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{{#Wiki_filter:ExelknExelon Generation Company, LLC www.exeloncorp.com Braidwood Station NUClear 35100 South Route 53, Suite 84 Braceville, IL 60407-9619 August 10, 2011 BW1 10084 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Facility Operating License No. NPF-77 NRC Docket No. STN 50-457  
{{#Wiki_filter:Exelon Generation Company, LLC       www.exeloncorp.com Exelkn Braidwood Station                                                                       NUClear 35100 South Route 53, Suite 84 Braceville, IL60407-9619 August 10, 2011 BW1 10084 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Facility Operating License No. NPF-77 NRC Docket No. STN 50-457


==Subject:==
==Subject:==
Braidwood Station, Unit 2 Inservice Inspection Summary Report Enclosed please find the post-outage summary report (i.e., 90 day report) for inservice inspection examinations conducted during Braidwood Station, Unit 2 Refueling Outage 15 (A2R1 5). This report is submitted in accordance with the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, "Rules for the Inservice Inspection of Nuclear Power Plant Components," Article IWA-6200, "Requirements." Please direct any questions you may have regarding this submittal to Mr. Chris VanDenburgh, Regulatory Assurance Manager, at (815) 417-2800.Respectfully, Daniel J. EnrighA Site Vice President Braidwood Station  
Braidwood Station, Unit 2 Inservice Inspection Summary Report Enclosed please find the post-outage summary report (i.e., 90 day report) for inservice inspection examinations conducted during Braidwood Station, Unit 2 Refueling Outage 15 (A2R1 5). This report is submitted in accordance with the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, "Rules for the Inservice Inspection of Nuclear Power Plant Components," Article IWA-6200, "Requirements."
Please direct any questions you may have regarding this submittal to Mr. Chris VanDenburgh, Regulatory Assurance Manager, at (815) 417-2800.
Respectfully, Daniel J. EnrighA Site Vice President Braidwood Station


==Enclosure:==
==Enclosure:==
Braidwood Station ISI Outage Report for A2R1 5 cc:            Regional Administrator- NRC Region III NRC Senior Resident Inspector - Braidwood Station Illinois Emergency Management Agency - Division of Nuclear Safety U47T


Braidwood Station ISI Outage Report for A2R1 5 cc: Regional Administrator-NRC Region III NRC Senior Resident Inspector
BRAIDWOOD STATION UNIT 2 INSERVICE INSPECTION  
-Braidwood Station Illinois Emergency Management Agency -Division of Nuclear Safety U47T BRAIDWOOD STATION UNIT 2 INSERVICE INSPECTION  


==SUMMARY==
==SUMMARY==
REPORT FOR: Interval 3, Period 1, Outage 2 A2R15 Outage STATION ADDRESS: Braidwood Station 35100 S. Route 53 Suite 84 Braceville, Illinois 60407 UNIT 2 COMMERCIAL SERVICE DATE: October 17, 1988 OWNER'S ADDRESS: Exelon Generation Co., LLC 300 Exelon Way Kennett Square PA 19348 Exeln.Braidwood Station Unit 2 A2R15 ISI Outage Report TABLE OF CONTENTS DESCRIPTION:
 
PAGE: TITLE PAGE TABLE OF CONTENTS 1.0 -INSPECTION INFORMATION 1-1 to 1-3 2.0 -INSERVICE EXAMINATION  
REPORT FOR:
Interval 3, Period 1, Outage 2 A2R15 Outage STATION ADDRESS:
Braidwood Station 35100 S. Route 53 Suite 84 Braceville, Illinois 60407 UNIT 2 COMMERCIAL SERVICE DATE:
October 17, 1988 OWNER'S ADDRESS:
Exelon Generation Co., LLC 300 Exelon Way Kennett Square PA 19348
 
Exeln.
Braidwood Station Unit 2 A2R15 ISI Outage Report TABLE OF CONTENTS DESCRIPTION:                                                         PAGE:
TITLE PAGE TABLE OF CONTENTS 1.0 - INSPECTION INFORMATION                                         1-1 to 1-3 2.0 - INSERVICE EXAMINATION  


==SUMMARY==
==SUMMARY==
2-1 to 2-5 3.0 -COMPONENT EXAMINATION RESULTS 3-1 to 3-54 4.0 -REPORT OF CONTAINMENT 4-1 to 4-4 DEGRADATION 5.0 -FORM NIS-1 (OWNER'S REPORT FOR INSERVICE INSPECTION) 5-1 to 5-4 FOR ISI THIRD INTERVAL AND THIRD INTERVAL INSPECTION STATUS AFTER A2R15 6.0 -FORM NIS-2, (OWNER'S REPORT FOR REPAIRS 6-1 to 6-47 OR REPLACEMENTS), Cover page plus 46 pages of Attachments ii Exei n_Braidwood Station Unit 2 A2R15 ISI Outage Report 1.0 INSPECTION INFORMATION 1.1 Summary Third Interval Inservice Inspections (ISI) and Preservice Inspections (PSI)of ASME Class 1, 2, and 3 components were conducted at Braidwood Station Unit 2 from November 2, 2009 through July 28, 2011. The majority of these inspections were performed during the Braidwood Station Unit 2 fifteenth refueling outage (A2R1 5). This report also contains the results of the remaining pressure tests that were not completed prior to submittal of the previous A2R1 4 outage report.For the Third Interval, examinations were performed in accordance with the rules and regulations of Section Xl, Division 1, "Rules for Inservice Inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 2001 Edition through 2003 Addenda, pursuant to the requirements of Title 10, Part 50.55a of the Code of Federal Regulations (10CFR50.55a).
2-1 to 2-5 3.0 - COMPONENT EXAMINATION RESULTS                                 3-1 to 3-54 4.0 - REPORT OF CONTAINMENT                                         4-1 to 4-4 DEGRADATION 5.0 - FORM NIS-1 (OWNER'S REPORT FOR INSERVICE INSPECTION)           5-1 to 5-4 FOR ISI THIRD INTERVAL AND THIRD INTERVAL INSPECTION STATUS AFTER A2R15 6.0 - FORM NIS-2, (OWNER'S REPORT FOR REPAIRS                       6-1 to 6-47 OR REPLACEMENTS), Cover page plus 46 pages of Attachments ii
The Containment Inspection Program was developed and implemented in accordance with the requirements and intent of Subsections IWE and IWL of ASME Section Xl, 2001 Edition through the 2003 Addenda, pursuant to the requirements of 1OCFR50.55a.
 
In addition to the ASME Section Xl requirements, certain NRC or industry augmented inspections were completed during A2R15. The Braidwood Unit 2 augmented examinations included: a) Examination of the Class 1 pressure boundary for leakage at nominal operating pressure, in accordance with Generic Letter 88-05.b) Examination of the 2B reactor coolant pump motor flywheel in accordance with Regulatory Guide 1.14 and Technical Specification 5.5.7.c) Examination of welds in accordance with Materials Reliability Project MRP-139, "Primary System Piping Butt Weld Inspection and Evaluation Guideline" and MRP-192, "Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants".d) Reinspection of all six pressurizer nozzle-to-safe end full structural overlays in accordance with ASME Section Xl Nonmandatory Appendix Q and Second Interval Relief Request 12R-48.The only documented indication requiring further evaluation was observed during the augmented inspections for MRP-192 in a tee-to-pipe circumferential weld. This indication was attributed to original construction and was not characterized as service-induced (i.e., thermal fatigue craze cracking).
Exei n_
The indication was accepted for continued service in accordance with IWB-3600 evaluation methods.Page 1-1 Exel .n-Braidwood Station Unit 2 A2R15 ISI Outage Report 1.2 Identification of Examination Requirements The Third Interval ISI Program contains the applicable Component Selection tables. These tables are presented in a tabular format consistent with the tables found in subsections IWB, IWC, IWD, IWE, and IWF-2500 of the ASME code. The Non-Destructive Examination (NDE) tables include the corresponding code category, item number, and component/weld population selection in conformance with examination requirements and intent of Subsection IWA, IWB, IWC, IWD, IWE, and IWF of Section Xl of the ASME Code. Program notes and relief requests and additional information are identified in the basis column.1.3 Exempted Components ASME Class 1, 2, and 3 components (or parts of components) that are not included in the Component inspection tables and that are exempt from examination, as specified in Section Xl Subsection IWB, IWC, IWD, and IWF are identified in the Braidwood Station Boundary Basis document, along with reference to the justification(s) for exempting the component/system.
Braidwood Station Unit 2 A2R15 ISI Outage Report 1.0 INSPECTION INFORMATION 1.1 Summary Third Interval Inservice Inspections (ISI) and Preservice Inspections (PSI) of ASME Class 1, 2, and 3 components were conducted at Braidwood Station Unit 2 from November 2, 2009 through July 28, 2011. The majority of these inspections were performed during the Braidwood Station Unit 2 fifteenth refueling outage (A2R1 5). This report also contains the results of the remaining pressure tests that were not completed prior to submittal of the previous A2R1 4 outage report.
For the Third Interval, examinations were performed in accordance with the rules and regulations of Section Xl, Division 1, "Rules for Inservice Inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 2001 Edition through 2003 Addenda, pursuant to the requirements of Title 10, Part 50.55a of the Code of Federal Regulations (10CFR50.55a).
The Containment Inspection Program was developed and implemented in accordance with the requirements and intent of Subsections IWE and IWL of ASME Section Xl, 2001 Edition through the 2003 Addenda, pursuant to the requirements of 10CFR50.55a.
In addition to the ASME Section Xl requirements, certain NRC or industry augmented inspections were completed during A2R15. The Braidwood Unit 2 augmented examinations included:
a)     Examination of the Class 1 pressure boundary for leakage at nominal operating pressure, in accordance with Generic Letter 88-05.
b)     Examination of the 2B reactor coolant pump motor flywheel in accordance with Regulatory Guide 1.14 and Technical Specification 5.5.7.
c)     Examination of welds in accordance with Materials Reliability Project MRP-139, "Primary System Piping Butt Weld Inspection and Evaluation Guideline" and MRP-192, "Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants".
d)     Reinspection of all six pressurizer nozzle-to-safe end full structural overlays in accordance with ASME Section Xl Nonmandatory Appendix Q and Second Interval Relief Request 12R-48.
The only documented indication requiring further evaluation was observed during the augmented inspections for MRP-192 in a tee-to-pipe circumferential weld. This indication was attributed to original construction and was not characterized as service-induced (i.e., thermal fatigue craze cracking). The indication was accepted for continued service in accordance with IWB-3600 evaluation methods.
Page 1-1
 
Exel .n-Braidwood Station Unit 2 A2R15 ISI Outage Report 1.2 Identification of Examination Requirements The Third Interval ISI Program contains the applicable Component Selection tables. These tables are presented in a tabular format consistent with the tables found in subsections IWB, IWC, IWD, IWE, and IWF-2500 of the ASME code. The Non-Destructive Examination (NDE) tables include the corresponding code category, item number, and component/weld population selection in conformance with examination requirements and intent of Subsection IWA, IWB, IWC, IWD, IWE, and IWF of Section Xl of the ASME Code. Program notes and relief requests and additional information are identified in the basis column.
1.3 Exempted Components ASME Class 1, 2, and 3 components (or parts of components) that are not included in the Component inspection tables and that are exempt from examination, as specified in Section Xl Subsection IWB, IWC, IWD, and IWF are identified in the Braidwood Station Boundary Basis document, along with reference to the justification(s) for exempting the component/system.
1.4 ISI Program Implementation Braidwood Station personnel, or their designee, visually examined (VT-1, VT-2, and VT-3) and/or NDE examined (UT, PT, MT) ASME components.
1.4 ISI Program Implementation Braidwood Station personnel, or their designee, visually examined (VT-1, VT-2, and VT-3) and/or NDE examined (UT, PT, MT) ASME components.
The components examined comply with the ISI Program Schedule, Braidwood Station Technical Specifications (TS), and/or compliance with the ASME Section Xl Repair/Replacement Program. All ISI NDE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section XI, Sub-article IWA-2200: "Examination Methods".Certified personnel performed and evaluated all NDE results. Personnel were certified to the requirements of the American Society for Non-destructive Testing SNT-TC-1A, 1984 Edition and ANSI/ASNT CP-189, 1995 Revision.
The components examined comply with the ISI Program Schedule, Braidwood Station Technical Specifications (TS), and/or compliance with the ASME Section Xl Repair/Replacement Program. All ISI NDE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section XI, Sub-article IWA-2200:
The NDE procedures were developed and certified in conformance with ASME Section V and Xl, 2001 Edition through 2003 Addenda, or approved alternatives (Performance Demonstration Initiative Program) as applicable.
    "Examination Methods".
In addition, ultrasonic examination personnel were qualified in accordance with ANSI/ASME CP-189, 1995 Revision.Certified personnel performed and evaluated visual examinations (i.e., VT-1, VT-2, and VT-3) of Class 1, 2, and 3 components and supports.Personnel were certified to the requirements of the American Society for Non-destructive Testing SNT-TC-1A, 1984 Edition and ANSI/ASNT CP-189, 1995 Revision.Certified personnel performed and evaluated examinations (UT, VT-1, and VT-3) of primary containment.
Certified personnel performed and evaluated all NDE results. Personnel were certified to the requirements of the American Society for Non-destructive Testing SNT-TC-1A, 1984 Edition and ANSI/ASNT CP-189, 1995 Revision. The NDE procedures were developed and certified in conformance with ASME Section V and Xl, 2001 Edition through 2003 Addenda, or approved alternatives (Performance Demonstration Initiative Program) as applicable. In addition, ultrasonic examination personnel were qualified in accordance with ANSI/ASME CP-189, 1995 Revision.
Personnel were certified in Page 1-2 Exekm..Braidwood Station Unit 2 A2R15 ISI Outage Report accordance with the requirements of the ANSI/ASNT CP-1i89, 1995 Revision, and/or ASME Section XI 2001 through 2003 Addenda, as applicable.
Certified personnel performed and evaluated visual examinations (i.e.,
1.5 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANII), L. Malabanan and J.Norville.
VT-1, VT-2, and VT-3) of Class 1, 2, and 3 components and supports.
The inspectors are associated with Hartford Steam Boiler Inspection and Insurance Company of Connecticut, Chicago Branch, at 2443 Warrenville Rd., Suite 500, Lisle, Illinois 60532.Page 1-3  
Personnel were certified to the requirements of the American Society for Non-destructive Testing SNT-TC-1A, 1984 Edition and ANSI/ASNT CP-189, 1995 Revision.
.Exelon-Braidwood Station Unit 2 A2R15 ISI Outage Report 2.0 INSERVICE EXAMINATION  
Certified personnel performed and evaluated examinations (UT, VT-1, and VT-3) of primary containment. Personnel were certified in Page 1-2
 
Exekm..
Braidwood Station Unit 2 A2R15 ISI Outage Report accordance with the requirements of the ANSI/ASNT CP-1i89, 1995 Revision, and/or ASME Section XI 2001 through 2003 Addenda, as applicable.
1.5 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANII), L. Malabanan and J.
Norville. The inspectors are associated with Hartford Steam Boiler Inspection and Insurance Company of Connecticut, Chicago Branch, at 2443 Warrenville Rd., Suite 500, Lisle, Illinois 60532.
Page 1-3
 
                                                                                        .Exelon-Braidwood Station Unit 2 A2R15 ISI Outage Report 2.0 INSERVICE EXAMINATION  


==SUMMARY==
==SUMMARY==
The following is a summary of ASME Section Xl Class 1 and 2, Risk Informed ISI, and augmented examinations performed during the Braidwood Station Unit 2 A2R15 refueling outage. Refer to the component detailed examination tabulations of Section 3.0 for additional information on specific welds, components, supports, snubbers and pressure test examinations and their respective results.2.1 Inservice Weld/Component Summary SSystem ... Number. of Welds/* z ;.System .......: S..
 
The following is a summary of ASME Section Xl Class 1 and 2, Risk Informed ISI, and augmented examinations performed during the Braidwood Station Unit 2 A2R15 refueling outage. Refer to the component detailed examination tabulations of Section 3.0 for additional information on specific welds, components, supports, snubbers and pressure test examinations and their respective results.
2.1    Inservice Weld/Component Summary
                  * .o..*
z SSystem
                          ;.System
                                .  ......... *.:*.., : Number. of Welds/
S...Components*
Containment Spray (CS)                                  2 Feedwater (FW)                                          11 Reactor Coolant (RC)                                    8 Residual Heat Removal (RH)                              11 Pressurizer (RY)                                        14 Safety Injection (SI)                                    1 TOTALS                                      47 Non-Section Xl Augmented, 10 CFR 50.55a, and Risk Informed ISI socket weld VT-2 examinations are not included in these counts but are contained in Section 3.1.1 of report.
2.2    Inservice Component Support Summary Number of SYSTEM: EXAMINED-                              Component
                                                            ........ Supports Auxiliary Feedwater (AF)                                    4 Chemical & Volume Control (CV)                              2 Feedwater (FW)                                              4 Main Steam (MS)                                            4 Reactor Coolant (RC)                                        2 Residual Heat Removal (RH)                                  7 Reactor Coolant/Pressurizer (RY)                            7 Safety Injection (SI)                                      16 Essential Service Water (SX)                              14 TOTALS                                      60 Page 2-1
 
Exek n-Braidwood Station Unit 2 A2R15 ISI Outage Report 2.3    Inservice Snubber Summary Number.of    %.Number of


== Description:==
== Description:==
                . .. ,...                            RequestsI Notes          Exam.
Comments      .':,                  >. .,:.:.
F-A  F01.20      2CS03022S                            2CS02AB-10"                              NOTE 01        VT-3    NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A  F01.20      2CS03106S                            2CS02AB-10"                              NOTE 01        VT-3    NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-29
IExelein-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Chemical & Volume Control System (CV)
Section XI      1"ISldenti.e*tier                    Line Number        .Relief              Technica v      Actu'ad  Results Cat. Item        Description'I$*      :equests                                                Notes?    lxa r Commentse>,                                              .              ,
NA      NA      2CV02005S                            2CV10CB-3"                                  NOTE 01      VT-3  PASS Snubber                                                                                          FT  MARG INITIAL SAMPLE DTPG 2-1, SERIAL NUMBER 12024 WAS REPLACED WITH SERIAL NUMBER 8014 DUE TO IDENTIFIED DEGRADATION DURING THE DRAG TEST IN COMPRESSION. REFERENCE ISSUE REPORT 1206126.
NA      NA      2CV03002S                            2CV10CA-3"                                  NOTE 01      VT-3    NRI Snubber                                                                                          FT  PASS INITIAL SAMPLE DTPG 2-2 F-A    F01.10  2CV06010S                            2CVB7A-3"                                    NOTE 01      VT-3    NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 NA      NA    2CV07032S                            2CV01 E-3"                                  NOTE 01      VT-3    NRI Snubber                                                                                          FT  PASS INITIAL SAMPLE DTPG 2-1 NA      NA    2CV07033S                            2CV01 E-3'                                  NOTE 01      VT-3    NRI Snubber                                                                                          FT  PASS INITIAL SAMPLE DTPG 2-2 NA      NA    2CV07069S                            2CV01 E-3"                                  NOTE 01      VT-3    NRI Snubber                                                                                          FT  PASS TESTED FOR SERVICE LIFE MONITORING NA      NA    2CV24024S                            2CV43BB-2"                                  NOTE 01      VT-3    NRI Snubber                                                                                          FT  PASS INITIAL SAMPLE DTPG 2-2 F-A    F01.10  2CV25009S                            2CVA7AA-2"                                  NOTE 01      VT-3    NRI Snubber                                                                                          FT  PASS INITIAL SAMPLE DTPG 2-2 NA      NA    2CV31007S                            2CV15DA-.75"                                NOTE 01      VT-3    NRI Snubber                                                                                          FT  PASS INITIAL SAMPLE DTPG 2-1 NA      NA    2CV31 011S                          2CV15DA-.75"                                NOTE 01      VT-3    NRI Snubber                                                                                          FT  PASS INITIAL SAMPLE DTPG 2-1 NA      NA    2CV40005S                            2CV14EC-2"                                  NOTE 01      VT-3    NRI Snubber                                                                                          FT  PASS INITIAL SAMPLE DTPG 2-1 F-A    F01.10  2RY06121S                            2CV45B-2"                                    NOTE 01      VT-3    NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-30
Exe kn.
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Feedwater System (FW)
-SectionXl              Identifier                  Line Number        :Reief                  Techn ica A    it"i Results1 Cat.          *::* ........                                .:                        Reques      Notes    Exam Cb'mmentsQ F-A    F01.20    2FW02016S                        2FW03DA-16"                                  NOTE 01    VT-3      NRI Snubber                                                                                      FT    PASS INITIAL SAMPLE DTPG 2-2 F-A    F01.20    2FW03010S                        2FW03DB-16"                                  NOTE 01    VT-3    PASS Snubber                                                                                      FT    PASS INITIAL SAMPLE DTPG 2-2 F-A    F01.20    2FW03015S                        2FW03DB-16"                                  NOTE 01    VT-3      NRI Snubber                                                                                      FT    PASS INITIAL SAMPLE DTPG 2-2 F-A    F01.20    2FW04015S                        2FW03DC-16"                                  NOTE 01    VT-3      NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A    F01.20    2FW04017S                        2FW03DC-16"                                  NOTE 01    VT-3    NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A    F01.20    2FW05011AS                        2FW03DD-16"                                  NOTE 01    VT-3    NRI Snubber                                                                                      FT    PASS TESTED FOR SERVICE LIFE MONITORING F-A    F01.20    2FW05011BS                        2FW03DD-16"                                  NOTE 01    VT-3    NRI Snubber                                                                                      FT    MARG TESTED FOR SERVICE LIFE MONITORING. Snubber With S.N. 7036 Is Being Replaced During A2R15 Due To Marginal Test Results Observed During A2R14 (Reference IR Number 985759 and W/O 01299417.
F-A    F01.20    2FW05020S                          2FW03DD-16"                                  NOTE 01    VT-3    NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A    F01.20    2FW05022S                          2FW03DD-16"                                  NOTE 01    VT-3    NRI Snubber                                                                                      FT    PASS INITIAL SAMPLE DTPG 2-2 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-31
Exet n.
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Main Steam System (MS)
Section Xl .      St. Idortifiene  ;                  Line Number,.                  Relief    , Technical .A:tual      B.esults Cat. Item..  "Description                    :",;                                Requests    N                    .
Comments.
F-A    F01.20  2MS01074AS                          2MSO7AA-28"                                  NOTE 01      VT-3      NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTID / CODE CASE OMN-13 F-A    F01.20  2MS01074BS                          2MS07AA-28"                                  NOTE 01      VT-3      NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A    F01.20  2MS01097S                            2MS07AB-28"                                  NOTE 01      VT-3      NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A    F01.20  2MS05007AS                          2MS01AA-30.25"                                NOTE 01      VT-3      NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A    F01.20  2MS05007BS                          2MS01AA-30.25"                                NOTE 01      VT-3      NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A    F01.20  2MS06007AS                          2MS01AB-32.75"                                NOTE 01      VT-3      NRI Snubber, integrally attached to pipe                                                              FT      PASS INITIAL SAMPLE DTPG 2-3 F-A    F01.20  2MS06007BS                          2MS01AB-32.75"                                NOTE 01      VT-3      NRI Snubber, integrally attached to pipe                                                              FT      PASS INITIAL SAMPLE DTPG 2-2 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-32
Exelun'.
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Reactor Coolant System (RC)
Section XL      ISI Identifier: -                    Line Number    :              Relief  :  Technical Atual    !Results,:'
Catitm          CtitmRequestsA escription                                                                    Notes,    xa A                    T Comments                                                                A F-A    F01.10  2CV06014S                            2RC36A-3"                                    NOTE 01    VT-3      NRI Snubber                                                                                        FT      PASS INITIAL SAMPLE DTPG 2-2 F-A    F01.10  2CV06016S                            2RC36A-3"                                    NOTE 01    VT-3      NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A    F01.10  2CV14001S                            2RC16AD-2"                                  NOTE 01    VT-3      NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A    F01.10  2CV25002S                            2RC14AD-2"                                  NOTE 01    VT-3      NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-1 3 F-A    F01.40  2RC01BA-A                            5.G. A                                      NOTE 01    VT-3      NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION. RESERVOIR LEVEL ACCEPTABLE.
F-A    F01.40  2RC01 BA-B                          5.G. A                                      NOTE 01    VT-3      NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION. RESERVOIR LEVEL ACCEPTABLE.
F-A    F01.40  2RC01BB-A                            S.G B                                        NOTE 01    VT-3      NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION. RESERVOIR LEVEL ACCEPTABLE.
F-A    F01.40  2RC01 BB-B                          S.G B                                        NOTE 01    VT-3      NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION. RESERVOIR LEVEL ACCEPTABLE.
F-A    F01.40  2RC01BC-A                            S.G C                                        NOTE 01    VT-3      NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION. RESERVOIR LEVEL ACCEPTABLE.
F-A    F01.40  2RC01BC-B                            S.G C                                        NOTE 01    VT-3      NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION. RESERVOIR LEVEL ACCEPTABLE.
F-A    F01.40  2RC01BD-A                            S.G D                                        NOTE 01    VT-3      NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION. RESERVOIR LEVEL ACCEPTABLE.
F-A    F01.40  2RC01BD-B                            S.G D                                        NOTE 01    VT-3      NRI Snubber                                                                                        FT      PASS Steam Generator Snubber Visual Examination and Functional Test. DTPG 2-4 F-A    F01l10  2RC03007S                            2RC21AC-8"                                  NOTE 01    VT-3    PASS Snubber                                                                                      FT      PASS INITIAL SAMPLE DTPG 2-2 Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-33
Exelkn.
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Reactor Coolant System (RC)
Section XI        ISIlIdentifier                      Line Number..                  Relief      TechnicalV Actual  Results' Cat. Item      Description .          .    .Requests                                        N!Jotes,
* am.    ..
comments~<
NA      NA      2RC1 7069S                          2RC20AB-.75"                                NOTE 01      VT-3    PASS Snubber                                                                                        FT    MARG TESTED FOR SERVICE LIFE MONITORING. Snubber Is Being Replaced During A2R15 Due To Marginal Test Results Observed During A2R14 (Reference IR Number 987527 and W/O 01299699).
F-A    F01.10    2RY06104S                          2RC26A-2"                                    NOTE 01      VT-3    NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A    F01.10    2RY06106S                          2RC26A-2"                                    NOTE 01      VT-3    NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-34
Exek n-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Residual Heat Removal System (RH)
Se Ieer.XI".  '.Line                      .Number"Relief                        Technical Atual    Results Ca.Item,~      DecipnRequestsi                                                                Notes    Exn<    ,
Comme~nts~
F-A    F01.10    2RH02013S                          2RHO1AB-12"                                  NOTE 01    VT-3    NRI Snubber                                                                                      FT    PASS INITIAL SAMPLE DTPG 2-2 F-A    F01.10    2RH02052S                          2RH01AA-12"                                  NOTE 01    VT-3    NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-35
Exe ,m.
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Reactor Coolant System (RY) sectionmXl..1. Identifier                            Pe LnNumber                      Relief  *Technical. "Actual . Results Ca.Item      De3scription.2                                                    Requests INotes.      Exam IComments NA      NA    2RC93A001S                          2RY34BB-.5"                                  NOTE 01    VT-3    NRI Snubber                                                                                        FT    PASS INITIAL SAMPLE DTPG 2-1 F-A    F01.10  2RY05010S                            2RY11A-14"                                  NOTE 01    VT-3    NRI Snubber                                                                                      FT    PASS INITIAL SAMPLE DTPG 2-2 F-A    F01.10  2RY06020S                            2RY01B-6"                                    NOTE 01    VT-3    NRI Snubber                                                                                      FT    PASS INITIAL SAMPLE DTPG 2-2 F-A    F01.10  2RY06025S                            2RY01B-6"                                    NOTE 01    VT-3    NRI Snubber                                                                                      FT    PASS INITIAL SAMPLE DTPG 2-2 F-A    F01.10  2RY06114S                            2RY18A-2"                                    NOTE 01    VT-3    NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 NA      NA    2RY06125S                            2RY09AB-.75"                                NOTE 01    VT-3    NRI Snubber                                                                                      FT    PASS INITIAL SAMPLE DTPG 2-1 F-A    F01.10  2RY09001S                            2RY02B-3"                                    NOTE 01    VT-3    NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A    F01.10  2RY09005S                            2RY02B-3"                                    NOTE 01    VT-3    NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A    F01.10  2RY09100S                            2RY02B-3"                                    NOTE 01    VT-3    NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A    F01.10  2RY09101S                            2RY06A-3"                                    NOTE 01    VT-3    NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-36
Exek n.
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Steam Generator Blowdown System (SD)
Section Xl *L liSI Identifier-!:;*'                jLine Number
* Relief  ",  Technical: A cual.c  Results" Cat. -item".  -Descrption                                                            Reques      Notes
* Exam NA        NA    2SD06032S                          2SDO1CE-2"                                    NOTE 01      VT-3      NRI Snubber                                                                                        FT      PASS INITIAL SAMPLE DTPG 2-1 NA        NA    2SD11066S                          2SD01CH-2"                                    NOTE 01      VT-3      NRI Snubber                                                                                        FT      MARG INITIAL SAMPLE DTPG 2-1. SN 2598 was replaced with SN 42820 due to high drag values in both the Tension and Compression directions. Reference Issue Report 1204436.
NA        NA    2SD12048S                          2SD01CG-2"                                  NOTE 01      VT-3      NRI Snubber                                                                                        FT      PASS INITIAL SAMPLE DTPG 2-1 Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-37
Exek n.
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Safety Injection System (SI)
Section Xl        Ist Identifier              .      LineNumber                        Rlf          Technical. .Actual      . Results Cat Item          Desciption..,, ,....                                  ,. .Requests                Notes          Exam Comments      .                                                                                                      ,
F-A    F01.10  2RH02018S                          &#xfd;2S104D-8"                                        NOTE 01        VT-3        NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A    F01.20  2RH02027S                          2SI04C-8"                                        NOTE 01        VT-3        NRI Snubber                                                                                                FT        PASS INITIAL SAMPLE DTPG 2-2 F-A    F01.10  2RH02061S                          2SI04D-8"                                        NOTE 01        VT-3        NRI Snubber                                                                                                FT        PASS INITIAL SAMPLE DTPG 2-2 F-A    F01.10    2RH02078S                          2SIA4B-8"                                        NOTE 01        VT-3        NRI Snubber                                                                                                FT        PASS INITIAL SAMPLE DTPG 2-2 F-A    F01.10    2SI03018S                          2SI05DD-6"                                        NOTE 01        VT-3        NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13. 10: Clamp is slightly skewed but well with the 10 degree conical tolerance. Acceptable per M-999 Sheet 10 Note 2A, and will not interfere with movement from cold to hot position and vice versa.
F-A    F01.20    2SI09002S                          2SI09BC-10"                                      NOTE 01        VT-3        NRI Snubber                                                                                                FT        PASS INITIAL SAMPLE DTPG 2-2 F-A    F01.10    2SI10036S                          2SI03FB-2"                                        NOTE 01        VT-3        NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-38
Exek-n.t Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Essential Service Water System (SX)
Section X11-1    ISI Identifier...:.                  Line'Number*6    . .:e.6fnicat eesults**a            At.*u      R Cat. Item-::    De.cr*ption                      .iRequests                                    Notes    Exam
: Comments, F-A    F01.20  2SX09038S                            2SX07CB-10"                                  NOTE 01      VT-3    NRI Snubber                                                                                          FT    PASS INITIAL SAMPLE DTPG 2-3 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-39
Exek n.
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM: Chemical & Volume Control System (CV)
Section X1    ComponentID                          Line Number                    Reliet    17 Technical  Exam&#xfd;.. Results Cat. Item~ Ilecription ;:&#xfd;~Rqests                                                            Not:
Commients, NA        NA    2CV02005S                            2CV1 0CB-3"                              NOTE 01    FT        PASS Snubber                                                                                    VT-3      NRI Existing mechanical snubber (Serial Number 12024) replaced with tested spare (Serial Number 8014) under WO# 1431482.
Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-40
Exeb n.
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM:          Feedwater System (FW)
Section Xl    !Component ID                        Line Numbe**lief                        Technical,  Exa      Results tm    Description
:ae                                                                IRequests  Nts Comments-*'
F-A    F01.20 2FW05011BS                            2FW03DD-16"                              NOTE 01      FT        PASS Snubber                                                                                    VT-3      NRI Existing mechanical snubber (Serial Number 7036) replaced with tested spare (Serial Number 47260) under WO# 1299417.
Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-41


... ,... RequestsI Notes Exam.Comments .':, >. .,: .:.F-A F01.20 2CS03022S 2CS02AB-10" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2CS03106S 2CS02AB-10" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-29 IExelein-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Chemical & Volume Control System (CV)Section XI 1" Line Number .Relief v Technica Actu'ad Results Cat. Item
Exe- n.
:equests Notes? lxa r Commentse>, ., NA NA 2CV02005S 2CV10CB-3" NOTE 01 VT-3 PASS Snubber FT MARG INITIAL SAMPLE DTPG 2-1, SERIAL NUMBER 12024 WAS REPLACED WITH SERIAL NUMBER 8014 DUE TO IDENTIFIED DEGRADATION DURING THE DRAG TEST IN COMPRESSION.
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM: Reactor Coolant System (RC)
REFERENCE ISSUE REPORT 1206126.NA NA 2CV03002S 2CV10CA-3" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2CV06010S 2CVB7A-3" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 NA NA 2CV07032S 2CV01 E-3" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 NA NA 2CV07033S 2CV01 E-3' NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 NA NA 2CV07069S 2CV01 E-3" NOTE 01 VT-3 NRI Snubber FT PASS TESTED FOR SERVICE LIFE MONITORING NA NA 2CV24024S 2CV43BB-2" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2CV25009S 2CVA7AA-2" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 NA NA 2CV31007S 2CV15DA-.75" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 NA NA 2CV31 011S 2CV15DA-.75" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 NA NA 2CV40005S 2CV14EC-2" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 F-A F01.10 2RY06121S 2CV45B-2" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-30 Exe kn.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Feedwater System (FW)-Section Xl Identifier Line Number :Reief Techn ica A it"i Results1 Cat. ........ .: Reques Notes Exam Cb'mmentsQ F-A F01.20 2FW02016S 2FW03DA-16" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.20 2FW03010S 2FW03DB-16" NOTE 01 VT-3 PASS Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.20 2FW03015S 2FW03DB-16" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.20 2FW04015S 2FW03DC-16" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2FW04017S 2FW03DC-16" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2FW05011AS 2FW03DD-16" NOTE 01 VT-3 NRI Snubber FT PASS TESTED FOR SERVICE LIFE MONITORING F-A F01.20 2FW05011BS 2FW03DD-16" NOTE 01 VT-3 NRI Snubber FT MARG TESTED FOR SERVICE LIFE MONITORING.
SectionnXl**0  ComponentID.*            .Line            Number.                 Relief: -.-, Technical, Exam      Results:
Snubber With S.N. 7036 Is Being Replaced During A2R15 Due To Marginal Test Results Observed During A2R14 (Reference IR Number 985759 and W/O 01299417.F-A F01.20 2FW05020S 2FW03DD-16" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2FW05022S 2FW03DD-16" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-31 Exet n.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Main Steam System (MS)Section Xl .St. Idortifiene
Cat. item .lDescription          "Requests.                                                   Notes.
; Line Number,. Relief , Technical .A:tual B.esults Cat. Item.. "Description Requests N :",; .Comments.F-A F01.20 2MS01074AS 2MSO7AA-28" NOTE 01 VT-3 NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTID / CODE CASE OMN-13 F-A F01.20 2MS01074BS 2MS07AA-28" NOTE 01 VT-3 NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2MS01097S 2MS07AB-28" NOTE 01 VT-3 NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2MS05007AS 2MS01AA-30.25" NOTE 01 VT-3 NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2MS05007BS 2MS01AA-30.25" NOTE 01 VT-3 NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2MS06007AS 2MS01AB-32.75" NOTE 01 VT-3 NRI Snubber, integrally attached to pipe FT PASS INITIAL SAMPLE DTPG 2-3 F-A F01.20 2MS06007BS 2MS01AB-32.75" NOTE 01 VT-3 NRI Snubber, integrally attached to pipe FT PASS INITIAL SAMPLE DTPG 2-2 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-32 Exelun'.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Reactor Coolant System (RC)Section XL ISI Identifier:
NA      NA    2RC17069S                            2RC20AB-.75"                               NOTE 01   FT        PASS Snubber                                                                                    VT-3       NRI Existing mechanical snubber (Serial Number 2653) replaced with tested spare (Serial Number 42825) under WO# 1299699.
-Line Number : Relief : Technical Atual ! Results,:'
Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-42
CtitmRequestsA Notes, xa Cat itm escription A T Comments A F-A F01.10 2CV06014S 2RC36A-3" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2CV06016S 2RC36A-3" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.10 2CV14001S 2RC16AD-2" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.10 2CV25002S 2RC14AD-2" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-1 3 F-A F01.40 2RC01BA-A 5.G. A NOTE 01 VT-3 NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION.
 
RESERVOIR LEVEL ACCEPTABLE.
Exelkn-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM: Reactor Coolant System (RY)
F-A F01.40 2RC01 BA-B 5.G. A NOTE 01 VT-3 NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION.
Section X. Co**mponent ID<*
RESERVOIR LEVEL ACCEPTABLE.
                                !..Line                   Number.             . eiie*.. Tchn6ical  Exam . Results Ct7      e    Description .                .                                   Requests    Notes .
F-A F01.40 2RC01BB-A S.G B NOTE 01 VT-3 NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION.
F-A    F01.10 2RY05010S                              2RY11A-14"                               NOTE 01   VT-3       NRI Snubber Existing damaged snubber pivot pin with a new pin under WO# 1432228.
RESERVOIR LEVEL ACCEPTABLE.
Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-43
F-A F01.40 2RC01 BB-B S.G B NOTE 01 VT-3 NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION.
 
RESERVOIR LEVEL ACCEPTABLE.
Exekn-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM: Steam Generator Blowdown System (SD)
F-A F01.40 2RC01BC-A S.G C NOTE 01 VT-3 NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION.
Section XI*    Component DO "Line                        Number    " .          Rwiif*    Technicali  &#xfd;Eam    " Results ,
RESERVOIR LEVEL ACCEPTABLE.
cat'. Iteim    Deescription:                                ,                    Reuests,;, Ntes      -
F-A F01.40 2RC01BC-B S.G C NOTE 01 VT-3 NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION.
Comments                                                  ,,                                          ..             ,
RESERVOIR LEVEL ACCEPTABLE.
NA      NA    2SD11066S                          2SD01CH-2"                               NOTE 01     FT          PASS Snubber                                                                                    VT-3       NRI Existing mechanical snubber (Serial Number 2598) replaced with tested spare (Serial Number 42820) under WO# 1430989.
F-A F01.40 2RC01BD-A S.G D NOTE 01 VT-3 NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION.
Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-44
RESERVOIR LEVEL ACCEPTABLE.
 
F-A F01.40 2RC01BD-B S.G D NOTE 01 VT-3 NRI Snubber FT PASS Steam Generator Snubber Visual Examination and Functional Test. DTPG 2-4 F-A F01l10 2RC03007S 2RC21AC-8" NOTE 01 VT-3 PASS Snubber FT PASS INITIAL SAMPLE DTPG 2-2 Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-33 Exelkn.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Reactor Coolant System (RC)Section XI ISIlIdentifier Line Number.. Relief TechnicalV Actual Results'Cat. Item Description
Exe0 n Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Chemical & Volume Control System (CV)
...Requests N!Jotes, am. ..comments~<
Section Xl     Component ID4 . .              ..                        .   .     Rel!e*  . Technica!. Reuird: .Results Cat.-   tem    hnspection NotesF        "7                  *.. ..  ,.              Requests  Notesi<    Exan  .  : ".      "
NA NA 2RC1 7069S 2RC20AB-.75" NOTE 01 VT-3 PASS Snubber FT MARG TESTED FOR SERVICE LIFE MONITORING.
Com me nts. *. j . .. ..       . . 1..   .           .
Snubber Is Being Replaced During A2R15 Due To Marginal Test Results Observed During A2R14 (Reference IR Number 987527 and W/O 01299699).
                                                        .... .  .... * . . . ...   .. .... **      .*.  , .. *  :* * *:.,  .. .  .
F-A F01.10 2RY06104S 2RC26A-2" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.10 2RY06106S 2RC26A-2" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-34 Exek n-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Residual Heat Removal System (RH)Se XI". Ieer. '.Line .Number"Relief Technical Atual Results Ca.Item,~
C-H      C07.10 A02CV-000004-M04-01A                                                                                VT-2       RI Period ASME Section Xl Pressure Test.
DecipnRequestsi Notes Exn< , Comme~nts~
2CV8409 - Recordable Indication - Through Wall Leak - IR 1166795 2CV8485A - Info Only - Packing leak - IR 1166609 2FT-0917 - Info Only- Minor Boric Acid - IR 1166613 2CV8109 - Info Only - Packing leak - IR1166614 2CV06A - Info Only - Bolted Conn Leak - IR 1166621 2CV8355A - Onfo Only - Packing leak - IR 1167003 2CV054A - Info Only - Valve Stem Packing - IR 1167007 2SI030B - Info Only - Valve Stem Packing - IR 1167012 2CV8355B - Info Only - Packing - IR 1167015 2CV203 - Info Only - Valve Stem - IR 1167122 2CV092A - Info Only - Valve Stem - IR 1167126 2CV8355C - Info Only - Packing - IR 1167136 2PS5274 - Info Only - Packing - IR 1166462 2CV03F - Info Only - Target Deposit - IR 1199169 Info Only:
F-A F01.10 2RH02013S 2RHO1AB-12" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2RH02052S 2RH01AA-12" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-35 Exe ,m.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Reactor Coolant System (RY)sectionmXl..1.
IR 1167152  - Minor Boric Acid  on 2A Ltd HX Drain Line IR 1167154  - Minor Boric Acid  on 2B LTD HX Drain Line IR 1167159  - Minor Boric Acid  at 2CV228A IR 1167165  - Minor Boric Acid  at 2CV8107A IR 1167181  - Minor Boric Acid  at 2CV031 Packing IR 1167187  - Minor Boric Acid  at 2BRO03B Valve Stem C-H      C07.10 A02CV-000004-M04-01 B                                                              NOTE 24        VT-2      10 Period ASME Section Xl Pressure Test.
Identifier Pe LnNumber Relief *Technical. "Actual .Results Ca.Item De3scription.2 Requests INotes. Exam IComments NA NA 2RC93A001S 2RY34BB-.5" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 F-A F01.10 2RY05010S 2RY11A-14" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2RY06020S 2RY01B-6" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2RY06025S 2RY01B-6" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2RY06114S 2RY18A-2" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 NA NA 2RY06125S 2RY09AB-.75" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 F-A F01.10 2RY09001S 2RY02B-3" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.10 2RY09005S 2RY02B-3" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.10 2RY09100S 2RY02B-3" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.10 2RY09101S 2RY06A-3" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-36 Exek n.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Steam Generator Blowdown System (SD)Section Xl liSI jLine Number Relief ", Technical:
WO 1130656 completed 4-8-11.
A cual.c Results" C at. -item". -Descrption Reques Notes Exam NA NA 2SD06032S 2SDO1CE-2" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 NA NA 2SD11066S 2SD01CH-2" NOTE 01 VT-3 NRI Snubber FT MARG INITIAL SAMPLE DTPG 2-1. SN 2598 was replaced with SN 42820 due to high drag values in both the Tension and Compression directions.
WO 1134996-01 started 4-18-11 in A2R15, completed 5-9-11.
Reference Issue Report 1204436.NA NA 2SD12048S 2SD01CG-2" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-37 Exek n.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Safety Injection System (SI)Section Xl Ist Identifier
No recordable indications.
.LineNumber Rlf Technical. .Actual .Results Cat Item Desciption..,, ,.... ,. .Requests Notes Exam Comments ., F-A F01.10 2RH02018S
See also WO 1134996.
&#xfd;2S104D-8" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2RH02027S 2SI04C-8" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2RH02061S 2SI04D-8" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2RH02078S 2SIA4B-8" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2SI03018S 2SI05DD-6" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13. 10: Clamp is slightly skewed but well with the 10 degree conical tolerance.
C-H      C07.10 A02ZZ-000078-M04-03D                                                                NOTE 22        VT-2      10 Period ASME Section X1 Pressure Test. Class 2 normally isolated components to be pressurized during mode 5.
Acceptable per M-999 Sheet 10 Note 2A, and will not interfere with movement from cold to hot position and vice versa.F-A F01.20 2SI09002S 2SI09BC-10" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2SI10036S 2SI03FB-2" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-38 Exek-n.t Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Essential Service Water System (SX)Section X11 -1 ISI Identifier...:.  
A2R15 Mode 3 on 5-11-11:
..:e.6fnicat R Cat. Item-:: .iRequests Notes Exam Comments, F-A F01.20 2SX09038S 2SX07CB-10" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-3 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-39 Exek n.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM: Chemical & Volume Control System (CV)Section X1 ComponentID Line Number Reliet 17 Technical Exam&#xfd;.. Results Cat. Item~ Ilecription
2CVF5A - 3/4" - Info Only - Pipe Cap - IR 1214395 2CV066D - Info Only - Pipe Cap - IR 1214407 2CV066A - Info Only - Packing - Duplicate IRs 1214053 & IR 1214418 2CV077A - Info Only - Packing - Duplicate IRs 1214050 & IR 1214428 2CV220 - Info Only - Pipe Cap - Dipl IR 1214130 & IR 1214450 2FIS-0164 - Info Only - Packing - IR 1214461 2FT-0434 - Info Only - Fitting - IR 1214473 Page 3-45
;:&#xfd;~Rqests Not: Commients, NA NA 2CV02005S 2CV1 0CB-3" NOTE 01 FT PASS Snubber VT-3 NRI Existing mechanical snubber (Serial Number 12024) replaced with tested spare (Serial Number 8014) under WO# 1431482.Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-40 Exeb n.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM: Feedwater System (FW)Section Xl !Component ID Line Technical, Exa Results:ae tm Description I Requests Nts F-A F01.20 2FW05011BS 2FW03DD-16" NOTE 01 FT PASS Snubber VT-3 NRI Existing mechanical snubber (Serial Number 7036) replaced with tested spare (Serial Number 47260) under WO# 1299417.Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-41 Exe- n.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM: Reactor Coolant System (RC).Line Number. Relief: -.-, Technical, Exam Results: Cat. item .lDescription "Requests.
 
Notes.NA NA 2RC17069S 2RC20AB-.75" NOTE 01 FT PASS Snubber VT-3 NRI Existing mechanical snubber (Serial Number 2653) replaced with tested spare (Serial Number 42825) under WO# 1299699.Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-42 Exelkn-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM: Reactor Coolant System (RY)Section X. !..Line Number. .Tchn6ical Exam .Results Ct7 e Description
Exel, n.
..Requests Notes .F-A F01.10 2RY05010S 2RY11A-14" NOTE 01 VT-3 NRI Snubber Existing damaged snubber pivot pin with a new pin under WO# 1432228.Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-43 Exekn-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM: Steam Generator Blowdown System (SD)Section Component DO "Line Number " .Technicali
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Fuel Pool Cooling System (FC)
&#xfd;Eam " Results , cat'. Iteim Deescription: , Reuests,;, Ntes -Comments ,, .., NA NA 2SD11066S 2SD01CH-2" NOTE 01 FT PASS Snubber VT-3 NRI Existing mechanical snubber (Serial Number 2598) replaced with tested spare (Serial Number 42820) under WO# 1430989.Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-44 Exe0 n Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Chemical & Volume Control System (CV)Section Xl Component ID 4 .... ...Technica!.
Section.Xi    Component:.lD;                                  Reh.e    TechniaL  Requ red. Results item  inspeCti..Notes&#xfd;.                         .. .. R* 1uests Notes . Exam cornrents            -i 0-H    007.1 0 A02FC-000001-1004-01 C                                                    VT-2      NRI Period ASME Section X1 Pressure Test.
Reuird: .Results Cat.- tem hnspection NotesF "7 *.. .. ,. Requests Notes i< Exan : .". " C om me nts. j .... .. ..1. ...... ...... ...... .. ...., .. .. ..C-H C07.10 A02CV-000004-M04-01A VT-2 RI Period ASME Section Xl Pressure Test.2CV8409 -Recordable Indication
C-H    C07.10 A02FC-000001-M04-01D                                                      VT-2      NRI Period ASME Section Xl Pressure Test.
-Through Wall Leak -IR 1166795 2CV8485A -Info Only -Packing leak -IR 1166609 2FT-0917 -Info Only- Minor Boric Acid -IR 1166613 2CV8109 -Info Only -Packing leak -IR1166614 2CV06A -Info Only -Bolted Conn Leak -IR 1166621 2CV8355A -Onfo Only -Packing leak -IR 1167003 2CV054A -Info Only -Valve Stem Packing -IR 1167007 2SI030B -Info Only -Valve Stem Packing -IR 1167012 2CV8355B -Info Only -Packing -IR 1167015 2CV203 -Info Only -Valve Stem -IR 1167122 2CV092A -Info Only -Valve Stem -IR 1167126 2CV8355C -Info Only -Packing -IR 1167136 2PS5274 -Info Only -Packing -IR 1166462 2CV03F -Info Only -Target Deposit -IR 1199169 Info Only: IR 1167152 -Minor Boric Acid on 2A Ltd HX Drain Line IR 1167154 -Minor Boric Acid on 2B LTD HX Drain Line IR 1167159 -Minor Boric Acid at 2CV228A IR 1167165 -Minor Boric Acid at 2CV8107A IR 1167181 -Minor Boric Acid at 2CV031 Packing IR 1167187 -Minor Boric Acid at 2BRO03B Valve Stem C-H C07.10 A02CV-000004-M04-01 B NOTE 24 VT-2 10 Period ASME Section Xl Pressure Test.WO 1130656 completed 4-8-11.WO 1134996-01 started 4-18-11 in A2R15, completed 5-9-11.No recordable indications.
Page 3-46
See also WO 1134996.C-H C07.10 A02ZZ-000078-M04-03D NOTE 22 VT-2 10 Period ASME Section X1 Pressure Test. Class 2 normally isolated components to be pressurized during mode 5.A2R15 Mode 3 on 5-11-11: 2CVF5A -3/4" -Info Only -Pipe Cap -IR 1214395 2CV066D -Info Only -Pipe Cap -IR 1214407 2CV066A -Info Only -Packing -Duplicate IRs 1214053 & IR 1214418 2CV077A -Info Only -Packing -Duplicate IRs 1214050 & IR 1214428 2CV220 -Info Only -Pipe Cap -Dipl IR 1214130 & IR 1214450 2FIS-0164
 
-Info Only -Packing -IR 1214461 2FT-0434 -Info Only -Fitting -IR 1214473 Page 3-45 Exel, n.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Fuel Pool Cooling System (FC)Section.Xi Component:.lD; Reh.e TechniaL Requ red. Results.. ..item inspeCti..Notes&#xfd;. 1uests Notes .Exam cornrents -i 0-H 007.1 0 A02FC-000001-1004-01 C VT-2 NRI Period ASME Section X1 Pressure Test.C-H C07.10 A02FC-000001-M04-01D VT-2 NRI Period ASME Section Xl Pressure Test.Page 3-46 Exek n.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Instrument Air System (IA)' .ectlla.nX
Exek n.
.... X.. m n. ' ID R"l ....Technicalli
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Instrument Air System (IA)
...ed- esu .,s .,Cat- Item Reuests 8N : 't C........
X..      m      n. ID                  '  .ectlla.nX
m m....... ... C-H C07.10 A021A-000004-M04-01A VT-2 NRI Period ASME Section XI Pressure Test. Verify Continuous Leak Detection System for Airlock is in operation prior to performing SNOOP or Ultraprobe examination of test boundary.Periodic Test using BwVS TRM 3.4.f.2-PC.
                                                            ....                   ' R"l    Technicalli ..  . ed- .. esu  .,s.
No leakage observed.Page 3-47 Exeu n.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Residual Heat Removal System (RH)Section Xl Component ID seuies ' Tcnca ... ..Cat. Item inspection Notes Requests Notes Exam Comments : C-H C07.10 A02RH-000003-M04-01A NOTE 22 VT-2 10 Period ASME Section Xl Pressure Test. VERIFY loop "A" in service.Pressurize 2A sample line per BwCP 613-3.The following were noted for Information:
,Cat- Item                                                                          Reuests    8N :    't m.......
Dry boron at packing on 2SI059A (IR 1212972);
m C........                                    ...                                                            *      *1ments C-H    C07.10 A021A-000004-M04-01A                                                                          VT-2      NRI Period ASME Section XI Pressure Test. Verify Continuous Leak Detection System for Airlock is in operation prior to performing SNOOP or Ultraprobe examination of test boundary.
dry boron on packing at 2RHO20A (IR 1212506);
Periodic Test using BwVS TRM 3.4.f.2-PC. No leakage observed.
dry boron on packing 2RHO21A (IR 1212508)C-H C07.10 A02RH-000003-M04-01B NOTE 22 VT-2 10 Period ASME Section Xl Pressure Test. VERIFY loop "B" in NRI service.Pressurize 2B sample line per BwCP 613-3.NRI RI Recordable indication of dry boric (Bolts #12, 13, 31, 36, 39, and 41) acid and weepage (Bolt #9) on 2B RHR heat exchanger (IR 1213307).The following were noted for Information:
Page 3-47
Dry boron at packing 2RHO03B (IR 1213315);
 
dry boron at packing 2RHO04B (1213313);
Exeu n.
dry boron at packing 2RH028B (IR 1207085)C-H C07.10 A02RH-000003-M04-01D NOTE 22 VT-2 10 Period ASME Section Xl Pressure Test.Noted for Information:
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Residual Heat Removal System (RH)
Dry boron at packing 2RH8701A (IR 1196781)C-H C07.10 A02RH-000003-M04-01E NOTE 22 VT-2 10 Period ASME Section XA Pressure Test.The following were noted for Information:
Section Xl    Component ID                                                                    '    Tcnca
Dry boron at packing 2RH8702A (IR 1196782);
                                                                                                        ...   ..               seuies Cat. Item     inspection Notes                                                      Requests     Notes      Exam Comments                                            :
Leakage past pipe cap threads downstream of 2SI094 (IR 1203992)Page 3-48 Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Safety Injection System (SI)Section X dComponent IDi Relief Technical:% -Requid ..at. emn. Inspection Notes. Requests Notes Exam Comments ~ ~ >C-H C07.10 A02SI-000010-M04-01G NOTE 22 VT-2 NRI Period ASME Section X1 Pressure Test.C-H C07.10 A02ZZ-000010-M04-01J NOTE 22 VT-2 10 Period ASME Section Xl Pressure Test.C-H C07.10 A02ZZ-000010-M04-01K NOTE 22 VT-2 NRI Period ASME Section Xl Pressure Test.C-H C07.10 A02ZZ-000010-M04-01L NOTE 22 VT-2 10 Period ASME Section Xl Pressure Test.C-H C07.10 A02ZZ-000010-M04-01M NOTE 22 VT-2 NRI Period ASME Section XI Pressure Test.Page 3-49 Exelon-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Essential Service Water System (SX)Section XI Component ID
C-H      C07.10 A02RH-000003-M04-01A                                                                  NOTE 22        VT-2          10 Period ASME Section Xl Pressure Test. VERIFY loop "A"in service.
.: Relief Technical; Required-;:.
Pressurize 2A sample line per BwCP 613-3.
Results9 .tem Irnspection Notes: ,, ":Requests-Notes IExam , *C-H C07.10 A02SX-000011-M04-01E VT-2 10 Period ASME Section XI Pressure Test. NRI Information only (4/18/2011 exam): Slight corrosion on piping wall due to sweat, no degradation noted.NRI: 2D RCFC 4/26/2011; 2B RCFC 4/27/2011 C-H C07.10 A02SX-000011-M04-01F VT-2 10 Period ASME Section Xl Pressure Test. NRI Information only (4/18/2011 exam): Slight corrosion on piping wall due to sweat, no degradation noted.NRI: 2C RCFC (right bank) 4/19/2011; 2C RCFC (left bank) 4/24/2011; 2A RCFC 4/22/2011 Page 3-50 Exek n.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Plant Systems Pressurized During Mode 3 (ZZ)Section XI tComponent ID.. Relief "Technica!l Requir Results Item inspection Notes; ,, Requests, .Exam B-P B15.10 A02ZZ-000005-M04-01A NOTE 22 VT-2 RI Each Refueling Outage Generic Letter 88-05 Examinations Class 1: NOTE 23 PMID 55141-01.
The following were noted for Information:
Class 2 and 3: PMID96032-17.
Dry boron at packing on 2SI059A (IR 1212972); dry boron on packing at 2RHO20A (IR 1212506); dry boron on packing 2RHO21A (IR 1212508)
2SI08JB: Recordable Indication
C-H      C07.10 A02RH-000003-M04-01B                                                                  NOTE 22        VT-2          10 Period ASME Section Xl Pressure Test. VERIFY loop "B" in                                                        NRI service.
-Dry boric acid found at flange (IR1214416).
Pressurize 2B sample line per BwCP 613-3.
2RC8037A:
NRI RI Recordable indication of dry boric (Bolts #12, 13, 31, 36, 39, and 41) acid and weepage (Bolt #9) on 2B RHR heat exchanger (IR 1213307).
Recordable Indication
The following were noted for Information:
-Inactive Body-Bonnet leak (IR 1214436).C-H C07.10 A02ZZ-000078-M04-03A Period ASME Section XI Pressure Test. All Class 2 components inside containment.
Dry boron at packing 2RHO03B (IR 1213315); dry boron at packing 2RHO04B (1213313); dry boron at packing 2RH028B (IR 1207085)
VT-2 visual inspection of components outside Missile Barrier may be performed during Mode 1/3 if conditions permit. Valve in EX and LTD HX'ers when perform.The following indications were noted for Information:
C-H      C07.10 A02RH-000003-M04-01D                                                                  NOTE 22        VT-2          10 Period ASME Section Xl Pressure Test.
NOTE 22 VT-2 10 2CV203 pipe cap (IR 1214395);
Noted for Information:
2CV066A pipe cap (IR 1214418);
Dry boron at packing 2RH8701A (IR 1196781)
2CV067A pipe cap (IR 1214428);
C-H      C07.10 A02RH-000003-M04-01E                                                                  NOTE 22        VT-2         10 Period ASME Section XAPressure Test.
2CV066D pipe cap (IR 1214407);2CV220 pipe cap (IR 1214450);
The following were noted for Information:
2FIS-0164 (IR 1214461);
Dry boron at packing 2RH8702A (IR 1196782); Leakage past pipe cap threads downstream of 2SI094 (IR 1203992)
2FT-0434 (IR 1214473);
Page 3-48
2FT-0424 (IR 1214484);C-H C07.10 A02ZZ-000078-M04-03B NOTE 22 VT-2 NRI Period ASME Section XI Pressure Test. Class 2 components inside / outside containment which are normally pressurized during modes 1-3.First period walkdown performed during plant start-up from A2R15, no evidence of leakage noted.Page 3-51 Exelkn Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.6 Detailed Borated Bolted Connection Table SYSTEM: Chemical & Volume Control System (CV)Sectio'-n X lComponentD
 
:, .7 Relief>, Technical.;
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Safety Injection System (SI)
Actual Results jbat tem Dscrfptjon' i .equests, JNotes T ~a C"-iments.
Section X dComponent IDi                                    Relief  Technical:%    *    -Requid Relts*"
B-P B15.10 2CV-03-B1 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)B-P B15.10 PG-2546C-214 F-2-2 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)C-H C07.10 PG-2546C-220 F-1 (C-H) VT-2 NRI FLANGED CONNECTION (4 STUDS)C-H C07.10 PG-2546C-241 F-1-1 (C-H) VT-2 NRI FLANGED CONNECTION (4 STUDS)EXAMINE DUE TO EVIDENCE OF LEAKAGE IDENTIFIED DURING A2R14.B-P B15.10 PG-2546C-271 F-2-3 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)C-H C07.10 PG-2546C-289 F-1 (C-H) VT-2 NRI FLANGED CONNECTION (8 STUDS)RE-EXAMINE DUE TO IDENTIFICATION OF LEAKAGE DURING A2R14 C-H C07.10 PG-2546C-290 F-1 (C-H) VT-2 NRI FLANGED CONNECTION (8 STUDS)B-P B15.10 PG-2546C-301 F-2-2 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)Page 3-52 Exelenn.Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.6 Detailed Borated Bolted Connection Table SYSTEM: Reactor Coolant System (RC)Seiction Xl !oponent ID',. Relief.. Techncl cta Resu~u Ca. te<Description Requests~
at... emn.Inspection Notes.                                 Requests Notes       Exam Comments     ~ ~      >
Notes~Ea Comments <>~B-P B15.10 2PZR-01-B1 (B-P) VT-2 NRI MANWAY BOLTING (16 TOTAL)B-P B15.10 2RC-20-B1 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)B-P B15.10 2RC-32-B4 (B-P) VT-2 NRI FLANGED CONNECTION (12 STUDS)B-P B15.10 2RC-32-B5 (B-P) VT-2 NRI FLANGED CONNECTION (12 STUDS)B-P B15.10 2RC-32-B6 (B-P) VT-2 NRI FLANGED CONNECTION (12 STUDS)B-P B15.10 2RV-03-STUDS (01 TO 54, B-P) VT-2 NRI CLOSURE HEAD STUDS (54 TOTAL)Note: Stud Number 37 Cut Off.B-P B15.10 2SG-01-B1 (B-P) VT-2 NRI 9A PRIMARY MANWAY (16 BOLTS)B-P B15.10 2SG-01-B2 (B-P) VT-2 NRI 9B PRIMARY MANWAY (16 BOLTS)B-P B15.10 2SG-02-B1 (B-P) VT-2 NRI 9A PRIMARY MANWAY (16 BOLTS)B-P B15.10 2SG-02-B2 (B-P) VT-2 NRI 9B PRIMARY MANWAY (16 BOLTS)B-P B15.10 2SG-03-B1 (B-P) VT-2 NRI 9A PRIMARY MANWAY (16 BOLTS)B-P B15.10 2SG-03-B2 (B-P) VT-2 NRI 9B PRIMARY MANWAY (16 BOLTS)B-P B15.10 2SG-04-B1 (B-P) VT-2 NRI 9A PRIMARY MANWAY (16 BOLTS)B-P B15.10 2SG-04-B2 (B-P) VT-2 NRI 9B PRIMARY MANWAY (16 BOLTS)Page 3-53 ExeJun.-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.6 Detailed Borated Bolted Connection Table SYSTEM: Residual Heat Removal System (RH)Section;Xl.
C-H    C07.10 A02SI-000010-M04-01G                                      NOTE 22        VT-2    NRI Period ASME Section X1 Pressure Test.
Component:.:Dlii f :
C-H    C07.10 A02ZZ-000010-M04-01J                                      NOTE 22        VT-2     10 Period ASME Section Xl Pressure Test.
ca~~ Description,~
C-H    C07.10 A02ZZ-000010-M04-01K                                      NOTE 22        VT-2    NRI Period ASME Section Xl Pressure Test.
Requests Notes lxa Comments>
C-H    C07.10 A02ZZ-000010-M04-01L                                      NOTE 22        VT-2     10 Period ASME Section Xl Pressure Test.
.C-H C07.10 2RH-12 F-3-1 (C-H) VT-2 NRI FLANGED CONNECTION (12 STUDS)EXAMINE DUE TO RI IDENTIFIED DURING THE PREVIOUS EXAM.Page 3-54 Exea! n Braidwood Station Unit 2 A2R15 ISI Outage Report 4.0 REPORT OF CONTAINMENT DEGRADATION Containment inspections are performed in accordance with Subsection IWE (Requirements for Class MC and Metallic Liners of Class CC Components of Light-Water Cooled Power Plants) and Subsection IWL (Requirements for Class CC Components of Light-Water Cooled Power Plants) of ASME Section Xl, Division 1, with specified modifications and limitations in 10 CFR 50.55a. The following sections are included in the Inservice Inspection Summary report as required by IWA-6000 of ASME Section Xl to meet the reporting conditions specified in 10CFR 50.55a(b)(2)(ix)(A)(1) through (3).The following discusses examinations performed in accordance with ASME Section XI, Subsections IWE and IWL respectively.
C-H    C07.10 A02ZZ-000010-M04-01M                                      NOTE 22        VT-2    NRI Period ASME Section XI Pressure Test.
4.1 A2R15 Containment Metal Liner Examinations (IWE)The Third Interval First Period Class MC General Visual Examinations were completed during A2R15. All indications identified during the General Visual Examinations were reviewed and accepted as is by the Responsible Individual as defined in ASME Section XI.The completed surveillances for IWE contain all the examination details along with indications recorded and their associated evaluations required by ASME Section XI.The following discusses augmented exams performed under the containment moisture barrier.Augmented Section XI IWE examinations of the Class CC liner examinations for the Third Interval were performed in accordance with the requirements of ASME Section XI, Table IWE-2500-1, Category E-C, Containment Surfaces Requiring Augmented Examination.
Page 3-49
Exelon Procedures ER-AA-330-007, "Visual Examination of ASME Section X1 Class MC Surfaces and Class CC Liners", ER-AA-335-018, "Detailed, General Visual, VT-1, VT-1 C, VT-3 and VT-3C, Visual Examination of ASME Class MC and CC Containment Surfaces and Components", and ER-AA-335-004 "Ultrasonic Measurement Of Material Thickness and Interfering Conditions" were used to perform the examinations.
 
Six sections of the containment moisture barrier were removed for the purpose of performing augmented examinations of the containment liner surface. These examinations were required due to identification of degradation during past examinations.
Exelon-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Essential Service Water System (SX)
The results of the examinations revealed no evidence of degradation that had not been identified during past examinations.
Section XI     Component ID                                        .         :      F!W:WU.Re**:
The conditions remained unchanged with no evidence of additional degradation.
Relief      Technical; Required-;:. Results9
A description of the type and estimated extent of degradation, and the conditions that led to the degradation
* cat*. tem    Irnspection Notes:          ,,                    ":Requests-                   Notes     IExam        ,
[10CFR 50.55a(b)(2)(ix)(A)(1)]:
* C-H    C07.10 A02SX-000011-M04-01E                                                                                VT-2         10 Period ASME Section XI Pressure Test.                                                                        NRI Information only (4/18/2011 exam): Slight corrosion on piping wall due to sweat, no degradation noted.
The results of the examinations revealed no evidence of degradation that had not been identified and evaluated as acceptable by the Responsible Individual during past Page 4-1 ExeI ~n Braidwood Station Unit 2 A2R15 ISI Outage Report examinations.
NRI: 2D RCFC 4/26/2011; 2B RCFC 4/27/2011 C-H    C07.10 A02SX-000011-M04-01F                                                                                VT-2        10 Period ASME Section Xl Pressure Test.                                                                        NRI Information only (4/18/2011 exam): Slight corrosion on piping wall due to sweat, no degradation noted.
The conditions remained unchanged.
NRI: 2C RCFC (right bank) 4/19/2011; 2C RCFC (left bank) 4/24/2011; 2A RCFC 4/22/2011 Page 3-50
The previous evaluation was documented under Engineering Change 377614.Extent of condition:
 
No extent of condition augmented examinations were required during A2R1 5.Description of the conditions that led to the degradation:
Exek n.
As originally identified during the A2R08 examinations, the identified liner degradation was a result of moisture barrier aging and mechanical damage of the moisture barrier that occurred during maintenance activities.
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Plant Systems Pressurized During Mode 3 (ZZ)
The damage of the moisture barrier resulted in a leakage path for water impingement on the liner. The primary source of the water is condensation from the containment fan cooling units. The entire moisture barrier was removed, examinations performed, areas coated and the moisture barrier was replaced during A2R08.Evaluation of each area, and the result of the evaluation
Section XI    tComponent ID..                                                       Relief  "Technica!l  Requir  Results Item  inspection Notes;          ,,                                  .Exam Requests, lNotes*
B-P        B15.10 A02ZZ-000005-M04-01A                                                              NOTE 22        VT-2       RI Each Refueling Outage Generic Letter 88-05 Examinations Class 1:                NOTE 23 PMID 55141-01. Class 2 and 3: PMID96032-17.
2SI08JB: Recordable Indication - Dry boric acid found at flange (IR1214416).
2RC8037A: Recordable Indication - Inactive Body-Bonnet leak (IR 1214436).
C-H        C07.10 A02ZZ-000078-M04-03A                                                              NOTE 22        VT-2      10 Period ASME Section XI Pressure Test. All Class 2 components inside containment. VT-2 visual inspection of components outside Missile Barrier may be performed during Mode 1/3 if conditions permit. Valve in EX and LTD HX'ers when perform.
The following indications were noted for Information:
2CV203 pipe cap (IR 1214395); 2CV066A pipe cap (IR 1214418); 2CV067A pipe cap (IR 1214428); 2CV066D pipe cap (IR 1214407);
2CV220 pipe cap (IR 1214450); 2FIS-0164 (IR 1214461); 2FT-0434 (IR 1214473); 2FT-0424 (IR 1214484);
C-H        C07.10 A02ZZ-000078-M04-03B                                                              NOTE 22        VT-2     NRI Period ASME Section XI Pressure Test. Class 2 components inside / outside containment which are normally pressurized during modes 1-3.
First period walkdown performed during plant start-up from A2R15, no evidence of leakage noted.
Page 3-51
 
Exelkn Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.6 Detailed Borated Bolted Connection Table SYSTEM: Chemical & Volume Control System (CV)
Sectio'-n X  lComponentD        :,                      .7 Relief>, Technical.; Actual  Results tem  Dscrfptjon' jbat                      .                    i equests, JNotes  T  ~a C"-iments.
B-P    B15.10 2CV-03-B1 (B-P)                                                      VT-2     NRI FLANGED CONNECTION (4 STUDS)
B-P    B15.10  PG-2546C-214 F-2-2 (B-P)                                           VT-2    NRI FLANGED CONNECTION (4 STUDS)
C-H    C07.10  PG-2546C-220 F-1 (C-H)                                              VT-2     NRI FLANGED CONNECTION (4 STUDS)
C-H    C07.10  PG-2546C-241 F-1-1 (C-H)                                           VT-2    NRI FLANGED CONNECTION (4 STUDS)
EXAMINE DUE TO EVIDENCE OF LEAKAGE IDENTIFIED DURING A2R14.
B-P    B15.10  PG-2546C-271 F-2-3 (B-P)                                            VT-2    NRI FLANGED CONNECTION (4 STUDS)
C-H    C07.10  PG-2546C-289 F-1 (C-H)                                              VT-2    NRI FLANGED CONNECTION (8 STUDS)
RE-EXAMINE DUE TO IDENTIFICATION OF LEAKAGE DURING A2R14 C-H    C07.10  PG-2546C-290 F-1 (C-H)                                              VT-2    NRI FLANGED CONNECTION (8 STUDS)
B-P    B15.10  PG-2546C-301 F-2-2 (B-P)                                            VT-2    NRI FLANGED CONNECTION (4 STUDS)
Page 3-52
 
Exelenn.
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.6 Detailed Borated Bolted Connection Table SYSTEM: Reactor Coolant System (RC)
Seiction Xl !oponent ID',.                              Relief.. Techncl  cta    Resu~u Ca. te<Description                                  Requests~ Notes~Ea Comments <>~
B-P    B15.10 2PZR-01-B1 (B-P)                                              VT-2      NRI MANWAY BOLTING (16 TOTAL)
B-P    B15.10 2RC-20-B1 (B-P)                                              VT-2      NRI FLANGED CONNECTION (4 STUDS)
B-P    B15.10  2RC-32-B4 (B-P)                                              VT-2      NRI FLANGED CONNECTION (12 STUDS)
B-P    B15.10  2RC-32-B5 (B-P)                                              VT-2      NRI FLANGED CONNECTION (12 STUDS)
B-P    B15.10  2RC-32-B6 (B-P)                                              VT-2      NRI FLANGED CONNECTION (12 STUDS)
B-P    B15.10  2RV-03-STUDS (01 TO 54, B-P)                                VT-2      NRI CLOSURE HEAD STUDS (54 TOTAL)
Note: Stud Number 37 Cut Off.
B-P    B15.10 2SG-01-B1 (B-P)                                              VT-2     NRI 9A PRIMARY MANWAY (16 BOLTS)
B-P    B15.10  2SG-01-B2 (B-P)                                              VT-2      NRI 9B PRIMARY MANWAY (16 BOLTS)
B-P    B15.10 2SG-02-B1 (B-P)                                              VT-2     NRI 9A PRIMARY MANWAY (16 BOLTS)
B-P    B15.10 2SG-02-B2 (B-P)                                              VT-2      NRI 9B PRIMARY MANWAY (16 BOLTS)
B-P    B15.10  2SG-03-B1 (B-P)                                              VT-2      NRI 9A PRIMARY MANWAY (16 BOLTS)
B-P    B15.10  2SG-03-B2 (B-P)                                              VT-2      NRI 9B PRIMARY MANWAY (16 BOLTS)
B-P    B15.10  2SG-04-B1 (B-P)                                              VT-2      NRI 9A PRIMARY MANWAY (16 BOLTS)
B-P    B15.10  2SG-04-B2 (B-P)                                              VT-2      NRI 9B PRIMARY MANWAY (16 BOLTS)
Page 3-53
 
ExeJun.-
Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.6 Detailed Borated Bolted Connection Table SYSTEM: Residual Heat Removal System (RH)
Section;Xl. Component:.:Dlii      :.eI*ef*.K.Reisul:s                        f ca~~ Description,~                                        Requests Notes   lxa Comments> .
C-H   C07.10 2RH-12 F-3-1 (C-H)                                                  VT-2     NRI FLANGED CONNECTION (12 STUDS)
EXAMINE DUE TO RI IDENTIFIED DURING THE PREVIOUS EXAM.
Page 3-54
 
Exea!n Braidwood Station Unit 2 A2R15 ISI Outage Report 4.0 REPORT OF CONTAINMENT DEGRADATION Containment inspections are performed in accordance with Subsection IWE (Requirements for Class MC and Metallic Liners of Class CC Components of Light-Water Cooled Power Plants) and Subsection IWL (Requirements for Class CC Components of Light-Water Cooled Power Plants) of ASME Section Xl, Division 1, with specified modifications and limitations in 10 CFR 50.55a. The following sections are included in the Inservice Inspection Summary report as required by IWA-6000 of ASME Section Xl to meet the reporting conditions specified in 10CFR 50.55a(b)(2)(ix)(A)(1) through (3).
The following discusses examinations performed in accordance with ASME Section XI, Subsections IWE and IWL respectively.
4.1 A2R15 Containment Metal Liner Examinations (IWE)
The Third Interval First Period Class MC General Visual Examinations were completed during A2R15. All indications identified during the General Visual Examinations were reviewed and accepted as is by the Responsible Individual as defined in ASME Section XI.
The completed surveillances for IWE contain all the examination details along with indications recorded and their associated evaluations required by ASME Section XI.
The following discusses augmented exams performed under the containment moisture barrier.
Augmented Section XI IWE examinations of the Class CC liner examinations for the Third Interval were performed in accordance with the requirements of ASME Section XI, Table IWE-2500-1, Category E-C, Containment Surfaces Requiring Augmented Examination.
Exelon Procedures ER-AA-330-007, "Visual Examination of ASME Section X1 Class MC Surfaces and Class CC Liners", ER-AA-335-018, "Detailed,General Visual, VT-1, VT-1C, VT-3 and VT-3C, Visual Examination of ASME Class MC and CC Containment Surfaces and Components", and ER-AA-335-004 "UltrasonicMeasurement Of Material Thickness and Interfering Conditions"were used to perform the examinations.
Six sections of the containment moisture barrier were removed for the purpose of performing augmented examinations of the containment liner surface. These examinations were required due to identification of degradation during past examinations. The results of the examinations revealed no evidence of degradation that had not been identified during past examinations. The conditions remained unchanged with no evidence of additional degradation.
A description of the type and estimated extent of degradation, and the conditions that led to the degradation [10CFR 50.55a(b)(2)(ix)(A)(1)]:
The results of the examinations revealed no evidence of degradation that had not been identified and evaluated as acceptable by the Responsible Individual during past Page 4-1
 
ExeI ~n Braidwood Station Unit 2 A2R15 ISI Outage Report examinations. The conditions remained unchanged. The previous evaluation was documented under Engineering Change 377614.
Extent of condition:
No extent of condition augmented examinations were required during A2R1 5.
Description of the conditions that led to the degradation:
As originally identified during the A2R08 examinations, the identified liner degradation was a result of moisture barrier aging and mechanical damage of the moisture barrier that occurred during maintenance activities. The damage of the moisture barrier resulted in a leakage path for water impingement on the liner. The primary source of the water is condensation from the containment fan cooling units. The entire moisture barrier was removed, examinations performed, areas coated and the moisture barrier was replaced during A2R08.
Evaluation of each area, and the result of the evaluation
[1 OCFR 50.55a(b)(2)(ix)(A)(2)]:
[1 OCFR 50.55a(b)(2)(ix)(A)(2)]:
The results of the A2R15 examinations revealed no evidence of degradation that had not been identified and evaluated as acceptable by the Responsible Individual during past examinations.
The results of the A2R15 examinations revealed no evidence of degradation that had not been identified and evaluated as acceptable by the Responsible Individual during past examinations. The conditions remained unchanged. The previous evaluation was documented under Engineering Change 377614.
The conditions remained unchanged.
Description of Necessary Corrective Actions Completed
The previous evaluation was documented under Engineering Change 377614.Description of Necessary Corrective Actions Completed[1 OCFR 50.55a(b)(2)(ix)(A)(3)]:
[1 OCFR 50.55a(b)(2)(ix)(A)(3)]:
Proposed Actions for A2R1 6: Additional VT-1 (Detailed Visual) and ultrasonic thickness examinations are scheduled in A2R1 6 refueling outage to examine the condition of the liner plate below the moisture barrier at the three locations.
Proposed Actions for A2R1 6:
These three locations were examined during A2R15 with no evidence of changes from conditions identified during the previous augmented examinations.
Additional VT-1 (Detailed Visual) and ultrasonic thickness examinations are scheduled in A2R1 6 refueling outage to examine the condition of the liner plate below the moisture barrier at the three locations. These three locations were examined during A2R15 with no evidence of changes from conditions identified during the previous augmented examinations. They are being scheduled for successive exams during A2R16.
They are being scheduled for successive exams during A2R16.Conclusions/Findings Based on the conclusions of the previous evaluation (Engineering Change Number 377614) and the fact that no additional degradation was identified during the A2R1 5 augmented examinations, the liner plate containing the degraded conditions below the moisture barrier (MB) in Unit 2 containment is acceptable and capable of performing its intended design function.4.2 A2R15 Class CC (IWL) Containment Examinations The Units 1 and 2 2 5 th Year ASME Section Xl WL Post Tensioning and Concrete examinations and tests began in June of 2011. The Post Tensioning surveillance is scheduled to be completed in September 2011 while the containment concrete examinations are scheduled to be completed in December 2011. Final reporting in Page 4-2 Exelon.Braidwood Station Unit 2 A2R15 ISI Outage Report accordance with ASME Section Xl IWL-3310 and 10CFR50.55a will be included in the IWA-6000 ISI Summary Report for Refuel Outage Al R1 6 which is currently scheduled for April 2012.At the time of preparation of this report, the presence of free water, IWL-3221.3 (a) is the only identified reportable condition.
Conclusions/Findings Based on the conclusions of the previous evaluation (Engineering Change Number 377614) and the fact that no additional degradation was identified during the A2R1 5 augmented examinations, the liner plate containing the degraded conditions below the moisture barrier (MB) in Unit 2 containment is acceptable and capable of performing its intended design function.
Chemical analysis for the sheathing filler and free water are in progress.
4.2 A2R15 Class CC (IWL) Containment Examinations The Units 1 and 2 2 5th Year ASME Section Xl WL Post Tensioning and Concrete examinations and tests began in June of 2011. The Post Tensioning surveillance is scheduled to be completed in September 2011 while the containment concrete examinations are scheduled to be completed in December 2011. Final reporting in Page 4-2
However, results are pending. Table 4.2-1 describes the presence of free water identified for the specific tendons for available results. With the exception of the dome tendons, all locations are below grade level.Table 4.2-1 Tendon Inspection Results (As of 7/25/2011)
 
Containment Free Water Visual Unit Reason For Examination Tendon Tendon Tendon Collected Examination Selection Identifier Type End (Ounces) Results 1 Augmented Free Water H-01 -AC Hoop Field 3 Note 1 1 Augmented Free Water H-02-AC Hoop Field 1 Note 1 1 Augmented Free Water H-02-BA Hoop Shop 6 Note 1 1 Augmented Free Water -H-02-BA Hoop Field 7 Note 1 1 25 t Year ISI V-1 42 Vertical Field 11 Note 1 2 Augmented Free Water H-01 -ED Hoop Field 7 Note 1 2 Augmented Free Water H-01 -ED Hoop Shop < 1 Note 1 2 Augmented Free Water H-01 -FE Hoop Shop 5 Note 1 2 Augmented Free Water H-02-ED Hoop Field < 2 Note 1 2 Augmented Free Water H-04-DF Hoop Field 60 Note 1 2 Augmented Free Water H-04-ED Hoop Field 50 Note 1 2 Augmented Free Water H-04-ED Hoop Shop 2 Note 1 2 Augmented Free Water H-05-ED Hoop Shop 6 Note 1 2 Augmented Free Water H-05-FE Hoop Field 55 Note 1 2 Augmented Free Water H-05-FE Hoop Shop < 1 Note 1 2 Augmented Free Water H-06-FE Hoop Field 26 Note 1 2 Augmented Free Water V-217 Vertical Field 2 Note 2 2 Augmented Free Water V-241 Vertical Field 1 Note 2 2 Augmented Free Water V-249 Vertical Field 84 Note 2 2 25In Year ISI D-04-36 Dome Field 54 Note 2 2 Augmented Free Water D-04-38 Dome Shop 2 Note 1 2 Augmented Free Water D-04-38 Dome Field 512 Note 2 2 Augmented Free Water D-04-27 Dome Shop 4 Note 2 2 Augmented Free Water D-04-27 Dome Field < 1 Note 2 2 Augmented Free Water D-06-13 Dome Shop 12 Note 1 2 Grease Leak Repair D-04-39 Dome Shop 14 Note 2 Note 1: No evidence of degradation or active corrosion was identified on either the anchorage components or the surrounding concrete.
Exelon.
Sheathing filler was not discolored (indicative of moisture saturation) in the as found condition.
Braidwood Station Unit 2 A2R15 ISI Outage Report accordance with ASME Section Xl IWL-3310 and 10CFR50.55a will be included in the IWA-6000 ISI Summary Report for Refuel Outage Al R1 6 which is currently scheduled for April 2012.
Note 2: No evidence of degradation or active corrosion was identified on either the anchorage components or the surrounding concrete.
At the time of preparation of this report, the presence of free water, IWL-3221.3 (a) is the only identified reportable condition. Chemical analysis for the sheathing filler and free water are in progress. However, results are pending. Table 4.2-1 describes the presence of free water identified for the specific tendons for available results. With the exception of the dome tendons, all locations are below grade level.
However, the sheathing filler was discolored (light, cream colored which is indicative of saturation) in the as found condition.
Table 4.2-1 Containment Tendon     Inspection   Results (As of 7/25/2011)
Page 4-3 Exeln..Braidwood Station Unit 2 A2R15 ISI Outage Report Conclusions/Findings Based on the as found conditions where no degradation or active corrosion was identified on the anchorage components or surrounding concrete, there is no indication the presence of free water has resulted in any degradation of the specific tendons, post tensioning systems, or the containment structures.
Free Water     Visual Unit Reason For Examination         Tendon     Tendon       Tendon     Collected   Examination Selection           Identifier   Type       End       (Ounces)       Results 1     Augmented Free Water       H-01 -AC     Hoop       Field           3         Note 1 1     Augmented Free Water       H-02-AC       Hoop       Field           1         Note 1 1     Augmented Free Water         H-02-BA     Hoop       Shop           6         Note 1 1     Augmented Free Water       -H-02-BA       Hoop       Field           7         Note 1 1             25t Year ISI           V-1 42     Vertical     Field         11         Note 1 2     Augmented Free Water       H-01 -ED     Hoop       Field           7         Note 1 2     Augmented Free Water       H-01 -ED     Hoop       Shop         <1           Note 1 2     Augmented Free Water         H-01 -FE     Hoop       Shop           5         Note 1 2     Augmented Free Water       H-02-ED       Hoop       Field         <2           Note 1 2     Augmented Free Water         H-04-DF     Hoop       Field         60         Note 1 2     Augmented Free Water       H-04-ED       Hoop       Field         50         Note 1 2     Augmented Free Water       H-04-ED       Hoop       Shop           2         Note 1 2     Augmented Free Water       H-05-ED       Hoop       Shop           6         Note 1 2     Augmented Free Water         H-05-FE     Hoop       Field         55         Note 1 2     Augmented Free Water         H-05-FE     Hoop       Shop         < 1         Note 1 2     Augmented Free Water         H-06-FE     Hoop       Field         26         Note 1 2     Augmented Free Water         V-217     Vertical     Field           2         Note 2 2     Augmented Free Water         V-241     Vertical     Field           1         Note 2 2     Augmented Free Water         V-249     Vertical     Field         84         Note 2 2             25In Year ISI         D-04-36     Dome       Field         54         Note 2 2     Augmented Free Water         D-04-38     Dome       Shop           2         Note 1 2     Augmented Free Water         D-04-38     Dome       Field         512         Note 2 2     Augmented Free Water         D-04-27     Dome       Shop           4         Note 2 2     Augmented Free Water         D-04-27     Dome       Field         < 1         Note 2 2     Augmented Free Water         D-06-13     Dome       Shop           12         Note 1 2         Grease Leak Repair       D-04-39     Dome       Shop           14         Note 2 Note 1: No evidence of degradation or active corrosion was identified on either the anchorage components or the surrounding concrete. Sheathing filler was not discolored (indicative of moisture saturation) in the as found condition.
At the time the A2R15 ISI Summary Report was being prepared these conditions were being evaluated in accordance with ASME Section Xl, IWL-3222.
Note 2: No evidence of degradation or active corrosion was identified on either the anchorage components or the surrounding concrete. However, the sheathing filler was discolored (light, cream colored which is indicative of saturation) in the as found condition.
Any additional examination results subject to reporting requirements will be incorporated into the next Braidwood Station ISI Summary Report which will be submitted within ninety days after the conclusion of the Al R16 (Spring 2012) outage.Page 4-4 Exei n.Braidwood Station Unit 2 A2R15 ISI Outage Report 5.0 NIS-1 FORM As required by IWA-6000 of Section XI, this section contains the Owner's Report for Inservice Inspections, Form NIS-1, for the inservice examination of Class 1 and Class 2 pressure retaining components.
Page 4-3
Page 5-1 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules 1. Owner Exelon Generation Company (EGC, LLC), 200 Exelon Way, Kennett Square, PA, 19348 (Name and Address of Owner)2. Plant Braidwood Station, 35100 South Route 53, Suite 84, Braceville, Illinois 60450 (Name and Address of Plant)3. Plant Unit 2 4. Owner Certificate of Authorization (if required)
 
Not Applicable
Exeln..
: 5. Commercial Service Date 10/17/1988
Braidwood Station Unit 2 A2R15 ISI Outage Report Conclusions/Findings Based on the as found conditions where no degradation or active corrosion was identified on the anchorage components or surrounding concrete, there is no indication the presence of free water has resulted in any degradation of the specific tendons, post tensioning systems, or the containment structures. At the time the A2R15 ISI Summary Report was being prepared these conditions were being evaluated in accordance with ASME Section Xl, IWL-3222. Any additional examination results subject to reporting requirements will be incorporated into the next Braidwood Station ISI Summary Report which will be submitted within ninety days after the conclusion of the Al R16 (Spring 2012) outage.
: 6. National Board Number for Unit N-197 7. Components Inspected See Section 3 of this report for all components (report is a total of 119 pages).Component or Manufacturer Manufacturer State or National Appurtenance Or Installer or Installer Province No. Board No.Serial No.Reactor Vessel Babcock & Wilcox 640-0014-52 B-24360 N-1 95 2RC01R Pressurizer Westinghouse 2101 U-199012 18696 2RY01S Steam Generator Westinghouse CDGT-2111 N/A 20 2RC01BA Steam Generator Westinghouse CDGT-2112 N/A 21 2RC01 BB Steam Generator Westinghouse CDGT-2113 N/A 22 2RC01BC Steam Generator Westinghouse CDGT-2114 N/A 23 2RC01 BD Residual Heat Joseph Oat 2267-1 F U-199322 841 Removal Heat Corporation Exchanger 2RH02AA Residual Heat Joseph Oat 2267-1H U-199325 843 Removal Heat Corporation Exchanger 2RH02AB See Sections 3.1 through 3.1.6 and associated tables for the specific Class 1 and 2 component locations examined for the Third Interval ISI Program.Page 5-2 FORM NIS-1 (Back)8. Examination Dates: November 3, 2009 to July 28, 2011 9. Inspection Period Identification:
Page 4-4
: 10. Inspection Interval Identification:
 
: 11. Applicable Edition of Section Xl 1 st Period, Third Interval -From October 16, 2008 through October 16, 2011 3rd Interval -From October 17, 2008 through October 16, 2018 2001 Edition Addenda 2003 Addenda 12. Date/Revision of Inspection Plan: May 5, 2011 / Revision 3b including Code Cases N-460, N-508-3, N-566-2, N-686-1, N-700, N-706, N-722, N-729-1 13. Abstract of Examination and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. See Attached Sections 2 and 3.14. Abstract of Results of Examinations and Tests. See Attached Sections 2 and 3.15. Abstract of Corrective Measures.See Attached Sections 2 and 3.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 Xl, and c) corrective measures taken conform to the rules of the ASME Code, Section XI.Certificate of Authorization No. (if applicable)
Exei n.
Not Applicable Expiration Date Not Applicable Date /?U9S.+/- 5 20 I Signed Exelon Nuclear Braidwood Station By 9 Braidwood ISI Program Manager 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 Illinois and employed by Hartford Steam Boiler Inspection and Insurance Company of Connecticut have inspected the components described in this Owner's Report during the period Ll --_' to -?- -t A 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 Xl.By signing this certificate neither the Inspector nor his employer makes and 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.
Braidwood Station Unit 2 A2R15 ISI Outage Report 5.0 NIS-1 FORM As required by IWA-6000 of Section XI, this section contains the Owner's Report for Inservice Inspections, Form NIS-1, for the inservice examination of Class 1 and Class 2 pressure retaining components.
L Commissions  
Page 5-1
' X.'-- S7 I " Inspector's Signature National Board, State, Province, and Endorsements Date ,- .._- & 20 IN Page 5-3 ExeLn_Braidwood Station Unit 2 A2R15 ISI Outage Report Braidwood Unit 2 Non-Deferrable Class 1 and Class 2 Inspection Status (Third Interval)
 
After A2R15 per IWA-6220(f)
FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
Code Category Code Item Number Total Number Selected Total Number Examined Current Percentage (Interval) in A2R15 Completed for Category B-A B1.30 1 0 0%B1.40 1 0 B-B B2.11 2 0 B2.12 2 0 2/5 40%B2.40 1 0 B-D B3.110 6 2 B3.120 6 2 4/20 =20%B3.140 8 0 B-K B10.10 1 0 1/3 33%B10.20 2 0 B-N-1 B13.10 1 1 Once Per Period B-P B15.10 Every Outage 1 Not Applicable B-Q B1 6.20 Per Technical Specifications 4 Not Applicable C-A C1.10 4 2 C1.20 2 0 2/7 = 28%C1.30 1 0 C-B C2.21 5 1 1/6 = 16%C2.22 1 0 C-C C3.10 1 0 C3.20 9 0 4/13 = 30.7%C3.30 3 0 C-H C7.10 38 18 18/38 =47.3%F-A F1.10 167 25 F1.20 186 35 F1.30 73 13 F1.40 29 2 R-A Butt Welds 202 23 Socket Welds 96 Welds Every Outage 96 Page 5-4 Exet n.Braidwood Station Unit 2 A2R15 ISI Outage Report 6.0 NIS-2 FORM (OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS)
: 1. Owner       Exelon Generation Company (EGC, LLC), 200 Exelon Way, Kennett Square, PA, 19348 (Name and Address of Owner)
: 2. Plant     Braidwood Station, 35100 South Route 53, Suite 84, Braceville, Illinois 60450 (Name and Address of Plant)
: 3. Plant Unit     2                         4. Owner Certificate of Authorization (if required)     Not Applicable
: 5. Commercial Service Date     10/17/1988       6. National Board Number for Unit                       N-197
: 7. Components Inspected       See Section 3 of this report for all components (report is a total of 119 pages).
Component or             Manufacturer               Manufacturer             State or             National Appurtenance             Or Installer               or Installer           Province No.           Board No.
Serial No.
Reactor Vessel       Babcock & Wilcox             640-0014-52               B-24360               N-1 95 2RC01R Pressurizer           Westinghouse                   2101                 U-199012               18696 2RY01S Steam Generator         Westinghouse               CDGT-2111                   N/A                   20 2RC01BA Steam Generator         Westinghouse               CDGT-2112                   N/A                   21 2RC01 BB Steam Generator         Westinghouse               CDGT-2113                   N/A                   22 2RC01BC Steam Generator         Westinghouse               CDGT-2114                   N/A                   23 2RC01 BD Residual Heat             Joseph Oat                 2267-1 F               U-199322                 841 Removal Heat             Corporation Exchanger 2RH02AA Residual Heat           Joseph Oat                 2267-1H               U-199325                 843 Removal Heat             Corporation Exchanger 2RH02AB See Sections 3.1 through 3.1.6 and associated tables for the specific Class 1 and 2 component locations examined for the Third Interval ISI Program.
Page 5-2
 
FORM NIS-1 (Back)
: 8.     Examination Dates:                     November 3, 2009 to July 28, 2011
: 9.     Inspection Period Identification:       1 st Period, Third Interval - From October 16, 2008 through October 16, 2011
: 10.      Inspection Interval Identification:    3rd Interval - From October 17, 2008 through October 16, 2018
: 11.      Applicable Edition of Section Xl        2001 Edition      Addenda     2003 Addenda
: 12.     Date/Revision of Inspection Plan:       May 5, 2011 / Revision 3b including Code Cases                   N-460, N-508-3, N-566-2, N-686-1, N-700, N-706, N-722, N-729-1
: 13.     Abstract of Examination and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan.         See Attached Sections 2 and 3.
: 14.     Abstract of Results of Examinations and Tests.           See Attached Sections 2 and 3.
: 15.     Abstract of Corrective Measures.                         See Attached Sections 2 and 3.
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 Xl, and c) corrective measures taken conform to the rules of the ASME Code, Section XI.
Certificate of Authorization No. (if applicable)         Not Applicable             Expiration Date Not Applicable Date         /?U9S.+/-     5       20 I     Signed       Exelon Nuclear Braidwood Station By     VSA#2-*Owne r*                9                 Braidwood ISI Program Manager 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 Illinois and employed by Hartford Steam Boiler Inspection and Insurance Company of Connecticut have inspected the components described in this Owner's Report during the period Ll -     _'
                                -        to -?- - t A     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 Xl.
By signing this certificate neither the Inspector nor his employer makes and 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.
L                                     Commissions                         ' X.'-- k*.OSS7        I "
Inspector's Signature                               National Board, State, Province, and Endorsements Date       ,- & _-
                      ..                         20 IN Page 5-3
 
ExeLn_
Braidwood Station Unit 2 A2R15 ISI Outage Report Braidwood Unit 2 Non-Deferrable Class 1 and Class 2 Inspection Status (Third Interval) After A2R15 per IWA-6220(f)
Code Category         Code Item Number         Total Number Selected       Total Number Examined       Current Percentage (Interval)                 in A2R15           Completed for Category B-A                     B1.30                         1                         0                           0%
B1.40                         1                         0 B-B                     B2.11                         2                           0 B2.12                         2                           0                     2/5 40%
B2.40                         1                           0 B-D                     B3.110                         6                         2 B3.120                         6                         2                     4/20 =20%
B3.140                         8                           0 B-K                     B10.10                         1                           0                     1/3 33%
B10.20                         2                           0 B-N-1                   B13.10                         1                           1                 Once Per Period B-P                     B15.10                   Every Outage                     1                   Not Applicable B-Q                     B1 6.20           Per Technical Specifications           4                   Not Applicable C-A                     C1.10                         4                           2 C1.20                         2                           0                     2/7 = 28%
C1.30                         1                           0 C-B                     C2.21                         5                           1                     1/6 = 16%
C2.22                         1                           0 C-C                     C3.10                         1                           0 C3.20                         9                           0                   4/13 = 30.7%
C3.30                         3                           0 C-H                     C7.10                         38                         18                   18/38 =47.3%
F-A                     F1.10                         167                         25 F1.20                         186                         35 F1.30                         73                         13 F1.40                         29                           2 R-A                   Butt Welds                     202                         23 Socket Welds           96 Welds Every Outage                 96 Page 5-4
 
Exet n.
Braidwood Station Unit 2 A2R15 ISI Outage Report 6.0     NIS-2 FORM (OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS)


==SUMMARY==
==SUMMARY==
OF NIS-2 FORMS The following table provides the Class 1 and 2 ASME Section XI repairs completed since the last outage report (A2R14). Activities where the replacement item installed was a rotated spare are not included in this summary as allowed by IWA-4132(g) and Code Case N-508-3.System CV CS FW MS RC RH RY SD SI Chemical & Volume Control Containment Spray Feedwater Main Steam Reactor Coolant Residual Heat Removal Reactor Coolant/Pressurizer Steam Generator Blowdown Safety Injection ASME Code Classification Code Class 1 Code Class 2 5 1 1 9 1 4 3 3 1 4 Total NIS-2 Forms 32 Associated NIS-2 Forms and associated Code Data Reports are attached (47 total pages).Page 6-1 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner : Exelon Generation Co., LLC Address: 300 Exelon Way, Kennett Square, PA 19348 2. Plant Name: Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 3. Work Performed By: Shaw/ Stone & Webster Address: 36400 South Essex Road, Wilmington, IL 60481 4. Identification of System: Chemical Volume and Control (CV) (Class 2)Date 7/7/2011 Sheet 1 of 1 Unit: 2 Work Order #01148456-01 Repair/Replacement Organization P.O., Job No., etc Type Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5 (a)(b)(c)Applicable Construction Code: ASME Section III 1971 Edition, Winter 1972 Addenda, No Code Cases Applicable Edition of Section XI Utilized for Repair/Replacement:
OF NIS-2 FORMS The following table provides the Class 1 and 2 ASME Section XI repairs completed since the last outage report (A2R14). Activities where the replacement item installed was a rotated spare are not included in this summary as allowed by IWA-4132(g) and Code Case N-508-3.
2001 Edition with 2003 Addenda Section XI Code
System                    ASME Code Classification Code Class 1      Code Class 2 CV    Chemical & Volume Control                                      5 CS    Containment Spray                                              1 FW    Feedwater                                                      1 MS    Main Steam                                                    4 RC    Reactor Coolant                            9                  3 RH    Residual Heat Removal                                          3 RY    Reactor Coolant/Pressurizer                1 SD    Steam Generator Blowdown                                        1 SI    Safety Injection                                                4 Total NIS-2 Forms                      32 Associated NIS-2 Forms and associated Code Data Reports are attached (47 total pages).
Page 6-1
 
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1            Owner      : Exelon Generation Co., LLC                                                Date 7/7/2011 Address: 300 Exelon Way, Kennett Square, PA 19348                                      Sheet 1 of 1
: 2.            Plant Name: Braidwood Station                                                          Unit:  2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #01148456-01 Repair/Replacement Organization P.O., Job No., etc
: 3.          Work Performed By: Shaw/ Stone & Webster Type Code Symbol Stamp: None Address: 36400 South Essex Road, Wilmington, IL 60481                                    Authorization No.: None Expiration Date: None
: 4.            Identification of System: Chemical Volume and Control (CV) (Class 2) 5      (a)      Applicable Construction Code: ASME Section III 1971 Edition, Winter 1972 Addenda, No Code Cases (b)      Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c)        Section XI Code Cases used: None
: 6. Identification of Components:
Name of Component                    Name of            Manufacturer        National          Other            Year Built          Corrected      ASME Code Manufacturer            Serial No.      Board No.      identification                          Removed, or    Stamped (Yes Installed      or No)
Existing Valve Cover and                Kerotest          Not Recorded            Not            Valve            Not Recorded        Removed        Yes (Valve)
Body-to-Cover Seal Weld                                                      Applicable        2CV8348 Valve 2CV8348                                    IIII                                                                _      III Body-to-Cover Seal Weld            Arcos Industries,        Lot CT8660            Not        Cat ID 8500-1            2007              Installed        No Weld Electrode                      LLC              Heat 734816        Applicable    UTC 2808606                              (Corrected) 3/32" ER316/316L
: 7.      Description of Work: Removed existing seal weld to provide access to valve internals for check valve inspection. After inspection was completed, the existing valve cover was reinstalled and seal weld was reapplied. Seal weld was examined by liquid penetrant and was rejected. Indication was removed and repaired by welding. Seal weld was again examined by liquid penetrant and found acceptable.
: 8.        Tests Conducted:            Hydrostatic [] Pneumatic E] Nominal Operating Pressure C] Exempt 0 Other 0    Pressure    Nominal        psig Test Temp.      Nominal    *F
: 9.        Remarks: Seal welds are exempt from Section Xl pressure testing requirements per IWA-4550(b)(8), but valve was examined by VT-2 method on 5/5/2011 during periodic system pressure testing and found acceptable. Applicable documentation for replacement valve seal weld filler material was attached at the time of final review and is maintained on file.
CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code, Section XI.
Type Code.*ymbol Stamp: Not              plicable  Certificate of Authorization No.: Not Applicable S i gn e d      ,.,l        4.    ,4        -*                  ISI Coordinator      Date    -77            2011 Owner or Owner's Designee, Title/
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this

Revision as of 16:04, 12 November 2019

Inservice Inspection Summary Report
ML11227A253
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 08/10/2011
From: Enright D
Exelon Corp, Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BW110084
Download: ML11227A253 (120)
v • d • e


Text

Exelon Generation Company, LLC www.exeloncorp.com Exelkn Braidwood Station NUClear 35100 South Route 53, Suite 84 Braceville, IL60407-9619 August 10, 2011 BW1 10084 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Facility Operating License No. NPF-77 NRC Docket No. STN 50-457

Subject:

Braidwood Station, Unit 2 Inservice Inspection Summary Report Enclosed please find the post-outage summary report (i.e., 90 day report) for inservice inspection examinations conducted during Braidwood Station, Unit 2 Refueling Outage 15 (A2R1 5). This report is submitted in accordance with the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, "Rules for the Inservice Inspection of Nuclear Power Plant Components," Article IWA-6200, "Requirements."

Please direct any questions you may have regarding this submittal to Mr. Chris VanDenburgh, Regulatory Assurance Manager, at (815) 417-2800.

Respectfully, Daniel J. EnrighA Site Vice President Braidwood Station

Enclosure:

Braidwood Station ISI Outage Report for A2R1 5 cc: Regional Administrator- NRC Region III NRC Senior Resident Inspector - Braidwood Station Illinois Emergency Management Agency - Division of Nuclear Safety U47T

BRAIDWOOD STATION UNIT 2 INSERVICE INSPECTION

SUMMARY

REPORT FOR:

Interval 3, Period 1, Outage 2 A2R15 Outage STATION ADDRESS:

Braidwood Station 35100 S. Route 53 Suite 84 Braceville, Illinois 60407 UNIT 2 COMMERCIAL SERVICE DATE:

October 17, 1988 OWNER'S ADDRESS:

Exelon Generation Co., LLC 300 Exelon Way Kennett Square PA 19348

Exeln.

Braidwood Station Unit 2 A2R15 ISI Outage Report TABLE OF CONTENTS DESCRIPTION: PAGE:

TITLE PAGE TABLE OF CONTENTS 1.0 - INSPECTION INFORMATION 1-1 to 1-3 2.0 - INSERVICE EXAMINATION

SUMMARY

2-1 to 2-5 3.0 - COMPONENT EXAMINATION RESULTS 3-1 to 3-54 4.0 - REPORT OF CONTAINMENT 4-1 to 4-4 DEGRADATION 5.0 - FORM NIS-1 (OWNER'S REPORT FOR INSERVICE INSPECTION) 5-1 to 5-4 FOR ISI THIRD INTERVAL AND THIRD INTERVAL INSPECTION STATUS AFTER A2R15 6.0 - FORM NIS-2, (OWNER'S REPORT FOR REPAIRS 6-1 to 6-47 OR REPLACEMENTS), Cover page plus 46 pages of Attachments ii

Exei n_

Braidwood Station Unit 2 A2R15 ISI Outage Report 1.0 INSPECTION INFORMATION 1.1 Summary Third Interval Inservice Inspections (ISI) and Preservice Inspections (PSI) of ASME Class 1, 2, and 3 components were conducted at Braidwood Station Unit 2 from November 2, 2009 through July 28, 2011. The majority of these inspections were performed during the Braidwood Station Unit 2 fifteenth refueling outage (A2R1 5). This report also contains the results of the remaining pressure tests that were not completed prior to submittal of the previous A2R1 4 outage report.

For the Third Interval, examinations were performed in accordance with the rules and regulations of Section Xl, Division 1, "Rules for Inservice Inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 2001 Edition through 2003 Addenda, pursuant to the requirements of Title 10, Part 50.55a of the Code of Federal Regulations (10CFR50.55a).

The Containment Inspection Program was developed and implemented in accordance with the requirements and intent of Subsections IWE and IWL of ASME Section Xl, 2001 Edition through the 2003 Addenda, pursuant to the requirements of 10CFR50.55a.

In addition to the ASME Section Xl requirements, certain NRC or industry augmented inspections were completed during A2R15. The Braidwood Unit 2 augmented examinations included:

a) Examination of the Class 1 pressure boundary for leakage at nominal operating pressure, in accordance with Generic Letter 88-05.

b) Examination of the 2B reactor coolant pump motor flywheel in accordance with Regulatory Guide 1.14 and Technical Specification 5.5.7.

c) Examination of welds in accordance with Materials Reliability Project MRP-139, "Primary System Piping Butt Weld Inspection and Evaluation Guideline" and MRP-192, "Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants".

d) Reinspection of all six pressurizer nozzle-to-safe end full structural overlays in accordance with ASME Section Xl Nonmandatory Appendix Q and Second Interval Relief Request 12R-48.

The only documented indication requiring further evaluation was observed during the augmented inspections for MRP-192 in a tee-to-pipe circumferential weld. This indication was attributed to original construction and was not characterized as service-induced (i.e., thermal fatigue craze cracking). The indication was accepted for continued service in accordance with IWB-3600 evaluation methods.

Page 1-1

Exel .n-Braidwood Station Unit 2 A2R15 ISI Outage Report 1.2 Identification of Examination Requirements The Third Interval ISI Program contains the applicable Component Selection tables. These tables are presented in a tabular format consistent with the tables found in subsections IWB, IWC, IWD, IWE, and IWF-2500 of the ASME code. The Non-Destructive Examination (NDE) tables include the corresponding code category, item number, and component/weld population selection in conformance with examination requirements and intent of Subsection IWA, IWB, IWC, IWD, IWE, and IWF of Section Xl of the ASME Code. Program notes and relief requests and additional information are identified in the basis column.

1.3 Exempted Components ASME Class 1, 2, and 3 components (or parts of components) that are not included in the Component inspection tables and that are exempt from examination, as specified in Section Xl Subsection IWB, IWC, IWD, and IWF are identified in the Braidwood Station Boundary Basis document, along with reference to the justification(s) for exempting the component/system.

1.4 ISI Program Implementation Braidwood Station personnel, or their designee, visually examined (VT-1, VT-2, and VT-3) and/or NDE examined (UT, PT, MT) ASME components.

The components examined comply with the ISI Program Schedule, Braidwood Station Technical Specifications (TS), and/or compliance with the ASME Section Xl Repair/Replacement Program. All ISI NDE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section XI, Sub-article IWA-2200:

"Examination Methods".

Certified personnel performed and evaluated all NDE results. Personnel were certified to the requirements of the American Society for Non-destructive Testing SNT-TC-1A, 1984 Edition and ANSI/ASNT CP-189, 1995 Revision. The NDE procedures were developed and certified in conformance with ASME Section V and Xl, 2001 Edition through 2003 Addenda, or approved alternatives (Performance Demonstration Initiative Program) as applicable. In addition, ultrasonic examination personnel were qualified in accordance with ANSI/ASME CP-189, 1995 Revision.

Certified personnel performed and evaluated visual examinations (i.e.,

VT-1, VT-2, and VT-3) of Class 1, 2, and 3 components and supports.

Personnel were certified to the requirements of the American Society for Non-destructive Testing SNT-TC-1A, 1984 Edition and ANSI/ASNT CP-189, 1995 Revision.

Certified personnel performed and evaluated examinations (UT, VT-1, and VT-3) of primary containment. Personnel were certified in Page 1-2

Exekm..

Braidwood Station Unit 2 A2R15 ISI Outage Report accordance with the requirements of the ANSI/ASNT CP-1i89, 1995 Revision, and/or ASME Section XI 2001 through 2003 Addenda, as applicable.

1.5 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANII), L. Malabanan and J.

Norville. The inspectors are associated with Hartford Steam Boiler Inspection and Insurance Company of Connecticut, Chicago Branch, at 2443 Warrenville Rd., Suite 500, Lisle, Illinois 60532.

Page 1-3

.Exelon-Braidwood Station Unit 2 A2R15 ISI Outage Report 2.0 INSERVICE EXAMINATION

SUMMARY

The following is a summary of ASME Section Xl Class 1 and 2, Risk Informed ISI, and augmented examinations performed during the Braidwood Station Unit 2 A2R15 refueling outage. Refer to the component detailed examination tabulations of Section 3.0 for additional information on specific welds, components, supports, snubbers and pressure test examinations and their respective results.

2.1 Inservice Weld/Component Summary

  • .o..*

z SSystem

.System

. ......... *.:*.., : Number. of Welds/

S...Components*

Containment Spray (CS) 2 Feedwater (FW) 11 Reactor Coolant (RC) 8 Residual Heat Removal (RH) 11 Pressurizer (RY) 14 Safety Injection (SI) 1 TOTALS 47 Non-Section Xl Augmented, 10 CFR 50.55a, and Risk Informed ISI socket weld VT-2 examinations are not included in these counts but are contained in Section 3.1.1 of report.

2.2 Inservice Component Support Summary Number of SYSTEM: EXAMINED- Component

........ Supports Auxiliary Feedwater (AF) 4 Chemical & Volume Control (CV) 2 Feedwater (FW) 4 Main Steam (MS) 4 Reactor Coolant (RC) 2 Residual Heat Removal (RH) 7 Reactor Coolant/Pressurizer (RY) 7 Safety Injection (SI) 16 Essential Service Water (SX) 14 TOTALS 60 Page 2-1

Exek n-Braidwood Station Unit 2 A2R15 ISI Outage Report 2.3 Inservice Snubber Summary Number.of  %.Number of,...

EXAMINED  : Snubbers. . Snubbers,",.

TM"xmie

. .... " y Functionally:

Vt.3 Tested*

Containment Spray (CS) 2 0 Chemical & Volume Control (CV) 12 10 Feedwater (FW) 9 6 Main Steam (MS) 7 2 Reactor Coolant (RC) 16 4 Residual Heat Removal (RH) 2 1 Reactor Coolant/Pressurizer (RY) 10 5 Steam Generator Blowdown (SD) 3 3 Safety Injection (SI) 7 4 Essential Service Water (SX) 1 1 TOTALS 69 36 2.4 Inservice Pressure Test Summary 2.4.1 Pressure Test Block Inspection Summary The components contained in Table 2.4.1-1 are the Class 1 and Class 2 pressure test blocks that were examined for Section XI Inservice Inspection since the A2R14 report was submitted.

Table 2.4.1-1 Class 1 and 2 System Pressure Tests Numberbof Test.

System Class Blocks-

_______________________Examiined Chemical Volume and Control (CV) 2 3 Fuel Pool Cooling and Clean Up (FC) 2 2 Instrument Air (IA) 2 1 Residual Heat Removal 2 4 Safety Injection (SI) 2 4 Essential Service Water (SX) 2 2 Plant Systems Pressurized During 1 &2 3 Mode 3 (ZZ)

TOTALS 19 Page 2-2

Ex4t nj.

Braidwood Station Unit 2 A2R15 ISI Outage Report 2.4.2 Borated Bolting Inservice Inspection Summary The components contained in Table 2.4.2-1 are those insulated borated bolted connections that were examined for Section XI Inservice Inspection credit. Inspections on these connections are performed per the ISI Program Plan.

Table 2.4.2-1 Borated Bolted Connections Numberof.. Number of SSEEXMNDConnections Connectio ns Examined by Examined by VT-3 Chemical & Volume Control (CV) 8 0 Reactor Coolant/Pressurizer 14 0 (RC/RY)

Residual Heat Removal (RH) 1 0 TOTALS 23 0 2.5 Steam Generator Eddy Current Testing Summary 2.5.1 Steam Generator Eddy Current Testing Summary In accordance with Braidwood Station Technical Specification (TS) 3.4.19, "Steam Generator (SG) Tube Integrity," TS 5.5.9, "Steam Generator (SG) Program," and American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code Section XI 2001 Edition through 2003 Addenda, IWB 2500-1, Examination Category B-Q, Item 816.20, SG eddy current examinations were performed during the Braidwood Station, Unit 2, fifteenth refueling outage (A2R15). In addition, the inspections were performed consistent with the Electric Power Research Institute (EPRI) "PWR Steam Generator Examination Guidelines," Revision 7, and Nuclear Energy Institute NEI 97-06, "Steam Generator Program Guidelines," Revision 2.

The following inspections were performed during this outage:

  • 100% full-length bobbin coil eddy current examination of all SGs, excluding the row 1 and row 2 U-Bend region, which were inspected as part of the 25% Plus-Point program.
  • 100% hot leg top of tubesheet (+4"/-1 8") +PointTM of in-service tubes identified as having increased residual stress Page 2-3

Exei n.

Braidwood Station Unit 2 A2R15 ISI Outage Report

  • 100% +PointTM inspection of the hot leg dents/dings > 3.0 volts and wear indications of in-service tubes identified as having increased residual stress
  • 100% +PointTM inspection of the "corner" preheater expansions at TSP 02-C in the 2B, 2C, and 2D SGs
  • +PointTM inspection of in-service tubes containing foreign object wear and re-sized with a qualified eddy current technique
  • +PointTM inspection of in-service tubes around all tubes that were previously plugged due to foreign objects
  • 25% hot leg top of tubesheet (+4"/-18") +PointTM in all SGs
  • 25% hot leg bulges > 18 Volts and over exNansions > 1.5 mils within top 18 inches of the hot leg tubesheet, +Point in all SGs
  • 25% row 1 and 2 U-bends +PointTM in all SGs. In addition to the 25%

inspection, an additional thirty nine (39) tubes identified with manufacturing artifacts during the A2R14 Independent Qualified Data Analyst (IQDA) review were inspected

  • 25% +PointTM inspection on the base population of hot leg dents/dings

>3.0 volts and 100% of hot leg dent / ding >3 volts identified during the A2R15 inspection and does not exist in history

  • 25% pre-heater baffle expansion +PointTM in all SGs
  • 100% visual inspection of the previously installed and newly installed tube plugs in all SGs.

The modes of tube degradation found during the A2R15 SG inspection were anti-vibration bar (AVB) wear, pre-heater tube support plate wear, axial outside diameter stress corrosion cracking and secondary side foreign object wear.

As a result of the eddy current inspection of the SGs, a total of thirty (30) tubes were removed from service by mechanical tube plugging.

Of the thirty (30) tubes removed from service, the following number of tubes were plugged due to an imperfection depth greater than or equal to the 40% through wall (TW) Technical Specification 5.5.9.c.1 acceptance criteria

  • Five (5) tubes were plugged due to AVB wear

" One (1) tube was plugged due to having wear from secondary side foreign objects

" One (1) tube was plugged due to having pre-heater wear Of the thirty (30) tubes removed from service, One (1) tube was plugged upon detection of axial outside diameter stress corrosion cracking (ODSCC).

Of the thirty (30) tubes removed from service, the following number of tubes were preventively plugged due to wear less than or equal to the 40% through wall (TW) Technical Specification 5.5.9.c.1 acceptance criteria Page 2-4

Exelkn.

Braidwood Station Unit 2 A2R15 ISI Outage Report 0 One (1) tube due to pre-heater wear 0 Seventeen (17) tubes due to having wear from secondary side foreign objects Of the thirty (30) tubes removed from service, four (4) tubes were preventatively removed from service due to the presence of potential secondary side foreign objects, but no wear was present.

There were no scanning limitations during the eddy current examinations.

Table 2.5-1 provides the total number of tubes plugged during A2R15 by degradation mode. Table 2.5-2 provides the tube plugging levels for each SG to date.

Table 2.5-1 Tubes Plugged During A2R15 SG2A SG2B SG2C SG2D Total Foreign Object Wear 5 6 0 7 18 Pre-Heater Wear 0 0 1 1 2 Axial ODSCC 0 0 0 1 1 Anti-Vibration Bar Wear 3 1 1 0 5 Preventative 4 0 0 0 4 A2R15 Plugging Totals 12 7 2 9 30 Table 2.5-2 Equivalent Tube Plu ging Level

.... .. ... . .... SG2A ".".SG2B . SG.%2C0" SG2D Total Tubes Previously Plugged 83 54 66 26 229 Tubes Plugged in A2R15 12 7 2 9 30 Total Tubes Plugged 95 61 68 35 259 Total Tubes Plugged (%)* 2.08% 1.34% 1.49% 0.77% 1.42%

Page 2-5

Exelkn.

Braidwood Station Unit 2 A2R15 ISI Outage Report 3.0 COMPONENT EXAMINATION RESULTS 3.1 Third Interval Inservice and Preservice Inspection Detailed Result Tables 3.1.1 Detailed Third Interval Inservice Weld/Component Table(s):

The table for this section (Pages 3-5 to 3-19) lists the examinations performed for Section Xl Inservice and Augmented Inspection requirements for Class 1 and 2 welds and components for the Third ISI Interval. The general format of how the table is set-up is shown below. A description of the information contained in each column can be found in Section 3.3.

i Section XI ISI Identifier Line Relief Program Coode Exam Actual ResultsI cat. Item Description I Number/EPN I Request Notes Coverage I Summary I Exam!]

Inspection Comments (A) (B) (C) (D) (E) (F) (G) (H) (I)

(K)

(J) 3.1.2 Detailed Third Interval Inservice Component Support Table:

The table for this section (Pages 3-20 to 3-28) lists the examinations performed for Section Xl Inservice Inspection requirements for Class 1 and 2 component supports for the Third ISI Interval. The general format of how the table is set-up is shown below. A description of the information contained in each column can be found in Section 3.3.

iSection XI ISI Identifier Line NumberEPN Relief PgI rram Exam Cat. Item I Description Request Notes Summary Inspection Comments (A) (B) (C) (D) (E) (G) (I)

(K)

(J) 3.1.3 Detailed Third Interval Inservice Snubber Table:

The table for this section (Pages 3-29 to 3-39) lists the examinations performed for Section Xl Inservice Inspection requirements for Class 1 and 2 snubbers. The general format of how the table is set-up is shown below. A description of the information contained in each column can be found in Section 3.3.

I Section XI SI Identifier I Line Number/EPN Relef I Program Exam I Results Cat. Item Description Request I Notes Summary I Inspection Comments (A) (B) (C) (D) (E) (G) (I)

(K)

(J)

Page 3-1

Exeitn.

Braidwood Station Unit 2 A2R15 ISI Outage Report 3.1.4 Detailed Third Interval Preservice Snubber Table:

The table for this section (Pages 3-40 to 3-44) lists the baseline examinations performed for Section XI Preservice Inspection requirements for Class 1 and 2 snubbers replaced during A2R1 5. The general format of how the table is set-up is shown below. A description of the information contained in each column can be found in Section 3.3.

MSection XI ISI Identifier Line Number/EPN Relief Program Exam I Resuls Cat. Item Description Inspection Comments Request Notes Summary I (A) (B) (c) (D) (E) (G) (I)

(K)

(J) 3.1.5 Detailed Listing of Third Interval System Pressure Tests The table for this section (Pages 3-45 to 3-51) lists the examinations performed for Section XI Inservice and Augmented Inspection requirements for Class 1 and 2 pressure test blocks credited to the Third ISI Interval. The general format of how the table is set-up is shown below.

A description of the information contained in each column can be found in Section 3.3.

Section Xl ISI Identifier Relief I Program Exam Results Cat. Item I Description SRequest I Notes I Summary Inspection Comments (A) (B) (D) (E) (G) (I)

(K)

(J) 3.1.6 Detailed Borated Bolted Connection Table The table for this section (Pages 3-52 to 3-54) lists the examinations performed for Inservice Inspection pressure testing requirements of Section XI Class 1 and 2 borated bolted connections. The general format of how the table is set-up is shown below. A description of the information contained in each column can be found in Section 3.3.

Section XlI ISI Identifier Relief I Program I Exam I Results Cat. Item I Descriotion Recuest Notes I Summary Inspection Comments (A) (B) (D) (E) (G) (I)

(K)

(J)

Page 3-2

Exelkn.

Braidwood Station Unit 2 A2R15 ISI Outage Report 3.3 General Inservice Report Information 3.3.1 Report Column Descriptions (A) This column contains the Section Xl Category and Item identifiers for the specified component. There are special cases, like snubbers, where an "S"has been added to the end of the Section Xl Item identifier. This was done to allow easy sorting of the snubber population by the ISI database.

(B) This column contains the ISI Identifier that the ISI Program uses to distinguish components.

(C) This column contains the line number or equipment piece number (EPN) associated with the component for identification.

(D) This column identifies the IS1 Program Plan relief request(s) that is associated with that component. A complete copy of the relief request can be found in the ISI Program Plan.

(E) This column identifies the ISI Program Plan note(s) that is associated with that component. A complete copy of the Program note can be found in the ISI Program Plan.

(F) This column identifies the percentage of code coverage achieved for the associated surface or volumetric examination for that component.

(G) This column summarizes the exams performed during this outage for the associated component.

(H) This column identifies actual exams performed during this outage for the associated component.

(I) This column summarizes the results for exams performed during this outage for the associated component.

(J) This row states inspection comments, when applicable, for the associated component.

(K) This column specifies the description of the associated component.

Page 3-3

Exek n.

Braidwood Station Unit 2 A2R15 ISI Outage Report 3.2.2 Report Abbreviations ATI - Action Tracking Item BMV - Bare Metal Visual Inspection ET - Eddy Current (Steam Generator)

FUNCT - Snubber Functional Test FSWOL - Full Structural Weld Overlay GE/IND - Geometry/Indication GEO - Geometry IND - Indication IR - Issue Report NRI - No Recordable Indications MT - Magnetic Particle Inspection PT - Liquid Penetrant Inspection SUR - Surface Exam TBD - To Be Developed WO - Work Order UT - Ultrasonic Inspection VOL - Volumetric Exam VOL-E - Volumetric Exam of an Extended Volume VT - Visual Inspection Page 3-4

Exe. n..

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Containment Spray System (CS)

Section XI Component ID  :...*' Line Number Relief Technical ýCode**., :.Required Ac esults Cat Descriio n . Requests Notes Cov erage* Exam Exam; .

Cments NA ECCS 2CS-01-06 2CS02AA-10" NOTE 19 100 VOL UT-0 NRI ELBOW - PIPE UT-45 UT-70 Zero degree performed to determine thickness and contour, no counterbore detected.

NA ECCS 2CS-01-12 2CS02AA-1 0" NOTE 19 100 VOL UT-0 NRI ELBOW - PIPE UT-45 UT-70 Zero degree performed to determine thickness and contour, no counterbore detected.

NA ECCS 2CS-01-15 2CS02AA-10" NOTE 19 100 VOL UT-0 NRI PIPE - PIPE UT-45 UT-70 Zero degree performed to determine thickness and contour, no counterbore detected.

R-A R01.20 2CS-03-06 2CS23AA-14" 13R-01 NOTE 17 100 VOL-E UT-0 NRI ELBOW - PIPE UT-45 Zero degree performed to determine thickness and contour, no counterbore detected.

R-A R01.20 2CS-04-04 2CS23AB-14" 13R-01 NOTE 17 100 VOL-E UT-0 NRI PIPE - ELBOW UT-45 Zero degree performed to determine thickness and contour, no counterbore detected.

NA ECCS 2CS-05-06 2CS02AB-10" NOTE 19 100 VOL UT-0 NRI ELBOW - PIPE UT-45 Zero degree performed to determine thickness and contour, no counterbore detected.

NA ECCS 2CS-05-14 2CS02AB-10" NOTE 19 100 VOL UT-0 NRI ELBOW - PIPE UT-45 Zero degree performed to determine thickness and contour, no counterbore detected.

NA ECCS 2CS-05-17 2CS02AB-10" NOTE 19 100 VOL UT-0 NRI PIPE - PIPE UT-45 Zero degree performed to determine thickness and contour, no counterbore detected.

Page 3-5

Exei n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Chemical & Volume Control System (CV)

SectionvXlIComponent ID Line Number .".ýRellef

... *Technkcal-lCode*,*... lRe:quired Actuafi Re7sults

~ ~cat. -c-riptlony~ Requests N1otes Coverage Exýxam: Exam Comnme rnts R-A R01.11 2CV-05-03 2GVA3B-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2CV-05-04 2CVA3B-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2CV-05-05 2CVA3B-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2CV-05-06 2CVA3B-2" 13RI-O1 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2CV-05-13 2CVA3B-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2CV-05-14 2CVA3B-2" 1313-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2CV-11-06 2CVA6AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2CV-11-07 2OVA6AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE NA ECCS 2CV-19-21 2CV05CB-6" NOTE 19 100 VOL UT-0 NRI ELBOW - PIPE UT-45 Zero degree performed to confirm no counterbore present. ID geometry observed below recordable levels.

NA ECCS 2CV-19-22 2CV05CB-6" NOTE 19 100 VOL UT-0 NRI PIPE - ELBOW UT-45 Zero degree performed to confirm no counterbore present. ID geometry observed below recordable levels.

R-A R01.11 2RC-36-15 2CVA3AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.1 1 2RC-36-16 2CVA3AA-2' 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2RC-36-17 2CVA3AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2RC-36-18 2CVA3AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2RC-37-13 2CVA7AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2RC-37-14 2CVA7AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE Page 3-6

Exeltn-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Feedwater System (FW)

Sectionxi "CoMioet ID Line Number Relief11 Technical Code Required, Actuakf Results Cat..... Description . Requests, !Notes~ lCoverage. Exami::

  • Exam*',i.

R-A R01.11 2FW-02-04 2FW03DA-16" 13R-01 NOTE 09 100 VOL-E UT-45 NRI R01.18 VALVE 2FW009A - PIPE NOTE 17 Increased examination coverage for RI-ISI requirements.

R-A R01.11 2FW-02-05 2FW03DA-16" 13R-01 NOTE 09 100 VOL-E UT-45 GEO R01.18 PIPE-PIPE NOTE 17 Increased examination coverage for RI-ISI requirements.

R-A R01.11 2FW-02-06 2FW03DA-1 6" 13P-01 NOTE 09 100 VOL-E UT-45 NRI R01.18 PIPE- PENETRATION (2PC-079) PIPE NOTE 17 Increased examination coverage for RI-ISI requirements.

R-A R01.11 2FW-02-19 2FW03DA-16" 13P-01 NOTE 17 100 VOL-E UT-45 NRI R01.18 PIPE-ELBOW ID geometry observed below recordable levels.

R-A R01.11 2FW-02-20 2FW03DA-1 6" 13R-01 NOTE 17 100 VOL-E UT-45 NRI R01.18 ELBOW-PIPE ID geometry observed below recordable levels.

R-A R01.11 2FW-02-23 2FW03DA-1 6" 13R-01 NOTE 17 100 VOL-E UT-45 NRI R01.18 PIPE-ELBOW Increased examination coverage for RI-ISI requirements. ID geometry observed below recordable levels.

R-A R01.11 2FW-06-11 2FW87CB-6" 13R-01 NOTE 17 100 VOL-E UT-45 NRI R01.18 ELBOW- ELBOW Increased examination volume for RI-ISI requirements.

R-A R01.11 2FW-11-21 2FW81BA-6" 13R-01 NOTE 09 100 VOL-E UT-45 NRI R01.18 PIPE-TEE NOTE 17 Zero degree performed to confirm no counterbore exists.

R-A R01.11 2FW-11-22 2FW87CA-6" 13R-01 NOTE 09 100 VOL-E UT-45 NRI R01.18 TEE - 6"X4" REDUCER NOTE 17 Zero degree performed to confirm no counterbore exists.

R-A R01.11 2FW-11-23 2FW87CA-6" 13R-01 NOTE 09 100 VOL-E UT-45 NRI R01.18 TEE-PIPE NOTE 17 Zero degree performed to confirm no counterbore exists.

R-A R01.11 2FW-11-24 2FW87CA-6" 13R-01 NOTE 09 100 VOL-E UT-45 NRI R01.18 PIPE-PIPE NOTE 17 Zero dearee performed to confirm no counterbore exists.

Page 3-7

Exel e;n Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)

SectionMX*I ComnonentID . .Line Number Relief- T! n 'bode Required jActual .Results;

'Cat. Descript*o* Requests Notes

.:...ra. Ex,# E.m<

Comments~ki>& Kx R-A R01.20 2RC-17-06 2RC24AA-4" 13R-01 NOTE 17 100 VOL-E UT-45 NRI PIPE - ELBOW UT-60 UT-70 Weld was stamped with incorrect weld number during initial construction, reference IR 1205964.

R-A R01.20 2RC-17-07 2RC24AA-4" 13R-01 NOTE 17 100 VOL-E UT-45 NRI ELBOW - PIPE UT-60 UT-70 Weld was stamped with incorrect weld number during initial construction, reference IR 1205964.

R-A R01.20 2RC-20-02 2RC22AD-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.20 2RC-20-03 2RC22AD-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.20 2RC-20-04 2RC22AD-1.5" 1314-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.20 2RC-20-05 2RC22AD-1.5" 1311-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.20 2RC-20-36 2RC22AD-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.20 2RC-20-37 2RC22AD-1.5" 1313-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.20 2RC-20-38 2RC22AD-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.20 2RC-20-39 2RC22AD-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.20 2RC-20-40 2RC22AD-1.5" 1311-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2RC-29-11 2RC16AC-2" 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 2RC8038C PIPE R-A R01.11 2RC-29-12 2RC16AC-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2RC-29-13 2 RC 16AC-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2RC-29-14 2RC16AC-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2RC-29-15 2RC16AC-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2RC-29-16 2RC16AC-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - BRANCH CONNECT.

R-A R01.20 2RC-30-11 2RC13AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW Page 3-8

Exekon-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)

Section Xl.' Component ID Line Number Cat. Description lRelief Requests<i.Technical INotes !Code¶ Required. lExamv Coverage. l~xm 'Actual " i~ets~

Comments;:.

R-A R01.20 2RC-30-12 2RC13AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.20 2RC-30-13 2RC13AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - TEE R-A R01.20 2RC-30-14 2RC13AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - 2"X.75" REEDUCER R-A R01.20 2RC-30-15 2RC13AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - PIPE R-A R01.20 2RC-30-16 2RC13AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - VALVE 21RC8040B R-A R01.20 2RC-30-18 2RC13AC-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.20 2RC-30-19 2RC13AC-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.20 2RC-30-20 2RC13AC-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - TEE R-A R01.20 2RC-30-21 2RC13AC-2" 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - 2"X.75" REEDUCER R-A R01.20 2RC-30-22 2RCl 3AC-2" 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - PIPE R-A R01.11 2RC-31-01 2RC14AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI BRANCH CONN ECTION - PIPE R-A R01.11 2RC-31-02 2RC14AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2RC-31-03 2RC14AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2RC-31-04 2RC14AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2RC-31-05 2RC14AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2RC-31-06 2RC14AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2RC-31-07 2RC14AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2RC-31-08 2RC14AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - VALVE 21RC8039B R-A R01.11 2RC-31-09 2RC14AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 2RC8039 B - PIPE R-A R01.11 2RC-31-09A.01 2RC14AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - TEE Page 3-9

Exek n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)

SectionX1" Component:lD: .. Lirne Number Relief tTechnhiical, Code Required c.A Itul lResults Ctat. Description Requests 'Notes" Ccoverage: Exam, , :

.Exam Commets.

R-A R01.11 2RC-31-09B.01 2RC14AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - PIPE R-A R01.11 2RC-31-09C.01 2RC86AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - 2"X1" REDUCER R-A R01.11 2RC-31-10 2RC14AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - TEE R-A R01.11 2RC-31-11 2RC15AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - 2"X.75" REDUCER R-A R01.11 2RC-31-12.01 2RC14AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - PIPE R-A R01.20 2RC-31-14 2RC26A-2" 13R-01 NOTE 17 VT-2 VT-2 NRI BRANCH CONNECTION - PIPE R-A R01.20 2RC-31-15 2RC26A-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - VALVE 2RC8057 R-A R01.11 2RC-37-07A.01 2RC14AD-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - TEE R-A R01.11 2RC-37-07B.01 2RC14AD-2" 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - PIPE R-A R01.11 2RC-37-07C.01 2RC14AD-2" 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - 2"X1" REDUCER R-A R01.11 2RC-37-08 2RC14AD-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - TEE R-A R01.11 2RC-37-09 2RC14AD-2" 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - 2"X.75" REDUCER R-A R01.11 2RC-37-10 2RC14AD-2" 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - PIPE R-A R01.11 2RC-37-11 2RC14AD-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - VALVE 2RC8037D R-A R01.11 2RC-41-03 2RC16AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 2RC8038A - PIPE R-A R01.11 2RC-41-04 2RC16AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2RC-41-05 2RC1 6AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2RC-41-06 2RC16AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2RC-41-07 2RC16AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2RC-41-08 2RC16AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - BRANCH CONNECT.

Page 3-10

Exel en.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)

Section._XL*Component IO  : lme-Number Relief- TechnicaiwlCodeý-: IRequired. jActuaV,,-l Results':l Catý" t Descption - . Requests-:- Notes Coverage Exam Exam" Comments R-A R01.11 2RC-41-11 2RC16AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 2RC8038B - PIPE R-A R01.11 2RC-41-12 2RC16AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2RC-41-13 2RC16AB-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE NA RG 1.14 2RCP-01-FLYWHEEL 2RCP01B NOTE 18 SUR PT NRI (PMP B)

RCP PUMP "B" FLYWHEEL Was to be rescheduled from A2R15 to A2R19 per Service Request 00070948, but ten-year overhaul of RCP motor was performed under WO# 1417672, credit predefine WO# 971109.

N-722 B15.090 2RV-01-022 N-722 2RC01R NOTE 14 Visual, VE Visual, NRI VE NOZZLE - SAFE END (22 DEG.) NOTE 17 MRP-139 N-722 B15.095 2RV-01-023 N-722 2RC01R NOTE 14 Visual, VE Visual, NRI VE SAFE END - NOZZLE (67 DEG.) NOTE 17 MRP-139 N-722 B15.095 2RV-01-024 N-722 2RC01R NOTE 14 Visual, VE Visual, NRI VE SAFE END - NOZZLE (113 DEG.) NOTE 17 MRP-139 Examination not credited for Code Case N-722 credit, all RPV nozzle-to-safe end welds were accessible (mirror insulation removed) for MSIP project dimension measurements and were examined by Visual, VE method.

N-722 B15.090 2RV-01-025 N-722 2RC01R NOTE 14 Visual, VE Visual, NRI VE NOZZLE - SAFE END (158 DEG.) NOTE 17 MRP-139 N-722 B15.090 2RV-01-026 N-722 2RC01R NOTE 14 Visual, VE Visual, NRI VE NOZZLE - SAFE END (202 DEG.) NOTE 17 MRP-139 N-722 B15.095 2RV-01-027 N-722 2RC01R NOTE 14 Visual, VE Visual, NRI VE SAFE END - NOZZLE (247 DEG.) NOTE 17 MRP-139 Page 3-11

Exek n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)

Section Xi,, ComponentID , Line Number " Relief Technical Code Required jActual Results CAt. Descripion Requests Notes Coverage* Exam >;< Exam;  :

Comments, ..

N-722 B15.095 2RV-01-028 N-722 2RC01R NOTE 14 Visual, VE Visual, NRI VE SAFE END - NOZZLE (293 DEG.) NOTE 17 MRP-139 Examination not credited for Code Case N-722 credit, all RPV nozzle-to-safe end welds were accessible (mirror insulation removed) for MSIP project dimension measurements and were examined by Visual, VE method.

N-722 B15.090 2RV-01-029 N-722 2RC01R NOTE 14 Visual, VE Visual, NRI VE NOZZLE - SAFE END (338 DEG.) NOTE 17 MRP-139 B-N-1 B13.10 2RV-01-RX INTERIOR 2RC01R VT-3 VT-3 NRI ACCESSIBLE INTERIOR SURFACES Examination completed using underwater camera and remote monitor.

N-722 B15.080 2RV-02-LOWER HEAD 2RC01R 13R-04 Visual, VE Visual, 10 VE N-722 LOWER HEAD SURFACE AND PENETRATIONS Bare metal visual in accordance with Code Case N-722. Stains from previous leaks through cavity boot seal are evident. Corrosion noted, but no significant wastage. Most significant staining at Penetrations 1, 4, 7, 18, 33, and 45.

NA 1-600 2RV-03-HEAD 2RC01 R 13R-07 95 Visual Visual, 10 VE N-729-1 REACTOR HEAD SURFACE VOL VOL NRI Volumetric and visual examinations required by Code Case N-729-1.

N-722 B15.120 2SG-01-2RC01BA DRAIN Visual, VE Visual, NRI DRAIN LINE VE STEAM GENERATOR BOWL DRAIN LINE Visual, VE examination of steam generator bowl drain inconel weld.

B-Q B16.20 2SG-01-2RC01BA 2RC01BA VOL ET IND TUBING STEAM GENERATOR TUBING Based on eddy current test results the following tubes (Row/Column) were plugged:

41/36, 45/64, 41/93, 10/50, 11/50, 10/51, 11/51, 30/84, 31/84, 30/85, 31/85, and 8/86 B-G-2 B07.30 2SG-01-B1 2RC01BA VT-1 VT-1 NRI 9A PRIMARY MANWAY (16 BOLTS)

B-G-2 B07.30 2SG-01-B2 2RC01BA VT-1 VT-1 NRI 9B PRIMARY MANWAY (16 BOLTS)

N-722 B15.120 2SG-02-2RC01BB DRAIN Visual, VE Visual, NRI DRAIN LINE VE STEAM GENERATOR BOWL DRAIN LINE CONNECTION Visual, VE examination of steam generator bowl drain inconel weld.

B-Q B16.20 2SG-02-2RC01BB 2RC01BB VOL ET IND TUBING STEAM GENERATOR TUBING Based on eddy current test results the following tubes (Row/Column) were plugged:

15/7, 6/8, 7/22, 32/56, 24/68, 32/70, and 29/95.

Page 3-12

Exei n-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)

Sectioni j(XI Component iD l 1LIne Number  : Relleftý'- 1rTechnicai jCode Reluired ActuaM k "lRes6Its*

a Descraption, - , Requests Notes= Covrage Exam *E xam N-722 B15.120 2SG-03-2RC01BC DRAIN Visual, VE Visual, NRI DRAIN LINE VE STEAM GENERATOR BOWL DRAIN LINE Visual, VE examination of steam generator bowl drain inconel weld.

B-Q B16.20 2SG-03-2RC01BC 2RC01BC VOL ET IND TUBING STEAM GENERATOR TUBING Based on eddy current test results the following tubes (Row/Column) were plugged:

43/41 and 49/65 C-A C01.10 2SG-03-SGC-05 2RC01BC NOTE 17 100 VOL UT-45 NRI LOWER SHELL (B) - TRANSIT CONE C-A C01.10 2SG-03-SGC-06 2RC01BC NOTE 17 100 VOL UT-45 NRI TRANSIT CONE - UPPER SHELL (A)

C-B C02.21 2SG-03-SGN-13 2RC01BC NOTE 17 100 SUR MT NRI 6" NOZZLE - UPPER SHELL (A) 100 VOL UT-0 UT-45 N-722 B15.120 2SG-04-2RC01 BD DRAIN Visual, VE Visual, NRI DRAIN LINE VE STEAM GENERATOR BOWL DRAIN LINE CONNECTION Visual, VE examination of steam generator bowl drain inconel weld.

B-Q B16.20 2SG-04-2RC01BD 2RC01BD VOL ET IND TUBING STEAM GENERATOR TUBING Based on eddy current test results the following tubes (Row/Column) were plugged:

7/61, 17/72, 44/73, 47/74, 47/75, 13/76, 43/86, 49/63, and 2/35 Page 3-13

Exeiln.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Residual Heat Removal System (RH) setn xilýX nComponent ID. Line:Number. :p Relief . JTechnical Code iRequired Actual Results Cat. , Description Requests Notes Cove*rage Exam Exam lComments NA ECCS 2RH-03-28 2RH03AA-8" NOTE 19 VOL UT-45 RI TEE - PIPE UT-60 UT-70 During augmented volumetric examination of RHR mixing tee for thermal fatigue/crazed cracking per MRP-192 an indication in the tee-to-pipe weld (nominal wall thickness of 0.322") was detected with 45 degree shear wave and confirmed by 60 degree shear wave. Through-wall sizing of the indication was performed using the Absolute Arrival Time Technique (AATT) which used 45, 60, and 70 degree shear wave scans (reference Data Sheet A2R15-UT-029). The flaw sized as 0.70" long with a remaining ligament of 0.185". IR 1208120 was initiated to document the flaw which was evaluated as acceptable for continued service under EC 384283. Although weld is not subject to ASME Section XI volumetric examinations due to wall thickness, weld will be examined during the next inspection period in accordance with IWC-2420(b) as tracked by ATI 1208120-02.

R-A R01.20 2RH-04-55 2RH01CA-16" 13R-01 NOTE 17 100 VOL-E UT-0 NRI PIPE - ELBOW UT-45 Zero degree performed to confirm no counterbore present. ID geometry observed below recordable levels.

C-A C01.10 2RHX-01-2RHEC-01 (A 2RH02AA NOTE 17 Visual VT-2 NRI HX)

FLANGE - HX SHELL NOTE 30 N-706 Periodic testing per Code Case N-706 completed/acceptable on 5/6/2011.

C-A C01.10 2RHX-01-2RHEC-01 (B 2RH02AB NOTE 17 Visual VT-2 NRI HX)

FLANGE - HX SHELL NOTE 30 N-706 Periodic testing per Code Case N-706 completed/acceptable on 5/6/2011.

C-A C01.20 2RHX-01-2RHEC-02 (A 2RH02AA N-706 NOTE 17 Visual VT-2 NRI HX)

HX SHELL - HEAD NOTE 30 Periodic testing per Code Case N-706 completed/acceptable on 5/6/2011.

C-A C01.20 2RHX-01-2RHEC-02 (B 2RH02AB N-706 NOTE 17 Visual VT-2 NRI HX)

HX SHELL - HEAD NOTE 30 Periodic testing per Code Case N-706 completed/acceptable on 5/6/2011.

C-B C02.22 2RHX-01-2RHXN1 (A 2RH02AA N-706 NOTE 17 Visual VT-2 NRI HX) (NIR) 2A RH HX SHELL - NOZZLE INNER RADIUS NOTE 30 Periodic testing per Code Case N-706 completed/acceptable on 5/6/2011.

C-B C02.21 2RHX-01-2RHXN1 (B HX) 2RH02AB N-706 NOTE 17 Visual VT-2 NRI 2B RH HX SHELL - NOZZLE NOTE 30 Periodic testing per Code Case N-706 completed/acceptable on 5/6/2011.

C-B C02.22 2RHX-01-2RHXN1 (B 2RH02AB N-706 NOTE 17 Visual VT-2 NRI HX) (NIR) 2B RH HX SHELL - NOZZLE INNER RADIUS NOTE 30 Periodic testing per Code Case N-706 completed/acceptable on 5/6/2011.

C-B C02.21 2RHX-01-2RHXN2 (A HX) 2RH02AA N-706 NOTE 17 Visual VT-2 NRI NOZZLE - 2A RH HX SHELL NOTE 30 Periodic testing per Code Case N-706 completed/acceptable on 5/6/2011.

Page 3-14

Exek nt Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Residual Heat Removal System (RH)

  • SeactlonXl Component 1D' Line Number Relief Technical Code. Required Actual Results C Description-: Requests Notes.. Coverage Exam Exam comments C-B C02.22 2RHX-01-2RHXN2 (A 2RH02AA N-706 NOTE 17 Visual VT-2 NRI HX) (NIR)

NOZZLE - 2A RH HX SHELL NOZZLE INNER NOTE 30 RADIUS Periodic testing per Code Case N-706 completed/acceptable on 5/6/2011.

C-B C02.22 2RHX-01-2RHXN2 (B 2RH02AB N-706 NOTE 17 Visual VT-2 NRI HX) (NIR)

NOZZLE - 2B RH HX SHELL NOZZLE INNER NOTE 30 RADIUS Periodic testing per Code Case N-706 completed/acceptable on 5/6/2011.

Page 3-15

Exek n~.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RY)

Section Xl.Component ID . Line: NUmber  : Relief..,: Technical. Code ... *Requireij Actuai Resultls Cat".s.c.iption R:qu'estsý'Notes Coveragec Ea

' Exam.".

" l'".... """

Comments .... .... . .".

B-D B03.110 2PZR-01-N2 2RY01S NOTE 17 88.5 VOL UT-0 NRI SPRAY NOZZLE - PRESSURIZER UT-45 Coverage limited due to nozzle configuration. Relief request required, tracked under ATI 894565-02.

B-D B03.120 2PZR-01-N2 (NIR) 2RY01S 10CFR NOTE 13 100 IRS UT-24 NRI SPRAY NOZZLE - PRESSURIZER INNER RADIUS NOTE 17 UT-60 UT-65 UT-70 Scans included 24 degree (=/- 90 degree skew), 65 degree (+/- 18 degree skew), 60 degree shear wave, and 70 degree shear wave.

B-D B03.110 2PZR-01-N3 2RY01S NOTE 17 88.5 VOL UT-0 NRI PRESSURIZER - RELIEF NOZZLE UT-45 Coverage limited due to nozzle configuration. Relief request required, tracked under ATI 894565-02.

B-D B03.120 2PZR-01-N3 (NIR) 2RY01S 10CFR NOTE 13 100 IRS UT-24 NRI PRESSURIZER - RELIEF NOZZLE INNER RADIUS NOTE 17 UT-60 UT-65 UT-70 Scans included 24 degree (=/- 90 degree skew), 65 degree (+/- 18 degree skew), 60 degree shear wave, and 70 degree shear wave.

R-A R01.15 2PZR-01-SE-01 2RY11A-14" 13R-01 NOTE 14 VOL-E UT-45L NRI R01.11 PZR SURGE NOZZLE - SAFE END 13R-06 NOTE 17 MRP-139 Overlay UT per Second Interval Relief Request 12R-48 and Section XI Appendix 0. Augmented exam credit only.

R-A R01.15 2PZR-01-SE-02 2RY03AA-6" 13R-01 NOTE 14 100 VOL-E UT-40L NRI MRP- PZR SAFETY NOZZLE - SAFE END 13R-06 NOTE 17 UT-45L 139 Overlay UT per Second Interval Relief Request 12R-48 and Section XI Appendix Q. Augmented exam credit only.

R-A R01.15 2PZR-01-SE-03 2RY03AB-6" 13R-01 NOTE 14 99.56 VOL-E UT-0 NRI MRP- PZR SAFETY NOZZLE - SAFE END 13R-06 NOTE 17 UT-40L 139 UT-45L Overlay UT per Second Interval Relief Request 12R-48 and Section XI Appendix 0. Coverage for circumferential scan is 99.56%,

coverage for axial scan is 99.53%. Coverage was limited due to shadow effects from laminar flaw. Augmented exam credit only.

R-A R01.15 2PZR-01-SE-04 2RY03AC-6" 13R-01 NOTE 14 100 VOL UT-40L NRI MRP- PZR SAFETY NOZZLE - SAFE END 13R-06 NOTE 17 UT-45L 139 Overlay UT per Second Interval Relief Request 12R-48 and Section Xl Appendix Q. Augmented exam credit only.

R-A R01.15 2PZR-01-SE-05 2RY01B-4" 13R-01 NOTE 14 100 VOL UT-40L NRI R01.11 SAFE END - PZR SPRAY NOZZLE 13R-06 NOTE 17 UT-43L MRP- UT-45L 139 Overlay UT per Second Interval Relief Request 12R-48 and Section XI Appendix Q.Section XI and augmented exam credit.

R-A R01.15 2PZR-01-SE-06 2RY02A-6" 13R-01 NOTE 14 100 VOL UT-40L NRI MRP- PZR RELIEF NOZZLE - SAFE END 13R-06 NOTE 17 UT-45L 139 Overlay UT per Second Interval Relief Request 12R-48 and Section Xl Appendix Q. Section Xl and augmented exam credit.

R-A R01.11 2RC-05-01 2RY11A-14" 13R-01 NOTE 17 100 VOL-E UT-45L NRI PZR SAFE END - PIPE Overlay UT per Second Interval Relief Request 12R-48 and Section Xl Appendix 0. Augmented exam credit only.

Page 3-16

Exektnt Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RY)

Section Xl lComponent ID Line Number Relief Technical Code-::... Required Actual. Results.

Cat.,: D?escription Requests Notes Coverage, Exam Exam I Comments .

R-A R01.11 2RC-05-03 2RY11A-14" 13R-01 NOTE 17 100 VOL-E UT-45 NRI PIPE - PIPE Examination coverage increased to meet RI-IS1 requirements. Previously recorded geometry observed below recordable levels.

R-A R01.11 2RC-05-04 2RY11A-14" 13R-01 NOTE 17 100 VOL-E UT-45 NRI PIPE - PIPE Examination coverage increased to meet RI-ISI requirements. Previously recorded geometry observed below recordable levels.

R-A R01.11 2RC-05-06 2RY11A-14" 13R-01 NOTE 17 100 VOL-E UT-45 NRI PIPE - PIPE Previously recorded geometry observed below recordable levels. Examination coverage increased to meet RI-ISI requirements.

R-A R01.11 2RC-16-01 2RY01C-4" 13R-01 NOTE 17 94.4 VOL-E UT-40L NRI SAFE END - 6"X4" REDUCER UT-43L UT-45L Overlay UT per Second Interval Relief Request 12R-48 and Section XI Appendix Q. Examination coverage for axial scan was 94.4%,

circumferential examination coverage was 100%. Augmented exam credit only.

R-A R01.11 2RC-16-02 2RY01B-6" 13R-01 NOTE 17 100 VOL-E UT-45 NRI 6"X4" REDUCER - ELBOW Examination coverage increased to meet RI-ISI requirements.

R-A R01.11 2RC-16-03 2RY01B-6" 13R-01 NOTE 17 100 VOL-E UT-45 NRI ELBOW - PIPE Previously recorded geometry observed below recordable levels. Examination coverage increased to meet RI-ISI requirements.

R-A R01.11 2RC-16-04 2RY01B-6" 13R-01 NOTE 17 100 VOL-E UT-45 NRI PIPE - ELBOW Examination coverage increased to meet RI-ISI requirements. Previously recorded geometry observed below recordable levels.

R-A R01.20 2RC-32-01 2RY03AA-6" 13R-01 NOTE 17 100 VOL-E UT-40L NRI SAFE END - ELBOW UT-45L Overlay UT per Second Interval Relief Request 12R-48 and Section XI Appendix 0. Augmented exam credit only.

R-A R01.20 2RC-32-07 2RY03AB-6" 13R-01 NOTE 17 100 VOL-E UT-40L NRI SAFE END - ELBOW UT-45L Overlay UT per Second Interval Relief Request 12R-48 and Section XI Appendix Q. Augmented exam credit only.

R-A R01.20 2RC-32-13 2RY03AC-6" 13R-01 NOTE 17 100 VOL-E UT-40L NRI SAFE END - ELBOW UT-45L Overlay UT per Second Interval Relief Request 12R-48 and Section XI Appendix 0. Augmented exam credit only.

R-A R01.20 2RC-35-01 2RY02A-6" 13R-01 NOTE 17 100 VOL-E UT-40L NRI SAFE END - ELBOW UT-45L Overlay UT per Second Interval Relief Request 12R-48 and Section XI Appendix Q. Section X1 and augmented exam credit.

B-G-2 B07.50 2SI-23-Bl 2RY76A-2" VT-1 VT-1 NRI FLANGED CONNECTION (8 STUDS)

Connection was examined prior to final reassembly under outage PM WO 1283152.

Page 3-17

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Safety Injection System (SI)

Section)1 XIc~omiponent i.m Line* Number. Relief Trechnical Code <* Re0uired Actual Results.

cat. Description .:::::A:*':*,

.;** *,::...:... ;.. .*ii.*.* i.l ~ e t ; Notes IRequests ovrg Exm Eiam -

Comments R-A R01.11 2SI-20-04 2Sl08JC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2SI-20-05 2SI08JC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2SI-20-06 2Sl08JC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2SI-20-07 2SI08JC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2SI-20-09 2SI08JC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - FLANGE R-A R01.11 2SI-20-10 2SI08JC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2SI-20-11 2SI08JC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2SI-20-12 2SI08JC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 2SI8810( >PIPE R-A R01.11 2SI-20-13 2SI08JC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - VALVE 2*31881 00

-PSI8810C CIPE R-A R01.11 2SI-20-14 2SI08JC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI 2"X1.5" REDUCEER - PIPE R-A R01.11 2SI-20-15 2SI08HC-2" 13R-01 NOTE 17 VT-2 VT-2 NRI COUPLING - 2"X11/ 2" REDUCER R-A R01.1 1 2SI-20-20 2SI08HC-2" 13R-01 NOTE 17 VT-2 VT-2 NRI 2"X1.5" REDUCER - COUPLING R-A R01.1 1 2SI-20-21 2SI08GC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - 2"X11/2" REDUCER R-A R01.1 1 2SI-20-22 2SI08GC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2SI-20-23 2SI08GC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2S1-20-24 2SI08GC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2SI-20-25 2SI08GC-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.1 1 2SI-20-27 2SI08GD-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI COUPLING - PIPE R-A R01.11 2SI-20-28 2SI08GD-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2SI-20-29 2SI08GD-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE Page 3-18

Exekon Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Safety Injection System (SI)

Section XI* .Componerit ID . Line Numbir JRelief. Technical. Code Required iActual. Results

- - slr....r oi ..  ; Requests- Notes Covrageb Exam ' Exam Comments~

R-A R01.11 2SI-20-30 2SI08GD-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 2SI-20-31 2SI08GD-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 2SI-20-32 2SI08GD-1.5" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - 2"Xl 1/2" REDUCER R-A R01.20 2SI-24-79 2SI06BB-24" 13R-01 NOTE 17 100 VOL-E UT-45 NRI ELBOW - 24"X16" REDUCER Zero degree performed to verify no counterbore exists.

Page 3-19

Exeken.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.2 Detailed Third Interval Inservice Component Support Table SYSTEM: Auxiliary Feedwater System (AF)

Section XlIS Identier - Line Numbe "Rellef .Technical o Actual lReRultsw,.?

cat. item~ iDescrito Requests Notes~ Examn

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

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

~ ".... ....... :- ".. ... . .. *,,:**:***i**::, ,,

F-A F01.20 2AF04031X 2AF02DB-4" VT-3 NRI Seismic This examination was added during the 3rd Interval ISI Program Update.

F-A F01.20 2AF05067X 2AF02DC-4" VT-3 NRI Seismic This examination was added during the 3rd Interval ISI Program Update.

F-A F01.20 2AF06044G 2AF02EA-4" VT-3 NRI Guide This examination was added during the 3rd Interval ISI Program Update.

F-A F01.20 2AF06046G 2AF02DA-4" VT-3 NRI Guide This examination was added during the 3rd Interval ISI Program Update.

Page 3-20

Exek n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.2 Detailed Third Interval Inservice Component Support Table SYSTEM: Chemical & Volume Control System (CV)

Section. X:: !S! Iden~tifIeY Line Number s Relief Techn.ica,.I Exa R Cat. Itemoclta .. Req.. s. . NotesI ! Exam, IcResult Commentsj, F-A F01.10 2RY06116V 2CV45B-2" VT-3 NRI (1) Variable Spring Can F-A F01.10 2RY06129V 2CV45B-2" VT-3 NRI (1) Variable Spring Can Page 3-21

Exel n, Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.2 Detailed Third Interval Inservice Component Support Table SYSTEM: Feedwater System (FW)

Section XI!i** idnii. . ne Number .Relief, ... hnil...:.. Actual Results.

Cat.- Item *Description . Requests Notes.. Exam 11 F-A F01.20 2AF07030X 2FW81AD-6" VT-3 NRI Strut RE-INSPECTION OF SUPPORT WITH RI FROM A2R14 F-A F01.20 2FW05007R 2FW03DD-16" VT-3 NRI Box F-A F01.20 2FW08022X 2FW87CC-6" VT-3 NRI Strut F-A F01.20 2FW09002C 2FW87CD-6" VT-3 NRI (1) Constant Spring Can Page 3-22

Exek n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.2 Detailed Third Interval Inservice Component Support Table SYSTEM: Main Steam System (MS)

SectionzXl . ISI.l identifier* .Line Number . .Rl 6ef " Technical6 Atual Resuits Cat. Item ... Descripion Requests :Notes Exam; Comments F-A F01.20 2MS01205X 2MS07AA-28" VT-3 NRI Strut, integrally attached to pipe F-A F01.20 2MS01221R 2MS07AB-28" VT-3 NRI Slide Plate F-A F01.20 2MS08006R 2MS01AD-30.25" VT-3 NRI Steel F-A F01.20 2PC-085A 2MS01 BB-32.75" VT-3 NRI Anchor, Flued Head VT-3 NRI 02/21 EXAM OUTSIDE CONTAINMENT, 03/31 EXAM INSIDE CONTAINMENT Page 3-23

I.....;x-e-

........ J.ln.-

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.2 Detailed Third Interval Inservice Component Support Table SYSTEM: Reactor Coolant System (RC)

Section Xl.*- 15 Infrine Number  : R11l4f4W Tihn*ical: 'Atuai(%S Results Cat.,: Itetnw, Depscription. Request Notes Exam~4 Comments. .

F-A F01.40 2RC01PC 2RC01PC VT-3 NRI C RCP F-A F01.40 2RC01R 2RC01R VT-3 10 REACTOR Performed VT-3 in conjunction with N-722 examinations of RPV safe end-to-nozzle DM welds (A Hot Leg, B Cold Leg, C Hot Leg, and D Cold Leg). Sand Box Covers and mirror insulation were removed for access to component supports in support of MSIP planning walkdowns.

Page 3-24

Exekin, Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.2 Detailed Third Interval Inservice Component Support Table SYSTEM: Residual Heat Removal System (RH)

Sectiont XI ietfrLine"Numble I**1"t Relief Technical ýArct.a Resultsi Cat. I.tem IDescription .Requests- Notes Exam.

Comimentsr.-,

F-A F01.10 2RH02053R 2RHO1AA-12" VT-3 NRI Strut F-A F01.10 2RH02062R 2RHO1AB-12" VT-3 NRI Strut F-A F01.10 2RH02065R 2RHO01AA-112" VT-3 NRI Box F-A F01.10 2RH02074X 2RHO1AB-12" VT-3 NRI Strut F-A F01.20 2RH07004R 2RH02AA-8" VT-3 NRI Slide Plate Remote exam (12' away).

F-A F01.20 2RH08002R 2RH02AB-8" VT-3 NRI Box Remote exam (12' away).

F-A F01.20 2SI18002R 2RH03AA-8" VT-3 NRI Rod Page 3-25

Exeekn.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.2 Detailed Third Interval Inservice Component Support Table SYSTEM: Reactor Coolant System (RY)

Section XL:.: IS .Identifiert. Line Number Re.ief: Technical Actual Reslt.

Cat.",. Item 1.DecrIption " *;eiiuests* Notes Exam cotmments~

F-A F01.10 2RY05009V 2RY1 1A-14" VT-3 NRI (1) Variable Spring Can F-A F01.10 2RY06021C 2RY01B-6" VT-3 NRI (2) Constant Spring Cans F-A F01.10 2RY06022G 2RY01B-6" VT-3 NRI (2) Struts F-A F01.10 2RY06023X 2RYO1 B-6" VT-3 NRI Strut F-A F01.10 2RY06024V 2RY01B-6" VT-3 NRI (1) Variable Spring Can F-A F01.10 2RY06028X 2RY01B-6" VT-3 NRI Box F-A F01.10 2RY06036X 2RY01B-6" VT-3 NRI Strut Page 3-26

Exek n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.2 Detailed Third Interval Inservice Component Support Table SYSTEM: Safety Injection System (SI)

Section Xl JISI Identifier !Line Number. 7 R~elief Kr~Technical~ Actual slt Cat. Item *.Descrlpt.on Requets Notes ExamK Comments~

F-A F01.10 2RH02017R 2SI04D-8" VT-3 NRI Strut F-A F01.10 2RHO202OR 2SI04D-8" VT-3 NRI Strut F-A F01.10 2RHO2021R 2SI04D-8" VT-3 NRI Box F-A F01.20 2RHO2026R 2SI04C-8" VT-3 NRI Strut F-A F01.20 2RHO2031V 2SI04B-12" VT-3 NRI (1) Variable Spring Can F-A F01.10 2RH02064V 2SIA4B-8" VT-3 NRI (1) Variable Spring Can F-A F01.10 2SHl1029X 2SI03DA-2" VT-3 NRI Box F-A F01.20 2SI18027R 2SI04A-12" VT-3 NRI Slide Plate F-A F01.20 2SI18039R 2SI05AB-8" VT-3 NRI Box F-A F01.10 2SI20016X 2SI08JC-1.5" VT-3 NRI Strut F-A F01.10 2SI20045X 2SI08JC-1.5" VT-3 NRI Strut F-A F01.10 2SI20049R 2SI08JC-1.5" VT-3 NRI Strut F-A F01.10 2SI21008R 2SI08JC-1.5" VT-3 NRI Box F-A F01.10 2SI24003G 2SI08JA-1.5" VT-3. NRI U-Bolt F-A F01.10 2SI24004G 2SI08JA-1.5" VT-3 NRI U-Bolt F-A F01.10 2SI24005G 2SI08JA-1.5" VT-3 NRI U-Bolt Page 3-27

Exejon.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.2 Detailed Third Interval Inservice Component Support Table SYSTEM: Essential Service Water System (SX)

SectionoXl, 1.S. Identifier . , LineNumber Relief Technical Actui . te',ult.

Cat. Itemem . Description. . . . . . . ,. .. .. t .. . ..m Comments3/4 F-A F01.20 2SX06001R 2SX06BA-16" VT-3 NRI Rod Examine upper attachment from 6' away.

F-A F01.20 2SX06030G 2SX08BA-10" VT-3 NRI Box F-A F01.20 2SX07099A 2SX08AD-10" VT-3 NRI Anchor, integrally attached to pipe F-A F01.20 2SX08001R 2SX07FA-16" VT-3 NRI Strut F-A F01.20 2SX08002G 2SX07FA-16" VT-3 NRI Box Remote exam (12' away).

F-A F01.20 2SX08007X 2SX07EA-14" VT-3 NRI Strut Remote exam (12' away).

F-A F01.20 2SX08008X 2SX07EA-14" VT-3 NRI Strut F-A F01.20 2SX08024X 2SX07CA-10" VT-3 NRI Strut F-A F01.20 2SX08026X 2SX07CA-10" VT-3 NRI Box Remote exam (6' away).

F-A F01.20 2SX09006G 2SX07EB-14" VT-3 NRI Box F-A F01.20 2SX09021R 2SX09CB-10" VT-3 NRI Box Remote Exam from above and below. Max. 12' away.

F-A F01.20 2SX09034G 2SX09CD-10" VT-3 NRI Box F-A F01.20 2SX09112X 2SX07CD-10" VT-3 NRI Strut F-A F01.20 2SX09118X 2SX07CB-10" VT-3 NRI Strut Page 3-28

Exet.n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Containment Spray System (CS)

StionXl ISI: Identifier: ' Line Number Relief Technical.:. Actuai'. Results Cat. :tem,'

Description:

. .. ,... RequestsI Notes Exam.

Comments .':, >. .,:.:.

F-A F01.20 2CS03022S 2CS02AB-10" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2CS03106S 2CS02AB-10" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-29

IExelein-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Chemical & Volume Control System (CV)

Section XI 1"ISldenti.e*tier Line Number .Relief Technica v Actu'ad Results Cat. Item Description'I$* :equests Notes? lxa r Commentse>, . ,

NA NA 2CV02005S 2CV10CB-3" NOTE 01 VT-3 PASS Snubber FT MARG INITIAL SAMPLE DTPG 2-1, SERIAL NUMBER 12024 WAS REPLACED WITH SERIAL NUMBER 8014 DUE TO IDENTIFIED DEGRADATION DURING THE DRAG TEST IN COMPRESSION. REFERENCE ISSUE REPORT 1206126.

NA NA 2CV03002S 2CV10CA-3" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2CV06010S 2CVB7A-3" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 NA NA 2CV07032S 2CV01 E-3" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 NA NA 2CV07033S 2CV01 E-3' NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 NA NA 2CV07069S 2CV01 E-3" NOTE 01 VT-3 NRI Snubber FT PASS TESTED FOR SERVICE LIFE MONITORING NA NA 2CV24024S 2CV43BB-2" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2CV25009S 2CVA7AA-2" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 NA NA 2CV31007S 2CV15DA-.75" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 NA NA 2CV31 011S 2CV15DA-.75" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 NA NA 2CV40005S 2CV14EC-2" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 F-A F01.10 2RY06121S 2CV45B-2" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-30

Exe kn.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Feedwater System (FW)

-SectionXl Identifier Line Number :Reief Techn ica A it"i Results1 Cat. *::* ........ .: Reques Notes Exam Cb'mmentsQ F-A F01.20 2FW02016S 2FW03DA-16" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.20 2FW03010S 2FW03DB-16" NOTE 01 VT-3 PASS Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.20 2FW03015S 2FW03DB-16" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.20 2FW04015S 2FW03DC-16" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2FW04017S 2FW03DC-16" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2FW05011AS 2FW03DD-16" NOTE 01 VT-3 NRI Snubber FT PASS TESTED FOR SERVICE LIFE MONITORING F-A F01.20 2FW05011BS 2FW03DD-16" NOTE 01 VT-3 NRI Snubber FT MARG TESTED FOR SERVICE LIFE MONITORING. Snubber With S.N. 7036 Is Being Replaced During A2R15 Due To Marginal Test Results Observed During A2R14 (Reference IR Number 985759 and W/O 01299417.

F-A F01.20 2FW05020S 2FW03DD-16" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2FW05022S 2FW03DD-16" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-31

Exet n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Main Steam System (MS)

Section Xl . St. Idortifiene  ; Line Number,. Relief , Technical .A:tual B.esults Cat. Item.. "Description  :",; Requests N .

Comments.

F-A F01.20 2MS01074AS 2MSO7AA-28" NOTE 01 VT-3 NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTID / CODE CASE OMN-13 F-A F01.20 2MS01074BS 2MS07AA-28" NOTE 01 VT-3 NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2MS01097S 2MS07AB-28" NOTE 01 VT-3 NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2MS05007AS 2MS01AA-30.25" NOTE 01 VT-3 NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2MS05007BS 2MS01AA-30.25" NOTE 01 VT-3 NRI Snubber, integrally attached to pipe VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2MS06007AS 2MS01AB-32.75" NOTE 01 VT-3 NRI Snubber, integrally attached to pipe FT PASS INITIAL SAMPLE DTPG 2-3 F-A F01.20 2MS06007BS 2MS01AB-32.75" NOTE 01 VT-3 NRI Snubber, integrally attached to pipe FT PASS INITIAL SAMPLE DTPG 2-2 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-32

Exelun'.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Reactor Coolant System (RC)

Section XL ISI Identifier: - Line Number  : Relief  : Technical Atual !Results,:'

Catitm CtitmRequestsA escription Notes, xa A T Comments A F-A F01.10 2CV06014S 2RC36A-3" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2CV06016S 2RC36A-3" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.10 2CV14001S 2RC16AD-2" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.10 2CV25002S 2RC14AD-2" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-1 3 F-A F01.40 2RC01BA-A 5.G. A NOTE 01 VT-3 NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION. RESERVOIR LEVEL ACCEPTABLE.

F-A F01.40 2RC01 BA-B 5.G. A NOTE 01 VT-3 NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION. RESERVOIR LEVEL ACCEPTABLE.

F-A F01.40 2RC01BB-A S.G B NOTE 01 VT-3 NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION. RESERVOIR LEVEL ACCEPTABLE.

F-A F01.40 2RC01 BB-B S.G B NOTE 01 VT-3 NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION. RESERVOIR LEVEL ACCEPTABLE.

F-A F01.40 2RC01BC-A S.G C NOTE 01 VT-3 NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION. RESERVOIR LEVEL ACCEPTABLE.

F-A F01.40 2RC01BC-B S.G C NOTE 01 VT-3 NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION. RESERVOIR LEVEL ACCEPTABLE.

F-A F01.40 2RC01BD-A S.G D NOTE 01 VT-3 NRI Snubber STEAM GENERATOR SNUBBER VISUAL EXAMINATION. RESERVOIR LEVEL ACCEPTABLE.

F-A F01.40 2RC01BD-B S.G D NOTE 01 VT-3 NRI Snubber FT PASS Steam Generator Snubber Visual Examination and Functional Test. DTPG 2-4 F-A F01l10 2RC03007S 2RC21AC-8" NOTE 01 VT-3 PASS Snubber FT PASS INITIAL SAMPLE DTPG 2-2 Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-33

Exelkn.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Reactor Coolant System (RC)

Section XI ISIlIdentifier Line Number.. Relief TechnicalV Actual Results' Cat. Item Description . . .Requests N!Jotes,

  • am. ..

comments~<

NA NA 2RC1 7069S 2RC20AB-.75" NOTE 01 VT-3 PASS Snubber FT MARG TESTED FOR SERVICE LIFE MONITORING. Snubber Is Being Replaced During A2R15 Due To Marginal Test Results Observed During A2R14 (Reference IR Number 987527 and W/O 01299699).

F-A F01.10 2RY06104S 2RC26A-2" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.10 2RY06106S 2RC26A-2" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-34

Exek n-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Residual Heat Removal System (RH)

Se Ieer.XI". '.Line .Number"Relief Technical Atual Results Ca.Item,~ DecipnRequestsi Notes Exn< ,

Comme~nts~

F-A F01.10 2RH02013S 2RHO1AB-12" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2RH02052S 2RH01AA-12" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-35

Exe ,m.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Reactor Coolant System (RY) sectionmXl..1. Identifier Pe LnNumber Relief *Technical. "Actual . Results Ca.Item De3scription.2 Requests INotes. Exam IComments NA NA 2RC93A001S 2RY34BB-.5" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 F-A F01.10 2RY05010S 2RY11A-14" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2RY06020S 2RY01B-6" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2RY06025S 2RY01B-6" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2RY06114S 2RY18A-2" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 NA NA 2RY06125S 2RY09AB-.75" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 F-A F01.10 2RY09001S 2RY02B-3" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.10 2RY09005S 2RY02B-3" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.10 2RY09100S 2RY02B-3" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.10 2RY09101S 2RY06A-3" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-36

Exek n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Steam Generator Blowdown System (SD)

Section Xl *L liSI Identifier-!:;*' jLine Number

  • Relief ", Technical: A cual.c Results" Cat. -item". -Descrption Reques Notes
  • Exam NA NA 2SD06032S 2SDO1CE-2" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 NA NA 2SD11066S 2SD01CH-2" NOTE 01 VT-3 NRI Snubber FT MARG INITIAL SAMPLE DTPG 2-1. SN 2598 was replaced with SN 42820 due to high drag values in both the Tension and Compression directions. Reference Issue Report 1204436.

NA NA 2SD12048S 2SD01CG-2" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-1 Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-37

Exek n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Safety Injection System (SI)

Section Xl Ist Identifier . LineNumber Rlf Technical. .Actual . Results Cat Item Desciption..,, ,.... ,. .Requests Notes Exam Comments . ,

F-A F01.10 2RH02018S ý2S104D-8" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 F-A F01.20 2RH02027S 2SI04C-8" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2RH02061S 2SI04D-8" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2RH02078S 2SIA4B-8" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2SI03018S 2SI05DD-6" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13. 10: Clamp is slightly skewed but well with the 10 degree conical tolerance. Acceptable per M-999 Sheet 10 Note 2A, and will not interfere with movement from cold to hot position and vice versa.

F-A F01.20 2SI09002S 2SI09BC-10" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-2 F-A F01.10 2SI10036S 2SI03FB-2" NOTE 01 VT-3 NRI Snubber VISUAL EXAMINATION ONLY FOR ISTD / CODE CASE OMN-13 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-38

Exek-n.t Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Snubber Table SYSTEM: Essential Service Water System (SX)

Section X11-1 ISI Identifier...:. Line'Number*6 . .:e.6fnicat eesults**a At.*u R Cat. Item-:: De.cr*ption .iRequests Notes Exam

Comments, F-A F01.20 2SX09038S 2SX07CB-10" NOTE 01 VT-3 NRI Snubber FT PASS INITIAL SAMPLE DTPG 2-3 Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-39

Exek n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM: Chemical & Volume Control System (CV)

Section X1 ComponentID Line Number Reliet 17 Technical Examý.. Results Cat. Item~ Ilecription ;:ý~Rqests Not:

Commients, NA NA 2CV02005S 2CV1 0CB-3" NOTE 01 FT PASS Snubber VT-3 NRI Existing mechanical snubber (Serial Number 12024) replaced with tested spare (Serial Number 8014) under WO# 1431482.

Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-40

Exeb n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM: Feedwater System (FW)

Section Xl !Component ID Line Numbe**lief Technical, Exa Results tm Description

ae IRequests Nts Comments-*'

F-A F01.20 2FW05011BS 2FW03DD-16" NOTE 01 FT PASS Snubber VT-3 NRI Existing mechanical snubber (Serial Number 7036) replaced with tested spare (Serial Number 47260) under WO# 1299417.

Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-41

Exe- n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM: Reactor Coolant System (RC)

SectionnXl**0 ComponentID.* .Line Number. Relief: -.-, Technical, Exam Results:

Cat. item .lDescription "Requests. Notes.

NA NA 2RC17069S 2RC20AB-.75" NOTE 01 FT PASS Snubber VT-3 NRI Existing mechanical snubber (Serial Number 2653) replaced with tested spare (Serial Number 42825) under WO# 1299699.

Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-42

Exelkn-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM: Reactor Coolant System (RY)

Section X. Co**mponent ID<*

!..Line Number. . eiie*.. Tchn6ical Exam . Results Ct7 e Description . . Requests Notes .

F-A F01.10 2RY05010S 2RY11A-14" NOTE 01 VT-3 NRI Snubber Existing damaged snubber pivot pin with a new pin under WO# 1432228.

Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-43

Exekn-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.4 Detailed Third Interval Preservice Snubber Table SYSTEM: Steam Generator Blowdown System (SD)

Section XI* Component DO "Line Number " . Rwiif* Technicali ýEam " Results ,

cat'. Iteim Deescription: , Reuests,;, Ntes -

Comments ,, .. ,

NA NA 2SD11066S 2SD01CH-2" NOTE 01 FT PASS Snubber VT-3 NRI Existing mechanical snubber (Serial Number 2598) replaced with tested spare (Serial Number 42820) under WO# 1430989.

Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-44

Exe0 n Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Chemical & Volume Control System (CV)

Section Xl Component ID4 . . .. . . Rel!e* . Technica!. Reuird: .Results Cat.- tem hnspection NotesF "7 *.. .. ,. Requests Notesi< Exan .  : ". "

Com me nts. *. j . .. .. . . 1.. . .

.... . .... * . . . ... .. .... ** .*. , .. *  :* * *:., .. . .

C-H C07.10 A02CV-000004-M04-01A VT-2 RI Period ASME Section Xl Pressure Test.

2CV8409 - Recordable Indication - Through Wall Leak - IR 1166795 2CV8485A - Info Only - Packing leak - IR 1166609 2FT-0917 - Info Only- Minor Boric Acid - IR 1166613 2CV8109 - Info Only - Packing leak - IR1166614 2CV06A - Info Only - Bolted Conn Leak - IR 1166621 2CV8355A - Onfo Only - Packing leak - IR 1167003 2CV054A - Info Only - Valve Stem Packing - IR 1167007 2SI030B - Info Only - Valve Stem Packing - IR 1167012 2CV8355B - Info Only - Packing - IR 1167015 2CV203 - Info Only - Valve Stem - IR 1167122 2CV092A - Info Only - Valve Stem - IR 1167126 2CV8355C - Info Only - Packing - IR 1167136 2PS5274 - Info Only - Packing - IR 1166462 2CV03F - Info Only - Target Deposit - IR 1199169 Info Only:

IR 1167152 - Minor Boric Acid on 2A Ltd HX Drain Line IR 1167154 - Minor Boric Acid on 2B LTD HX Drain Line IR 1167159 - Minor Boric Acid at 2CV228A IR 1167165 - Minor Boric Acid at 2CV8107A IR 1167181 - Minor Boric Acid at 2CV031 Packing IR 1167187 - Minor Boric Acid at 2BRO03B Valve Stem C-H C07.10 A02CV-000004-M04-01 B NOTE 24 VT-2 10 Period ASME Section Xl Pressure Test.

WO 1130656 completed 4-8-11.

WO 1134996-01 started 4-18-11 in A2R15, completed 5-9-11.

No recordable indications.

See also WO 1134996.

C-H C07.10 A02ZZ-000078-M04-03D NOTE 22 VT-2 10 Period ASME Section X1 Pressure Test. Class 2 normally isolated components to be pressurized during mode 5.

A2R15 Mode 3 on 5-11-11:

2CVF5A - 3/4" - Info Only - Pipe Cap - IR 1214395 2CV066D - Info Only - Pipe Cap - IR 1214407 2CV066A - Info Only - Packing - Duplicate IRs 1214053 & IR 1214418 2CV077A - Info Only - Packing - Duplicate IRs 1214050 & IR 1214428 2CV220 - Info Only - Pipe Cap - Dipl IR 1214130 & IR 1214450 2FIS-0164 - Info Only - Packing - IR 1214461 2FT-0434 - Info Only - Fitting - IR 1214473 Page 3-45

Exel, n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Fuel Pool Cooling System (FC)

Section.Xi Component:.lD; Reh.e TechniaL Requ red. Results item inspeCti..Notesý. .. .. R* 1uests Notes . Exam cornrents -i 0-H 007.1 0 A02FC-000001-1004-01 C VT-2 NRI Period ASME Section X1 Pressure Test.

C-H C07.10 A02FC-000001-M04-01D VT-2 NRI Period ASME Section Xl Pressure Test.

Page 3-46

Exek n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Instrument Air System (IA)

X.. m n. ID ' .ectlla.nX

.... ' R"l Technicalli .. . ed- .. esu .,s.

,Cat- Item Reuests 8N : 't m.......

m C........ ... * *1ments C-H C07.10 A021A-000004-M04-01A VT-2 NRI Period ASME Section XI Pressure Test. Verify Continuous Leak Detection System for Airlock is in operation prior to performing SNOOP or Ultraprobe examination of test boundary.

Periodic Test using BwVS TRM 3.4.f.2-PC. No leakage observed.

Page 3-47

Exeu n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Residual Heat Removal System (RH)

Section Xl Component ID ' Tcnca

... .. seuies Cat. Item inspection Notes Requests Notes Exam Comments  :

C-H C07.10 A02RH-000003-M04-01A NOTE 22 VT-2 10 Period ASME Section Xl Pressure Test. VERIFY loop "A"in service.

Pressurize 2A sample line per BwCP 613-3.

The following were noted for Information:

Dry boron at packing on 2SI059A (IR 1212972); dry boron on packing at 2RHO20A (IR 1212506); dry boron on packing 2RHO21A (IR 1212508)

C-H C07.10 A02RH-000003-M04-01B NOTE 22 VT-2 10 Period ASME Section Xl Pressure Test. VERIFY loop "B" in NRI service.

Pressurize 2B sample line per BwCP 613-3.

NRI RI Recordable indication of dry boric (Bolts #12, 13, 31, 36, 39, and 41) acid and weepage (Bolt #9) on 2B RHR heat exchanger (IR 1213307).

The following were noted for Information:

Dry boron at packing 2RHO03B (IR 1213315); dry boron at packing 2RHO04B (1213313); dry boron at packing 2RH028B (IR 1207085)

C-H C07.10 A02RH-000003-M04-01D NOTE 22 VT-2 10 Period ASME Section Xl Pressure Test.

Noted for Information:

Dry boron at packing 2RH8701A (IR 1196781)

C-H C07.10 A02RH-000003-M04-01E NOTE 22 VT-2 10 Period ASME Section XAPressure Test.

The following were noted for Information:

Dry boron at packing 2RH8702A (IR 1196782); Leakage past pipe cap threads downstream of 2SI094 (IR 1203992)

Page 3-48

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Safety Injection System (SI)

Section X dComponent IDi Relief Technical:% * -Requid Relts*"

at... emn.Inspection Notes. Requests Notes Exam Comments ~ ~ >

C-H C07.10 A02SI-000010-M04-01G NOTE 22 VT-2 NRI Period ASME Section X1 Pressure Test.

C-H C07.10 A02ZZ-000010-M04-01J NOTE 22 VT-2 10 Period ASME Section Xl Pressure Test.

C-H C07.10 A02ZZ-000010-M04-01K NOTE 22 VT-2 NRI Period ASME Section Xl Pressure Test.

C-H C07.10 A02ZZ-000010-M04-01L NOTE 22 VT-2 10 Period ASME Section Xl Pressure Test.

C-H C07.10 A02ZZ-000010-M04-01M NOTE 22 VT-2 NRI Period ASME Section XI Pressure Test.

Page 3-49

Exelon-Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Essential Service Water System (SX)

Section XI Component ID .  : F!W:WU.Re**:

Relief Technical; Required-;:. Results9

  • cat*. tem Irnspection Notes: ,, ":Requests- Notes IExam ,

NRI: 2D RCFC 4/26/2011; 2B RCFC 4/27/2011 C-H C07.10 A02SX-000011-M04-01F VT-2 10 Period ASME Section Xl Pressure Test. NRI Information only (4/18/2011 exam): Slight corrosion on piping wall due to sweat, no degradation noted.

NRI: 2C RCFC (right bank) 4/19/2011; 2C RCFC (left bank) 4/24/2011; 2A RCFC 4/22/2011 Page 3-50

Exek n.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.5 Detailed Third Interval Pressure Tests SYSTEM: Plant Systems Pressurized During Mode 3 (ZZ)

Section XI tComponent ID.. Relief "Technica!l Requir Results Item inspection Notes; ,, .Exam Requests, lNotes*

B-P B15.10 A02ZZ-000005-M04-01A NOTE 22 VT-2 RI Each Refueling Outage Generic Letter 88-05 Examinations Class 1: NOTE 23 PMID 55141-01. Class 2 and 3: PMID96032-17.

2SI08JB: Recordable Indication - Dry boric acid found at flange (IR1214416).

2RC8037A: Recordable Indication - Inactive Body-Bonnet leak (IR 1214436).

C-H C07.10 A02ZZ-000078-M04-03A NOTE 22 VT-2 10 Period ASME Section XI Pressure Test. All Class 2 components inside containment. VT-2 visual inspection of components outside Missile Barrier may be performed during Mode 1/3 if conditions permit. Valve in EX and LTD HX'ers when perform.

The following indications were noted for Information:

2CV203 pipe cap (IR 1214395); 2CV066A pipe cap (IR 1214418); 2CV067A pipe cap (IR 1214428); 2CV066D pipe cap (IR 1214407);

2CV220 pipe cap (IR 1214450); 2FIS-0164 (IR 1214461); 2FT-0434 (IR 1214473); 2FT-0424 (IR 1214484);

C-H C07.10 A02ZZ-000078-M04-03B NOTE 22 VT-2 NRI Period ASME Section XI Pressure Test. Class 2 components inside / outside containment which are normally pressurized during modes 1-3.

First period walkdown performed during plant start-up from A2R15, no evidence of leakage noted.

Page 3-51

Exelkn Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.6 Detailed Borated Bolted Connection Table SYSTEM: Chemical & Volume Control System (CV)

Sectio'-n X lComponentD  :, .7 Relief>, Technical.; Actual Results tem Dscrfptjon' jbat . i equests, JNotes T ~a C"-iments.

B-P B15.10 2CV-03-B1 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)

B-P B15.10 PG-2546C-214 F-2-2 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)

C-H C07.10 PG-2546C-220 F-1 (C-H) VT-2 NRI FLANGED CONNECTION (4 STUDS)

C-H C07.10 PG-2546C-241 F-1-1 (C-H) VT-2 NRI FLANGED CONNECTION (4 STUDS)

EXAMINE DUE TO EVIDENCE OF LEAKAGE IDENTIFIED DURING A2R14.

B-P B15.10 PG-2546C-271 F-2-3 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)

C-H C07.10 PG-2546C-289 F-1 (C-H) VT-2 NRI FLANGED CONNECTION (8 STUDS)

RE-EXAMINE DUE TO IDENTIFICATION OF LEAKAGE DURING A2R14 C-H C07.10 PG-2546C-290 F-1 (C-H) VT-2 NRI FLANGED CONNECTION (8 STUDS)

B-P B15.10 PG-2546C-301 F-2-2 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Page 3-52

Exelenn.

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.6 Detailed Borated Bolted Connection Table SYSTEM: Reactor Coolant System (RC)

Seiction Xl !oponent ID',. Relief.. Techncl cta Resu~u Ca. te<Description Requests~ Notes~Ea Comments <>~

B-P B15.10 2PZR-01-B1 (B-P) VT-2 NRI MANWAY BOLTING (16 TOTAL)

B-P B15.10 2RC-20-B1 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)

B-P B15.10 2RC-32-B4 (B-P) VT-2 NRI FLANGED CONNECTION (12 STUDS)

B-P B15.10 2RC-32-B5 (B-P) VT-2 NRI FLANGED CONNECTION (12 STUDS)

B-P B15.10 2RC-32-B6 (B-P) VT-2 NRI FLANGED CONNECTION (12 STUDS)

B-P B15.10 2RV-03-STUDS (01 TO 54, B-P) VT-2 NRI CLOSURE HEAD STUDS (54 TOTAL)

Note: Stud Number 37 Cut Off.

B-P B15.10 2SG-01-B1 (B-P) VT-2 NRI 9A PRIMARY MANWAY (16 BOLTS)

B-P B15.10 2SG-01-B2 (B-P) VT-2 NRI 9B PRIMARY MANWAY (16 BOLTS)

B-P B15.10 2SG-02-B1 (B-P) VT-2 NRI 9A PRIMARY MANWAY (16 BOLTS)

B-P B15.10 2SG-02-B2 (B-P) VT-2 NRI 9B PRIMARY MANWAY (16 BOLTS)

B-P B15.10 2SG-03-B1 (B-P) VT-2 NRI 9A PRIMARY MANWAY (16 BOLTS)

B-P B15.10 2SG-03-B2 (B-P) VT-2 NRI 9B PRIMARY MANWAY (16 BOLTS)

B-P B15.10 2SG-04-B1 (B-P) VT-2 NRI 9A PRIMARY MANWAY (16 BOLTS)

B-P B15.10 2SG-04-B2 (B-P) VT-2 NRI 9B PRIMARY MANWAY (16 BOLTS)

Page 3-53

ExeJun.-

Braidwood Station Unit 2 A2R15 ISI Outage Report Section 3.1.6 Detailed Borated Bolted Connection Table SYSTEM: Residual Heat Removal System (RH)

Section;Xl. Component:.:Dlii  :.eI*ef*.K.Reisul:s f ca~~ Description,~ Requests Notes lxa Comments> .

C-H C07.10 2RH-12 F-3-1 (C-H) VT-2 NRI FLANGED CONNECTION (12 STUDS)

EXAMINE DUE TO RI IDENTIFIED DURING THE PREVIOUS EXAM.

Page 3-54

Exea!n Braidwood Station Unit 2 A2R15 ISI Outage Report 4.0 REPORT OF CONTAINMENT DEGRADATION Containment inspections are performed in accordance with Subsection IWE (Requirements for Class MC and Metallic Liners of Class CC Components of Light-Water Cooled Power Plants) and Subsection IWL (Requirements for Class CC Components of Light-Water Cooled Power Plants) of ASME Section Xl, Division 1, with specified modifications and limitations in 10 CFR 50.55a. The following sections are included in the Inservice Inspection Summary report as required by IWA-6000 of ASME Section Xl to meet the reporting conditions specified in 10CFR 50.55a(b)(2)(ix)(A)(1) through (3).

The following discusses examinations performed in accordance with ASME Section XI, Subsections IWE and IWL respectively.

4.1 A2R15 Containment Metal Liner Examinations (IWE)

The Third Interval First Period Class MC General Visual Examinations were completed during A2R15. All indications identified during the General Visual Examinations were reviewed and accepted as is by the Responsible Individual as defined in ASME Section XI.

The completed surveillances for IWE contain all the examination details along with indications recorded and their associated evaluations required by ASME Section XI.

The following discusses augmented exams performed under the containment moisture barrier.

Augmented Section XI IWE examinations of the Class CC liner examinations for the Third Interval were performed in accordance with the requirements of ASME Section XI, Table IWE-2500-1, Category E-C, Containment Surfaces Requiring Augmented Examination.

Exelon Procedures ER-AA-330-007, "Visual Examination of ASME Section X1 Class MC Surfaces and Class CC Liners", ER-AA-335-018, "Detailed,General Visual, VT-1, VT-1C, VT-3 and VT-3C, Visual Examination of ASME Class MC and CC Containment Surfaces and Components", and ER-AA-335-004 "UltrasonicMeasurement Of Material Thickness and Interfering Conditions"were used to perform the examinations.

Six sections of the containment moisture barrier were removed for the purpose of performing augmented examinations of the containment liner surface. These examinations were required due to identification of degradation during past examinations. The results of the examinations revealed no evidence of degradation that had not been identified during past examinations. The conditions remained unchanged with no evidence of additional degradation.

A description of the type and estimated extent of degradation, and the conditions that led to the degradation [10CFR 50.55a(b)(2)(ix)(A)(1)]:

The results of the examinations revealed no evidence of degradation that had not been identified and evaluated as acceptable by the Responsible Individual during past Page 4-1

ExeI ~n Braidwood Station Unit 2 A2R15 ISI Outage Report examinations. The conditions remained unchanged. The previous evaluation was documented under Engineering Change 377614.

Extent of condition:

No extent of condition augmented examinations were required during A2R1 5.

Description of the conditions that led to the degradation:

As originally identified during the A2R08 examinations, the identified liner degradation was a result of moisture barrier aging and mechanical damage of the moisture barrier that occurred during maintenance activities. The damage of the moisture barrier resulted in a leakage path for water impingement on the liner. The primary source of the water is condensation from the containment fan cooling units. The entire moisture barrier was removed, examinations performed, areas coated and the moisture barrier was replaced during A2R08.

Evaluation of each area, and the result of the evaluation

[1 OCFR 50.55a(b)(2)(ix)(A)(2)]:

The results of the A2R15 examinations revealed no evidence of degradation that had not been identified and evaluated as acceptable by the Responsible Individual during past examinations. The conditions remained unchanged. The previous evaluation was documented under Engineering Change 377614.

Description of Necessary Corrective Actions Completed

[1 OCFR 50.55a(b)(2)(ix)(A)(3)]:

Proposed Actions for A2R1 6:

Additional VT-1 (Detailed Visual) and ultrasonic thickness examinations are scheduled in A2R1 6 refueling outage to examine the condition of the liner plate below the moisture barrier at the three locations. These three locations were examined during A2R15 with no evidence of changes from conditions identified during the previous augmented examinations. They are being scheduled for successive exams during A2R16.

Conclusions/Findings Based on the conclusions of the previous evaluation (Engineering Change Number 377614) and the fact that no additional degradation was identified during the A2R1 5 augmented examinations, the liner plate containing the degraded conditions below the moisture barrier (MB) in Unit 2 containment is acceptable and capable of performing its intended design function.

4.2 A2R15 Class CC (IWL) Containment Examinations The Units 1 and 2 2 5th Year ASME Section Xl WL Post Tensioning and Concrete examinations and tests began in June of 2011. The Post Tensioning surveillance is scheduled to be completed in September 2011 while the containment concrete examinations are scheduled to be completed in December 2011. Final reporting in Page 4-2

Exelon.

Braidwood Station Unit 2 A2R15 ISI Outage Report accordance with ASME Section Xl IWL-3310 and 10CFR50.55a will be included in the IWA-6000 ISI Summary Report for Refuel Outage Al R1 6 which is currently scheduled for April 2012.

At the time of preparation of this report, the presence of free water, IWL-3221.3 (a) is the only identified reportable condition. Chemical analysis for the sheathing filler and free water are in progress. However, results are pending. Table 4.2-1 describes the presence of free water identified for the specific tendons for available results. With the exception of the dome tendons, all locations are below grade level.

Table 4.2-1 Containment Tendon Inspection Results (As of 7/25/2011)

Free Water Visual Unit Reason For Examination Tendon Tendon Tendon Collected Examination Selection Identifier Type End (Ounces) Results 1 Augmented Free Water H-01 -AC Hoop Field 3 Note 1 1 Augmented Free Water H-02-AC Hoop Field 1 Note 1 1 Augmented Free Water H-02-BA Hoop Shop 6 Note 1 1 Augmented Free Water -H-02-BA Hoop Field 7 Note 1 1 25t Year ISI V-1 42 Vertical Field 11 Note 1 2 Augmented Free Water H-01 -ED Hoop Field 7 Note 1 2 Augmented Free Water H-01 -ED Hoop Shop <1 Note 1 2 Augmented Free Water H-01 -FE Hoop Shop 5 Note 1 2 Augmented Free Water H-02-ED Hoop Field <2 Note 1 2 Augmented Free Water H-04-DF Hoop Field 60 Note 1 2 Augmented Free Water H-04-ED Hoop Field 50 Note 1 2 Augmented Free Water H-04-ED Hoop Shop 2 Note 1 2 Augmented Free Water H-05-ED Hoop Shop 6 Note 1 2 Augmented Free Water H-05-FE Hoop Field 55 Note 1 2 Augmented Free Water H-05-FE Hoop Shop < 1 Note 1 2 Augmented Free Water H-06-FE Hoop Field 26 Note 1 2 Augmented Free Water V-217 Vertical Field 2 Note 2 2 Augmented Free Water V-241 Vertical Field 1 Note 2 2 Augmented Free Water V-249 Vertical Field 84 Note 2 2 25In Year ISI D-04-36 Dome Field 54 Note 2 2 Augmented Free Water D-04-38 Dome Shop 2 Note 1 2 Augmented Free Water D-04-38 Dome Field 512 Note 2 2 Augmented Free Water D-04-27 Dome Shop 4 Note 2 2 Augmented Free Water D-04-27 Dome Field < 1 Note 2 2 Augmented Free Water D-06-13 Dome Shop 12 Note 1 2 Grease Leak Repair D-04-39 Dome Shop 14 Note 2 Note 1: No evidence of degradation or active corrosion was identified on either the anchorage components or the surrounding concrete. Sheathing filler was not discolored (indicative of moisture saturation) in the as found condition.

Note 2: No evidence of degradation or active corrosion was identified on either the anchorage components or the surrounding concrete. However, the sheathing filler was discolored (light, cream colored which is indicative of saturation) in the as found condition.

Page 4-3

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Braidwood Station Unit 2 A2R15 ISI Outage Report Conclusions/Findings Based on the as found conditions where no degradation or active corrosion was identified on the anchorage components or surrounding concrete, there is no indication the presence of free water has resulted in any degradation of the specific tendons, post tensioning systems, or the containment structures. At the time the A2R15 ISI Summary Report was being prepared these conditions were being evaluated in accordance with ASME Section Xl, IWL-3222. Any additional examination results subject to reporting requirements will be incorporated into the next Braidwood Station ISI Summary Report which will be submitted within ninety days after the conclusion of the Al R16 (Spring 2012) outage.

Page 4-4

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Braidwood Station Unit 2 A2R15 ISI Outage Report 5.0 NIS-1 FORM As required by IWA-6000 of Section XI, this section contains the Owner's Report for Inservice Inspections, Form NIS-1, for the inservice examination of Class 1 and Class 2 pressure retaining components.

Page 5-1

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

1. Owner Exelon Generation Company (EGC, LLC), 200 Exelon Way, Kennett Square, PA, 19348 (Name and Address of Owner)
2. Plant Braidwood Station, 35100 South Route 53, Suite 84, Braceville, Illinois 60450 (Name and Address of Plant)
3. Plant Unit 2 4. Owner Certificate of Authorization (if required) Not Applicable
5. Commercial Service Date 10/17/1988 6. National Board Number for Unit N-197
7. Components Inspected See Section 3 of this report for all components (report is a total of 119 pages).

Component or Manufacturer Manufacturer State or National Appurtenance Or Installer or Installer Province No. Board No.

Serial No.

Reactor Vessel Babcock & Wilcox 640-0014-52 B-24360 N-1 95 2RC01R Pressurizer Westinghouse 2101 U-199012 18696 2RY01S Steam Generator Westinghouse CDGT-2111 N/A 20 2RC01BA Steam Generator Westinghouse CDGT-2112 N/A 21 2RC01 BB Steam Generator Westinghouse CDGT-2113 N/A 22 2RC01BC Steam Generator Westinghouse CDGT-2114 N/A 23 2RC01 BD Residual Heat Joseph Oat 2267-1 F U-199322 841 Removal Heat Corporation Exchanger 2RH02AA Residual Heat Joseph Oat 2267-1H U-199325 843 Removal Heat Corporation Exchanger 2RH02AB See Sections 3.1 through 3.1.6 and associated tables for the specific Class 1 and 2 component locations examined for the Third Interval ISI Program.

Page 5-2

FORM NIS-1 (Back)

8. Examination Dates: November 3, 2009 to July 28, 2011
9. Inspection Period Identification: 1 st Period, Third Interval - From October 16, 2008 through October 16, 2011
10. Inspection Interval Identification: 3rd Interval - From October 17, 2008 through October 16, 2018
11. Applicable Edition of Section Xl 2001 Edition Addenda 2003 Addenda
12. Date/Revision of Inspection Plan: May 5, 2011 / Revision 3b including Code Cases N-460, N-508-3, N-566-2, N-686-1, N-700, N-706, N-722, N-729-1
13. Abstract of Examination and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. See Attached Sections 2 and 3.
14. Abstract of Results of Examinations and Tests. See Attached Sections 2 and 3.
15. Abstract of Corrective Measures. See Attached Sections 2 and 3.

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 Xl, and c) corrective measures taken conform to the rules of the ASME Code,Section XI.

Certificate of Authorization No. (if applicable) Not Applicable Expiration Date Not Applicable Date /?U9S.+/- 5 20 I Signed Exelon Nuclear Braidwood Station By VSA#2-*Owne r* 9 Braidwood ISI Program Manager 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 Illinois and employed by Hartford Steam Boiler Inspection and Insurance Company of Connecticut have inspected the components described in this Owner's Report during the period Ll - _'

- to -?- - t A 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 Xl.

By signing this certificate neither the Inspector nor his employer makes and 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.

L Commissions ' X.'-- k*.OSS7 I "

Inspector's Signature National Board, State, Province, and Endorsements Date ,- & _-

.. 20 IN Page 5-3

ExeLn_

Braidwood Station Unit 2 A2R15 ISI Outage Report Braidwood Unit 2 Non-Deferrable Class 1 and Class 2 Inspection Status (Third Interval) After A2R15 per IWA-6220(f)

Code Category Code Item Number Total Number Selected Total Number Examined Current Percentage (Interval) in A2R15 Completed for Category B-A B1.30 1 0 0%

B1.40 1 0 B-B B2.11 2 0 B2.12 2 0 2/5 40%

B2.40 1 0 B-D B3.110 6 2 B3.120 6 2 4/20 =20%

B3.140 8 0 B-K B10.10 1 0 1/3 33%

B10.20 2 0 B-N-1 B13.10 1 1 Once Per Period B-P B15.10 Every Outage 1 Not Applicable B-Q B1 6.20 Per Technical Specifications 4 Not Applicable C-A C1.10 4 2 C1.20 2 0 2/7 = 28%

C1.30 1 0 C-B C2.21 5 1 1/6 = 16%

C2.22 1 0 C-C C3.10 1 0 C3.20 9 0 4/13 = 30.7%

C3.30 3 0 C-H C7.10 38 18 18/38 =47.3%

F-A F1.10 167 25 F1.20 186 35 F1.30 73 13 F1.40 29 2 R-A Butt Welds 202 23 Socket Welds 96 Welds Every Outage 96 Page 5-4

Exet n.

Braidwood Station Unit 2 A2R15 ISI Outage Report 6.0 NIS-2 FORM (OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS)

SUMMARY

OF NIS-2 FORMS The following table provides the Class 1 and 2 ASME Section XI repairs completed since the last outage report (A2R14). Activities where the replacement item installed was a rotated spare are not included in this summary as allowed by IWA-4132(g) and Code Case N-508-3.

System ASME Code Classification Code Class 1 Code Class 2 CV Chemical & Volume Control 5 CS Containment Spray 1 FW Feedwater 1 MS Main Steam 4 RC Reactor Coolant 9 3 RH Residual Heat Removal 3 RY Reactor Coolant/Pressurizer 1 SD Steam Generator Blowdown 1 SI Safety Injection 4 Total NIS-2 Forms 32 Associated NIS-2 Forms and associated Code Data Reports are attached (47 total pages).

Page 6-1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co., LLC Date 7/7/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #01148456-01 Repair/Replacement Organization P.O., Job No., etc
3. Work Performed By: Shaw/ Stone & Webster Type Code Symbol Stamp: None Address: 36400 South Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: Chemical Volume and Control (CV) (Class 2) 5 (a) Applicable Construction Code: ASME Section III 1971 Edition, Winter 1972 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Components:

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

Existing Valve Cover and Kerotest Not Recorded Not Valve Not Recorded Removed Yes (Valve)

Body-to-Cover Seal Weld Applicable 2CV8348 Valve 2CV8348 IIII _ III Body-to-Cover Seal Weld Arcos Industries, Lot CT8660 Not Cat ID 8500-1 2007 Installed No Weld Electrode LLC Heat 734816 Applicable UTC 2808606 (Corrected) 3/32" ER316/316L

7. Description of Work: Removed existing seal weld to provide access to valve internals for check valve inspection. After inspection was completed, the existing valve cover was reinstalled and seal weld was reapplied. Seal weld was examined by liquid penetrant and was rejected. Indication was removed and repaired by welding. Seal weld was again examined by liquid penetrant and found acceptable.
8. Tests Conducted: Hydrostatic [] Pneumatic E] Nominal Operating Pressure C] Exempt 0 Other 0 Pressure Nominal psig Test Temp. Nominal *F
9. Remarks: Seal welds are exempt from Section Xl pressure testing requirements per IWA-4550(b)(8), but valve was examined by VT-2 method on 5/5/2011 during periodic system pressure testing and found acceptable. Applicable documentation for replacement valve seal weld filler material was attached at the time of final review and is maintained on file.

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

Type Code.*ymbol Stamp: Not plicable Certificate of Authorization No.: Not Applicable S i gn e d ,.,l 4. ,4 -* ISI Coordinator Date -77 2011 Owner or Owner's Designee, Title/

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 11/22/2010 to 7/7/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

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

4-*. \,_L- ._ Commissions ILl 085 Inspector's Signature National Board, State, Province, and Endorsements Date :'" k\- ,20 X.\

Page 6-2

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co., LLC Date 7/28/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #01269949-01 Repair/Replacement Organization P.O., Job No., etc
3. Work Performed By: Shaw / Stone & Webster Type Code Symbol Stamp: None Address: 36400 South Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: Chemical Volume and Control (CV) (Class 2) 5 (a) Applicable Construction Code: ASME Section I1l1971 Edition. Winter 1972 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section X) Code Cases used: None
6. Identification of Components:

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

Existing Valve Cover and Borg Warner Not Recorded Not Valve Not Recorded Removed Yes (Valve)

Body-to-Cover Seal Weld Applicable 2CV8368B Valve 2CV8368B Weld Rod Arcos Industries, Lot CM8256 Not Cat ID 8500-1 2007 Installed No 3/32" ER316/316L LLC Heat 734816 Applicable UTC 2808606

7. Description of Work: Removed existing seal weld to provide access to valve internals for check valve inspection. After inspection was completed, the existing valve cover was reinstalled and seal weld was reapplied. Seal weld was examined by liquid penetrant in the finished condition.
8. Tests Conducted: Hydrostatic [] Pneumatic [] Nominal Operating Pressure 0 Exempt [I 0

Other 0 Pressure Nominal psig Test Temp. Nominal F

9. Remarks: Valve was examined during the ascending Mode 3 walk down on 5/1112011 after four hour hold time and was found acceptable. There is no specific instrumentation for monitoring system pressure or temperature for this valve. Applicable documentation for replacement seal weld filler materials was attached at the time of final review and is maintained on file.

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

Type Code ,ymbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed , SI Coordinator Date _____ 20-_L Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/5/2011 to 7/28/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

L -Commissions ILl 085 Inspector's Signature National Board, State, Province, and Endorsements Date :-k- ,20 k' Page 6-3

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co., LLC Oate 7126/2011 Address: 300 Exelon Way. Kennett Square, PA 19348 S:heet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84. Braceville, IL 60407 Work Order #00819603-01 Repair/Replacement Organization P.O., Job No., etc
3. Work Performed By: Shaw / Stone & Webster Type Code Symbol Stamp: None Address: 36400 South Essex Road. Wilmington. IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: Chemical Volume and Control (CV) (Class 2) 5 (a) Applicable Construction Code: ASME Section III 1971 Edition, Summer 1972 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section X1 Code Cases used: None
6. Identification of Components:

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

Bonnet f9r Valve ITT Grinnell Valve Not Recorded Not Valve 2CV8394 Not Removed Yes (Valve) 2CVg18394 Co. Applicable Recorded Bonnet from New Valve [ITT Grinnell Valve Serial Number Not Cat ID40478-1 1980 Installed Yes Assembly Co. 76-2099-3-1 Applicable UTC 2885756 (Valve Bonnet) Sl# 803D13 QRI A91-02574

7. Description of Work: Removed and replaced existing valve bonnet to correct leakage. Repair/Replacement Plan was not initiated prior to replacement (reference Issue Report 1241901).
8. Tests Conducted: Hydrostatic 13Pneumatic C3 Nominal Operating Pressure 0 Exempt C]

Other E Pressure 25 psig Test Temp. 105 `F

9. Remarks: Visual leak check had been performed and accepted by Operations on 5/2/2011. VT-2 examination was performed and acceptable on 7/20/2011. Applicable documentation for replacement valve bonnet (Form NPV-1) was attached at the time of final review and is maintained on file.

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

Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed & k -* .J: .6.-c- ISI Coordinator Date 7P(2 , 20 )I Owner or Owner' Designee. TifA CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 7/20/2011 to 7/26/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

-L t "- 5-- Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date - , 20-s-,,

Page 6-4

~'INFORMATION ONLY ---- ý-

3 FORM NPV-I MANUFACTURERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES*

As Required by the Provisions of tbe ASHE Code Rules 1, Manufacturedby ITT Grinnell Valve Co., Inc., Lancaster, Pa. OrdeNr 76-2099-3 (Nme & Address of Mmitactu'rQ)

2. Manufacturedfor Westinghouse Electric Corp., Pgh. Pa. OftefNo. 546-CC0-191008 (Naser nd Address)
3. Owner Commonwealth Edison Co. CCE
4. LocationofPlant Braidwood No. 1 Braidvood, Ill.
5. Pump or ValveIdenfication 4" ITT Grinnell Diaphragm Valves, HWO v/T.S.

Reactor Coolant, Spent Fuel Pit Fluid (brief desedrptIon of service for whch equipsont was designed) 00 5 54 (a) DrawinS No.SDC-1 Rev.L Prepared ITT Grinnt 1 lve Co.* Inc.

No.

(b) National Board

6. Design Conditions 300psi 150JL F" (Pressu re) (T omperetur.)

i

7. The material, design, construction, and workmansh*p 2 ijea,;i.a. Class _ _ _ _

Edit'o 1971 - , Addenda Date Summer C

. Case No.. 1540-1

...

Mark No. Jsrteriat Spec. No. Menutsetaw Resmaft (a) Castings 76-2099-3-1 Body ASME SA351 Investment Cs a. CF8 76-2099-3-1 Bonnet ASMESA351 Investment Cs 3. CFO (b) Forgings Y .? 9

-, 4.

.7 4.

4. 4. 4.
4. 4. 4.

t 4.

t 1* I

4. 4. I sheets I. 1mm at Urns., ehetehes m dawiaee

'Supplemestal .v hs used presided 0) aSs. is SW s 35, (2) i~aa~m he ~. 3.2. Se A. ____________ ___________________ I

  • o u eta In rae s o f Liti r .o o b e ta b oo as dt we i

':l ktso 5b on this do eirm no r be usee d psI b I 8 P to otetuded oe asebsheet, sed (3) Ossk sheet is 14110e0ed saed WNmbs of sbeeft is eemiad in ma a" hem.

i , ( ) Je ~ ~i m i , l o , l e a 9 ?aOg e -7 I

U

t~.. - a INFORM AlTIO! ONLY_ V *.

A FORM NPV-1 (back)

MaerIgo. Material Ioec. No. Manufactuare Raoria (c) Bohtina 76-2099-3-1 Studs ASME SA453 Victor Prods. Grade 660 76-2099-3-1 ____

Nuts ASME SA194 V R.Machine Grade 6 (d) Other Parts Diaphragm-Grade If - Colonial Rubber EPT Nordel Vent Plugs ASME SA194 Stainless Prod Grade 6

______ I___ I

____ I _____

8. Hydrostatic tear 450 psi. Rjt4IQR1 p9 1 -0 2 5 7 4 CERTIFICAI1ON OF DESIGN Designinfotmationonfileat ]ITT G.rinnell

,, Valve ii Co.,

,

Inc..

,, Lancaster,Ii Pa.,,

on file ae Stress analysis report Desig, specifications certified by Louis J. Ma.an dra (1) Prof. Es.&state PA . eas.No. 13868 E Stress analysis report certified by NA (1) Prof. Eng. State - Re$. No.__

f (I) Signature not required. List nsae only. 'a We certify that the statements made in this report wec correct.

Date, *C*= 2..., 19 i2-.. > SignedITT C Certificate of Authouizatioa No. N-2092- Inspires 4/7/81 CERTIFICATE OF SHOP INSPECT1ON I, the tnders4lmed, bolding a valid commissiom issued by the Nationsl Boaer of Soiler sad Proestre Vessel anspectors and/or the Seat of Province of PA and employed by H.S.B.Z.41. C92 of , Hartford.* CT have inspected the equipmnt described in this Dora Report o - 2." 19o.0&3 , m state that to the best of my knowledg sand belief, the MsaIfacturee has constructed this equalmI-- [n accordasce with the aplicable Subsectinos of ASME Code, Seetdm. UI.

By sipina this ceoinfce, neither the Imapector not his employee makes my Warreny, e.pressed oe implied. cascare.

teequlpment a described is tiis Date Repor. Furthermore neither the inspector at. hiM employse sowli be liable in Wa manmer for Say perso*a* Ianjury or property damage o a loss of my kind se*siag from o cosnnected with this inspecdton.

Date A-. 1'J)(

9 v\ ~ m os J . Comissloas hj lA L-(Ratimnal Seaen, Staa. Prvfrey~. sad We.)

ý6(Inspsetet)

Printed in U.S.A. (61/12) This rwo OL37) tsoelaimaie bemt the AM#. 349 8 4Mt OR"Sew Teak. N.Y. 1661?

Page 6-6 I F

1

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

1. Owner  : Exelon Generation Co., LLC Date 7/20/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1
2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #01405325-06 Repair/Replacement Organization P.O., Job No., etc
3. Work Performed By: Shaw / Stone & Webster Type Code Symbol Stamp: None Address: 36400 South Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: CV (Chemical Volume and Control) (Class 2) 5 (a) Applicable Construction Code: ASME Section Ill 1974 Edition, Summer 1975 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Comp onents:

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

Support 2CV38024G Not Recorded Unknown Not 2CV38024G Not Removed No Applicable Recorded E7018 3/32" Diameter Weld ESAB Heat M902234 Not Cat ID 8491-1 2010 Installed No Electrode Lot 2H012D04 Applicable UTC 2870136 Control NNNO24 Angle Bar 2" X 2" X 114" SDI Roanoke Heat JH4541 Not Cat ID 514025-1 2010 Installed No A-36 Bar Division Applicable UTC 2882044

7. Description of Work: Removed existing angle (Item 6 on Drawing M-2CV38024G) to support replacement of Valve 2CV8409/Line 2CV02G-2". New piece of angle iron was welded into place to restore component support back to original configuration.
8. Tests Conducted: Hydrostatic E] Pneumatic E] Nominal Operating Pressure El Exempt 0 Other 0 Pressure Not Applicable psig Test Temp. Not Applicable IF
9. Remarks: Applicable material documentation for welding electrode was attached at the time of final review and is maintained on file.

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

Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed Y-J,#.,1&4U 461 A

  • ISI Coordinator Date _____ 20,/

Owner or Owner'sesieTi CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 2/21/2011 to 7/20/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

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

4 ___ Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date" -1ý:ýl-.., 20 k N Page 6-7

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co., LLC Date 7/20/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #01405325-08 Repair/Replacement Organization P.O., Job No., etc
3. Work Performed By: Shaw / Stone & Webster Type Code Symbol Stamp: None Address: 36400 South Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: Chemical Volume and Control (CV) (Class 2) 5 (a) Applicable Construction Code: Valve: ASME Section III 1971 Edition, Winter 1972 Addenda, No Code Cases Pipe: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Coin onents:

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

Valve 2CV8409 / Not Recorded Not Recorded Not Valve 2CV8409 / Not Corrected/ Yes (Valve)

Line 2CV02G-2" Applicable Line 2CV02G-2" Recorded Removed 2" 1500# Class Globe Flowserve Serial Number Not Cat ID 30706-1 2011 Installed Yes Valve Corporation 22BRU Applicable UTC 2884290 2" Schedule 40 Seamless Sandvik Materials Heat 507498 Not Cat ID 26883-1 2006 Installed No Pipe Technology WO 517390 Applicable UTC 2745358 1/8" Diameter Arcos Industries, Lot DF8147 Not Cat ID 8513-1 2004 Installed No ER308/308L Welding LLC Applicable UTC 2702659 Rod_

1/8" Diameter Arcos Industries, Lot D9077 Not Cat ID 8513-1 2009 Installed No ER308/308L Welding LLC Heat 249076 Applicable UTC 2844829 Rod 3/32" Diameter Arcos Industries, Lot CT9218 Not Cat ID 8497-1 2010 Installed No ER308/308L Welding LLC Heat 739540 Applicable UTC 2870439 Rod

7. Description of Work: Removed and replaced existing valve and adjacent piping, through-wall leak was noted at valve-to-pipe socket weld (reference IR 1167334). Flawed weld was captured and sent out for root cause analysis. All welds were examined by the liquid penetrant method and were found acceptable.
8. Tests Conducted: Hydrostatic [] Pneumatic E] Nominal Operating Pressure El Exempt C Other 0 Pressure 351 psig Test Temp. 94 OF
9. Remarks: VT-2 examination was performed and acceptable on 5111/2011. Applicable documentation for replacement valve (Form NPV-1), pipe, and welding filler material was attached at the time of final review and is maintained on file.

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

Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed "At*i tb"4 6d.._K. SI Coordinator Date "71Z0' , 20k Owner or Owner' Designee, TitI6 CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 2/21/2011 to 7/20/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

37 v" Commissions IL1085 Inspector's Signature National Board, State, Province. and Endorsements nqte -t-0-1 . 20 Q Paae 6-8 aa 6vv-8 Dae.. 2~.20 ....

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

As Required by the Provisions of the ASME Code,Section III, Division 1 2 Pg. 1 of __

1. Manufactured and certified by Flowserve Corporation, 1900 South Saunders St. Raleigh, NC 27603 (name and address of N Certificate Holder)
2. Manufactured for Exelon Business Services, An Exelon Company P.O. Box 805388 Chicago, IL 60680-5388 (name and address of Purchaser)
3. Location of installation Braidwood Station East of IL 53 1-1/2 miles South of RT 113 Braidwood, IL 60408 (name and address) 72590565
4. Model No., Series No., or Type 1500-GLOBE VALVE Drawing 72590565 Rev. CRN N/A
5. ASME Code,Section III, Division 1: 1971 WINTER 1972 2 N/A (edition) (addenda date) (class) (Code Case no.)
6. Pump or valve Valve Nominal inlet size 2 Outlet size 2 fin.) (in.)
7. Material:

(a) valve Body SA182-F316 Bonnet SA479-316 Disk SA479-316 Bolting N/A (b) pump Casing Cover Bolting (a) (b) (c) (d) (e)

Cart. Nat'l Body/Casing Bonnet/Cover Disk Holder's Board Serial Serial Serial Serial No. No. No. No. No.

22BRU N/A A7-64 33619-1-17 33618-3-30

  • Supplemental information in the form of lists, sketches, or drawings may be used provided (1) size is 81/2 x 11, W2 Information in items I through 4 on this Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7P Page 6-9

FORM NPV-1 (Back - Pg. 2 of 2

. 22BRU Certificate Holder's Serial No. 22BU

8. Design conditions 2580 psi 650 'F or valve pressure class 1500 (pressure) (temperature)
9. Cold working pressure 3600 psi at 100°F 5400 4000
10. Hydrostatic test 5400 psi. Disk differential test pressure psi
11. Remarks: S.D. 61289 YOKE - MATERIAL SA105 ; HEAT NO.: L0785-1 S/N: 1 CERTIFICATION OF DESIGN Design Specification certified by L Ike Ezekoye P.E. State PA Reg. no. 18379-E Design Report certified by P.E. State - Reg. no.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this pump or valve conforms to the rules for construction of the ASME Code,Section III, Division 1.

N Certificate of Authorization No. N-1562 Expires 11-26-12 Date

  • Name Flowserve Corporation Signed IIN Certificate Holder) (authorized representative)

CERTIFICATE OF 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 NC and employed by HSB CT

./. . . of Hartford, CT have inspected the pump, or valve, described in this Data Report on f, and state that to the best of my knowledge and belief, the Certificate Holder has constructed this pump, or valve, in accordanle 4ith the ASME Code,Section III, Division 1.

By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the component described in this Data 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.

Date __ L Signed I Commissions I A 1*7- *!-, f ,C-5.,-

ff NNet'l. 8d. (Incl. endorsements) end state or prov. and no.)

3 Page 6-10

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

1. Owner  : Exelon Generation Co., LLC Date 3/22/2010 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1
2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #01115699-01 Repair/Replacement Organization P.O., Job No., etc
3. Work Performed By: Braidwood Station Mechanical Maintenance Type Code Symbol Stamp: None Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Authorization No.: None Expiration Date: None
4. Identification of System: Containment Spray (CS) (Class 2) 5 (a) Applicable Construction Code: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases (b) Applicable Edition of Section Xl Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section Xl Code Cases used: None
6. Identification of Components:

Name of Name of Manufacturer National Other Year Built Corrected ASME Code Component Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No) 3/4"-10 Flange Not Recorded Not Recorded Not 2CS01SA Not Recorded Removed No Bolting at Applicable (Connections Containment Spray CS-20-F-2, CS-Eductor 2CS01SA 20-F-3, and CS-20-F-4) 3/4"-10 Heavy Hex NOVA / AUGE Heat 241436 Not Cat ID 1394886-1 2009 Installed No Nuts Industrial Lot 50182991 Applicable UTC 2842694 Fasteners LLC 3/4"-10 Threaded NOVA / Heat 243163 Not Cat ID 37094-1 2009 Installed No Rod AUGE Industrial Lot 50159824 Applicable UTC 2823137 Fasteners LLC Trace 0K45

7. Description of Work: Bolted connections CS-20-F-2 and CS-20-F-4 were identified as leaking (reference IR 745929). Removed bolting closest to source of leakage at three bolted connections on eductor and performed VT-1 examination on 3/3/2010. No wastage was noted, but existing studs were replaced with new material.
8. Tests Conducted: Hydrostatic [I Pneumatic [I Nominal Operating Pressure 0 Exempt 0 Other [] Pressure Not Applicable psig Test Temp. Not Applicable °F
9. Remarks: Section Xl pressure testing is not applicable. Applicable documentation for the replacement threaded rod and heavy hex nuts was attached at the time of final review and is maintained on file.

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

Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed 9 . 4 ISI Coordinator Date __ _, 20 Owner or Ownelvs Designee, 4ýitle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 5/29/2009 to 3/22/2010, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

L--- _" Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date 2-Lý3-z-* ,20.-jZ Page 6-11

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co.. LLC Date 7/5/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit 2 Work Order #01299417-01 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Repair Organization P.O., Job No., etc
3. Work Performed By: Shaw / Stone & Webster Code Symbol Stamp: None Address: 36400 S. Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: Main Feedwater (FW) Class 2 system 5 (a) Applicable Construction Code: ASME Section III 1974 Edition, Summer 1974 Addenda, Code Cases: 1644 (N71, N249) and 1651 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 2001 Edition with 2003 Addenda (c) Section Xl Code Cases used: None
6. Identification of Comp nents Repaired or Replaced and Replacement Com ponents:

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

PSA- 10 Mechanical ITT Grinnell S/N 7036 Not 2FW0501 1S 1980 Replaced No Snubber Applicable B" Snubber 2FW05011S

'B" Snubber PSA-10 Mechanical Basic-PSA Inc. S/N 41260 Not Cat ID 27676-1 1999 Replacement No Snubber Applicable UTC 2052199

7. Description of Work: Existing snubber exhibited marginal performance during A2R14 functional testing (reference Issue Report 985759) and was replaced in A2R1 5. The replacement snubber was functionally tested prior to installation.
8. Tests Conducted: Hydrostatic El Pneumatic [] Nominal Operating Pressure El Other E] Pressure Not Applicable psig Test Temp. Not Applicable 'F
9. Remarks: VT-3 exam of snubber was performed after reinstallation on 4/25/2011. Applicable snubber documentation was attached at the time of final review and is maintained on file.

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

Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable z Signed 6Ai J, '4L-. ISI Coordinator Date 7ZZ0 ,'20_L Owne, or Owner'l Designee, Titld-CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid oommission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of IL and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/13/2011 to 7/5/2011, and state that to the best of my knowledge and belief, th6 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 lnspecto,- nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Fu,-thermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

'7

".'- \/-L-' -Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date 1 -(,< .20 k \

Page 6-12

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co.. LLC Date 8/1/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit 2 Work Order #01408014-01 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Repair Organization P.O., Job No., etc
3. Work Performed By: Shaw / Stone & Webster Code Symbol Stamp: None Address: 36400 S. Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: Main Steam (MS) (Class 2 System) 5 (a) Applicable Construction Code: ASME Section III 1974 Edition, No Addenda, No Code Cases (b) Applicable Edition of Section X1 Utilized for Repairs or Replacements: 2001 Edition with 2003 Addenda (c) Section XI code Cases used: None
6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Component Name of Manufacturer National Other Identification Year Built Repaired, ASME Code Manufacturer Serial No. Board No. Replaced, or Stamped (Yes Replacement or No) 6" Safety Relief Valve Dresser Spring: B19 Not Valve 2MS013A Unknown Replaced Yes (Valve)

Main Spring and Main Disc: ADE57 Applicable (Serial Number (Valve Built Disc for Safety Relief BR09654) in 1979)

Valve 2MS013A 6" Safety Relief Valve Dresser 163636-3 Not Cat ID 1432297-1 2011 Replacement No Main Spring (AGD97) Applicable UTC 2883943 6" Safety Relief Valve Dresser ADE71 Not Cat ID 1387627-1 2001 Replacement No Main Disc Applicable UTC 2663784

7. Description of Work: Removed valve was sent to NWS Technologies for set point verification and refurbishment under PO #473892, valve UTC 2714347. NWS Technologies replaced existing main spring and main disc of valve with parts provided by Exelon. Valve was reinstalled back to same position.
8. Tests Conducted: Hydrostatic C3 Pneumatic _] Nominal Operating Pressure 0 Other 0l Pressure Not Applicable psig Test Temp. Not Applicable IF
9. Remarks: Section XI pressure testing was not applicable. Applicable documentation for refurbished valve (NVR-1) and replacement disc (N-2 Certificate Holders' Data Report for Identical Nuclear Parts and Appurtenances) were attached at the time of final review and is on file.

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

Type Code,§ymbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable 7

Signed -*¥Ad 4 6_

  • -/., ISI Coordinator Date b/i ,20 i__

Owner or Owner's Designee, F4de CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 2/21/2011 to 8/1/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

J-

  • Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date ý t- - ,20X.\

Page 6-13

FORM NVR-1 REPORT OF REPAIR IXI REPLACEMENT Ell 6 9 0 5 5 OF NUCLEAR PRESSURE RELIEF DEVICES

1. Work performed by: NWS Technologies, LLC Purchase Order # 473892 131 Venture Boulevard, Spartanburn, SC 29306
2. Work performed for: Exelon Corporation, Braidwood Station 314. Owner - name, address and identification of nuclear power plant: Exelon Corp. - Braidwood Station East of IL RT 53, 1-1/2 Miles South of RT 113 Braidwood IL 60408
5. a: Repaired pressure relief device: Main Steam Safety Valve b: Name of manufacturer: Consolidated / Dresser c: Identifying nos.

3707R BR09S654 n/a steam 6" 1979 (type) (mfr's S/PN) (NB#) (service) (size) (yr.built) d: Construction Code: ASME / III / 1 1974 n/a n/a 2 (name/section/division) (edition) (addenda) (Code Cases(s)) (Code Class)

6. ASME Code Section Xl applicable for inservice inspection: 2001 2003 n/a (edition) (addenda) (Code Case(s))
7. ASME Code Section Xl used for repairs, replacements: 2001 2003 n/a (edition) (addenda) (Code Case(s))

I n/a

8. Construction Code used for repairs, replacements: 1974 n/a (edition) (addenda) (Code Case(s))
9. Design responsibilities: n/a
10. Opening pressure: 1220 psig Set-pressure adjustment made at: NWS Technologies, LLC using steam
11. Description of work (include name and identifying number of replacement parts): Disassembled, inspected, installed a preoxidized disc, lapped and passivated nozzle seat, replaced spring assembly, cleaned, lubricated, assembled. Certified set-pressure and seat tightness using steam.
12. Remarks: NWS Traveler # 11-150. Replacement disc s/n ADE71, new replacement spring assy s/n AGD97.

CERTIFICATE OF COMPLIANCE I, Jason C. Gibson certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code '"VR" and "NR" rules.

National Board Certificate of Authorization No. 632 to use the 'VR" stamp expires April 3, 2012.

National Board Certificate of Authorization No. 81 to use the "NR" stamp expires April 9, 2012.

'11-,-111i NWS Technologies, LLC q-c.u4t*oze Manager, QA

. Obte Renair Oroanization ý-Authorlzedrepresentative Title

.... r CERTIFICATE OF INSPECTION I, Charles F. Toegel Jr. holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT of Hartford, CT have inspected the repair, modification or replacement described in this report on 23 A*lL.I( and state that to the best of my knowledg6 and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.

By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected 4'lhis -ispectn.

4 / - ' - NB #8462, A, N, I NC# 1073 s ignat"uren oatd Commissions (NB (tnci endorsements), jurisdiction,& no.)

Page 6-14

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co., LLC Date 7/28/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit 2 Work Order #01270008-01 Address: 35100 S. Rte. 53, Suite 84. Braceville, IL 60407 Repair Organization P.O., Job No., etc
3. Work Performed By: Shaw / Stone & Webster Code Symbol Stamp: None Address: 36400 S. Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: Main Steam (MS) (Class 2 System) 5 (a) Applicable Construction Code: ASME Section Il11974 Edition, No Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 2001 Edition with 2003 Addenda (c) Section Xl code Cases used: None
6. Identification of Coi ponents Repaired or Replaced and Replacement Components:

Name of Component Name of Manufacturer National Other identification Year Built Repaired, ASME Code Manufacturer Serial No. Board No. Replaced, or Stamped (Yes Replacement or No) 6" Safety Relief Valve Dresser BR09651 Not 2MS013B Unknown Replaced Yes (Valve) 2MS013B Applicable 6" Safety Relief Valve Dresser DA 34740 Not Cat ID 1445407-1 2010 Replacement No Applicable UTC 2885034

7. Description of Work: Existing relief valve was removed valve and sent to NWS Technologies for set point verification and refurbishment, replaced with a tested spare relief valve.
8. Tests Conducted: Hydrostatic E0 Pneumatic [] Nominal Operating Pressure 0 Other E] Pressure Not Applicable psig Test Temp. Not Applicable OF
9. Remarks: Section XI pressure testing applicable. Applicable documentation for refurbished valve (Form NVR-1) was attached at the time of final review and is on file.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI. Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed , &Ue OIL-.,,. ISI Coordinator Date 7 2: ,20JL Owner or Owner's Designeg, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 3/17/2009 to 7/28/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

4 L -"

  • Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date7 '!' ý- 20 k Page 6-15

. ,

FORM NVR-1 REPORT OF REPAIR S REPLACEMENT C3 OF NUCLEAR PRESSURE RELIEF DEVICES

1. Work performed by: NWS Technologies, LLC Purchase Order # 474050 131 Venture Boulevard, Spartanburg, SC 29306 16905 4
2. Work performed for: Exelon Corporation, Braidwood Station 3/4. Owner - name, address and identification of nuclear power plant: Exelon Corp. - Braidwood Station East of ILRT 53, 1-1/2 Miles South of RT 113 Braidwood IL60408
5. a: Repaired pressure relief device: Main Steam Safety Valve b: Name of manufacturer: Consolidated / Dresser c: Identifying nos.

3707RA-RT25 DA34740 n/a steam 6" 2010 (type) (mfrs SIN) (NB#) (service) (size) (yr.built) d: Construction Code: ASME / III / 1 1974 n/a n/a 2 (name/section/division) (edition) (addenda) (Code Cases(s)) (Code Class)

6. ASME Code Section XI applicable for inservice inspection: 2001 2003 n/a (edition) (addenda) (Code Case(s))
7. ASME Code Section XI used for repairs, replacements: 2001 2003 n/a (edition) (addenda) (Code Case(s))
8. Construction Code used for repairs, replacements: 1974 n/a n/a (edition) (addenda) (Code Case(s))
9. Design responsibilities: n/a
10. Opening pressure: 1235 psig Set-pressure adjustment made at: NWS Technologies, LLC using steam
11. Description of work (include name and identifying number of replacement parts): Valve had not been used at site.

Disassembled, inspected, reused disc, lapped and passivated nozzle seat, cleaned, lubricated, assembled.

Certified set-pressure and seat tightness using steam.

12. Remarks: NWS Traveler # 11-154. No parts were replaced. Set was changed from 1205 to 1235 psig.

CERTIFICATE OF COMPLIANCE I, Jason C.Gibson certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules.

National Board Certificate of Authorization No. 632 to use the "VR" stamp expires April 3, 2012.

National Board Certificate of Authorization No. 81 to use the "NR" stamp expires April 9, 2012.

1lZzol NWS Technologies, LLC C_,

C_. Manager, QA Date Repair Organization Authorized representative Title CERTIFICATE OF INSPECTION I, Charles F. Toegel Jr. holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT of Hartford, CT have inspected the repair, modification or replacement described in this report on 23,4PRIL- Zoii and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules.

By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any man er for y personal injury, property damage or loss of any kind arising from or connect iis i ion.

Date 6f v It I NBp#n8462, A, N, I NC# 1073

'Datel p~ect~'Signaire fiI I/ ' Commissions (NB (inci endorsements), jurisdiction,& no.),.

Page 6-16

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co.. LLC Date 8/1/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit 2 Work Order #01 408012-01 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Repair Organization P.O., Job No., etc
3. Work Performed By: Shaw / Stone & Webster Code Symbol Stamp: None Address: 36400 S. Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: Main Steam (MS) (Class 2 System) 5 (a) Applicable Construction Code: ASME Section III 1974 Edition, No Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 2001 Edition with 2003 Addenda (c) Section XI code Cases used: None
6. Identification of Components Repaired or Replaced and Re placement Components:

Name of Component Name of Manufacturer National Other Identification Year Built Repaired, ASME Code Manufacturer Serial No. Board No. Replaced, or Stamped (Yes Replacement or No) 6" Safety Relief Valve Dresser Spring: B18 Not Valve 2MS014A Unknown Replaced Yes (Valve)

Main Spring and Main Disc: AED43 Applicable (Serial Number (Valve Built Disc for Safety Relief BR09650) in 1979)

Valve 2MS014A 6" Safety Relief Valve Dresser 163636-4 Not Cat ID 1432297-1 2011 Replacement No Main Spring (AGD98) Applicable UTC 2883943 6" Safety Relief Valve Dresser ADE47 Not Cat ID 1387627-1 2001 Replacement No Main Disc Applicable UTC 2700421

7. Description of Work: Removed valve was sent to NWS Technologies for set point verification and refurbishment under PO #473892, valve UTC 2714348. NWS Technologies replaced existing main spring and main disc of valve with parts provided by Exelon. Valve was reinstalled back to same position.
8. Tests Conducted: Hydrostatic D] Pneumatic [] Nominal Operating Pressure 0 Other 0 Pressure Not Applicable psig Test Temp. Not Applicable OF
9. Remarks: Section XI pressure testing was not applicable. Applicable documentation for refurbished valve (NVR-1) and replacement disc (N-2 Certificate Holders' Data Report for Identical Nuclear Parts and Appurtenances) were attached at the time of final review and is on file.

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

Type CodeymboI Stamp: Not plicable Certificate of Authorization No.: Not Applicable Signed .LAT/ ('% ISI Coordinator Date _____,20-__

Owner or Owner's Designee, TitlV CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 2/21/2011 to 8/1/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

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

____ ------

,-____--__... . Commissions IL(1086 Inspector's Signature National Board, State, Province, and Endorsements Date L - 20-.Lk Page 6-17

' f FORM NVR-1 REPORT OF REPAIR CK REPLACEMENT 29 OF NUCLEAR PRESSURE RELIEF DEVICES

1. Work performed by: NWS Technologies, LLC Purchase Order # 473892 131 Venture Boulevard, SDartanbum, SC 29306
2. Work performed for: Exelon Corporation, Braidwood Station 1 A 9055 3/4. Owner - name, address and identification of nuclear power plant: Exelon Corp. - Braidwood Station East of ILRT 53,.1-1/2 Miles South of RT 113 Braidwood IL60408
5. a: Repaired pressure relief device: Main Steam Safety Valve b: Name of manufacturer. Consolidated I Dresser c: Identifying nos.

3707R BRO9650 n/a steam 6" 1979 (type) Craf(ms SIN) (INB#) (service) (size) (yr.built) d: Construction Code: ASME I III / 1 1974 n/a n/a 2 (name/sectlonIldslon) (edition) (addenda) (Code Cases(s)) (Code Class)

6. ASME Code Section Xl applicable for inservice inspection: 2001 2003 n/a (edition) (addenda) (Code Case(s))
7. ASME Code Section XI used for repairs, replacements: 2001 2003 n/a (edition) (addenda) (code Case(s))
8. Construction Code used for repairs, replacements: 1974 n/a n/a (edition) (addenda) (Code Case(s))
9. Design responsibilities: n/a
10. Opening pressure: 1235 psig Set-pressure adjustment made at: NWS Technologies, LLC using steam
11. Description of work (include name and identifying number of replacement parts): Disassembled, inspected, installed a preoxidized disc, lapped and passivated nozzle seat, replaced spring assembly, cleaned, lubricated, assembled. Certified set-pressure and seat tightness using steam..
12. Remarks: NWS Traveler # 11-149. Reolacement disc s/n ADE47. new reolacement sorina assy s/n AGD98.

CERTIFICATE OF COMPLIANCE I, Jason C. Gibson certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules.

National Board Certificate of Authorization No. 632 to use the 'VR" stamp expires April 3,2012.

National Board Certificate of Authorization No. 81 to use the "NR' stamp expires April 9, 2012.

___il____

. A-,*,

NWS Technologies, LLC . C&..- Me.

aanager, QA Rnpair C-rninztitn v Authorized reoresentative trdle t,,aa'l,*

CERTIFICATE OF INSPECTION I, Charles F. Toegel Jr. holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT of Hartford, CT have Inspected the repair, modification or replacement described In this report on z,3 ,TAfa.. zot and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules.

By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described in this report Furthermore, neither the undersigned nor my from employer shall be liable in any manner for any personal injury, property damage or loss of any kind arisin7 or connectedv~ in)ct*.

ins from o2, A, N, I NC# 1073 Date ioA#s §gn r Commissions (NB (Inci endorsements), Jurisdiction,& no.)

Page 6-18

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co., LLC Date 8/2/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit 2 Work Order #01408011-01 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Repair Organization P.O.. Job No.. etc
3. Work Performed By: Shaw / Stone & Webster Code Symbol Stamp: None Address: 36400 S. Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: Main Steam (MS) (Class 2 System) 5 (a) Applicable Construction Code: ASME Section III 1974 Edition, No Addenda, No Code Cases (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements: 2001 Edition with 2003 Addenda (c) Section XI code Cases used: None
6. Identification of Components Repaired or Replaced and R placement Components:

Name of Component Name of Manufacturer National Other Identification Year Built Repaired, ASME Code Manufacturer Serial No. Board No. Replaced, or Stamped (Yes Replacement or No) 6" Safety Relief Valve Dresser BR09656 Not Valve 2MS014C Not Replaced Yes Valve 2MS014C Applicable Recorded 6" Safety Relief Valve Dresser DA-34741 Not Cat ID 1445405-1 2010 Replacement Yes Applicable UTC 2869321

7. Description of Work: Removed valve was sent to NWS Technologies for set point verification and refurbishment, replacement valve was refurbished and tested under PO #473371, valve UTC 2869321.
8. Tests Conducted: Hydrostatic C] Pneumatic C] Nominal Operating Pressure 0 Other [] Pressure Not Applicable psig Test Temp. Not Applicable IF
9. Remarks: Section Xl pressure testing was not applicable. Applicable documentation for refurbished valve (NVR-1) was attached at the time of final review and is on file.

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

Type Code symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed 4 - e#1VO-1d4~t 15,)Ad.

Coordinator Date ,201-Owner or Owner's Designeer"itle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 2/21/2011 to 8/2/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

J,- , Commissions IL1085 Inspector's Signature National Board, State. Province, and Endorsements Date r ,20_1L Page 6-19

FORM NVR-1 REPORT OF REPAIR 99 REPLACEMENT 0 OF NUCLEAR PRESSURE RELIEF DEVICES

1. Work performed by: NWS Technologies, LLC Purchase Order # 473371 131 Venture Boulevard, Soartanburq, SC 29306
2. Work performed for: Exelon Corporation, Braidwood Station I 18 '15 6i 1) 314. Owner - name, address and identification of nuclear power plant: Exelon Corp. - Braidwood Station East of IL RT 53, 1-1/2 Miles South of RT 113 Braidwood IL60408
5. a: Repaired pressure relief device: Main Steam Safety Valve b: Name of manufacturer: Consolidated / Dresser c: Identifying nos.

3707RA-RT25 DA34741 n/a steam all 2010 (type) (mfr's SIN) (1NJB#) (service) (size) (yr.built) d: Construction Code: ASME I III / 1 1974 n/a n/a 2 (name/section/diviaion) (edition) (addenda) (Code Cases(s)) (Code Cases)

6. ASME Code Section Xl applicable for inservice inspection: 2001 2003 n/a (edition) (addenda) (Code Case(s))
7. ASME Code Section XI used for repairs, replacements: 2001 2003 n/a (edition) (addenda) (Code Case(s))
8. Construction Code used for repairs, replacements: 1974 n/a n/a (edition) (addenda) (Code Case(s))
9. Design responsibilities: n/a
10. Opening pressure: 1220 psig Set-pressure adjustment made at: NWS Technologies, LLC using steam
11. Description of work (include name and identifying number of replacement parts): New valve. Disassembled, inspected, lapped and preoxidized disc, lapped and passivated nozzle seat, tested spring rate, cleaned, lubricated, assembled. Certified set-pressure and seat tightness using steam.
12. Remarks: NWS Traveler # 11-126. No parts were replaced.

CERTIFICATE OF COMPLIANCE I, Jason C. Gibson certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code 'IR" and "NR" rules.

5 National Board Certificate of Authorization No. S32 to use the 'y R" stamp expires April 3, 2012.

National Board Certificate of Authorization No. 81 to use the "NR" stamp expires April 9, 2012.

%/i NWS Technologles, LLC - z Manager, QA Date Repair Organization (L/ Authorized representative Title CERTIFICATE OF INSPECTION I, Charles F. Toegel Jr. holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT of Hartford, CT have inspected the repair, modification or replacement described in this report on /3.AqLi.2?l/ 'and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules.

By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected

  • i*nspe.ot

.. N8...U2, A, N, I NCO 1073

/Daie i In~ct~s ggnatuit I Commissions (NB (mine endorsements), jurisdiction,& no.)

Page 6-20

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co., LLC Date 6/8/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #00631306-01 Repair Organization P.O., Job No., etc
3. Work Performed By: Braidwood Station Mechanical Maintenance Type Code Symbol Stamp: None Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Authorization No.: None Expiration Date: None
4. Identification of System: Reactor Coolant (RC) (Class 1) 5 (a) Applicable Construction Code: Piping: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases Valves: ASME Section III 1974 Edition, Summer 1976 Addenda, Code Case N-141 (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Con ponents Repaired or Replaced and Replacement Con oonents:

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

Unit 2 Reactor Head Vent Unknown Unknown Not 2RC014A through Not Removed Unknown Valves (2RC014A, Applicable 2RC01 4D Recorded 2RC014B, 2RC014C and Lines 2RC014D) and 2RC031DA-1" associated piping 2RC031DB-1" Solenoid Valve Valcor Assembly Not Cat ID 1397111-1 2011 Installed Yes Assemblies Engineering Serial Numbers Applicable UTC 2881807 Corporation 4 and 5 Valve Serial Numbers 64, 65, 66, and 67 3/32" ER308/308L Arcos Industries, Heat 739540 Not Cat ID 8497-1 2010 Installed No LLC Lot CT9218 Applicable UTC 2870439 Control 9218

7. Description of Work: Replaced existing reactor head vent manifold valves (which leaked by seats) with new solenoid valve assemblies. Three Class 1 field welds (3-3, 5-1, and 11-1) were performed by Braidwood Mechanical Maintenance. The Class 1 field welds were examined by liquid penetrant method.
8. Tests Conducted: Hydrostatic C] Pneumatic [] Nominal Operating Pressure [I Exempt 0 Other 0 Pressure Not Required _ psig Test Temp. Not Required *'F
9. Remarks: Section X1 pressure testing is not required per IWA-4540(b)(6), but were examined by VT-2 during the system leakage test on 5/11/2011.

Applicable documentation for replacement assemblies (Form NPP-1), solenoid valves (Form NPV-1), and weld filler material was attached at the time of final review and is maintained on file.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI. Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed , i-X*-, Isi 13 Coordinator Date 6/4 ,20 Owner or Owner'§ Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 3/1/2011 to 6/8/2011. and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

L ____.__,____-_--..-_.___Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Page 6-21 Date 1 I , 20k%

FORM NPP-1 CERTIFICATE HOLDERS' DATA REPORT FOR FABRICATED Valcor#21 NUCLEAR PIPING SUBASSEMBUES*

As Required by the Provisions of the ASME Code,Section III, Division 1 Pg. 1 of 2 1.Fabricated and certified by Valcor Engineering Corp.,(name2andLawrence Road, Springfield, NJ 07081 address of NPT Certificate Holder)

2. Fabricated for Exelon Nuclear, 4300 Winfield Road, Warrenville, IL 60555 (name and address)
3. Location of installation Braidwood Generating Station, IL (name and address of Purchaser)
4. Type 218135101 SN: 4 N/A 218135101 N/A 2011 (CTry.

Holder's serial no.) (CRN) (drawing no.) (Net'l ad. no.) (year built)

5. ASME Code,Section III, Division 1: 1974 Summer 75 1 NA (edition) (addenda date) (class) (Code Case no.)
6. Shop hydrostatic test 5500 psi at 70 oF (ifperformed)
7. Description of piping Assembly consists of 2 Solenoid Valves PN 214130005 and Nipples (1 of each)

PN V52638-62. PN V5263B-63. and PN V52638-64 SA-376 TPE 304

8. Certificate Holders' Data Reports properly identified and signed by commissioned inspectors have been furnished for the following items of this report: Solennid Valve PN 2141130005 SN 64 & 65
9. Remarks:

CERTIFICATE OF SHOP COMPLIANCE We certify that the statements made in this report are correct and that the fabrication of the described piping subassembly conforms to the rules for construction of the ASME Code, Section I11,Division 1.

NPT Certificate of Authorization No. N-1077 Expires 5/6/2011 Date 1/27/2011 Name Valcor Engineering Corp.

(NPT Certificate Holderl Signed A I

-\-,

represenlative)

CERTIFICATE OF SHOP 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 New Jersey and employed by OneBeacon America Insurance Company

_ of Lynn, MA have inspected the piping subassembly described in this Data Report on January 27,2011 , and state that to the best of my knowledge and belief, the Certificate Holder has fabricated this piping subassembly in accordance with the ASME Code.Section III,Division 1.

By signing this certificate neither the inspector nor hi employer makes any warranty, expressed or implied, concerning the piping subassembly described in this Data Report. Furthermore, e e nspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arisin or conn t d with this inspection.

Date January 27, 2011 Signed -- (7A0oflzedNuclear Inspector)

Commissions (Nat'l. Bd. (ind. endorsements) and state or orov. and no.)

' Supplemental information in the form of lists, sketches, or drawings may be used provided (I1 size is 8V2 x II, (21 information in items I through 4 on this Data Report is included on each sheet. (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

(7198) This form (E000621 may be obtained from the Order Dept., ASME. 22 Law Drive. Box 2300, Fairfield, NJ 07007-2300.

Page 6-22

FORM NPP-1 CERTIFICATE HOLDERS' DATA REPORT FOR FABRICATED Valcor#22 NUCLEAR PIPING SUBASSEMBLIES*

As Required by the Provisions of the ASME Code,Section III, Division 1 Pg. 1 of 2

1. Fabricated and certified by Valcor Engineering Corp., 2 Lawrence Road, Springfield, NJ 07081 (name and address of NPT Certificate Holder)
2. Fabricated for Exelon Nuclear, 4300 Winfield Road, Warrenville, IL 60555 (name and address)
3. Location of installation Braidwood Generating Station, IL (name and address of Purchaser)
4. Type 218135101 SN: 5 N/A 218135101 N/A 2011 (Cart. Holder's serial no.) (CRN) (drawing no.) (Nat'l. Od.no.) (year built)
5. ASME Code,Section III, Division 1: 1974 Summer 75 1 NA (edition) (addenda date) (class) (Code Case no.)
6. Shop hydrostatic test 5500 psi at 70 *F (if performed)
7. Description of piping Assembly consists of 2 Solenoid Valves PN 214130005 and Nipples (1 of each)

- PN V52638-62. PN V52638-63. and PN V52638-64 SA-376 TP. 304

8. Certificate Holders' Data Reports properly identified and signed by commissioned inspectors have been furnished for the following items of this report: Solenoid Valve PN *714130005SN 66 & 67
9. Remarks:

CERTIFICATE OF SHOP COMPLIANCE We certify that the statements made in this report are correct and that the fabrication of the described piping subassembly conforms to the rules for construction of the ASME Code,Section III. Division 1.

No. N-1077 Expires 5/6/2011 Date Certificate of AuthorizationName NPT 1/27/2011 Valcor Engineerfing Corp. Signed * '*

(NPT Certificate Holder) (sh~frzed reprwntativel CERTIFICATE OF SHOP INSPECTION 1, the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by OneBeacon America Insurance Company of Lynn. MA have inspected the piping subassembly described in this Data Report on January 27, 2011 , and state that to the best of my knowledge and belief, the Certificate Holder has fabricated this piping subassembly in accordance with the ASME Code.Section III, Division 1.

By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the piping subassembly described in this Data Report. Furthermore, ne e iopector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from r connct ith this inspection.

Date January 27, 2011 Signed V

,ad uclerInpector)

Commissions PJa")a a io 2-(p' r INal.. Rd. had. endorsements) and stAle or pfev. and no I

  • Supplemental information in the form of lists, sketches, or drawings may be used provided (1) size is 8a 2 x 11, 12) information in items I through 4 on this Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

(7/981 This form (E00062) may be obtained from the Order Dept., ASME. 22 Law Drive. Box 2300. Fairfield, NJ 07007-2300.

Page 6-23

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co.. LLC Date 6/8/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84. Braceville, IL 60407 Work Order 000631306-02 Repair Organization P.O., Job No.. etc
3. Work Performed By: Braidwood Station Mechanical Maintenance Type Code Symbol Stamp: None Address: 35100 S. Rte. 53. Suite 84, Braceville, IL 60407 Authorization No.: None Expiration Date: None
4. Identification of System: Reactor Coolant (RC) (Class 1) 5 (a) Applicable Construction Code: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Components Repaired or Heplaced and Heplacement Coin onents:

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

Unit 2 Reactor Head Vent Unknown Unknown Not 2RC99004G Not Removed No Line Support Applicable Line 2RC031DB-1" Recorded 2RC99004G 3/32" E7018 Weld ESAB Heat M902234 Not Cat ID 8491 -1 2010 Installed No Electrode Lot 2HO12D04 Applicable UTC 2870136 Control NNN024

7. Description of Work: Removed and reinstalled existing support pieces in order to assist with replacement of reactor head vent manifold valves.
8. Tests Conducted: Hydrostatic [] Pneumatic [] Nominal Operating Pressure C1 Exempt 0 Other 0 Pressure Not Required psig Test Temp. Not Required IF
9. Remarks: Applicable documentation for replacement material and weld filler material was attached at the time of final review and is maintained on file.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI. Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed "I.2 ,-l , - ,SI Coordinator Date .,& 20 Owner or Owner' /Designee, TiL%

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/5/2011 to 6/8/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

I

,J. I ... _L._._. Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date 20-Page 6-24

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co.. LLC Date 6/8/2011 Address: 300 Exelon Way, Kennert Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #00631306-03 Repair Organization P.O.. Job No., etc
3. Work Performed By: Braidwood Station Mechanical Maintenance Type Code Symbol Stamp: None Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Authorization No.: None Expiration Date: None
4. Identification of System: Reactor Coolant (RC) (Class 1) 5 (a) Applicable Construction Code: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases (b) Applicable Edition of Section Xl Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section Xl Code Cases used: None 6, Identification of om ponents Repaired or Replaced and Heplacement (omponents:

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

Unit 2 Reactor Head Vent Unknown Not 2RC99008G Not Removed No Line Support Unknown Applicable Line 2RC031DA-1" Recorded 2RC99008G 3/32" E7018 Weld ESAB Heat M902234 Not Cat ID 8491-1 2010 Installed No Electrode Lot 2H012D04 Applicable UTC 2870136 Control NNN024

7. Description of Work: Removed and reinstalled existing box guide in order to assist with replacement of reactor head vent manifold valves.

. 4.'icted: Hydrostatic El Pneumatic Q Nominal Operating Pressure El Exempt a Other @ Pressure Not Required psig Test Temp. Not Required IF

9. Remarks: Appl~iLaoie documentation for replacement material and weld filler material was attached at the time of final review and is maintained on file.

CERTIFICATE OF COMPLIANCE We certify that the ýLatements made in the report are correct and this replacement conforms to the rules of the 4SME Code, Sectionjl. , Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed t-"2iM* C '-- 4* SI Coordinator Date (o/S: ,20__

Owner or Owner'sýOesignee, Tite CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/5/2011 to 6/8/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

4 .--, .Commissions ILl 085 Inspector's Signature National Board, State, Province, and Endorsements Date U 20 L\

Page 6-25

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co., LLC Date 6/8/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84, Braceville. IL 60407 Work Order #00631306-04 Repair Organization P.O., Job No., etc
3. Work Performed By: Braidwood Station Mechanical Maintenance Type Code Symbol Stamp: None Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Authorization No.: None Expiration Date: None
4. Identification of System: Reactor Coolant (RC) (Class 1) 5 (a) Applicable Construction Code: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Components Repaired or Replaced and Replacement Con ponents:

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

Unit 2 Reactor Head Vent Unknown Unknown Not 2RC99007G Not Removed No U-Bolt Support Tack Applicable Line 2RC031DB-1" Recorded Welds 2RC99007G 3/32" E7018 Weld ESAB Heat M902234 Not Cat ID 8491-1 2010 Installed No Electrode Lot 2H012D04 Applicable UTC 2870136 Control NNN024

7. Description of Work: Removed and reinstalled existing lock nut tack welds in order to assist with replacement of reactor head vent manifold valves.
8. Tests Conducted: Hydrostatic [] Pneumatic E] Nominal Operating Pressure El Exempt ED Other (D Pressure Not Required psig Test Temp. Not Required °F
9. Remarks: Applicable documentation for replacement material and weld filler material was attached at the time of final review and is maintained on file.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Sectfin X1. Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed -ISI Coordinator Date 20_1L Owner or Ownefs Designee, S ie CERTIFICATE OF INSERVICE INSPECTION I, the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/5/2011 to 6/8/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

IL- ý,L.-. Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date CLiUi ,20_1A Page 6-26

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co., LLC Date 6/8/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1 2, Plant Name: Braidwood Station Unit 2 %A1 1, n or r.4er 4nilInnrnn Al Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Repair Organization P.O., Job No., etc

3. Work Performed By: Shaw / Stone & Webster Code Symbol Stamp: None Address: 36400 S. Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: Reactor Coolant (RC) Class 1 system 5 (a) Applicable Construction Code: ASME Section 111974 Edition, Summer 1974 Addenda, Code Cases: 1644 Revision 7,1682,1683, 1685, 1686, 1651, 1728, 1729, 1734, N-180 and N-108 (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements: 2001 Edition with 2003 Addenda (c) Section Xl Code Cases used: None
6. Identification of Components Repaired or Replaced and Replacement Coin onents:

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

PSA-1/4 Mechanical Not Recorded S/N 2653 Not 2RC17069S 1977 Replaced No Snubber Applicable 2RC17069S PSA--1/4 Mechanical Basic-PSA Inc. S/N 42825 Not Cat ID 27625-1 2004 Replacement No Snubber Applicable UTC 2807875

7. Description of Work: Existing snubber exhibited declining performance during A2R14 functional testing (reference Issue Report 987527) and was replaced in A2R15. The replacement snubber was functionally tested prior to installation.
8. Tests Conducted: Hydrostatic El Pneumatic E] Nominal Operating Pressure El 0

Other C] Pressure Not Applicable psig Test Temp. Not Applicable F

9. Remarks: VT-3 exam of snubber was performed after reinstallation on 4/23/2011. Applicable snubber documentation was attached at the time of final review and is maintained on file.

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

Type Code §ymbof Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed t-4K 4A4*/ ISI Coordinator Date V'M 20 /

Owner or Owner'lDesignee, Titft CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of IL and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/13/2011 to 6/8/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

L- L t- Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date C - , 20 \

Page 6-27

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl 1 Owner  : Exelon Generation Co.. LLC Date 6/7/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53. Suite 84, Braceville, IL 60407 Work Order #01281639-02 Repair/Replacement Organization P.O., Job No., etc
3. Work Performed By: Westinghouse Electric Corporation Type Code Symbol Stamp: None Address: P. 0. Box 158, Madison, PA 15663 Authorization No.: None Expiration Date: None
4. Identification of System: Reactor Coolant/Steam Generator 5 (a) Applicable Construction Code: ASME Section III 1971 Edition, Summer 1972 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Cor onents:

Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No) 2A Steam Generator Westinghouse Unknown Not 2RC01BA Not Recorded Corrected No (Tubes)

Tubes Applicable Plugs in Hot Leg and Westinghouse Heat Not Cat ID 45903-1 Not Recorded Installed No Cold Leg End of Tubes: Electric NX4418HK Applicable Corporation/ Lot 11 UTC 2884983 Row 10, Column 50 Tooling Serial Numbers Row 11, Column 50 Specialists, Inc Hot Leg Row 10, Column 51 1X524, 1X532, Row 11, Column 51 1X533, 1X534, Row 30, Column 84 1X535, 1X536, Row 31, Column 84 1X537, IX538 Row 30, Column 85 1X539, 1X540, Row 31, Column 85 1X541, 1X542 Row 8, Column 86 Cold Leg Row 41, Column 36 1X543, 1X544, Row 45, Column 64 1X545, 1X546, Row 41, Column 93 1X550, 1X551, 1X552, 1X553, 1X554, 1X555, 1X556,_1X557

7. Description of Work: Mechanically plugged steam generator tubes in the 2A steam generator based on eddy current test results.
8. Tests Conducted: Hydrostatic [3 Pneumatic El Nominal Operating Pressure [] Exempt 0 Other 0 Pressure Not Required psig Test Temp. Not Required IF
9. Remarks: Section XI pressure testing is not applicable. Applicable material documentation for tube plugs was attached at the time of final review and is maintained on file.

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

Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed j6Ae i oId.i* SI Coordinator Date , 20_ _/

Owner or OwnEgr's Designeei'ritle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/13/2011 to 6/1/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

~' ~

Signature Page b-2B Commissions National IL1085 Board, State, Province, and Endorsements Inspector's Signature Page b-21:

,;ýo %ý,

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co., LLC Date 6/7/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #01283161-02 Repair/Replacement Organization P.O., Job No., etc
3. Work Performed By: Westinghouse Electric Corporation Type Code Symbol Stamp: None Address: P. 0. Box 158, Madison, PA 15663 Authorization No.: None Expiration Date: None
4. Identification of System: Reactor Coolant/Steam Generator 5 (a) Applicable Construction Code: ASME Section III 1971 Edition, Summer 1972 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Co ponents:

Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No) 2B Steam Generator Westinghouse Unknown Not 2RC01 BB Not Recorded Corrected No (Tubes)

Tubes Applicable Plugs in Hot Leg and Westinghouse Heat Not Cat ID 45903-1 Not Recorded Installed No Cold Leg End of Tubes: Electric NX4418HK Applicable Corporation/ Lot 11 UTC 2884983 Row 6, Column 8 Tooling Serial Numbers Row 15, Column 7 Specialists, Inc 1X517, lX518, Row 7, Column 22 1X519, 1X520, Flow 32, Column 56 1X521, 1X5221 Row 24, Column 68 1X523, 1X525 Row 32, Column 70 1X526, 1X527 Row 29, Column 95 1X528, 1X529, 1X530, 1X531 (Did Not List Which Leg Plug Was Installed)

7. Description of Work: Mechanically plugged steam generator tubes in the 2B steam generator based on eddy current test results.
8. Tests Conducted: Hydrostatic E0 Pneumatic E] Nominal Operating Pressure El Exempt 0 Other 0 Pressure Not Required psig Test Temp. Not Required IF
9. Remarks: Section Xl pressure testing is not applicable. Applicable material documentation for tube plugs was attached at the time of final review and is maintained on file.

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

Type Code Symbol Stamp: Not Applipable Certificate of Authorization No.: Not Applicable Signed W, Owner or Owner's,,esignee, Title/

ISI Coordinator Date *Lt, 20 it CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the componE its described in this Owner's Report during the period 1/13/2011 to 6/7/2011, 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 X1.

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

L . -LCommissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements n~tAL~ISs D*== *_OQ 20 " On CZ-00 Date LC I ý-

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

1. Owner  : Exelon Generation Co.. LLC Date 6/9/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1
2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53. Suite 84, Braceville, IL 60407 Work Order #01281304-02 Repair/Replacement Organization P.O., Job No., etc
3. Work Performed By: Westinghouse Electric Corporation Type Code Symbol Stamp: None Address: P. 0. Box 158, Madison, PA 15663 Authorization No.: None Expiration Date: None
4. Identification of System: Reactor Coolant/Steam Generator 5 (a) Applicable Construction Code: ASME Section III 1971 Edition, Summer 1972 Addenda, No Code Cases (b) Applicable Edition of Section Xi Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Coin onents:

Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No) 2C Steam Generator Westinghouse Unknown Not 2RC01BC Not Recorded Corrected No (Tubes)

Tubes Applicable Plugs in Hot Leg and Westinghouse Heat Not Cat ID 45903-1 Not Recorded Installed No Cold Leg End of Tubes: Electric NX4418HK Applicable Corporation/ Lot 11 UTC 2884983 Row 43, Column 41 Tooling Serial Numbers Row 49, Column 65 Specialists, Inc Hot Leg 1X514, 1X516 Cold Leg 1X513, 1X515

7. Description of Work: Mechanically plugged steam generator tubes in the 2C steam generator based on eddy current test results.
8. Tests Conducted: Hydrostatic El Pneumatic [] Nominal Operating Pressure E0 Exempt 0 Other 0 Pressure Not Required - psig Test Temp. Not Required 'F
9. Remarks: Section XI pressure testing is not applicable. Applicable material documentation for tube plugs was attached at the time of final review and is maintained on file.

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

Type Code Symbol Stamp: Not A plicable Certificate of Authorization No.: Not Applicable Signed ', ** xt.{s (/. -*t't-- ISI Coordinator Date / 201L_

Owner or Owner's Designee, Title/

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/14/2011 to 6/9/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

J- V. - -.-.- Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date t" io ,20 t Page 6-30

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co., LLC Date 6/1/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53. Suite 84, Braceville. IL 60407 Work Order #01282384-02 Repair/Replacement Organization P.O., Job No., etc
3. Work Performed By: Westinghouse Electric Corporation Type Code Symbol Stamp: None Address: P. 0. Box 158, Madison, PA 15663 Authorization No.: None Expiration Date: None
4. Identification of System: Reactor Coolant/Steam Generator 5 (a) Applicable Construction Code: ASME Section III 1971 Edition, Summer 1972 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None Id1~ntific~tinn nf Cnm nnents:

Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No) 2D Steam Generator Westinghouse Unknown Not 2RC01BD Not Recorded Corrected No (Tubes)

Tubes Applicable Plugs in Hot Leg and Westinghouse Heat Not Cat ID 45903-1 Not Recorded Installed No Cold Leg End of Tubes: Electric NX4418HK Applicable Corporation/ Lot 11 UTC 2884983 Row 17, Column 72 Tooling Serial Numbers Row 13, Column 76 Specialists, Inc Hot Leg Row 7, Column 61 1X547, 1X548, Row 47, Column 75 1X549, 1X558, Row 44, Column 73 1X559, 1X560, Row 43, Column 86 1X561, 1X562 Row 2, Column 35 Cold Leg 1X563, 1X564, 1X565, 1X566, 1X567, 1X568, 1X578, 1X579, 1T986, 1T987

7. Description of Work: Mechanically plugged steam generator tubes in the 2D steam generator based on eddy current test results.
8. Tests Conducted: Hydrostatic [] Pneumatic [] Nominal Operating Pressure [I Exempt 0 Other 0 Pressure Not Required psig Test Temp. Not Required IF
9. Remarks: Section XI pressure testing is not applicable. Applicable material documentation for tube plugs was attached at the time of final review and is maintained on file.

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

Type Code 5ymbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed ISI Coordinator Date , 20-LJ 1'//

Owner or Owner's'Designee, TitlW' ne ,TiI CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/13/2011 to 6/1/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

  • .4 *v Commissions ILl 085 Inspec :tor's Signature National Board, State, Province, and Endorsements Page 6-31 Date 20 I\

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

1. Owner  : Exelon Generation Co., LLC Date: 6/1/2011 Address: 300 Exelon Way, Kennett Square. PA 19348 Sheet 1 of 1
2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53. Suite 84, Braceville. IL 60407 Work Order 401340784-01 Repair Organization P.O., Job No., etc
3. Work Performed By: Westinghouse Electric Corporation Type Code Symbol Stamp: None Address: P. 0. Box 158, Madison, PA 15663 Authorization No.: None Expiration Date: None
4. Identification of System: Reactor Coolant/Steam Generator (RC) 5 (a) Applicable Construction Code: ASME Section III 1971 Edition, Summer 1972 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section X1 Code Cases used: None
6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No) 2B Steam Generator Westinghouse Not Recorded Not 2RC01 BB Not Removed No Secondary Side Applicable Covers 8A Recorded Inspection Covers through 8D, 9A and 9R Inspection Cover Westinghouse Serial Number: Not Cat ID 40458-1 2010 Installed No 8A Electric 00107-10 Applicable UTC 2874216-1 8B Corporation/ 00107-12 UTC 2874218-1 8C Consolidated 00107-09 UTC 2874215-1 8D Power Supply 00107-06 UTC 2874212-1 Handhole Covers Westinghouse Serial Number: Not Cat ID 34908-1 2010 Installed No 9A Electric 00107-04 Applicable UTC 2874210 9C Corporation/ 00107-01 UTC 2874207 Consolidated Power Supply

7. Description of Work: Replaced existing covers on steam generator secondary side inspection covers/handhole covers due to degraded gasket surfaces which were being trended (reference IRs 769951 and 985628). There was no active leakage identified at any of these locations.
8. Tests Conducted: Hydrostatic El Pneumatic C] Nominal Operating Pressure 0 Exempt El Other 0 Pressure Nominal psig Test Temp. Nominal "F
9. Remarks: Section XI VT-2 examination was performed and acceptable during the ascending Mode 3 walk down on 5/11/2011. There is no specific plant instrumentation for obtaining system pressure and temperature, inspection was performed with reactor coolant at 2235.6 psig at 545.430 after four hour hold time (reference WO# 1290953). Applicable documentation for replacement inspection covers was attached at the time of final review and is maintained on file.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the., SME Code,Section XI.. Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed ;6, sZ.--f 1, 9' J---'y ISI Coordinator Date 6 / , 20-._

Owner or Owner's Designee, TitA CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/13/2011 to 6/1/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

Lt..L\.-- Commissions ILl 085 Inspector's Signature National Board, State, Province, and Endorsements Date (-4 20 I.\ Page 6-32

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co.. LLC Date: 5/18/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53. Suite 84, Braceville, IL 6(407 Work Order #01340786-01 Repair Organization P.O., Job No., etc
3. Work Performed By: Westinghouse Electric Corporation Type Code Symbol Stamp: None Address: P. 0. Box 158, Madison, PA 15663 Authorization No.: None Expiration Date: None
4. Identification of System: Reactor Coolant/Steam Generator (RC) 5 (a) Applicable Construction Code: ASME Section Il 1971 Edition, Summer 1972 Addenda. No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No) 2C Steam Generator Westinghouse Not Recorded Not 2RC01 BC Not Removed No Secondary Side Applicable Covers 8A, 8B, Recorded Inspection Covers 80, and 9A Inspection Covers Westinghouse Serial Number: Not Cat ID 40458-1 2010 Installed No 8A Electric 00107-08 Applicable UTC 2874214-1 8B Corporation/ 00107-07 UTC 2874213-1 8D Consolidated 00107-13 UTC 2874219-1 Power Supply Handhole Cover Westinghouse Serial Number: Not Cat ID 34908-1 2010 Installed No 9A Electric 00107-03 Applicable UTC 2874209 Corporation/

Consolidated Power Supply

7. Description of Work: Replaced existing covers on steam generator secondary side inspection covers/handhole covers due to degraded gasket surfaces which were being trended (reference A2R14 Issue Report 980839). There was no active leakage identified at any of these locations. Due to tight clearance/contact between covers, excess material was trimmed from new covers for 8A and 86 per Westinghouse guidance (LTR-SGDA-11-136, dated April 26, 2011) a through ECR 400039.

appcrov*r*10 1JoIo

8. Tests Conducted: Hydrostatic E] Pneumatic 0] Nominal Operating Pressure 0 Exempt El 0

Other 0 Pressure Nominal psig Test Temp. Nominal F

9. Remarks: Section Xl VT-2 examination was performed and acceptable during the ascending Mode 3 walk down on 5/10/2011. There is no specific plant instrumentation for obtaining system pressure and temperature, inspection was performed with reactor coolant at 2235.6 psig at 545.43o after four hour hold time (reference WO# 1290953). Applicable documentation for replacement inspection covers was attached at the time of final review and is maintained on file.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section Xl. Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed 4"ý,, *-* (*- ISI Coordinator Date 5/il , 20__L Owner or Owner'sOesignee, Tif1e CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 4/27/2011 to 5/18/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code. Section Xl.

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

__- Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements 2 Page 6-33 Date*'- -c ,20_j_

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co., LLC Date: 6/1/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #01340787-01 Repair Organization P.O., Job No., etc
3. Work Performed By: Westinghouse Electric Corporation Type Code Symbol Stamp: None Address: P. 0. Box 158. Madison, PA 15663 Authorization No.: None Expiration Date: None
4. Identification of System: Reactor Coolant/Steam Generator (RC) 5 (a) Applicable Construction Code: ASME Section III 1971 Edition, Summer 1972 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No) 2D Steam Generator Westinghouse Not Recorded Not 2RC01 BD Not Removed No Secondary Side Applicable Covers 8D, 9A Recorded Inspection Covers and 9C Inspection Cover Westinghouse Serial Number: Not Cat ID 40458-1 2010 Installed No 8D Electric 00107-11 Applicable UTC 2874217-1 Corporation/

Consolidated Power Supply Handhole Covers Westinghouse Serial Number: Not Cat ID 34908-1 2010 Installed No 9A Electric 00107-02 Applicable UTC 2874208 9C Corporation/ 00107-05 UTC 2874211 Consolidated Power Supply

7. Description of Work: Replaced existing covers on steam generator secondary side inspection covers/handhole covers due to degraded gasket surfaces which were being trended (reference IR 985639). There was no active leakage identified at any of these locations.
8. Tests Conducted: Hydrostatic El Pneumatic C] Nominal Operating Pressure 0 Exempt 01 Other 0@ Pressure Nominal psig Test Temp. Nominal "F
9. Remarks: Section XI VT-2 examination was performed and acceptable during the ascending Mode 3 walk down on 5/11/2011. There is no specific plant instrumentation for obtaining system pressure and temperature, inspection was performed with reactor coolant at 2235.6 psig at 545.430 after four hour hold time (reference WO# 1290953). Applicable documentation for replacement inspection covers was attached at the time of final review and is maintained on file.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI. Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed - 4_

  • ISI Coordinator Date ____-_ 20 Owner or Owner9 Designee, Otle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/6/2011 to 6/1/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

L - ,._______Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date . ,20__LV Page 6-34

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI I (U'),ner  : Exelon Generation Co.. LLC i)ite 8/1/2011 u'diross: :100 Exelon Way. Konnett Square. PA 19:348 '.;heet 1 at 1 I'I.ant Name: 13raidwood Station I hnit: 2

.Aldress: :35100 S. Fife. 53. Suite 84, Braceville. IL 60407 Work Order 0l 1178448-02 Repair/Replacement Organization P.O.. Job No.. etc

3. Work Performed By: Shaw / Stone & Webster rIpe Code Symbol Stamp: None Address: 36400 South Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
1. Identification of System: Residual Heat Removal (RH) (Class 2) a ~ai Applicable Construction Code: ASME Section III 1971 Edition. Summer 1972 Addenda. No Code Cases (I)) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda Section XI Code Cases used: None
6. Identitication of Components:

Na*ane of Component Name of Manufacturer National Other '(ear Built Corrected ASME Code Manufacturer Serial No. Board No. Identification Removed. or Stamped (Yes Installed or No)

Main Pump Flange Unknown Unknown Not 2RHO1 PA Not Removed Yes (Pump)

Heavy Hex Nut (2"-8) Applicable Recorded ZRHO0 PA Pump Seal Unknown UJnknown Not L2RHO1PA Not Removed No (includinq gland plate) Applicable Recorded Heavy Hex Nut (2"-8) Ingersoll- Serial Number 880 Cat ID 39080-1 1993 Installed Yes (Form N-2)

Dresser 93P-10564 UTC 2037737 A93-01336 2RHO1 PA Pump Seal Flowserve Heat 247046 Not Cat ID 42201-1 2009 Installed No

Gland Plate) included (Gland Plate) Applicable UTC 2838057 with replacement seal Seal 09-003289
7. Description of Work: During overhaul of pump one main flange hex nut was replaced. There was no reason for replacement documented in work package.
3. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure 0 Exempt El Other El Pressure 24 (Suction)/174 (Discharge) psig Test Temp. 93/84 '"F
9. Remarks: Section XI pressure testing was acceptable on 5/6/2011 (WO# 1259540). Applicable documentation for replacement hex nut (Form N-2)

,ind pump seal was attached at the time of final review and is maintained on file. Reference IR 01246535 for documentation errors in receipt nspection package.

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

Type Code ýymbol Stamp: NoL.pp~jcabte Certificate of Authorization No.: Not Applicable Signed , ISI Coordinator Date / 20/

Owner or Owner's Designee, Tltfe CERTIFICATE OF INSERVICE INSPECTION I. the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/18/2011 to 8/1i2011. and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

- ~',~----

, -Commissions IL1085 Inspectors Signature National Board. State. Province. and Endorsements Date " ,"0 IN - -- Page 6-35b

rqjIIVI IV-1jeC l I UiJS.I .esi a * .-. .- .%

NUCLEAR PARTS AND APPURTENANCES*

As Required by the Provisions of the ASME Code,Section III Not to Exceed One Day's Production Pg. 1 of -

I. Manufactured and certified by Ingersoll-Dresser

- Pump a*T addeo . o NFT Company

-Inore Cen~tfifcat HokWa I Pump Engtnpered 'rnrnp *

2. Manufactured for Commonwealth Edison Company. Braldwood. IL .... - .. 1.

(name and sdleas of PwcftheU

3. Location of installation Braidwood Station No. 20, Braidwood IIL ASME SA 194 (aimaddfrel
4. Type: 46A4XI8 Grade 6 N/A N/A 19q3 (drawing no.) (mat'l. spoc. no.) (tal'nee ataingt3ICRN) iyeer Woitlt
5. ASME Code,Section III, Division 1: 1971 Stiinhr 1972 2 NIA ledition) addende date) (ctaeal (Coda Ca .. no.)
6. Fabricated in accordance with Const. Spec. (Div. 2 only) (no.) Revision Date
7. Remarks: * ( 942 Memorial Parkway, Phillipsburg, NJ 08865 ) 2.00" Hex Nuts for SX20WDF Pump, Vitco trace code: EAF, MR 49306-1A, Heat 32635 (Non-we Comm. Edison Order: 4P2569. IDP Order: 002-40688 Hvdrotest not required Dart;
8. Nom. thickness (in.) N/A Min. design thickness (in.) N/A Dia. ID (ft & in.) N/A Length overall (ft & in.) N/A
9. When applicable, Certificate Holders' Data Reports are attached for each item of this report:

Part or Appurtenance National Part or Appurtenance National Serial Number Board No. Serial Number Board No.

in Numerical Order in Numerical Order (1) 93P-10564 880 126)

(2) 93P-10565 881 (27)

(3) (28) 9-(4) (291 (5) (30)

(6) (31)

(7) (32)

(8) (33)

(9) (34)

(10) -k 135)

(11) (36) 4 (12) (37)

(13) (38)

(14) (39)

(15)

(16)

(17) _______________________________

(18) _______________________________

(19)

.1 I

____________________________________

____________________________________

(40)

(41) 142)

(43)

(44)

(20) 4 (45)

(21) .3. (46)

(22) (47)

(23) 148)

(24) (49)

(25) (501

10. Design pressure 600 psi. Temp. 400 Page 7 OF. Hydro. test pressure N/A when apgaca*

e at ter

  • 'uoplemental information in the form of lists. sketches, or drawings may be used provided (1) size is 8fl x 11, (2) Infotmation in iteys 2 and 3 on this Oata

.s included on each sheet. (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

a ~@s*ua 5~ a ~ . - -

Certificate Holder's Senal Nos. 9 3P- 10564 through -9 3P- I CERTIFICATION OF DESIGN Design specifications certified by Albert John Wettlaufer P.E. State PA Rag. no.km

.!ahen a(oplicaheI Design report

  • certified by N/A P.E. State N/A Reg. no.

(whon aopiecablel CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this (these) Nuts conforms to the rules of construction of the ASME Code,Section III, Division 1.

NPT Certificate of Authorization No. N- 1867 Expires Sepvtember 27, 1995 r/ Ingersoll-Dresser Pump Company Date Name Engineered Pump Group Signed J1L.LLL.......Nam ,iri'r c~rate Holder)

CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Proi PA and employed by H.S.B.I. & 1. Co.

of - Hartford, CT have inspected these items described in this Data Report on -_____________ nd sttet the best of my knowledge and belief, the Certificate Holder has fabricated these parts or dppurtenances in accordance with the ASME Code.

Ill, Division 1. Each part listed has been authorized for stamping on the date shown above.

By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied. concerning the equipment d4 in this Data Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property def loss of any kind arising from or connected with this inspection.

I- I - - W tý __ Authorizd441' spector) Ir Weall. ad. Md gfldorserents) and state or pro Page 6-37

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner  : Exelon Generation Co.. LLC Date 7/20/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #01359794-01 Repair/Replacement Organization P.O., Job No.. etc
3. Work Performed By: Braidwood Station Mechanical Maintenance Type Code Symbol Stamp: None Address: 35100 South Route 53, Braceville, IL 60407 Authorization No.: None Expiration Date: None
4. Identification of System: Residual Heat Removal (RH) (Class 2) 5 (a) Applicable Construction Code: ASME Section III 1974 Edition, No Addenda. No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Components:

Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No. Board No. Identification Removed. or Stamped (Yes Installed or No) 2RH02AB (2B RHR Heat Joseph Oats Unknown Not 2RH02AB Not Removed Yes Exchanger) Cover Bolting (HX) Applicable Recorded 1 1/8"-8 Heavy Hex Nuts NOVA Machine Heat 13616 Not Cat ID 37040-1 2003 Installed No Products Lot C040082008 Applicable UTC 2678422 Trace TRS 1 1/8"-8 Threaded Rod NOVA Machine Heat 59761 Not Cat ID 37102-1 2009 Installed No Products Lot 50191408 Applicable UTC 2849029 Trace 3U41

7. Description of Work: Evidence of leakage was noted during walk down (reference IR 1095831), existing bolt and hex nuts were removed to perform VT exam (no degradation noted). Existing material was replaced for ALARA purposes.
8. Tests Conducted: Hydrostatic E] Pneumatic 0l Nominal Operating Pressure C0 Exempt 0 Other E3 Pressure Not Applicable psig Test Temp. Not Applicable *F
9. Remarks: Section Xl pressure testing is not applicable. Applicable documentation for replacement bolting materials was attached at the time of final review and is maintained on file.

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

Type Code .9ymbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed t -- -ISI Coordinator Date 7/2.6 ,20'/

Owner or Owner'ý-besignee, TitIl CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 11/12/2010 to 7/20/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

L . Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date -*- -- ,20 kV Page 6-38

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

1. Owner  : Exelon Generation Co., LLC Date 6/8/2011 Address: 300 Exelon Way. Kennett Square, PA 19348 Sheet 1 of 1
2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #01302365-01 Repair/Replacement Organization P.O., Job No., etc
3. Work Performed By: Shaw / Stone & Webster Type Code Symbol Stamp: None Address: 36400 South Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: Residual Heat Removal (RH) (Class 2) 5 (a) Applicable Construction Code: ASME Section III 1971 Edition, Winter 1972 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Components:

Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No) 2RH8734A Valve Disk Kerotest Not Recorded Not 2RH8734A Not Recorded Removed Yes (Valve)

Applicable Disk from Spare Valve Flowserve Valve Serial Not Cat ID 1969-1 2011 Installed Yes (Valve)

Assembly Number: Applicable UTC 2884282 (2" 1500# Class Y-Globe 92BRU Valve) Disk Serial Number:

33618-5-2

7. Description of Work: During corrective maintenance on valve, replaced existing valve disk with a new disk obtained from an available spare valve assembly.
8. Tests Conducted: Hydrostatic E] Pneumatic [] Nominal Operating Pressure [I Exempt 0 Other C] Pressure Not Applicable psig Test Temp. Not Applicable -F
9. Remarks: Section Xl pressure testing was not applicable. Applicable documentation for replacement yoke (Form NPV-1 for valve) was attached at the time of final review and is maintained on file.

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

Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed *Aid ,.4Lt 62ISI Coordinator Date d/t ,20A_

Owner or Owner' Designee, Title' CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 12/17/2010 to 6/8/2011, 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 X1.

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

__

_ \,,,,.- L_,._-----_ Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date ( / - 20 k\

Page 6-39

FORMAIPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES-As Required by the Provisions of the ASME Code,Section III, Division 1 P(g, 1 of __2

' 1. Manufactured and certified by Flowserve Corporation, 1900 South Saunders St. Raleigh, NC 27603 /

(name end address of N Certificate Holder)

2. Manufactured for Exelon Business Services, An Exelon Company P.O. Box 805388 Chicago, IL 60680-5388 (name and address of Purchaser)
3. Location of installation Braidwood Station East of IL 53 1-1/2 miles South of RT 113 Braidwood, IL 60408 (name and address) 150GLB VLE rwig 72577034
4. Model No., Series No., or Type 1500-GLOBE VALVE Drawing 72577034 Rev. L CRN N/A
5. ASME Code,Section III, Division 1: 1971 / WINTER 1972 / 1 N/A (edition) (addenda date) (class) (Code Case no.)
6. Pump or valve Valve Nominal inlet size 2 / Outlet size 2 /

(in.) (in.)

7. Material:

(a) valve Body SA182-F316/ Bonnet SA479-316/ Disk SA479-316/ Bolting N/A (b) pump Casing Cover Bolting (a) (b) (c) (d) (e)

Cert. Nat'l Body/Casing Bonnet/Cover Disk Holder's Board Serial Serial Serial Serial No. No. No. No. No.

91BRU - N/A AB-49 o JB7-1 Z 33618-5-1 r 92BRU / N/A AB 3B7-2 7 33618-5-2 /

93BRU - N/A A7-67 " JB7-3 / 33618-5-3 /

  • Supplemental information in the form of lists, sketches, or drawings may be used provided (1) size is 892z x 11, (2) information in items 1 through 4 on this Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Page 6-40

79 2

FORM NPV-1/(Back - Pg. 2 of ___)

Certificate Holder's Serial No. 91BRUTHRU 93BRU

8. Design conditions 2580 / psi 650 '°F or valve pressure class 1500 (pressurel (tern per ature)
9. Cold working pressure 3600 psi at 100'F 5400 4000
10. Hydrostatic test psi. Disk differential test pressure psi
11. Remarks: 5.0. 61465 YOKE - MATERIAL SA105; HEAT NO.: L1391-1 S/N: 1 THRU 3/

CERTIFICATION OF DESIGN P.E. State PA Reg. no. 18379-E Design Specification certified by L. Ike Ezekoye Design Report'certified by R.S. FARRELL P.E. State NC Reg. no.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this pump or valve conforms to the rules for construction of the ASME Code,Section III, Division 1. 11-26-12 N Certificate of Authorization No. CoN-1562 / Expires y Date - 2~L...Name Date . -- Name fowserve Corporation Sge Signed _6 .

(N Certificate Holder) (authorized representative)

CERTIFICATE OF 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 NC and employed by HSB CT

//_ _ _ of Hartford, CT have inspected the pump, or valve, described in this Data Report on Y' ' fi ,and state that to the best of my knowledge and belief, the Certificate Holder has constructed this pump, or valve, in accordince with the ASME Code,Section III, Division 1.

By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the component described in this Data 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.

Date Signed Commissions IVAt[31,2o AIJ/ lh/g'--,9

/I*- N(Authorized Nuclear1Iia tor) [Na'l. Bd. incl. endorsemenis) end state or prov. and no.1 Page 6-41

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI Owner  : Exelon Generation Co., LLC Date 5/17/2011 Address: 300 Exelon Way. Kennett Square, PA 19348 Sheet 1 of 1

) Plant Name: Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville. IL 60407 Unit: 2 Work Order #01432228-01 Repair Organization P.O., Job No., etc

3. Work Performed By: Shaw / Stone & Webster Type Code Symbol Stamp: None Address: 36400 South Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: Reactor Coolant/Pressurizer (RY) (Class 1) 5 (a) Applicable Construction Code: ASME Section III 1974 Edition, Summer 1974 Addenda, Code Cases 1644, N71, and N249 (b) Applicable Edition of Section X1 Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section X1 Code Cases used: None
6. Identification of Coi ponents Repaired or Replaced and Replacement Components:

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

Pivot Pin for PSA-10 Unknown Unknown Not 2RY05010S Unknown Removed No Mechanical Snubber Applicable (Snubber 2RY05010S Serial Number 2537)

Pivot Pin for PSA-10 Anvil Serial Number Not Cat ID 42019-1 2004 Installed No Mechanical Snubber International, Inc. G7420-2 Applicable UTC 2700549

7. Description of Work: Replaced existing mechanical pivot pin, (was damaged and difficult to remove) during removal of existing PSA-10 mechanical snubber for functional testing. Post installation VT-3 examination was completed and satisfactory on 4/25/2011.
8. Tests Conducted: Hydrostatic :0 Pneumatic [ Nominal Operating Pressure El Exempt 0 Other 0 Pressure Not Required psig Test Temp. Not Required *F
9. Remarks: Applicable material documentation for replacement mechanical snubber was attached at the time of final review and is maintained on file.

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

Type Code,%ymbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed -0Aen .- ISI Coordinator Date /-71 , 20L_

Owner or Owner'!VDesignee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 4/25/2011 to 5/17/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

L " _-__ Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Dateý- k-& - ,201A Page 6-42

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner : Exelon Generation Co., LLC Date 7/18/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit 2 Work Order #01430989-01 Address: 35100 S. Rte. 53. Suite 84, Braceville, IL60407 Repair Organization P.O., Job No., etc
3. Work Performed By: Shaw / Stone &Webster Code Symbol Stamp: None Address: 36400 S. Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: Steam Generator Blowdown (SD) Class 2 system 5 (a) Applicable Construction Code: ASME Section III 1974 Edition, Summer 1974 Addenda, Code Cases: 1644 (N-71, N-249), 1651 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Comp nents Repaired or Replaced and Replacement Coi onents:

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

PSA-1/4 Mechanical ITT Grinnell S/N 2598 Not 2SD11066S 1977 Replaced No Snubber Applicable 2S01 1066S PSA-1/4 Mechanical Basic-PSA Inc. S/N 42820 Not Cat ID 27625-1 2004 Replacement No Snubber Applicable UTC 2807874

7. Description of Work: Existing snubber exhibited marginal performance during A2R15 functional testing (reference Issue Report 1204436) and was replaced in A2R15. The replacement snubber was functionally tested prior to installation.
8. Tests Conducted: Hydrostatic E] Pneumatic [] Nominal Operating Pressure 0l 0

Other E] Pressure Not Applicable psig Test Temp. Not Applicable F

9. Remarks: VT-3 exam of snubber was performed after reinstallation on 10/12/2011. Applicable snubber documentation was attached at the time of final review and is maintained on file.

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

Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed 4. t. tI?, LK64ec-. SI Coordinator Date 7/-0 ,20/L Owner or Owne~s Designee, Ttle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of IL and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 4/21/2011 to 7/18/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

t , Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date 20 "

Page 6-43

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

1. Owner  : Exelon Generation Co., LLC Date 5/17/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

) Plant Name: Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Unit: 2 Work Order #01306936-01 Repair Organization P.O.. Job No., etc

3. Work Performed By: Shaw / Stone & Webster Type Code Symbol Stamp: None Address: 36400 South Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: SI (Safety Injection) (Class 2) 5 (a) Applicable Construction Code: Piping: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Components:

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

Existing Socket Welds on Not Recorded Not Recorded Not Lines 2SI79AA-2" Not Removed No 2" Piping (Lines 2SI79AA-2" Applicable and 2SI79PA-2" Recorded and 2SI79PA-2" 3/32" Diameter Arcos Heat 739540 Not Cat ID 8497-1 2010 Installed No ER 308L Weld Rod Industries, LLC Lot CT9218 Applicable UTC 2870439 Control 9218 1/8" Diameter Arcos Heat 249076 Not Cat ID 8513-1 2009 Installed No ER 308/308L Industries, LLC Lot D-9077 Applicable UTC 2844829

_ Control 9077

7. Description of Work: Removed existing socket welds to support performing borescope inspection looking for foreign material. Reinstalled existing valve and piping and inspected socket welds by liquid penetrant method.

Tests Conducted: Hydrostatic C] Pneumatic [] Nominal Operating Pressure 0 Exempt [I Other 0 Pressure 617 psig TestTemp. Ambient OF

9. Remarks: Section XI pressure testing was performed and acceptable on 5/9/2011, instrument for specific temperature is not available. Applicable material documentation for associated weld filler materials was attached at the time of final review and is maintained on file.

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

Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed 44464l ISI Coordinator Date 5"/7 ,201/_

Owner or Owner'srDesignee, Titl9 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectors and the State of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/14/2011 to 5/17/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

___ __Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements

\Date *- t" ,20-1 Page 6-44

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

1. Owner  : Exelon Generation Co.. LLC Date 5/17/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1 Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53. Suite 84, Braceville, IL 60407 Work Order #f01306936-09 Repair Organization P.O., Job No., etc
3. Work Performed By: Shaw / Stone & Webster Type Code Symbol Stamp: None Address: 36400 South Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None
4. Identification of System: SI (Safety Injection) (Class 2) 5 (a) Applicable Construction Code: Piping: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases (b) Applicable Edition of Section Xl Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Components:

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

U-Bolt for Support Not Recorded Not Recorded Not Line 2SI79AA-2" Not Removed No 2SI30A017G on Line Applicable Recorded 2S179AA-2" 5/8" X 2" U-Bolt Bergen-Power None Not Cat ID 24580-1 2009 Installed No (with Hex Nuts) Applicable UTC 2828870

7. Description of Work: Removed existing u-bolt to assist with removing existing pipe under Task 01 in support of borescope inspection looking for foreign material.
8. Tests Conducted: Hydrostatic C] Pneumatic C] Nominal Operating Pressure C1 Exempt 0 Other E] Pressure Not Applicable psig Test Temp. Not Applicable IF NiW9. Remarks: Applicable material documentation for u-bolt was attached at the time of final review and is maintained on file.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed ISI Coordinator Date ,- . ,20_j Owner or OwnerY Designee, Tig CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 4/19/2011 to 5/17/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

Commissions IL1085 Inspe ctor's Signature National Board, State, Province, and Endorsements Date =-Il, ,20.-AA

)

Page 6-45

I-UHM N1S--2 UWNIH'5 HPUHI I'FUR HIEPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI Owner  : Exelon Generation Co., LLC Date 5/23/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet I of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84, Braceville. IL 60407 Work Order #01432505-01 RepairiReplacement Organization P.O.. Job No., etc
3. 'Work Performed By: Braidwood Station Mechanical Maintenance Type Code Symbol Stamp: None Address: 35100 South Route 53, Suite 84, Braceville, IL 60407 Authorization No.: None Expiration Date: None
4. Identification of System: Safety Injection (SI) (Class 2 Portion) 5 (a) Applicable Construction Code: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None
6. Identification of Components:

Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No) 7/8"-9 Bolting Material at Not Recorded Not Recorded Not 2FE-0987 Not Recorded Removed No Flow Element 2FE-0987 Applicable 7/8"-9 Heavy Hex Nuts NOVA Machine Heat 02280A Not Cat ID 30520-1 2002 Installed No Products/ Lot 50118737 Applicable UTC 2790896 Nedschroef Trace D315 Corporation NOVA Machine Heat 1-5126JE UTC 2790897 2007 Products Lot 50118854 Chaparral Steel Co.

1"-8 Threaded Rod NOVA Machine Heat 7527550 Not Cat ID 44337-1 2002 Installed No Products/ Lot 50118889 Applicable UTC 2790905 BowSteel Trace 0Z81

7. Description of Work: Bolted connection was discovered leaking di ection XI pressure test (reference IR 1206971) which required IWA-5250(a)(2) corrective actions. Existing bolting material was remove,, -- examined by VT-3 method, no corrosion/degradation noted in existing bolts. Existing bolting was replaced with new material.
8. Tests Conducted: Hydrostatic [] Pneumatic E] Nominal Operating Pressure El Exempt ED Other 0 Pressure Not Required psig Test Temp. Not Required IF
9. Remarks: Bolted connection was inspected during the system leakage test on 5/11/2011 and was acceptable. Applicable documentation for replacement bolting material was attached at the time of final review and is maintained on file.

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

Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed ISI Coordinator Date *23 , 201.

Owner or Ownerfs Designee, (Kitle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 2/25/2009 to 5/23/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

__,_L.__,_ Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date-- , 20_AL- Page 6-46

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI Owner  : Exelon Generation Co., LLC Date: 6/6/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: 2 Address: 35100 S. Rte. 53, Suite 84, Braceville. IL 60407 Work Order #*01354741-01 Repair/Replacement Organization P.O., Job No., etc
3. Work Performed By: Braidwood Station Mechanical Maintenance Type Code Symbol Stamp: None Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Authorization No.: None Expiration Date: None
4. Identification of System: Safety Injection (SI) (Class 2) 5 (a) Applicable Construction Code: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases (b) Applicable Edition of Section Xl Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None Ildpntific'~tinn nf ('.rnmnonp.nt.*

Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No) 5/8" X 1 /2" U-Bolt for Not Recorded Unknown Not 2SIK53013T Not Recorded Removed No Support 2SIK53013T Applicable 5/8" X 1 /2" U-Bolt Anvil U-Bolt Heat Not Cat ID 2006 Installed No Code B-2000 Applicable 1394240-1 Hex Nuts Heat UTC 2736259 Code 43599

7. Description of Work: During maintenance on valve 2SI8919B, u-bolt from adjacent support was replaced. Reason for u-bolt replacement was not specified in work package. Reference Issue Report 1224452 for u-bolt replacement without approved Section XI repair/replacement plan.
8. Tests Conducted: Hydrostatic E] Pneumatic E] Nominal Operating Pressure [I Exempt 0 Other El Pressure Not Applicable psig Test Temp. Not Applicable 'F
9. Remarks: Applicable material documentation for replacement u-bolt was attached at the time of final review and is maintained on file.

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

Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed ISI Coordinator Date eo '* 20 Ii Owner or Owner's 1esignee, Title 6f CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/27/201 Ito 6/6/2011, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code.Section XI.

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

J~L I., LC-.-----_..-_._._-- Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date L* - 120iLj Page 6-47

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