006-08462

Page: 15 of 15 NEDC: 05-001 Rev. Number: 1 Nebraska Public Power District DESIGN CALCULATIONS SHEET

6. ATTACHMENTS 6.1 Review of Contractor Calculation "Attachments"for COOP-20Q-301, Rev. 0 The Contractor's calculation "Attachments/Appendices" section is acceptable. SI was requested to include two items listed as References as Appendices to their calculation. These two items were the Areva Examination/Inspection Report and the TransWare Enterprises Report.

6.2 Review of Contractor Calculation "Attachments" for COOP-20Q-302, Rev. 0 The Contractor's calculation "Attachments/Appendices" section is acceptable. No changes were required. 6.3 Review of Contractor Calculation "Attachments" for COOP-20Q-302, Rev. 1 SI was requested to address the following comment(s): 6.3.1 The exam summary sheet numbers do not correlate with the data on pages A2, A4, A6 and A8 of Appendix A. Unsure where the discrepancies are from.. .with AREVA's data sheet or the calculation sheets. After incorporation/resolution of this comment, the Contractor's "References" section is acceptable. 6.4 Attachments 6.4.1 Structural Integrity Associates Calculation Package COOP-20Q-301, Rev. 0 (Not attached to this revision, see Attachment 6.2.1 of Revision 0 of NEDC 05-001) 6.4.2 Structural Integrity Associates Calculation Package COOP-20Q-302, Rev. 0 6.4.3 Structural Integrity Associates Calculation Package COOP-20Q-302, Rev. 1}}

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