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| issue date = 02/28/2011
| issue date = 02/28/2011
| title = Form OAR-1 Owner'S Activity Report
| title = Form OAR-1 Owner'S Activity Report
| author name = Carlson M H
| author name = Carlson M
| author affiliation = Indiana Michigan Power Co
| author affiliation = Indiana Michigan Power Co
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:INDIANA MICHIGAN POWERO A unit of American Electric Power February 28, 2011 Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 AEP.com AEP-NRC-2011-4 10 CFR 50.55a Docket No.: 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 2 Form OAR-1 Owner's Activity Report This letter provides a copy of Form OAR-1 Owner's Activity Report for inservice inspection activities performed at Donald C. Cook Nuclear Plant (CNP) Unit 2 through the completion of the U2C19 refueling outage. This report meets the requirements of the American Society of Mechanical Engineers (ASME) Code Case N-532-4, "Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission, Section XI, Division 1." This code case is used as an alternative to the requirements of the ASME Boiler and Pressure Vessel Code, Section XI, Article IWA-6000 as approved by Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section Xl, Division 1, Revision 15." The Authorized Code Inspection Company is One CIS Insurance Co., of Lynn, Massachusetts.
{{#Wiki_filter:Indiana Michigan Power INDIANA                                                                              Cook Nuclear Plant MICHIGAN                                                                            One Cook Place Bridgman, Ml 49106 POWERO                                                                                AEP.com A unit of American Electric Power February 28, 2011                                                                  AEP-NRC-2011-4 10 CFR 50.55a Docket No.:           50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 2 Form OAR-1 Owner's Activity Report This letter provides a copy of Form OAR-1 Owner's Activity Report for inservice inspection activities performed at Donald C. Cook Nuclear Plant (CNP) Unit 2 through the completion of the U2C19 refueling outage. This report meets the requirements of the American Society of Mechanical Engineers (ASME) Code Case N-532-4, "Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission, Section XI, Division 1."
The Authorized Nuclear Inspector is Reuel Schenck.There are no new or revised commitments in this letter. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.Sincerely, Michael H. Carlson Vice President  
This code case is used as an alternative to the requirements of the ASME Boiler and Pressure Vessel Code, Section XI, Article IWA-6000 as approved by Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section Xl, Division 1, Revision 15."
-Site Support Services MCS/jmr  
The Authorized Code Inspection Company is One CIS Insurance Co., of Lynn, Massachusetts. The Authorized Nuclear Inspector is Reuel Schenck.
There are no new or revised commitments in this letter. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.
Sincerely, Michael H. Carlson Vice President - Site Support Services MCS/jmr


==Attachment:==
==Attachment:==
Form OAR-1 Owner's Activity Report for the Donald C. Cook Nuclear Plant Unit 2 Refueling Outage U2C19


Form OAR-1 Owner's Activity Report for the Donald C. Cook Nuclear Plant Unit 2 Refueling Outage U2C19 U. S. Nuclear Regulatory Commission AEP-NRC-2011-4 Page 2 c: R. Aben -DLEG/BCCFS/BD J. T. King -MPSC, w/o attachment S. M. Krawec -AEP Ft. Wayne, w/o attachment MDNRE -WHMD/RPS, w/o attachment NRC Resident Inspector M. A. Satorius -NRC Region III P. K. Tam -NRC Washington DC Attachment to AEP-NRC-2011-4 FORM OAR-1 OWNER'S ACTIVITY REPORT FOR DONALD C. COOK NUCLEAR PLANT UNIT 2 CYCLE 19 2010 REFUELING OUTAGE DCCook Nuclear UJnit2 Form OAR-1 Owner's Activity Report Report Number Plant 2-2010-4-1-01 Donald C. Cook Nuclear Plant, One Cook Place, Bridgman, Michigan 49106 Unit No. 2 (if applicable)
U. S. Nuclear Regulatory Commission                 AEP-NRC-2011-4 Page 2 c:     R. Aben - DLEG/BCCFS/BD J. T. King - MPSC, w/o attachment S. M. Krawec - AEP Ft. Wayne, w/o attachment MDNRE - WHMD/RPS, w/o attachment NRC Resident Inspector M. A. Satorius - NRC Region III P. K. Tam - NRC Washington DC
Current Inspection Interval Current Inspection Period (Name and Address of Plant)Commercial Service Date 7/1/1978 Refueling Outage No. U2C1 9 4th for Components and Supports (C&S) and 2nd for Containment ISI (CISI) Program (1st, 2nd, 3rd, 4th, other)1st for C&S and 1st for CISI (1st, 2nd, 3rd)Edition and Addenda of Section XI applicable to the inspection plans 2004 Edition/No Addenda Date and Revision of inspection plans 7128/2010, Revision I for C&S, and 5/26/2010, Revision 0 for CISI Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Edition and Addenda same as the inspection Dlans Code Case used: N-526, N-532-4, N-566-2, N-586-1, N-624, N-716, N-722 and N-729-1 for C&S and N-649 for CISI (If applicable)
 
CERTIFICATE OF CONFORMANCE I 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) the repair/replacement activities and evaluations supporting the completion of U2C19 conform to the requirements of Section XI. pAvio Aue" al (Refueling Outage Number)Signed o6W, 49. 5uDesignee Owners or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by One CIS Insurance Co. of Lynn, MA have inspected the items described in this Owner's ActivityReport, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.
Attachment to AEP-NRC-2011-4 FORM OAR-1 OWNER'S ACTIVITY REPORT FOR DONALD C. COOK NUCLEAR PLANT UNIT 2 CYCLE 19 2010 REFUELING OUTAGE
I. /Commissions Michigan 300959, NB 11412, Endorsements:
 
A, N & I Inspectors Signature National Board, State, Province, and Endorsements Date t C d--&4" e P-.,v 2110/2011 Page 1 of 3 D.C. Cook Nuclear Unit 2 Table I Items with flaws or relevant conditions that required evaluation for continued service Examination Item Number Item Description Evaluation Description Category B-N-3 B313.70 Core Support Structure Accessible Surfaces Broken Core Barrel Baffle Bolts evaluated for minimum bolting pattern and B-N-3___13.70
DCCook Nuclear UJnit2 Form OAR-1 Owner's Activity Report Report Number                   2-2010-4-1-01 Plant                            Donald C. Cook Nuclear Plant, One Cook Place, Bridgman, Michigan 49106 (Name and Address of Plant)
_CoreSupportStructureAccessibleSurfacesreplacement.
Unit No.          2                                        Commercial Service Date         7/1/1978                     Refueling Outage No. U2C1 9 (ifapplicable)
Loose Base Plate Nuts -Acceptable per previous evaluation under AIR 00820122-F-A, F1.30B 2-GCCW-R-308 Pipe Support Component 02 and -03 and WOT 55306855-01.
Current Inspection Interval                          4th for Components and Supports (C&S) and 2nd for Containment ISI (CISI) Program (1st, 2nd, 3rd, 4th, other)
2/10/2011 Page 2 of 3 D.C. Cook Nuclear Unit 2 Table 2 Abstract of repair/replacement activities required for continued service Code Class Item Description Description of Work Date Complete Repair I Replacement Plan Number 1 Reactor (2-OME-1)
Current Inspection Period                            1st for C&S and 1st for CISI (1st, 2nd, 3rd)
Core Barrel Baffle Bolts Modification EC-50972:
Edition and Addenda of Section XI applicable to the inspection plans                       2004 Edition/No Addenda Date and Revision of inspection plans                       7128/2010, Revision I for C&S, and 5/26/2010, Revision 0 for CISI Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Edition and Addenda same as the inspection Dlans Code Case used:                 N-526, N-532-4, N-566-2, N-586-1, N-624, N-716, N-722 and N-729-1 for C&S and N-649 for CISI (If applicable)
Removal/replacement of baffle plate 11/16/2010 55371767-27  
CERTIFICATE OF CONFORMANCE I 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) the repair/replacement activities and evaluations supporting the completion of                           U2C19 conform to the requirements of Section XI.                       pAvio         Aue" al                                                   (Refueling Outage Number)
& 78, 55371564-02 to former plate bolting.MC Containment Penetration 2-CPN-80 Replaced flange bolting 10/27/2010 55349023-18 3 East Component Cooling Water Heat Exchanger Replaced heat exchanger tubing 11/2/2010 55330326-02 (2-HE-15E) 3 Essential Service Water Piping Isometric Replaced elbow and flange 10/28/2010 55361123-01 2-ESW-46 3 Essential Service Water Piping Isometric Replaced elbow and flange 10/17/2010 55369102-29 2-ESW-53 2 South Safety Injection Pump 2-PP-26S Discharge Repair seal weld on valve bonnet 10/23/2010 55323817-15 Containment Isolation Valve 2-ICM-265 2 Feedwater to Steam Generator  
Signed                                               o6W,                 T'*e      49. 5uDesignee Owners or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of       Michigan                           and employed by One CIS Insurance Co.                   of       Lynn, MA have inspected the items described in this Owner's ActivityReport, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.
#1 Containment Insert hell-coils on valve body bolt holes and replace bolting 11/13/2010 55367139-07 Isolation Check Valve 2-FW-1 18-1. 1 1 2/10/2011 Page 3 of 3}}
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.
I.
              /Commissions                                               Michigan 300959, NB 11412, Endorsements: A, N & I Inspectors Signature                                                               National Board, State, Province, and Endorsements Date                     t d--&4" C                e P-.,v 2110/2011                                                                                                                                 Page 1 of 3
 
D.C. Cook Nuclear Unit 2 Table I Items with flaws or relevant conditions that required evaluation for continued service Examination     Item Number                       Item Description                                         Evaluation Description Category B-N-3           B313.70           Core Support Structure Accessible Surfaces   Broken Core Barrel Baffle Bolts evaluated for minimum bolting pattern and B-N-3___13.70             _CoreSupportStructureAccessibleSurfacesreplacement.
Loose Base Plate Nuts - Acceptable per previous evaluation under AIR 00820122-F-A,           F1.30B             2-GCCW-R-308 Pipe Support Component                           02 and -03 and WOT 55306855-01.
2/10/2011                                                                                                                                     Page 2 of 3
 
D.C. Cook Nuclear Unit 2 Table 2 Abstract of repair/replacement activities required for continued service Code Class                   Item Description                                     Description of Work                       Date Complete Repair I Replacement Plan Number 1           Reactor (2-OME-1) Core Barrel Baffle Bolts   Modification EC-50972: Removal/replacement of baffle plate         11/16/2010   55371767-27 & 78, 55371564-02 to former plate bolting.
MC               Containment Penetration 2-CPN-80                             Replaced flange bolting                       10/27/2010             55349023-18 3         East Component Cooling Water Heat Exchanger                   Replaced heat exchanger tubing                     11/2/2010             55330326-02 (2-HE-15E) 3             Essential Service Water Piping Isometric                     Replaced elbow and flange                       10/28/2010             55361123-01 2-ESW-46 3             Essential Service Water Piping Isometric                     Replaced elbow and flange                       10/17/2010             55369102-29 2-ESW-53 2       South Safety Injection Pump 2-PP-26S Discharge                 Repair seal weld on valve bonnet                   10/23/2010             55323817-15 Containment Isolation Valve 2-ICM-265 2         Feedwater to Steam Generator #1 Containment   Insert hell-coils on valve body bolt holes and replace bolting   11/13/2010             55367139-07 Isolation Check Valve 2-FW-1 18-1.     1                                                               1 2/10/2011                                                                                                                                                         Page 3 of 3}}

Latest revision as of 02:21, 13 November 2019

Form OAR-1 Owner'S Activity Report
ML110670423
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 02/28/2011
From: Carlson M
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2011-4
Download: ML110670423 (6)
v • d • e


Text

Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place Bridgman, Ml 49106 POWERO AEP.com A unit of American Electric Power February 28, 2011 AEP-NRC-2011-4 10 CFR 50.55a Docket No.: 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 2 Form OAR-1 Owner's Activity Report This letter provides a copy of Form OAR-1 Owner's Activity Report for inservice inspection activities performed at Donald C. Cook Nuclear Plant (CNP) Unit 2 through the completion of the U2C19 refueling outage. This report meets the requirements of the American Society of Mechanical Engineers (ASME) Code Case N-532-4, "Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission,Section XI, Division 1."

This code case is used as an alternative to the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Article IWA-6000 as approved by Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section Xl, Division 1, Revision 15."

The Authorized Code Inspection Company is One CIS Insurance Co., of Lynn, Massachusetts. The Authorized Nuclear Inspector is Reuel Schenck.

There are no new or revised commitments in this letter. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.

Sincerely, Michael H. Carlson Vice President - Site Support Services MCS/jmr

Attachment:

Form OAR-1 Owner's Activity Report for the Donald C. Cook Nuclear Plant Unit 2 Refueling Outage U2C19

U. S. Nuclear Regulatory Commission AEP-NRC-2011-4 Page 2 c: R. Aben - DLEG/BCCFS/BD J. T. King - MPSC, w/o attachment S. M. Krawec - AEP Ft. Wayne, w/o attachment MDNRE - WHMD/RPS, w/o attachment NRC Resident Inspector M. A. Satorius - NRC Region III P. K. Tam - NRC Washington DC

Attachment to AEP-NRC-2011-4 FORM OAR-1 OWNER'S ACTIVITY REPORT FOR DONALD C. COOK NUCLEAR PLANT UNIT 2 CYCLE 19 2010 REFUELING OUTAGE

DCCook Nuclear UJnit2 Form OAR-1 Owner's Activity Report Report Number 2-2010-4-1-01 Plant Donald C. Cook Nuclear Plant, One Cook Place, Bridgman, Michigan 49106 (Name and Address of Plant)

Unit No. 2 Commercial Service Date 7/1/1978 Refueling Outage No. U2C1 9 (ifapplicable)

Current Inspection Interval 4th for Components and Supports (C&S) and 2nd for Containment ISI (CISI) Program (1st, 2nd, 3rd, 4th, other)

Current Inspection Period 1st for C&S and 1st for CISI (1st, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the inspection plans 2004 Edition/No Addenda Date and Revision of inspection plans 7128/2010, Revision I for C&S, and 5/26/2010, Revision 0 for CISI Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Edition and Addenda same as the inspection Dlans Code Case used: N-526, N-532-4, N-566-2, N-586-1, N-624, N-716, N-722 and N-729-1 for C&S and N-649 for CISI (If applicable)

CERTIFICATE OF CONFORMANCE I 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) the repair/replacement activities and evaluations supporting the completion of U2C19 conform to the requirements of Section XI. pAvio Aue" al (Refueling Outage Number)

Signed o6W, T'*e 49. 5uDesignee Owners or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by One CIS Insurance Co. of Lynn, MA have inspected the items described in this Owner's ActivityReport, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

I.

/Commissions Michigan 300959, NB 11412, Endorsements: A, N & I Inspectors Signature National Board, State, Province, and Endorsements Date t d--&4" C e P-.,v 2110/2011 Page 1 of 3

D.C. Cook Nuclear Unit 2 Table I Items with flaws or relevant conditions that required evaluation for continued service Examination Item Number Item Description Evaluation Description Category B-N-3 B313.70 Core Support Structure Accessible Surfaces Broken Core Barrel Baffle Bolts evaluated for minimum bolting pattern and B-N-3___13.70 _CoreSupportStructureAccessibleSurfacesreplacement.

Loose Base Plate Nuts - Acceptable per previous evaluation under AIR 00820122-F-A, F1.30B 2-GCCW-R-308 Pipe Support Component 02 and -03 and WOT 55306855-01.

2/10/2011 Page 2 of 3

D.C. Cook Nuclear Unit 2 Table 2 Abstract of repair/replacement activities required for continued service Code Class Item Description Description of Work Date Complete Repair I Replacement Plan Number 1 Reactor (2-OME-1) Core Barrel Baffle Bolts Modification EC-50972: Removal/replacement of baffle plate 11/16/2010 55371767-27 & 78, 55371564-02 to former plate bolting.

MC Containment Penetration 2-CPN-80 Replaced flange bolting 10/27/2010 55349023-18 3 East Component Cooling Water Heat Exchanger Replaced heat exchanger tubing 11/2/2010 55330326-02 (2-HE-15E) 3 Essential Service Water Piping Isometric Replaced elbow and flange 10/28/2010 55361123-01 2-ESW-46 3 Essential Service Water Piping Isometric Replaced elbow and flange 10/17/2010 55369102-29 2-ESW-53 2 South Safety Injection Pump 2-PP-26S Discharge Repair seal weld on valve bonnet 10/23/2010 55323817-15 Containment Isolation Valve 2-ICM-265 2 Feedwater to Steam Generator #1 Containment Insert hell-coils on valve body bolt holes and replace bolting 11/13/2010 55367139-07 Isolation Check Valve 2-FW-1 18-1. 1 1 2/10/2011 Page 3 of 3

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