ML110350512

Inservice Inspection Summary Report

ML110350512
Person / Time
Site:	Braidwood
Issue date:	02/04/2011
From:	Shahkarami A Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BW110012
Download: ML110350512 (10)

Text

February 4, 2011 BW110012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRC Docket No. STN 50-456

Subject:

Braidwood Station Unit 1 Inservice Inspection Summary Report Enclosed please find the post-outage summary report (Le., 90 day report) for inservice inspection examinations conducted during the Braidwood Station Unit 1 fifteenth refueling outage (A1R15).

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. Ronald Gaston, Regulatory Assurance Manager, at (815) 417-2800.

Enclosure:

Braidwood Station lSI Outage Report for A1R15 cc: NRR Project Manager - Braidwood Station Illinois Emergency Management Agency - Division of Nuclear Safety NRC Regional Administrator - NRC Region III NRC Senior Resident Inspector - Braidwood Station

BRAIDWOOD STATION UNIT 1 INSERVICE INSPECTION

SUMMARY

REPORT FOR:

Interval 3, Period 1, Outage 2 Interval 3, Period 2 A1R15 Outage STATION ADDRESS:

Braidwood Station 35100 S. Route 53 Suite 84 Braceville, Illinois 60407 UNIT 1 COMMERCIAL SERVICE DATE:

July 29, 1988 OWNER'S ADDRESS:

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

Braidwood Station Unit 1 A1R15 lSI Outage Report TABLE OF CONTENTS DESCRIPTION: PAGE:

TITLE PAGE TABLE OF CONTENTS ii 1.0 - INSPECTION INFORMATION 1-1 to 1-2 2.0 - INSERVICE EXAMINATION

SUMMARY

2-1 to 2-3 3.0 - COMPONENT EXAMINATION RESULTS 3-1 to 3-59 4.0 - FORM NIS-1 (OWNER'S REPORT FOR INSERVICE INSPECTION) 4-1 to 4-4 FOR lSI THIRD INTERVAL AND THIRD INTERVAL INSPECTION STATUS AFTER A1R15 5.0 - REPORT OF CONTAINMENT DEGRADATION (IWE) 5-1 to 5-3 6.0 - FORM NIS-2, (OWNER'S REPORT FOR REPAIRS 6-1 to 6-36 OR REPLACEMENTS), Cover page plus 35 pages of Attachments ii

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Braidwood Station Unit 1 A1R15 lSI Outage Report 1.0 INSPECTION INFORMATION 1.1 Summary Third Interval Inservice Inspections (lSI) and Preservice Inspections (PSI) of ASME Class 1, 2, and 3 components were conducted at Braidwood Station Unit 1 between June 10, 2009 to January 12, 2011, with the majority of these inspections being performed during the Braidwood Station Unit 1 fifteenth refueling outage (A1R15). One examination performed during the A1R15 outage was credited to the Second Inspection Period after the Second Inspection Period start date for Category B-B was adjusted as permitted by IWA-2430(d)(3). The adjustment was performed to take advantage of no scheduled steam generator tubing inspections in A1R15.

All examinations were performed in accordance with the rules and regulations of Section XI, 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 is developed and implemented in accordance with the requirements and intent of Subsections IWE and IWL of ASME Section XI, 2001 Edition through the 2003 Addenda, pursuant to the requirements of 10CFR50.55a.

In addition to the ASME Section XI requirements, certain augmented lSI inspections were completed during A1R15. The Braidwood Unit 1 augmented lSI examinations included:

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

b) Bare Metal Visual examination of the Unit 1 reactor pressure vessel closure head penetration #74 in accordance with Braidwood Relaxation Request approval contained in T. J. McGinty (NRR) letter to C. Crane (Exelon) dated September 26, 2007 (ADAMS ML072430457).

c) Examination of the spare (preservice) and 1D (inservice) reactor coolant pump motor flywheels in accordance with Regulatory Guide 1.14.

d) Exam ination of welds in accordance with Materials Reliability Project MRP-139 and MRP-192.

e) Examination of pressurizer nozzle dissimilar metal weld overlays in accordance with Second Interval lSI Relief Request 12R-48 and ASME Section XI Appendix Q.

There were no significant findings associated with any of the augmented lSI exam inations.

Page 1-1

Braidwood Station Unit 1 A 1R15 lSI Outage Report 1.2 Identification of Examination Requirements The Third Interval lSI Program contains the Component Selection tables. These tables are presented in a tabular format consistent with the tables found in subsections IWB, IWC, IWD, and IWF-2500 of the ASME code. The Non-Destructive Examination (NDE) tables include the corresponding code category, item number, and componenVweld population selection in conformance with examination requirements and intent of Subsection IWA, IWB, IWC, IWD, and IWF of Section XI 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 XI 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 componenVsystem.

1.4 lSI Program Implementation Braidwood Station personnel, ortheir 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 lSI Program Schedule, Braidwood Station Technical Specifications (TS), and/or compliance with the ASME Section XI Repair/Replacement Program. All lSI 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. Personnel were certified to the requirements of the American Society for Non-destructive Testing SNT-TC-1A, 1984 Edition. The NDE procedures were developed and certified in conformance with ASME Section V and XI, 2001 Edition through 2003 Addenda or approved alternates (Performance Demonstration Initiative Program) as applicable. In addition, ultrasonic examination personnel were qualified in accordance with ANSI/ASME CP-189, 1995.

Certified personnel performed and evaluated visual examinations (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/or ASME Section XI 2001 Edition through 2003 Addenda.

Certified personnel performed and evaluated visual examinations (UT, VT-1, and VT-3) of containment structures. Personnel were certified to the requirements of the ANSI/ASNT CP-189, 1991 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 (AN"), L. Malabanan, M. Bosnich, and J. Scholl.

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 1-2

Braidwood Station Unit 1 A1R15 lSI Outage Report 2.0 INSERVICE EXAMINATION

SUMMARY

The following is a summary of ASME Section XI Class 1 and 2 examinations performed during the Braidwood Station Unit 1 A1R15 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 Chemical & Volume Control (C 1 Feedwater (FW) 3 Main Steam (MS) 5 Pressurizer (RY) 6 Reactor Coolant (RC) 19 Residual Heat Removal (RH) 2 Safety Injection (SI) 3 TOTALS 39

• Non-Section XI Augmented examinations and Risk Informed lSI socket weld VT-2 examinations are not included in these counts but are listed in Section 3.1.1.

2.2 Inservice Component Support Summary Auxiliary Feedwater (AF) 11 Component Cooling (CC) 9 Chemical & Volume Control (CV) 1 Main Steam (MS) 3 Reactor Coolant (RC) 15 Residual Heat Removal (RH) 3 Safety Injection (SI) 16 Essential Service Water (SX) 32 TOTALS 80 Page 2-1

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Braidwood Station Unit 1 A 1R15 151 Outage Report 2.3 Inservice Snubber Summary Auxiliary Feedwater (AF) 2 2 Chemical & Volume Control (CV) 3 3 Containment Spray (CS) 1 Main Steam (MS) 1 1 Reactor Coolant (RC) 14 6 Reactor Coolant (RY) 2 2 Residual Heat Removal (RH) 6 6 Steam Generator Slowdown (SO) 1 1 Safety Injection (SI) 21 20 TOTALS 51 42 2.4 Inservice Pressure Test Summary 2.4.1 Pressure Test Block Inspection Summary The components contained in Table 2.4.1-1 are pressure test blocks that were examined for Section Xllnservice Inspection and surveillance results were available at the time of report completion.

Table 2.4.1-1 A1R15 Section XI Pressure Tests 1

2 2

4 10 2

TOTALS 23 Page 2-2

Braidwood Station Unit 1 A 1R15 151 Outage Report 2.4.2 Borated Bolting Inservice Inspection Summary The components contained in this table are those insulated borated bolted connections that were examined for Section Xllnservice Inspection credit.

Inspections on these connections are performed per the lSI Program Plan.

Chemical & Volume Control (CV) 13 o Pressurizer (PZR) 1 o Reactor Coolant (RC) 13 o Residual Heat Removal (RH) 11 o TOTALS 38 o 2.5 Steam Generator Eddy Current Testing Summary Steam generator eddy current testing was not performed during the A1R15 outage.

Page 2-3

Braidwood Station Unit 1 A 1R15 lSI Outage Report 3.0 COMPONENT EXAMINATION RESULTS 3.1 Third Interval Inservice and Preservice Inspection Detailed Result Tables 3.1.1 Detailed Third Intervallnservice Weld/Component Table(s):

The table for this section (Pages 3-6 to 3-22) lists the examinations performed for Section XI Inservice and Augmented Inspection requirements for Class 1 and 2 welds and components. 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 3.2.

Results (I) 3.1.2 Detailed Third Interval Preservice Weld/Component Table(s):

The table for this section (Page 3-23) lists the baseline examinations performed for Section XI Preservice Inspection requirements for Class 1 and Class 2 components replaced during A1R15. 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 3.2.

Line Results Number/EPN (C) (0) (E) (F) (G) (H) (I) 3.1.3 Detailed Third Interval Inservice Component Support Table:

The table for this section (Pages 3-24 to 3-32) lists the examinations performed for Section Xllnservice Inspection requirements for Class 1 and 2 component supports. 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 3.2.

Section XI Cat. Item I 151 Identifier Description I Line Number/EPN I Relief Reauest I Program Notes I Exam Summary I Results Inspection Comments (A) (B) (C) (0) (E) (G) (I) 3.1.4 Detailed Third Interval Preservice Component Support Table:

The table for this section (Pages 3-33) lists the examinations performed for Section Xllnservice Inspection requirements for a replaced Class 2 component support. The general format of how the table is set-up is shown below. A Page 3-1

Braidwood Station Unit 1 A1R15 lSI Outage Report description of the information contained in each column can be found in Section 3.2.

Line Number/EPN Results (C) (0) (E) (G) (I) 3.1.5 Detailed Third Interval Inservice Snubber Table:

The table for this section (Pages 3-34 to 3-43) lists the examinations performed for Section XI 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 3.2.

Section XI Cat. Item I lSI Identifier Description I Line NumberlEPN I Relief Reauest I Program Notes I Exam Summary I Results Inspection Comments (A) (8) (C) (0) (E) (G) (I)

(K)

(J) 3.1.6 Detailed Third Interval Preservice Snubber Table:

The table for this section (Pages 3-44 to 3-46) lists the baseline examinations performed for Section XI Preservice Inspection requirements for Class 1 and 2 snubbers replaced during A1 R15. 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 XI Cat. Item I lSI Identifier Description I Line Number/EPN I Relief Reauest I Program Notes I Exam Summary I Results Inspection Comments (A) (8) (C) (0) (E) (G) (I)

(K)

(J) 3.1.7 Detailed Listing of Third Interval System Pressure Tests The table for this section (Pages 3-47 to 3-55) lists the examinations performed for Section XI Inservice and Augmented Inspection requirements for Class 1 and 2 pressure test blocks. 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 3.2.

Section XI Cat. Item I lSI Identifier Description I Relief Reauest I Program Notes I Exam Summary I Results Inspection Comments (A) (8) (0) (E) (G) (I)

(K)

(J)

Page 3-2

Braidwood Station Unit 1 A1R15 151 Outage Report 3.1.8 Detailed Borated Bolted Connection Table The table for this section (Pages 3-56 to 3-59) 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 3.2.

Section XI Cat. Item I lSI Identifier Description I Relief Reauest I Program Notes I Exam Summary I Results Inspection Comments (A) (B) (D) (E) (G) (I)

(K)

(J)

Page 3-3

Braidwood Station Unit 1 A1R15 lSI Outage Report 3.2 Generallnservice Report Information 3.2.1 Report Column Descriptions (A) This column contains the Section XI Category and Item identifiers for the specified component. There are special cases, like snubbers, where an "5" has been added to the end of the Section XI Item identifier. This was done to allow easy sorting of the snubber population by the 151 database.

(8) This column contains the 151 Identifier that the 151 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 151 Program Plan relief request(s) that is associated with that component. A complete copy of the relief request can be found in the 151 Program Plan.

(E) This column identifies the 151 Program Plan note(s) that is associated with that component. A complete copy of the Program note can be found in the 151 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 com ponent.

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

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

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

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

Page 3-4

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Braidwood Station Unit 1 A1R15 lSI Outage Report 3.2.2 Report Abbreviations ATI - Action Tracking Item BMV - Bare Metal Visual Inspection FUNCT Snubber Functional Test FSWOL - Full Structural Weld Overlay GE/IND - Geometry/Indication GEOM - Geometry IND - Indication 10 - Information Only 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 3-5

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Containment Spray System (CS)

NA ECCS 1CS-03-S7 1CS06AA-S* NOTE 19 VOL UT-0 NA ELBOW - PIPE 100 UT45 Nru UT-70 Augmented examination on stagnant borated thin-wall pipe weld. UT thickness performed to obtain weld contour and to confinn that no counterbore exists.

NA ECCS 1CS-03-70 1CS06AA-S* NOTE 19 VOL UT-O NA PIPE - PIPE 100 UT45 NRI UT-70 Augmented examination on stagnant borated thin-wall pipe weld. UT thickness performed to obtain weld contour and to confinn that no counterbore exists.

C-C C03.30 1CSP-01-CSP04, 05, 06 1CS01 PB NOTE 17 100 SUR VT-1 NA 1CS01 PB PUMP LUG Supplemental VT-1 due to limited coverage obtained during A1R14 inspection. Relief request is required << 90% coverage achieved).

Submittal of relief request is being tracked through ATI 894565-02.

Page 3-6

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3"1"1 Detailed Third Intervallnservice Inspection Weld Table SYSTEM: Chemical & Volume Control System (CV)

R-A R01.11 1CY-05-03 1CYA3B-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1CY-05-04 1CYA3B-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 1CY-05-05 1CYA3B-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1CY-05-06 1CYA3B-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 1CY-05-13 1CYA3B-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1CY-05-14.01 1CYA3B-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE B-G-2 B07.50 1CY-06-B1 1CY14GA-1.5" SUR VT-1 NRI FLANGE BOLTING (4 STUDS)

VT-1 performed after flange disassembly during pump seal replacement under WO# 1262834.

R-A R01.11 1CY-11-06 1CYA6AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1CY-11-o7 1CYA6AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW- PIPE NA ECCS 1CY-17-13 1CY05CB-6" NOTE 19 VOL UT-O NA ELBOW - PIPE 100 UT-45 NRI UT-70 Augmented examination on stagnant borated thin-wall pipe weld. UT thickness performed to obtain weld contour and to confirm that no CQunterbore exists.

R-A R01.11 1RC-36-15 1CYA3AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1RC-36-16 1CYA3AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW- PIPE R-A R01.11 1RC-36-17 1CYA3AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1RC-36-18 1CYA3AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 1RC-37-11 1CYA7AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1RC-37-12 1CYA7AA-2" 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE Page 3-7

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Feedwater System (FW)

R-A R01.11 1FW-02-37 1FW03DA-16* 13R-01 NOTE 17 100 VOL-E UT-45 NRI R01.18 PIPE - ELBOW Counterbore exists downstream of weld centerline, additional volume inspected in accordance with Risk-Informed lSI requirements.

Previously recorded geometry observed below recordable levels.

R-A R01.11 1FW-03-39 1FW03DB-16* 13R-01 NOTE 17 100 VOL-E UT-45 NRI R01.18 PIPE - ELBOW Counterbore exists downstream of weld centerline, additional volume inspected in accordance with Risk-Informed lSI requirements.

Previously recorded geometry observed below recordable levels.

R-A R01.11 1FW-04-38 1FW03DC-16* 13R-01 NOTE 17 100 VOL-E UT-45 NRI ROU8 PIPE - ELBOW Counterbore exists downstream of weld centerline, additional volume inspected in accordance with Risk-Informed lSI requirements.

Previously recorded geometry observed below recordable levels.

Page 3-8

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Braidwood Station Unit 1 A 1R15 lSI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Main Steam System (MS)

R-A R01.20 1MS-04-34 1MS13AA-S' 13R-01 NOTE 09 VOL-E UT-O NA ELBOW - PIPE NOTE 17 100 UT-45 NRI UT thickness performed to verify previous thickness and contour and to confirm that no counterbore exists.

R-A R01.20 1MS-04-35 1MS13AA-S' 13R-01 NOTE 09 VOL-E UT-O NA PIPE - ELBOW NOTE 17 100 UT-45 NRI UT thickness performed to verify previous thickness and contour and to confirm that no counteroore exists.

R-A R01.20 1MS-04-36 1MS13AA-S' 13R-01 NOTE 09 VOL-E UT-O NA ELBOW - PIPE NOTE 17 100 UT-45 NRI UT thickness performed to verify previous thickness and contour and to confirm that no counteroore exists.

R-A R01.20 1MS-04-37 1MS13AA-S' 13R-01 NOTE 09 VOL-E UT-O NA PIPE - ELBOW NOTE 17 100 UT-45 NRI UT thickness performed to verify previous thickness and contour and to confirm that no counterbore exists. Previously recorded geometry observed below recordable levels.

R-A R01.20 1MS-04-38 1MS13AA-S' 13R-01 NOTE 09 VOL-E UT-O NA ELBOW - PIPE NOTE 17 100 UT-45 NRI UT thickness performed to verify previous thickness and contour and to confirm that no counterbore exists. Previously recorded geometry observed below recordable levels.

Page 3*9

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)

NA RG 1.14 1/2RCP-01-FLYWHEEL SPARE NOTE1S SUR PT NRI (SPARE)

SPARE RCP PUMP FLYWHEEL Spare Marble Hill RCP motor (Serial Number 4S88P961). Flywheel examination was completed during motor refurbishment under WO 1209274 prior to A1R1S outage.

R-A R01.20 1RC-02-04A THERMOWELL 13R-01 NOTE 17 VT-2 VT-2 NRI BRANCH CONNECTION - THERMOWELL R-A R01.20 1RC-03-21 A THERMOWELL 13R-01 NOTE 17 VT-2 VT-2 NRI BRANCH CONNECTION - THERMOWELL R-A R01.11 1RC-06-11 1RC21AA-S* 13R-01 NOTE 17 VOL-E UT-O NA PIPE- ELBOW 100 UT-45 NRI Zero degree performed to locate counterbore and/or any inside diameter transition. Counterbore confirmed, extended exam volume to meet Risk-Informed lSI requirements. Previously recorded geometry observed below recordable levels.

R-A R01.20 1RC-23-01 1RC22AA-1.S* 13R-01 NOTE 17 VT-2 VT-2 NRI 3*X1S REDUCER - PIPE R-A R01.20 1RC-23-02 1RC22AA-1.S* 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.20 1RC-23-03 1RC22AA-1.S* 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.20 1RC-23-04 1RC22AA-1.S* 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.20 1RC-23-0S 1RC22AA-1.S* 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.20 1RC-27-04AA 1RC22AA-1.S* 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.20 1RC-27-QSAA 1RC22AA-1.S* 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.20 1RC-27-06AA 1RC22AA-1.S* 13R-Q1 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.20 1RC-27-07AA 1RC22AA-1.S* 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW- PIPE R-A R01.20 1RC-27-08AA 1RC22AA-1.S* 13R-Q1 NOTE 17 VT-2 VT-2 NRI PIPE - VALVE 1RCS04SA R-A R01.11 1RC-29-01-03 1RC16AC-2* 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - BRANCH CONNECTION R-A R01.11 1RC-29-01-04 1RC16AD-2* 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - BRANCH CONNECTION R-A R01.11 1RC-29-02-03 1RC16AC-2* 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW- PIPE R-A R01.11 1RC-29-Q2-04 1RC16AD*2* 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW- PIPE Page 3-10

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)

R-A R01.11 1RC-29-03-03 1RC16AC-2* 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1RC-29-03-04 1RC16AD-2* 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1RC-29-04-03 1RC16AC-2* 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 1RC-29-04-04 1RC16AD*2* 13R-01 NOTE 17 VT*2 VT-2 NRI ELBOW - PIPE R-A R01.11 1RC-29*05-03 1RC16AC-2* 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1RC-29-05-04 1RC16AD-2* 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1RC-29-06-03 1RC16AC-2* 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 1RC8038C - PIPE R-A R01.11 1RC-29-06-04 1RC16AD-2* 13R-G1 NOTE 17 VT-2 VT-2 NRI VALVE 1RC8038D - PIPE R-A R01.11 1RC-31-01 1RC14AB*2* 13R-01 NOTE 17 VT-2 VT-2 NRI BRANCH CONNECTION - PIPE R-A R01.11 1RC-31-02 1RC14AB*2* 13R-01 NOTE 17 VT*2 VT-2 NRI PIPE - VALVE 1RC8039B R-A R01.11 1RC-31-03 1RC14AB-2* 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 1RC8039B - PIPE R-A R01.11 1RC-31-04 1RC14AB-2* 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - TEE R*A R01.11 1RC-31-05 1RC14AB-2* 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - 2*X.75* REDUCER R-A R01.11 1RC-31-06 1RC14AB-2* 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - PIPE R-A R01.11 1RC-31-07 1RC14AB-2* 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - VALVE 1RC8037B R-A R01.20 1RC-31-08 1RC26A-2* 13R-01 NOTE 17 VT-2 VT-2 NRI BRANCH CONNECTION* PIPE R-A R01.11 1RC-36-01 1RC14AA-2* 13R-01 NOTE 17 VT*2 VT-2 NRI BRANCH CONNECTION - PIPE R-A R01.11 1RC-36-02 1RC14AA-2* 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1RC-36-03 1RC14AA-2* 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW- PIPE R-A R01.11 1RC-36-04 1RC14AA-2* 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - VALVE 1RC8039A Page 3-11

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3,1,1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)

R-A R01.11 1RC-36-0S 1RC14AA-2' 13R-Q1 NOTE 17 VT-2 VT-2 NRI VALVE 1RC8039A - PIPE R-A R01.11 1RC-36-06 1RC14AA-2' 13R-Q1 NOTE 17 VT-2 VT-2 NRI PIPE -TEE R-A R01.11 1RC-36-07 1RC14AA-2' 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - 2'X.7S' REDUCER R-A R01.11 1RC-36-08 1RC14AA-2' 13R-Q1 NOTE 17 VT-2 VT-2 NRI TEE - PIPE R-A R01.11 1RC-36-09 1RC14AA-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - VALVE 1RC8037A R-A R01.11 1RC-36*20 1RC14AA*2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - TEE R-A R01.11 1RC-36-22 1RC86AA-2' 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - 2'X1' REDUCER R-A R01.11 1RC-37-01 1RC14AD-2' 13R-01 NOTE 17 VT-2 VT-2 NRI BRANCH - PIPE R-A R01.11 1RC-37*02 1RC14AD-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1RC-37*03 1RC14AD-2' 13R-01 NOTE 17 VT*2 VT-2 NRI ELBOW- PIPE R-A R01.11 1RC-37-04 1RC14AD-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE* VALVE 1RC8039D R-A R01.11 1RC-37*0S 1RC14AD*2' 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 1RC8039D - PIPE R-A R01.11 1RC-37-06 1RC14AD-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - TEE R-A R01.11 1RC-37-07 1RC14AD-2' 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - 2'X.7S' REDUCER R-A R01.11 1RC*37-08 1RC14AD*2' 13R-01 NOTE 17 VT-2 VT*2 NRI TEE - PIPE R-A R01.11 1RC-37-09 1RC14AD-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - VALVE 1RC8037D R-A R01.11 1RC-41-01AA 1RC16AA-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - BRANCH CONNECTION R-A R01.11 1RC-41-01AB 1RC16AB-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - BRANCH CONNECTION R-A R01.11 1RC-41-02AA 1RC16AA-2' 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW- PIPE R-A R01.11 1RC*41-02AB 1RC16AB-2' 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW- PIPE Page 3-12

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)

R-A R01.11 1RC-41-03AA 1RC16AA-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1RC-41-03AB 1RC16AB-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1RC-41-04AA 1RC16AA-2' 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 1RC-41-04AB 1RC16AB-2' 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 1RC8038B - PI PE R-A R01.11 1RC-41-05AA 1RC16AA-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1RC-41-06AA 1RC16AA-2' 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 1RC8038A - PIPE R-A R01.11 1RC-42-01 1RC14AC-2' 13R-01 NOTE 17 VT-2 VT-2 NRI BRANCH CONNECTION - PIPE R-A R01.11 1RC-42-02 1RC14AC-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - ELBOW R-A R01.11 1RC-42-03 1RC14AC-2' 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 1RC-42-04 1RC14AC-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - VALVE 1RC8039C R-A R01.11 1RC-42-05 1RC14AC-2' 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 1RC8039C - PIPE R-A R01.11 1RC-42-06 1RC14AC-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - TEE R-A R01.11 1RC-42-07 1RC14AC-2' 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - 2'X3I4' REDUCER R-A R01.11 1RC-42-08 1RC14AC-2' 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - PIPE R-A R01.11 1RC-42-09 1RC14AC-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - VALVE 1RC8037C R-A R01.11 1RC-42-1 0 1RC14AC-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - TEE R-A R01.11 1RC-42-11 1RC14AC-2' 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - PIPE R-A R01.11 1RC-42-12 1RC14AC-2' 13R-01 NOTE 17 VT-2 VT-2 NRI TEE - 2'X1' REDUCER NA RG 1.14 1RCP-01-FLYWHEEL 1RCP01D NOTE 18 100 SUR PT NRI (PMPD)

RCP 'D' PUMP FLYWHEEL PT RCP motor flywheel in conjunction with motor overhaul performed under WO# 1309340.

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC) 8-G-2 807.60 1ACP-01-PS8-PA-81 1AC01 PA NOTE 03 SUA VT-1 NAI PUMP SHAFT SEALS (12 80LTS) NOTE 16 Perform exam during pump seal replacement under WO# 1262834.

N-722 815.090 1AV-01-022 N-722 1AC01A NOTE 14 Visual, VE Visual, NAI VE NOZZLE - SAFE END (22 DEG.) NOTE 17 MAP-139 Visual, VE (Code Case N-722) examination performed after mirror insulation was removed from nozzle to perform MSIP accessibility walk down.

N-722 815.095 1AV-01-023 N-722 1AC01A NOTE 14 Visual, VE Visual, NAI VE SAFE END - NOZZLE (67 DEG.) NOTE 17 MAP-139 Visual, VE (Code Case N-722) examination performed after mirror insulation was removed from nozzle to perform MSIP accessibility walk down.

N-722 815.095 1AV-01-024 N-722 1AC01A NOTE 14 Visual, VE Visual, NAI VE SAFE END - NOZZLE (113 DEG.) NOTE 17 MAP-139 Visual, VE (not credited for Code Case N-722) examination performed after mirror insulation was removed from nozzle to perform MSIP accessibility walk down.

N-722 815.090 1AV-01-025 N-722 1AC01A NOTE 14 Visual, VE Visual, NAI VE NOZZLE - SAFE END (158 DEG.) NOTE 17 MAP-139 Visual, VE (Code Case N-722) examination performed after mirror insulation was removed from nozzle to perform MSIP accessibility walk down.

N-722 815.090 1AV-01-Q26 N-722 1AC01A NOTE 14 Visual, VE Visual, NAI VE NOZZLE - SAFE END (202 DEG.) NOTE 17 MAP-139 Visual, VE (Code Case N-722) examination performed after mirror insulation was removed from nozzle to perform MSIP accessibility walk down.

N-722 815.095 1AV-01-027 N-722 1AC01A NOTE 14 Visual, VE Visual, NAI VE SAFE END - NOZZLE (247 DEG.) NOTE 17 MAP-139 Visual, VE (Code Case N-722) examination performed after mirror insulation was removed from nozzle to perform MSIP accessibility walk down.

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)

N-722 B15.095 1RV-01-028N-722 1RC01R NOTE 14 Visual, VE Visual, NRI VE SAFE END - NOZZLE (293 DEG.) NOTE 17 MRP-139 Visual, VE (not credited for Code Case N-722) examination performed after mirror insulation was removed from nozzle to perform MSIP accessibility walk down.

N-722 B15.090 1RV-01-029 N-722 1RC01R NOTE 14 Visual, VE Visual, NRI VE NOZZLE - SAFE END (338 DEG.) NOTE 17 MRP-139 Visual, VE examination performed after mirror insulation was removed.

B-N-1 B13.10 1RV-01-RX INTERIOR 1RC01R 100 VT-3 VT-3 NRI ACCESSIBLE INTERIOR SURFACES N-722 B15.080 1RV-02-INSTR. 1RC01 R 13R-04 Visual, VE Visual, 10 NOZZLES VE RX VESSEL INSTRUMENTATION NOZ.

Code Case N-722 examination. Minor staining from previous boot seal leakage, no change from previous examination.

NA NA 1RV-03-74-BMV 1RC01R NOTE 17 100 Visual, VE Visual, NRI VE WELD IN PERIPHERAL CRD HOUSING Bare metal visual examination of reactor head surface and annulus around penetration per previous commitment in Unit 1 Relaxation Request.

B-G-2 B07.10 1RV-03-75CETNA 1RC01R SUR VT-1 NRI CLAMP BOLTING INCORE THERMOCOUPLE CLAMP (Pen. #75)

Connection was disassembled under WO# 1286769-29 to correct boriC acid leakage.

B-G-2 B07.10 1RV-03-77CETNA 1RC01R SUR VT-1 NRI CLAMP BOLTING INCORE THERMOCOUPLE CLAMP (Pen. #77)

Connection was disassembled under WO# 1286769-29 to correct boric acid leakage.

B-G-1 B06.10 1RV-03-NUTS (01 TO 54) 1RC01R NOTE 03 SUR VT-1 NRI CLOSURE HEAD NUTS (54 TOTAL)

Examined nuts 1 through 18 and 37 through 54 which were not examined during A1R14. The remaining nuts were examined in A1R14, reference report A1R14VT-037 B-G-2 B07.10 1RV-03-RVLlS BOLTING 1RC01 R SUR VT-1 NRI (NORTH)

NORTH RVLlS ASSEMBLY Connection was disassembled during A1R15 under WO# 1286769.

B-G-2 B07.10 1RV-03-RVLlS BOLTING 1RC01R SUR VT-1 NRI (SOUTH)

SOUTH RVLlS ASSEMBLY Connection was disassembled during A1R15 under WO# 1286769.

B-G-1 B06.50 1RV-03-WASHERS 1RC01 R NOTE 03 SUR VT-1 NRI CLOSURE WASHERS (01 TO 54) NRI Examined washers 1 through 18 and 37 through 54 which were not examined during A1R14. The remaining nuts were examined in A1R14, reference report A1R14VT-037 Page 3*15

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3,1,1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)

B-B B02.40 1SG-QS-SGC-01 1RC01BA NOTE 17 100 VOL UT-O NRI PRIMARY HEAD - TUBESHEET UT-45 NRI UT-60 NRI Initially scheduled in A1R16 (Second Period). Second period start date was accelerated into A1R1S by adjusting Second Period start date from 7/29/2011 to 10/8/2010 as permitted by IWA-2430(d)(3) to take advantage of steam generator skip outage and to combine with UT of 1SG-OS-SGC-02 (Category C-A, Item C1.30). This examination is to be credited to the Second Period.

C-A C01.30 1SG-QS-SGC-02 1RC01BA NOTE 17 100 VOL UT-O NRI TUBE SHEET - LOWER SECONDARY SHELL 99.7S UT-45 98.4 UT-60 Examination limitations due to four 8' hand holes and two 6' blow down lines. Cumulative coverage is 99.38%.

CoB C02.22 1SG-QS-SGN-04 (NIR) 1RC01BA NOTE 17 100 IRS UT-3S NRI FW NOZZLE - STEAM DRUM LOWER SHELL NIR UT-40 NRI UT-45 NRI UT-60 NRI R-A R01.11 1SI-16-22.01 1RC30AD-1.S' 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 1S189OOD - PIPE R-A R01.11 1SI-16-23 1RC30AD-1.S' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - 3'X1Y2' REDUCER R-A R01.11 1SI-17-01 1RC30AB-1.S' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - 3'X1Y2' REDUCER R-A R01.11 1SI-17-02 1RC30AB-1.S' 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 1S189OOB - PIPE R-A R01.11 1SI-31-01 1RC30AA-1.S' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - REDUCER R-A R01.11 1SI-31-02 1RC30AA-1.S' 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 1S189OOA - PIPE Page 3-16

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3"1"1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Residual Heat Removal System (RH)

NA ECCS 1RH-06-35 1RH03AB-8" NOTE 19 VOL UT-O NA TEE - PIPE UT-45 NRI UT-70 NRI Zero degree to confirm thickness and contour. Examination performed in accordance with EPRI Good Practice MRP-192 Revision 1.

Examination will also be credited towards the ECCS augmented pipe inspection program.

NA NA 1RH-06-36 1RH03AB-8" VOL UT-O NA PIPE LONG SEAM UT-45 NA Augmented examination per MRP-192 Revision 1.

C-C C03.10 1RHX-01-1RHES-01 (A 1RH02AA N-700 NOTE 17 SUR PT RI HX)

BOnOM HEAD - SUPPORT SKIRT NOTE 29 A 3116" rounded indication was noted 0.30" from the toe of the weld on the skirt side, 38.5" clockwise from the vessel long seam looking down. Indication was considered "recordable" since Acceptance Standard IWC-3512 does not address rounded indications. Per IWA-3100(b) the Acceptance Standard of NC-5352 of ASME Section 1111974 Edition (original Code of Construction) was applied. Per NC-5352, rounded indications with dimensions greater than 3/16" are unacceptable. Since the rounded indication recorded is not greater than 3116" it is acceptable for continued service.

COB C02.21 1RHX-01-1RHXN2 (A HX) 1RH02AA N-706 NOTE 17 VT-2 VT-2 NRI NOZZLE - SHELL NOTE 30 VT-2 per Code Case N-706 performed during system leakage test (WO 1224128).

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Braidwood Station Unit 1 A 1R15 lSI Outage Report Section 3,1,1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RY)

R-A R01.11 1CV-02-13 1RY18A-2' 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 1CV8377 - PIPE R-A R01.11 1CV-02-14 1RY18A-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1CV-02-15 1RY18A-2' 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 1CV-02-16 1RY18A-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1CV-02-17 1RY18A-2' 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 1CV-02-18 1RY18A-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 1CV-02-19 1RY18A-2' 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE B-D B03.110 1PZR-01-N2 1RY01S NOTE 17 56.56 VOL UT-O NRI SPRAY NOZZLE - PRESSURIZER UT-45 NRI UT-60 NRI Cumulative examination coverage is 56.56%. Relief request is being tracked through ATI 894565-02.

B-D B03.120 1PZR-01-N2 (NIR) 1RY01S 10CFR NOTE 13 100 IRS UT-24 NRI SPRAY NOZZLE - PRESSURIZER INNER RADIUS NOTE 17 UT-60 NRI UT-65 NRI UT-70 NRI B-D B03.110 1PZR-Q1-N3 1RY01S NOTE 17 60.92 VOL UT-Q NRI PRESSURIZER - RELIEF NOZZLE UT-45 NRI UT-60 NRI Cumulative examination coverage is 60.92%. Relief request is being tracked through ATI 894565-02.

B-D B03.120 1PZR-01-N3 (NIR) 1RY01S 10CFR NOTE 13 100 IRS UT-24 NRI PRESSURIZER - RELIEF NOZZLE INNER RADIUS NOTE 17 UT-60 NRI UT-65 NRI UT-70 NRI R-A R01.15 1PZR-01-SE-01 1RY11A-14' 13R-01 NOTE 14 100 VOL-E UT-45L NRI R01.11 PZR SURGE NOZZLE - SAFE END NOTE 17 MRP-139 Overlay UT per previous Second Interval Relief Request 12R-48 and Section XI Appendix Q.

R-A R01.15 1PZR-01-SE-02 1RY03AA-6' 13R-01 NOTE 14 99.7 VOL UT-45L 10 MRP- PZR 'A' SAFETY NOZZLE - SAFE END NOTE 17 139 Overlay UT per previous Second Interval Relief Request 12R-48 and Section XI Appendix Q. Examination performed using 45 degree refracted longitudinal wave angle. One spot indication was recorded which was not recorded dUring baseline examination. Indication has no through-wall depth and is acceptable when compared to Acceptance Standards.

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RY)

R-A R01.15 1PZR-01-SE-03 1RY03AB-6' 13R-01 NOTE 14 100 VOL UT-45L NRI MRP- PZR 'B' SAFETY NOZZLE - SAFE END NOTE 17 139 Overlay UT per previous Second Interval Relief Request 12R-48 and Section XI Appendix Q. Examination performed using 45 degree refracted longitudinal wave.

R-A R01.15 1PZR-01-SE-04 1RY03AC-6' 13R-01 NOTE 14 100 VOL UT-45L 10 MRP- PZR 'C' SAFETY NOZZLE - SAFE END NOTE 17 139 Overlay UT per previous Second Interval Relief Request 12R-48 and Section XI Appendix Q. Examination performed using 45 degree refracted longitudinal wave.

R-A R01.15 1PZR-01-SE-05 1RY01 B-6' 13R-01 NOTE 14 100 VOL VOL NRI R01.11 PZR SPRAY NOZZLE - SAFE END NOTE 17 MRP-139 Overlay UT per previous Second Interval Relief Request 12R-48 and Section XI Appendix Q. Examination performed using numerous refracted longitudinal wave angles (33, 40, 43, 45, and 60 degrees).

R-A R01.15 1PZR-01-SE-06 1RY02A-6' 13R-01 NOTE 14 100 VOL UT-45L NRI MRP- PZR REUEF NOZZLE - SAFE END NOTE 17 139 Overlay UT per previous Second Interval Relief Request 12R-48 and Section XI Appendix Q. Examination performed using 45 degree refracted longitudinal wave.

R-A R01.11 1RC-05-01 1RY11A-14' 13R-01 NOTE 17 100 VOL-E UT-45L NRI PZR SAFE END - PIPE 13R-06 Overlay combined with 1PZR-01-SE-01. Reinspection in accordance with ASME Section XI Appendix Q and per previous Second Interval Relief Request 12R-48 commitment.

R-A R01.11 1RC-16-01 1RY01C-4' 13R-01 NOTE 17 100 VOL-E VOL NRI 6'X4' REDUCER - SAFE END 13R-06 Overlay UT per previous Second Interval Relief Request 12R-48 and Section XI Appendix Q. Examination performed using numerous refracted longitudinal wave angles (33, 40, 43, 45, and 60 degrees).

R-A R01.20 1RG-16-02 1RY01B-6' 13R-01 NOTE 17 VOL-E UT-O NA 4'X6' REDUCER - ELBOW 100 UT-45 NRI Zero degree performed to confirm no counterbore present. Previously recorded geometry observed below recordable levels.

R-A R01.11 1RC-16-03 1RY01B-6' 13R-01 NOTE 17 VOL-E UT-O NA ELBOW - PIPE 100 UT-45 NRI Zero degree performed to confirm no counterbore present. Previously observed geometry observed below recordable levels.

R-A R01.11 1RC-16-07 1RY01 B-6' 13R-01 NOTE 17 VOL-E UT-O NA ELBOW - PIPE 100 UT-45 NRI Zero degree performed to confirm no counterbore exists. Previously recorded geometry observed below recordable levels.

R-A R01.11 1RC-16-08 1RY01B-6' 13R-01 NOTE 17 VOL-E UT-O NA PIPE - ELBOW 100 UT-45 NRI Zero degree performed to confirm thickness and contour and to confirm counterbore is not present. Root geometry observed below recordable levels.

R-A R01.20 1RC-32-01 1RY03AA-6' 13R-01 NOTE 17 99.5 VOL UT-45L NRI SAFE END - ELBOW 13R-06 Overlay UT per previous Second Interval Relief Request 12R-48 and Section XI Appendix Q. Examination performed using 45 degree refracted longitudinal wave angle.

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Braidwood Station Unit 1 A 1R15 lSI Outage Report Section 30101 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RY)

R-A R01.20 1RC-32-07 1RY03AB-6° 13R-01 NOTE 17 98.8 VOL UT-45L NRI SAFE END - ELBOW 13R-06 Overlay UT per previous Second Interval Relief Request 12R-48 and Section XI Appendix Q. Examination performed using 45 degree refracted longitudinal wave.

R-A R01.20 1RC-32-13 1RY03AC-6° 13R-01 NOTE 17 100 VOL UT-45L NRI SAFE END - ELBOW 13R-06 Overlay UT per previous Second Interval Relief Request 12R-48 and Section XI Appendix Q. Examination performed using 45 degree refracted longitudinal wave.

R-A R01.20 1RC-35-01 1RY02A-6° 13R-01 NOTE 17 100 VOL-E UT-45L NRI SAFE END - ELBOW 13R-06 Overlay UT per previous Second Interval Relief Request 12R-48 and Section XI Appendix Q. Examination performed using 45 degree refracted longitudinal wave.

R-A R01.20 1RC-35-02 1RY02A-6° 13R-01 NOTE 17 VOL-E UT-O NA ELBOW - PIPE 100 UT-45 NRI Zero degree performed to confirm no counterbore present. Previously recorded geometry observed below recordable levels.

R-A R01.20 1RC-35-04 1RY02A-6° 13R-01 NOTE 17 VOL-E UT-O NA TEE - 6°X3° REDUCER 100 UT-45 NRI Zero degree performed to confirm counterbore not present. Previously recorded geometry obserserved below recordable levels.

B-G-2 B07.50 1SI-23-B1 1RY76A-2° SUR VT-1 NRI FLANGED CONNECTION (8 STUDS)

VT-1 of bolting completed prior to final reassembly under WO# 1277042-01.

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3,1,1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Safety Injection System (SI)

B-G-2 B07.70 151-06-1 518818B (BLT) 151050B-6' NOTE 03 5UR VT-1 NRI 1518818B CHECK VALVE (16 BLT) NOTE 16 Valve was disassembled for maintenance under WO# 1060109-01, VT-1 and VT-3 examinations performed.

B-M-2 B12.50 151-06-1518818B (INT) 151050B-6' NOTE 16 5UR VT-3 NRI 1518818B CHECK VALVE INTERNAL5 Valve was disassembled for maintenance under WO# 1060109-01, VT-1 and VT-3 examinations performed.

R-A R01.11 151-10-25 15118FC-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 151-10-26.01 15118FC-2' 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 151-18-23 15108JB-1 .5' 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 1518810B - PIPE R-A R01.11 151-18-24 15108JB-1.5' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 151-18-25 15108JB-1.5' 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW - PIPE R-A R01.11 151-18-26 15108JB-1.5' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 151-19-01 15108GA-1.5' 13R-01 NOTE 17 VT-2 VT-2 NRI BRANCH CONNECTION - PIPE R-A R01.11 151-19-06 15108HA-2' 13R-01 NOTE 17 VT-2 VT-2 NRI COUPLING - PIPE R-A R01.11 151-19-07 15108HA-2' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - FLANGE R-A R01.11 151-19-08 15108HA-2' 13R-01 NOTE 17 VT-2 VT-2 NRI FLANGE - PIPE R-A R01.11 151-19-14 15108JA-1.5' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 151*19-15 15108JA-1.5' 13R-01 NOTE 17 VT-2 VT-2 NRI ELBOW- PIPE R-A R01.11 151-19-16 15108JA-1.5' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - VALVE 1518810A R-A R01.11 151-19-17 15108JA-1.5' 13R-01 NOTE 17 VT-2 VT-2 NRI VALVE 1518810A - PIPE R-A R01.11 151-19-18 15108JA-1.5' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE - FLANGE R-A R01.11 151-19-20 15108JA-1.5' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW R-A R01.11 151-19-22 15108JA-1.5' 13R-01 NOTE 17 VT-2 VT-2 NRI PIPE- ELBOW Page 3-21

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Safety Injection System (SI)

A-A A01.11 1SI-19-23 1SI08JA-1.5" 13A-01 NOTE 17 VT-2 VT-2 NAI ELBOW - PIPE A-A A01.11 1SI-19-24 1SI08JA-1.5" 13A-01 NOTE 17 VT-2 VT-2 NAI PIPE- ELBOW NA EGGS 1SI-30-23AA 1SI09AA-1 0" NOTE 19 VOL UT-O NA PIPE- ELBOW 100 UT-45 NAI Zero degree performed to verify weld contour and confirm no counterbore exists.

NA EGGS 1SI-35-54 1SI01A-S' NOTE 19 VOL UT-O NA ELBOW - ELBOW 100 UT-45 NAI Zero degree performed for thickness and counterbore detection. No counterbore detetcted.

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 30102 Detailed Third Interval Preservice Weld I Component Table SYSTEM: Safety Injection System (SI)

R-A R01.11 1SI-06-24 1SI18F8-2° 13R-01 NOTE 17 100 SUR PT NRI VALVE 1SI88198 - PIPE Existing weld was replaced during replacement of Valve 1SI88198 under WO# 1281799-01, documented as Weld FW 4A-1.

R-A R01.11 1SI-06-24A 1SI18F8-2° 13R-01 NOTE 17 100 SUR PT NRI PIPE- EL80W Existing weld was replaced during replacement of Valve 1SI88198 under WO# 1281799-01, documented as Weld FW 23A-1.

R-A R01.11 1SI-10-27.01 1SI18FC-2° 13R-01 NOTE 17 100 SUR PT NRI PIPE- ELBOW Replaced existing weld during replacement of Valve 1SI8819C under WO# 609949*01. Documented as Weld FW 5-1.

R-A R01.11 1SI-10-28.01 1SI18FC-2° 13R-01 NOTE 17 100 SUR PT NRI VALVE 1S18819C - PIPE Replaced existing weld during replacement of Valve 1SI8819C under WO# 609949-01. Documented as Weld FW 6-1.

R-A R01.11 1SI-23-06-FD 1SI18FD-2° 13R-01 NOTE 17 100 SUR PT NRI VALVE 1SI8819D - PIPE Existing weld was replaced during replacement of Valve 1SI8819D under WO# 1224737*01, documented as Weld FW 6-1.

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.3 Detailed Third Interval Inservice Component Support Table SYSTEM: Auxiliary Feedwater System (AF)

F-A F01.20 1AF04031X 1AF02DB-4* VT-3 NRI Seismic Added for 3rd Interval. Reference IWC-1222(b) ASME SECTION XI, 2003 Edition / Addenda.

F-A F01.20 1AF04032V 1AF02DB-4* VT-3 NRI Variable Added for 3rd Interval. Reference IWC-1222(b) ASME SECTION XI, 2003 Edition / Addenda. (As Found Load: 643#).

F-A F01.20 1AF05001R 1AF02EC-4* VT-3 NRI Rigid F-A F01.20 1AF05002X 1AF02DC-4* VT-3 NRI Seismic Added for 3rd Interval. Reference IWC-1222(b) ASME SECTION XI, 2003 Edition / Addenda.

F-A F01.20 1AF05003V 1AF02DC-4* VT-3 NRI Variable Added for 3rd Interval. Reference IWC-1222(b) ASME SECTION XI, 2003 Edition / Addenda. (As Found Load Setting: 488#)

F-A F01.20 1AF05067X 1AF02DC-4* VT-3 NRI Seismic Added for 3rd Interval. Reference IWC-1222(b) ASME SECTION XI, 2003 Edition / Addenda.

F-A F01.20 1AF06046G 1AF02DA-4* VT-3 NRI Guide Added for 3rd Interval. Reference IWC-1222(b) ASME SECTION XI, 2003 Edition / Addenda.

F-A F01.20 1AF06047R 1AF02DA-4* VT-3 NRI Rigid Added for 3rd Interval. Reference IWC-1222(b) ASME SECTION XI, 2003 Edition / Addenda.

F-A F01.20 1FW1 0002R 1FW87BC-3* VT-3 NRI Rigid F-A F01.20 1FW1 0003R 1FW87BC-3* VT-3 NRI Rigid Added for 3rd Interval. Reference IWC-1222(b) ASME SECTION XI, 2003 Edition / Addenda.

F-A F01.20 1FW12002R 1FW87BB-3* VT-3 NRI Rigid Added for 3rd Interval. Reference IWC-1222(b) ASME SECTION XI, 2003 Edition / Addenda.

Page 3*24

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.3 Detailed Third Interval Inservice Component Support Table SYSTEM: Component Cooling System (CC)

F-A F01.30 1CC01017R 2CC01B-16* VT-3 NRI (1) Strut F-A F01.30 1CC02008R 2CC02B-16* VT-3 NRI Rod F-A F01.30 1CC02142X 2CC02CA-12* VT-3 NRI (1) Strut F-A F01.30 1CC03021 X OCC04B-16* NOTE 02 VT-3 NRI (1) Strut, integrally attached to pipe F-A F01.30 1CC03031R 2CC04AB-12* VT-3 NRI (2) Rods F-A F01.30 1CC03110R 2CC14DB-14* VT-3 NRI U-Bolt F-A F01.30 1CC03116R 2CC05G-16* VT-3 NRI (2) Rods F-A F01.30 1CC03143A 1CC05G-16* VT-3 NRI Anchor, integrally attached to pipe F-A F01.30 1CC03A131R 2CC14DB*14* VT-3 NRI (1) Strut Page 3-25

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.3 Detailed Third Intervallnservice Component Support Table SYSTEM: Chemical & Volume Control System (CV)

F-A F01.20 1CV47009X 1CV05B-S* VT-3 NRI (1) Strut Page 3-26

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.3 Detailed Third Interval Inservice Component Support Table SYSTEM: Main Steam System (MS)

F-A F01.20 1MSOSOO6R 1MS01 AA-30.2S* VT-3 NRI Steel F-A F01.20 1MS0700SR 1MS01 AC-32.7S* VT-3 NRI Steel F-A F01.20 1MS08006R 1MS01 AD-30.2S* VT-3 NRI Steel Page 3-27

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3,1,3 Detailed Third Interval Inservice Component Support Table SYSTEM: Reactor Coolant System (RC)

F-A F01.10 1CV03003X 1RC28A-3' VT-3 NRI (1) Strut F-A F01.10 1CV0602OC 1RC36A-3' VT*3 NRI (1) Constant Spring Can Actual Travel Setting: 2 1/2' F*A F01.40 1RC01R 1RC01R VT-3 10 REACTOR VT-3 of reactor vessel support ('A' Cold Leg, 'B' Hot Leg, 'C' Cold Leg, and "D" Hot Leg Nozzles) performed after mirror insulation was removed in support of Code Case N-722 Visual, VE examinations and MSIP clamp field walkdowns. Minor corrosion (no associated wastage/degradation) noted.

F*A F01.10 1RC16104X 1RC22AA-1.S" VT-3 NRI Box F-A FOUO 1RC16116R 1RC22AA-1.S" VT-3 NRI Box F-A F01.10 1RC17053R 1RC22AB-1.S' VT-3 NRI (1) Strut F-A F01.10 1RC17057X 1RC22AB-1.S" VT-3 NRI (1) Strut F-A F01.10 1RC18031G 1RC22AC*1.S" VT-3 NRI Box F-A F01.10 1RC18032X 1RC22AC*1.S" VT-3 NRI Box F-A FOUO 1RC19041X 1RC22AD*1.S' VT-3 NRI (1) Strut F-A F01.10 1RC19044G 1RC22AD*1.S" VT-3 NRI U-Bolt F-A F01.10 1RC19056R 1RC22AD-1.S" VT*3 NRI Box F*A F01.10 1RY06006X 1RC24AB-4" VT-3 NRI (1) Strut F-A F01.10 1RY06013V 1RC24AA-4" VT*3 NRI (1) Variable Spring Can F*A FOUO 1RY06OS6X 1RC24AA-4" VT-3 NRI (1) Strut Page 3-28

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.3 Detailed Third Interval Inservice Component Support Table SYSTEM: Residual Heat Removal System (RH)

F-A F01.20 1CV47044A 1RH12A-S* VT-3 NRI Anchor, integrally attached to pipe F-A F01.20 1S11S007R 1RH03AB-S* VT-3 NRI Slide Plate F-A F01.20 1S11S009R 1RH03AB-S* VT-3 NRI (1) Strut Page 3-29

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3,1,3 Detailed Third Interval Inservice Component Support Table SYSTEM: Safety Injection System (SI)

F-A F01.10 1RB-064A 1S103FB-2' VT-3 NRI Anchor, integrally attached to pipe F-A F01.40 1RH01 SA-INBOARD-SUPPORT 1RH01SA VT-3 NRI Ref. Dwgs. 1-CISI-1000 Sht. 6A, Rev. A, Sht.6B, Rev. A ,Dwg.1SI06A01X Rev. E, 1SI06A02R Rev. K.

F-A F01.40 1RH01 SA-OUTBOARD- 1RH01SA VT-3 NRI SUPPORT Ref. Dwgs. 1-CISI-1000 Sht. 6A, Rev. A, Sht.6B, Rev. A ,Dwg.1SI06A01X Rev. E, 1SI06A02R Rev. K.

F-A F01.10 1RH02037R 1SIA4B-8' VT-3 NRI (1) Strut F-A F01.10 1RH02040R 1SIA4B-8' VT-3 NRI (2) Struts F-A F01.10 1RH02064V 1SIA4B-8" VT-3 NRI (1) Variable Spring Can As Found Load Setting: 1717#.

F-A F01.10 1SI01023R 1S105DA-6' VT-3 NRI Box F-A F01.10 1SI04014V 1SI05DB-6" VT-3 NRI (1) Variable Spring Can F-A F01.20 1SI06105X 1SI01B-24" VT-3 NRI (1) Strut F-A F01.40 1SI06A01X 1RH01SA VT-3 NRI (2) Struts F-A F01.40 1SI06A02R 1RH01SA VT-3 NRI Steel, Attached to Can Valve Assembly F-A F01.20 1S118013X 1SI05AB-8" VT-3 NRI Box F-A F01.20 1S118039R 1SI05AB-8" VT-3 NRI (1) Rod F-A F01.20 1S118082R 1SI05AA-8" VT-3 NRI (2) Struts F-A F01.20 1S118083A 1SI05AB-8" VT-3 NRI Anchor, integrally attached to pipe F-A F01.10 1S123007R 1S108FA-3' VT-3 NRI Box Page 3-30

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Braidwood Station Unit 1 A 1R15 lSI Outage Report Section 3,1,3 Detailed Third Interval Inservice Component Support Table SYSTEM: Essential Service Water System (SX)

F-A F01.30 1AF03014X 1SXB7A-S' VT-3 NRI (2) Struts F-A F01.30 1AF03030X 1SX25AA-6' VT*3 NRI Box F-A F01.20 1PC-015A 1SX06BA*16' VT-3 NRI Anchor, integrally attached to pipe F-A F01.30 1SX01001R 2SX02AB*36' VT-3 NRI (2) Rods F*A F01.30 1SX01003R 2SX13A*36' VT-3 NRI (2) Rods F-A F01.30 1SX0101SX 1SX02AB-36' VT-3 NRI U-Bolt F-A F01.30 1SX01020R 2SX13A*36' VT-3 NRI Strut F*A F01.30 1SX01022R 1SX04AB-20' VT*3 NRI (1) Strut F*A F01.30 1SX02002R OSX03CA-48' NOTE 02 VT-3 NRI (1) Strut F-A F01.30 1SX02038X 1SX03A-30' VT-3 NRI (1) Strut, integrally attached to pipe F-A F01.30 1SX02045X OSX03A-30' NOTE 02 VT*3 NRI (1) Strut, integrally attached to pipe F*A F01.30 1SX02060R 1SX03A-30' VT-3 NRI (1) Strut, integrally attached to pipe F-A F01.30 1SX02069X OSX02CB-48' NOTE 02 VT-3 NRI (1) Strut F-A F01.30 1SX02073X 1SX03B-42' VT-3 NRI (1) Strut F*A F01.30 1SX0207SR 1SX03A-30' VT-3 NRI Stanchion, integrally attached to pipe F-A F01.20 1SX06002G 1SX06BA*16' VT-3 NRI Box F-A F01.20 1SX06007R 1SX06CA*14' VT*3 NRI Box F*A F01.20 1SX07007G 1SX06CB-14' VT-3 NRI (1) Strut F-A F01.20 1SX07012R 1SX06EB-1 0' VT*3 NRI Box F-A F01.20 1SX07034X 1SX06CB-14' VT*3 NRI (1) Strut Page 3-31

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.3 Detailed Third Interval Inservice Component Support Table SYSTEM: Essential Service Water System (SX)

F-A F01.20 1SX08001R 1SX07FA-16* VT-3 NRI (1) Strut F-A F01.20 1SX0801OG 1SX07EA-14* VT-3 NRI Strut and U-Bolt F-A F01.20 1SX08097X 1SX09CA-1 O* VT-3 NRI (1) Strut F-A F01.20 1SX09001R 1SX07FB-16* VT-3 NRI (1) Strut F-A F01.20 1SX09046R 1SX07FB-16* VT-3 NRI (1) Strut F-A F01.30 1SX24001R 1SX07HB-20* VT-3 NRI (2) Rods F-A F01.30 1SX24003R 1SX07HB-20* VT-3 NRI (2) Rods F-A F01.30 1SX24013R 1SX07HB-20* VT-3 NRI (2) Rods F-A F01.30 1SX25015R 1SX02B-30* VT-3 NRI (1) Strut F-A F01.30 1SX30019G 1SX05CB-6* VT-3 NRt (2) Struts F-A F01.30 1SX36021R 1SX05CA-6* VT-3 NRt U-Bolt F-A F01.30 1SX7101OG 1SXA9A-6* VT-3 NRI U-Bolt Page 3-32

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.4 Detailed Preservice Component Support Table SYSTEM: Reactor Coolant System (RC)

F-A F01.40 1RC01 BA 1RC01 BA VT-3 NRI S.G A Performed post maintenance VT-3 after repairs specified in EC 381691 were completed under WO 1375122. VT-3 examinations were IJerformed with system cold (10/20/2010) and hot (11/4/2010).

F-A F01.40 1RC01 BC 1RC01 BC VT-3 NRI S.G C During visual examination of 1RC01 BC shim packs, the upper right nut on the southwest shim pack was found to be loose (reference IR 1121934). The remaining bolting was tight and intact. Tightened loose bolting and performed post maintenance VT-3 examination with system cold (10/15/2010) and again with system hot (11/4/2010).

Page 3-33

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM: Auxiliary Feedwater System (AF)

F-A F01.20 1AF06004S 1AF02EA-4' NOTE 01 VT-3 NRI Snubber FT NRI Functionally Tested For Service Life Monitoring.

F-A F01.20 1FW12025S 1FW87BB-3' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-1.

Note: Section XI Category numbers identified as 'N/A' are exempt from IWF-1220 and IWF-2500 tables Page 3-34

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Braidwood Station Unit 1 A 1R15 lSI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM: Containment Spray System (CS)

NA NA 1CS0401 OS 1CS02AA-10* NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

Note: Section XI Category numbers identified as *N/A* are exempt from IWF-1220 and IWF-2500 tables Page 3-35

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.5 Detailed Third Intervallnservice Snubber Table SYSTEM: Chemical & Volume Control System (CV)

NA NA 1CV30002S 1CV1SAD-.7S* NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-1.

NA NA 1CV31007S 1CV1SDA-.7S* NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-1.

NA NA 1CV41036S 1CV14ED-2* NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-1.

Note: Section XI Category numbers identified as *N/A' are exempt from IWF-1220 and IWF-2S00 tables Page 3-36

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM: Main Steam System (MS)

F-A F01.20 1MS01079S 1MS07AA*28* NOTE 01 VT-3 NRI Snubber, integrally attached to pipe FT NRI Snubber selected for Functional Testing for Service Life Monitoring.

Note: Section XI Category numbers identified as 'N/A' are exempt from IWF*1220 and IWF-2500 tables Page 3-37

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.5 Detailed Third Intervallnservice Snubber Table SYSTEM: Reactor Coolant System (RC)

F-A F01.10 1CV1S111S 1RC14AB-2' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

F-A F01.40 1RC01BA-A S.G A NOTE 01 VT-3 NRI Snubber F-A F01.40 1RC01 BA-B S.G A NOTE 01 VT-3 NRI Snubber F-A F01.40 1RC01BB-A S.G B NOTE 01 VT-3 NRI Snubber F-A F01.40 1RC01BB-B S.G B NOTE 01 VT-3 NRI Snubber F-A F01.40 1RC01BC-A S.G C NOTE 01 VT-3 NRI Snubber VT-3 NRI F-A F01.40 1RC01 BC-B S.G C NOTE 01 VT-3 NRI Snubber F-A F01.40 1RC01BD-A S.G D NOTE 01 VT-3 NRI Snubber F-A F01.40 1RC01BD-B S.G D NOTE 01 VT-3 NRI Snubber FT NRI Functional test per WO# 1293926. Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-4.

F-A F01.10 1RC03006S 1RC21AC-S' NOTE 01 VT-3 NRI Snubber VT-3 NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-3.

F-A F01.10 1RC04OO5S 1RC21AD-S' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

F-A F01.10 1RC170S85 1RC22AB-1.S' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-1.

F-A F01.10 1RC19042S 1RC22AD-1.S' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-1.

NA NA 1RC19060S 1RC20AD-.7S' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-1.

Note: Section XI Category numbers identified as 'N/A' are exempt from IWF-1220 and IWF-2S00 tables Page 3-38

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.5 Detailed Third Intervallnservice Snubber Table SYSTEM: Residual Heat Removal System (RH)

F-A F01.10 1RH02012S 1RH01AB-12' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Sample Expansion due to Functional Test Failure in the 1st Mandatory Sample (1SI09015S, reference IR 1124493): Design Test Plan Grouping DTPG-1-2.

F-A F01.10 1RH02047S 1RH01 AA-12' NOTE 01 VT-3 NRI Snubber FT NRI Snubber replaced during A1R15 under WO# 1224658. New Snubber Serial Number 41264. Old Serial Number is 9657. Snubber was functionally tested for Service Life Monitoring. Pre Service test was performed on the replacement and an as found test was performed on the replaced snubber.

F-A F01.10 1RH02205AS 1RH01 AA-12' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

F-A F01.10 1RH02205BS 1RH01 AA-12' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

NA NA 1RH02217S 1RH26AB-.75' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Service Life Monitoring.

F-A F01.20 1RH04011 S 1RH03AB-S' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

Note: Section XI Category numbers identified as 'N/A' are exempt from IWF-1220 and IWF-2500 tables Page 3-39

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM: Reactor Coolant System (RY)

F-A F01.10 1RY06027S 1RY01 8-6' NOTE 01 VT-3 NRI Snubber FT NRI Snubber was functionally tested for Service Life Monitoring because it was removed from it's location to support Maintenance on pump 1RC01 PD. Reference Issue Reports 1124383 and 112sn6 for identification of RegUlatory Non Compliance with regard to the fact that the snubber was removed 2 previous times without having the Code Case OMN-13, required VT-3 Examination of the snubber prior to removal during the first 2 evoultions. The snubber was removed 3 times in support of maintenance during A1R15.

F-A F01.10 1RY06031 S 1RY01 8-6' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

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

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.5 Detailed Third Intervallnservice Snubber Table SYSTEM: Steam Generator Slowdown System (SO)

NA NA 1SD24078S 1SD01CD*2* NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

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

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM: Safety Injection System (SI)

F-A F01.10 1RH02069S 1SI04D-8' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Sample Expansion due to Functional Test Failure in the 1st Mandatory Sample (1SI09015S, reference IR 1124493): Design Test Plan Grouping DTPG-1-2.

NA NA 1SI01007S 1S109BA-10' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Sample Expansion due to Functional Test Failure in the 1st Mandatory Sample (1SI09015S, reference IR 1124493): Design Test Plan Grouping DTPG-1-2.

F-A F01.10 1SI01029S 1SI05DA-6' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

F-A F01.20 1SI01032S 1S109AA-1 0' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

F-A F01.10 1SI01 0345 1SI05DA-6' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

F-A F01.20 1SI02oo3S 1SIOSCA-8' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

F-A F01.10 1SI030165 1S105DD-6' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

F-A F01.10 1S103020S 1S105DD-6' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

F-A F01.10 1S103023S 1S109BD-1 0' NOTE 01 VT-3 NRI Snubber VT-3 NRI Reason for Selection for Functional Testing: Sample Expansion due to Functional Test Failure in the 1st Mandatory Sample (1SI09015S, reference IR 1124493): Design Test Plan Grouping DTPG-1-2.

F-A F01.10 1S104016S 1S105DB-6' NOTE 01 VT-3 NRI Snubber FT NRI Preservice functional and VT-3 examinations required after existing snubber (Serial Number 16732) was replaced under WO# 1294115.

New Snubber S.N. 25622. Reason for Functional Testing: Service Life Monitoring.

F-A F01.20 1SI040245 1SI05CB-S' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG 1-2.

F-A F01.20 1SI040265 1SI05CB-S' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Sample Expansion due to Functional Test Failure in the 1st Mandatory Sample (1SI09015S, reference IR 1124493): Design Test Plan Grouping DTPG-1-2.

Note: Section XI Category numbers identified as 'N/A' are exempt from IWF-1220 and IWF-25oo tables Page 3-42

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.5 Detailed Third Intervallnservice Snubber Table SYSTEM: Safety Injection System (SI)

F-A F01.20 1SI09006S 1SI05GB-8' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

F-A F01.10 1SI090135 1SI05DC-6' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

F-A F01.10 1S109015AS 1SI05DC-6' NOTE 01 VT-3 NRI Snubber FT FAIL Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2. Snubber Serial Number 15517 failed functional test for drag in compression and was replaced with Serial Number 20643. Reference Issue Report 1124493 for identification in CAPand Engineering Change 381733 for evaluation for adverse affects on piping system. Sample expansion to snubbers 1SI030235, 1SI04026S, 1RH02069S, 1RH02012S, 1SI01 031 S, 1SI01 007S, 1SI03021 S, 1S109038S1 , and 1SI09038S2.

F-A F01.10 1S109015BS 1SI05DC-6' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing (Sample expansion due to failed snubber 1SI09015AS, reference IR 1124493): Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-2.

F-A F01.10 1S109039S 1SI05DC-6' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Mandatory 1st Sample: Design Test Plan Grouping DTPG-1-3.

F-A F01.10 1S116029S 1SI18FC-2' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Service Life Monitoring as snubber was removed from its location in support of maintenance (Valve Work)

F-A F01.10 1S124012S 1SI0&JA-1.5' NOTE 01 VT-3 NRI Snubber FT NRI Reason for Selection for Functional Testing: Sample Expansion due to Functional Test Failure in the 1st Mandatory Sample: Design Test Plan Grouping DTPG-1-1.

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

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Braidwood Station Unit 1 A1R15 151 Outage Report Section 3.1.6 Detailed Third Interval Preservice Snubber Table SYSTEM: Reactor Coolant System (RC)

F*A F01.40 1RC01 BO-B S.G 0 NOTE 01 VT-3 NRI Snubber Post maintenance examination after existing cap screws for adaptor were replaced under WO# 1293926-01.

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

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.6 Detailed Third Interval Preservice Snubber Table SYSTEM: Residual Heat Removal System (RH)

F-A F01.10 1RH02047S 1RH01AA-12' NOTE 01 VT-3 NRI Snubber Post maintenance VT-3 examination, existing PSA-3 snubber (Serial Number 9657) was replaced by functionally tested spare (Serial Number 41624) under WO# 1224658-01.

Note: Section XI Category numbers identified as 'N/A' are exempt from IWF-1220 and IWF-2500 tables Page 3*45

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Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.6 Detailed Third Interval Preservice Snubber Table SYSTEM: Safety Injection System (SI)

F-A F01.10 1SI040168 1S10508-6' NOTE 01 VT-3 NRI Snubber Removed existing PSA-3 mechanical snubber (Serial Number 15517) and tested under Service Life Monitoring Program, replaced with tested spare snubber Serial Number 25622 in accordance with IWA-4132 requirements.

F-A F01.10 1S109015AS 1S1050C-6' NOTE 01 VT-3 NRI Snubber Post maintenance VT-3 after existing PSA-3 snubber (Serial Number 15517) failed functional test (reference IR 1124493) and was replaced with functionally tested spare (Serial Number 20643).

Note: Section XI Category numbers identified as 'N/A' are exempt from IWF-1220 and IWF-2500 tables Page 3-46

Exelon~

Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.7 Detailed Third Interval Pressure Tests SYSTEM: Auxiliary Feedwater System (AF)

C-H C07.10 A01AF-OOOOO5-M04-02C VT-2 NRI Period ASME Section XI Pressure Test.

Partial examination complete on 7/2312010, balance of test block was completed on 1011/2010 when access to AF steam tunnel was available. No indications noted.

Page 3*47

Exelon~

Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.7 Detailed Third Interval Pressure Tests SYSTEM: Chemical & Volume Control System (CV)

C-H C07.1 0 A01 CV-OOOOO4-M04-01 A NOTE 21 VT-2 10 Period ASME Section XI Pressure Test. NOTE 24 Packing leaks (10) were noted at the following valves:

1CV012 (IR 1093212); 1CV210 (also threaded cap, IR 1093210); 1CV110A (IR 1093207); 1CV072 (IR 1093205); 1CV8133 (IR 1093203);

1CV017A (1093202); 1CV471 (IR 1093199); 1CV8355D (IR 1092541); 1CV051 0 (IR 1092538); 1CV83848 (IR 1092485); 1CV207 (IR 1092479); 1CV8109 (IR 1092474); and 1CV8355C (IR 1092548)

Leaks at mechanical connections (pipe caps, compression fittings, etc.) were noted at the following:

1CV03P fitting (IR 1093196); 1CV0658 pipe cap (IR 1092545); 1CV206 threaded cap (1092488)

C-H C07.10 A01CV-OOOOO4-M04-018 NOTE 21 VT-2 NRI Period ASME Section XI Pressure Test. NOTE 24 No recordable indications.

Page 3-48

Exelon~

Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.7 Detailed Third Interval Pressure Tests SYSTEM: Fuel Pool Cooling System (FC)

C-H C07.10 A01 FC-OOOOO1-M04-01 C NOTE 22 VT-2 NRI Period ASME Section XI Pressure Test.

No recordable indications.

C-H C07.10 A01FC-OOOOO1-M04-01D NOTE 22 VT-2 NRI Period ASME Section XI Pressure Test.

No recordable indications.

Page 3*49

Exelon.

Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.7 Detailed Third Interval Pressure Tests SYSTEM: Instrument Air System (IA)

C-H C07.10 A01IA-000004-M04-01 A 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.

Page 3*50

Exelen.

Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1,7 Detailed Third Interval Pressure Tests SYSTEM: Residual Heat Removal System (RH)

C-H C07.1 0 AO 1RH-OOOOO3-M04-01 A NOTE 22 VT-2 IND Period ASME Section XI Pressure Test. VERIFY loop 'A' in service.

Pressurize 1A sample line per BwCP 613-3.

Performed walkdowns on 10/17/201, 10/19/2010 and remainder on 1213/2010.

The following indications were noted during 10/19/2010 examination:

Line 1RH02AA-1 0' target residue (I R 1128858); dry boron on Valve 1SI8812A actuator (IR 1128846)

Dry boron at the following valve packing: 1RH026A (IR 1129856); 1RH011 A (IR 1129857); 1SI058A (IR 1129861)

Dry boron at Pump 1RH01 PA seal cooler line (previously identified under IR 1120716)

C-H C07.1 0 A01 RH-OOOOO3-M04-01 B NOTE 22 VT-2 10 Period ASME Section XI Pressure Test. VERIFY loop 'B' in service.

Pressurize 1B sample line per BwCP 613-3.

Performed walkdowns on 10/17/201, 10/19/2010 and remainder on 1213/2010.

The following indications were noted during 10/19/2010 examination:

Line 1RH10AB-3' significant boron deposit upstream of Valve 1RH611 (IRs 1128331 and 1128397). Determined to be from old leak above (insulation was removed to verify no through-wall pipe leakage).

1RH8716B body-to-bonnet interface (IR 1129888 for gasket replacement in A1R16).

Dry boron at packing of the following valves: 1RH011 B (including pipe cap) (IR 1129883; 1RH027 (IR 1129884); 1RH028B (including downstream fitting) (IR 1129886); 1SI059B (including quick disconnect fitting) (IR 1129887; 1SI160 (IR 1129893)

C-H C07.10 A01RH-OOOOO3-M04-01 D NOTE 22 VT-2 RI Period ASME Section XI Pressure Test.

Performed walkdown on 10/1612010. Dry boron residue at body-to-bonnet of Valve 1SI8818A (IR 1127299), evaluation performed C-H C07.10 A01RH-OOOOO3-M04-01E NOTE 22 VT-2 RI Period ASME Section XI Pressure Test.

Performed walkdown on 10/17/2010. Dry boron residue at body-to-bonnet interface of Valve 1SI8818C (previously identified on 10/6/2010, IR 1127298). Bolting evaluated for continued service.

Page 3*51

Exel~n ..

Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.7 Detailed Third Interval Pressure Tests SYSTEM: Safety Injection System (SI)

C-H C07.10 A01SI-OOOO10-M04-01A NOTE 22 VT-2 10 Period ASME Section XI Pressure Test.

Portions of test block examined in conjuction with 1BwVSA TAM 2.5.c.3 (SI Cold leg Injection test, WO# 1291457) on 10/17/2010, balance of test block inspected on 12/3/2010.

Information Only dried boric acid/packing leaks at the following:

1PI-S1116 (IA 1149700); 1SI016A (IA 1149729); 1S18888 (IA 1149790); 1SI051 (IA 1149794)

C-H C07.10 A01SI-OOOO1Q-M04-01B NOTE 22 VT-2 10 Period ASME Section XI Pressure Test.

AI at 1SI01PB (1B SI pump) discharge flange (IA 1144185). Bolting closest to the source of leakage was pulled and examined by VT-3 method in accordance with ASME Section XI IWA-5250(a)(2) under WO# 1391611. No degradation was noted on bolting.

10 indications were noted at the follwing packing/mechanical connections:

1SI050 quick disconnect (IA 1144165); 1SI0270 (IA 1144174); 1SI027C (IA 1144178); 1S18919B threaded body-to-cap connection (IA 1144197); 1SI01 PB (1 B SI pump) inboard seal drain connection (IA 1144212); 1SI01 PB (1 B SI pump) outboard seal flush line connection (IA 1144223)

C-H C07.10 A01SI-OOOO1Q-M04-01C NOTE 22 VT-2 NAI Period ASME Section XI Pressure Test.

No recordable indications.

C-H C07.10 A01SI-OOOO1Q-M04-01D NOTE 22 VT-2 NAI Period ASME Section XI Pressure Test.

Examination performed in conjunction with 1BwVSA TAM 2.5.c.2 for 1A CV pump flow balancing.

10 for dry packing leak on 1SI045, outside of test boundary (IA 1127865)

C-H C07.10 A01SI-OOOO1Q-M04-01F NOTE 22 VT-2 AI Period ASME Section XI Pressure Test.

Examination performed in conjunction with APV cavity fill under 1BwOSA 5.5.8.AH-6 using BwOP AH-8.

AI for unquantifiable weeping at body-to-bonnet interface of 1SI8841 B (IA 1116141 and 1164972). Evaluation of bolting performed in accordance with Code Case N-566-2, WA 00356995 initiated to clean/tighten bolting in A1A16 outage.

10 leaks at packing/mechanical connections on the following:

1SI09O (IA 1123717); 1SI089 pipe cap (IA 1123715); 1SI8825 (IA 1123714); dry boric acid residue on Une 1SI04B-12* (IA 1125134)

C-H C07.10 A01SI-OOOO1Q-M04-01G NOTE 22 VT-2 10 Period ASME Section XI Pressure Test.

10 indication of packing leak at 1S18888 (IA 1149790)

C-H C07.10 A01SI-OOOO1Q-M04-01J NOTE 22 VT-2 10 Period ASME Section XI Pressure Test.

1A SI accumulator. Snoop solution used on nitrogen side of accumulator.

10 packing leak at 1SI8878A (IA 1134696).

C-H C07.10 A01SI-OOOO1Q-M04-01K NOTE 22 VT-2 NAI Period ASME Section XI Pressure Test.

1B SI accumulator. No recordable indications. Snoop solution used on nitrogen side of accumulator.

Page 3-52

Exelon..

Braidwood Station Unit 1 A 1R15 lSI Outage Report Section 3.1.7 Detailed Third Interval Pressure Tests SYSTEM: Safety Injection System (SI)

C-H C07.10 A01SI-OOOO10-M04-01L NOTE 22 VT-2 NRI Period ASME Section XI Pressure Test.

1C SI accumulator. No recordable indications. Snoop solution used on nitrogen side of accumulator.

1SI04TC pneumatic test completed on 11/2/2010 for post maintenance test for WO# 1294485 activities.

C-H C07.10 A01SI-OOOO10-M04-01M NOTE 22 VT-2 10 Period ASME Section XI Pressure Test.

10 SI accumulator. Snoop solution used on nitrogen side of accumulator.

10 indication for dry boric acid residue 1SI8878D (IR 1134697).

C-H C07.10 A01 SI-OOOOlO-M04-01 P NOTE 22 VT-2 NRI Period ASME Section XI Pressure Test.

No recordable indications.

Page 3-53

Exelfbn..

Braidwood Station Unit 1 A 1R15 lSI Outage Report Section 3.1.7 Detailed Third Interval Pressure Tests SYSTEM: Essential Service Water System (SX)

C-H C07.10 A01SX-OOOO11-M04-01N VT-2 10 Period ASME Section XI Pressure Test.

18 RCFC completed 10/10/2010, 10 RCFC completed 10/12/2010. Piping outside of plenums (377' and 401' elevations) was examined on 10/3/2010. Minor corrosion was noted for information on bolting on Valves 1SX021 8 and 1SX025C (reference IR 1134644), WO#

1384275 initiated to clean and coat Valves 1SX021A, 1SX0218, 1SX021C, a1SX021O, 1SX025A, 1SX0258, 1SX025C, and 1SX025D during A1R16.

C-H C07.10 A01 SX-OOOO11-M04-01 P VT-2 NRI Period ASME Section XI Pressure Test.

1A RCFC completed on 10/1612010, 1C RCFC completed on 10/612010. Piping outside of plenums (377' and 401' elevations) was examined on 10/3/2010. Minor corrosion was noted for information on bolting on Valves 1SX021 8 and 1SX025C (reference IR 1134644),

WO# 1384275 initiated to clean and coat Valves 1SX021A, 1SX0218, 1SX021C, a1SX021D, 1SX025A, 1SX0258, 1SX025C, and 1SX025D during A1R16.

Page 3-54

Exelon..

Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.7 Detailed Third Interval Pressure Tests SYSTEM: Plant Systems Pressurized During Mode 3 (ZZ)

B-P B15.10 A01ZZ-000005*M04-01A NOTE 22 VT*2 NRI Each Refueling Outage ASME Section XI Pressure Test & Generic NOTE 23 Letter 88-05. Class 1 components.

System leakage test at conclusion of A1R15. No recordable indications noted in Class 1 systems.

Page 3-55

Exel~n_

Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.8 Detailed Borated Bolted Connection Table SYSTEM: Chemical & Volume Control System (CV)

B-P B15.10 PG-2546C-014 F-2-2 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Component is Located Inside Containment C-H C07.10 PG-2546C-018 F-1-5 (C-H) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Component is Located Inside Containment C-H C07.10 PG-2546C-020 F-1-1 (C-H) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Component is Located Inside Containment C-H C07.10 PG-2546C-022 F-2-3 (C-H) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Component is Located Inside Containment C-H C07.10 PG-2546C-041 F-1-1 (C-H) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Component is Located Inside Containment C-H C07.10 PG-2546C-063 F-1-1 (C-H) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Component is Located Inside Containment G-H C07.10 PG-2546C-068 F-1 (C-H) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Component is Located Inside Containment C-H C07.10 PG-2546C-083 FL-1-2 (C-H) VT-2 NRI FLANGED CONNECTION (8 STUDS)

Component is Located Inside Containment C-H C07.10 PG-2546C-089 FL-1-1 (C-H) VT-2 NRI FLANGED CONNECTION (8 STUDS)

Component is Located Inside Containment C-H C07.10 PG-2546C-090 F-1-1 (C-H) VT-2 NRI FLANGED CONNECTION (8 STUDS)

Component is Located Inside Containment B-P B15.10 PG-2546C-091 F-2-3 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Component is Located Inside Containment C-H C07.10 PG-2546C-093 F-1 (C-H) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Component is Located Inside Containment B-P B15.10 PG-2546C-101 F-2-3 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Component is Located Inside Containment Page 3-56

Exelon.

Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.8 Detailed Borated Bolted Connection Table SYSTEM: Pressurizer (PZR)

B-P B15.10 1PZR-01-B1 (B-P) VT-2 NRI MANWAY BOLTING (16 TOTAL)

Component is Located Inside Containment Page 3*57

Exelon_

Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.8 Detailed Borated Bolted Connection Table SYSTEM: Reactor Coolant System (RC)

B-P B15.10 1RC-19-B3 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Component is Located Inside Containment B-P B15.10 1RC-2Q-B1 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Component is Located Inside Containment B-P B15.10 1RC-2S-B1 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Component is Located Inside Containment B-P B15.10 1RC-27-B1 (B-P) VT-2 NRI FLANGED CONNECTION (4 STUDS)

Component is Located Inside Containment B-P B15.10 1RV-OS-STUDS (01 TO 54, B-P) VT-2 NRI CLOSURE HEAD STUDS (54 TOTAL)

Component is Located Inside Containment B-P B15.10 1SG-05-SGB-01 (B-P) VT-2 NRI PRIMARY MANWAY (20 STUDS)

Component is Located Inside Containment B-P B15.10 1SG-Q5-SGB-02 (B-P) VT-2 NRI PRIMARY MANWAY (20 STUDS)

Component is Located Inside Containment B-P B15.10 1SG-QS-SGB-01 (B-P) VT-2 NRI PRIMARY MANWAY (20 STUDS)

Component is Located Inside Containment B-P B15.10 1SG-QS-SGB-02 (B-P) VT-2 NRI PRIMARY MANWAY (20 STUDS)

Component is Located Inside Containment B-P B15.10 1SG-Q7-SGB-01 (B-P) VT-2 NRI PRIMARY MANWAY (20 STUDS)

Component is Located Inside Containment B-P B15.10 1SG-Q7-SGB-02 (B-P) VT-2 NRI PRIMARY MANWAY (20 STUDS)

Component is Located Inside Containment B-P B15.10 1SG-QS-SGB-01 (B-P) VT-2 NRI PRIMARY MANWAY (20 STUDS)

Component is Located Inside Containment B-P B15.10 1SG-QS-SGB-02 (B-P) VT-2 NRI PRIMARY MANWAY (20 STUDS)

Component is Located Inside Containment Page 3-58

Exelon.~

Braidwood Station Unit 1 A1R15 lSI Outage Report Section 3.1.8 Detailed Borated Bolted Connection Table SYSTEM: Residual Heat Removal System (RH)

C-H C07.10 1RH-02 F-1-1 (C-H) VT-2 NRI FLANGED CONNECTION (20 STUDS)

Component is located Outside Containment C-H C07.10 1RH-02 F-2-1 (C-H) VT-2 NRI FLANGED CONNECTION (20 STUDS)

Component is located Outside Containment C-H C07.10 1RH-02 F-4 (C-H) VT-2 NRI FLANGED CONNECTION (8 STUDS)

Component is located Outside Containment C-H C07.10 1RH-03 F-2 (C-H) VT-2 NRI FLANGED CONNECTION (24 STUDS)

Component is located Outside Containment C-H C07.10 1RH-05 F-1 (C-H) VT-2 NRI FLANGED CONNECTION (24 STUDS)

Component is located Outside Containment C-H C07.10 1RH-05 F-2 (C-H) VT-2 NRI FLANGED CONNECTION (24 STUDS)

Component is located Outside Containment C-H C07.10 1RH-05 F-3-1 (C-H) VT-2 NRI FLANGED CONNECTION (12 STUDS)

Component is located Outside Containment C-H C07.10 1RH-06 F-1-1 (C-H) VT-2 NRI FLANGED CONNECTION (12 STUDS)

Component is located Outside Containment C-H C07.10 1RH-07 F-2-1 (C-H) VT-2 NRI FLANGED CONNECTION (20 STUDS)

Component is located Outside Containment C-H C07.10 1RH-07 F-3-1 (C-H) VT-2 NRI FLANGED CONNECTION (20 STUDS)

Component is located Outside Containment C-H C07.10 1RH606 (C-H) VT-2 NRI 1RH606 VLV (4 STUDS)

Component is located Outside Containment Page 3-59

Braidwood Station Unit 1 A1R15 lSI Outage Report 4.0 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 4-1

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 4. Owner Certificate of Authorization (if required) Not Applicable

5. Commercial Service Date 7/29/1988 6. National Board Number for Unit N-195

7. Components Inspected See Section 3 of this report for all components (report is a total of 99 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-195 1RC01R Pressurizer Westinghouse 2101 U-199012 18696 1RY01S Residual Heat Joseph Oats 2267-1 E Not Applicable 840 Removal 1RH02AA Steam Generator ComEd / BWI 7735-01 U-237763 168 1RC01BA See Sections 3.1 through 3.1.8 and associated tables for specific Class 1 and 2 component locations examined for the Third Interval lSI Program.

Page 4-2

FORM NIS-1 (Back)

8. Examination Dates: June 11,2009 to January 12,2011

9. Inspection Period Identification: 151 Period, Third Interval - From July 29, 2008 through July 28,2011 (except Category B-B which ended October 7,2010)

10. Inspection Interval Identification: 3'd Interval - From July 29,2008 through July 28,2018

11. Applicable Edition of Section XI 2001 Edition Addenda 2003 Addenda

12. Date/Revision of Inspection Plan: August 4,2010/ Revision 3

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 XI, 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 20 J...L Signed Exelon Nuclear Braidwood Station By X1:.~~~?:::!:::.f=J-~~~:7-:"-_-- Braidwood lSI Program Manager 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 t.. ~ l \ - D 9 to C> \ - l '"2.. - \ \. and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.

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

. ..,..k~~J:::.==J:::..:::.~:::::: Commissions ~\ T3 0 e., S""l.." , J:L":l:o'< \ 0 ' 0 s- I~. N. \ _ C-Inspector's Signature National Board, State, Province, and Endorsements Date Page 4-3

Exelcnm Braidwood Station Unit 1 A1R15 lSI Outage Report Braidwood Unit 1 Non-Deferrable Inspection Status (Third Interval) After A1R15 per IWA-6220ff)

Code Category Code Item Number Total Number Selected Total Number Examined Current Percentage (Interval) in A1R15 Completed for Category B-A B1.30 1 0 0%

B1.40 1 0 B-B B2.11 2 0 3/5 =60%

B2.12 2 0 *Credited to Second Period B2.40 1 1*

B-O B3.110 6 2 B3.120 6 2 4/20 =20%

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

B10.20 2 0 B-N-1 B13.10 1 1 Once per period B-P B15.10 Everv Outaae 1 Not Applicable B-Q B16.20 Per Technical Soecifications 0 Not Applicable C-A C1.10 2 0 C1.20 2 0 1/5 = 20%

C1.30 1 1 C-B C2.21 5 1 2/6 = 33%

C2.22 1 1 C-C C3.10 1 1 C3.20 10 0 5/14 = 35.7%

C3.30 3 0 C-H C7.10 38 22 Once per period O-A 01.10 6 2 01.20 13 4 6/20 = 30%

01.30 1 0 O-B 02.10 35 11 Once per period E-A E1.11 256 256 Once per period E1.30 1 1 E-C E4.11 19 19 100%

F-A F1.10 199 21 F1.20 175 34 180/562 =32%

F1.30 151 32 F1.40 37 9 L-A L1.11 2 0 0%

L-B L.2.10 965 0 0%

R-A Butt Welds 186 18 44/186 = 23.7%

Socket Welds 123 Welds Everv Outaae 123 Page 4-4

Braidwood Station Unit 1 A1 R15 lSI Outage Report 5.0 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 XI, 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 XI to meet the reporting conditions specified in 10CFR 50.55a(b)(2)(ix)(A)( 1) through (3).

The third Interval 1first Period Class MC General Visual Examinations were completed.

All indications identified during the General Visual Examinations were reviewed and accepted as is without further evaluation 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.

There were no IWL surveillances completed prior to or during A1R15 and thus there are no results to report.

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

5.1 A1 R15 Containment Metal Liner Examinations (IWE)

Augmented Section XIIWE 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 XI 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 "Ultrasonic Measurement Of Material Thickness and Interfering Conditions" were used to perform the examinations.

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)]:

During the performance of augmented examinations of the Unit 1 containment liner plate, additional degradation was discovered in surfaces below the moisture barrier (MB).

Approximately 150' of moisture barrier removal and examinations were included in the initial A1R15 scope. The most notable type of degradation was liner pitting just below the MB resulting in metal loss of varying depths. The examination methods included VT-1 (Detailed Visual) and UT. With regard to initial scope for A1R15, the maximum pit depth identified was 10/64" at one location between R-19 and R-20. A pit depth of 6/64" was identified at two other locations. These locations were between R-19 and R-20 and near R-13.

Extent of condition:

As a result of discovery of the 10/64" and 6/64" pitted areas as previously discussed, the inspection scope was expanded during A1R15. Approximately 50' of additional moisture barrier was removed and VT-1 (Detailed Visual) UT examinations were performed. The Page 5-1

Braidwood Station Unit 1 A1R15 lSI Outage Report areas included in the expanded scope focused on those adjacent to those with large metal loss. The results of the exams performed in the expanded scope revealed a pit depth of 10/64" at one location between R-20 and R-21 and a pit depth of 6/64" at another location between R-12 and R-13.

The results of the exams performed in all other areas included in the initial and expanded scopes revealed pit depths ranging from 1/64" to 4/64". There was no further scope expansion in A1R15.

Description of the conditions that led to the degradation:

It is evident based on the recorded observations that the significant portions of the liner plate degradation below the MB are attributed to corrosion. The liner plate surface below the MB was coated with Carbo Zinc CZ11 in year 2000 which does not tolerate improper surface preparation. This coating product is not recommended for use unless white metal condition with a contoured surface profile is achieved. Since this strip of liner plate below the MB is not easily accessible, it is unlikely that the proper surface preparation was attained.

Furthermore, the liner plate surface may not have been completely dried (some moisture left in the wall from the wet Cerafibre resting against it) when the MB was replaced in 2000. In the year 2000 the Cerefibre was found wet and adhering to the metal liner. The liner most likely experienced a slow chronic corrosion rate prior to 2000. After the year 2000 when the MB was opened up, the bulk of the liner corrosion probably occurred in the early years after the year 2000 when MB was replaced. It has conservatively been considered that the corrosion rate had a linear progression over the past ten years since 2000. The new coating applied in A1R15 was Keeler and Long 9600 Series used for Service Level I coating in containment which it does not require white metal surface conditions.

Evaluation of each area, and the result of the evaluation

[10CFR 50.55a(b)(2)(ix)(A)(2)]:

One engineering evaluation (Engineering Change 381781) was performed to address all the indications. The evaluation determined that the liner plate with the highest degraded condition (10/64") will remain operational and meet its intended design function during the upcom ing run cycle until A1R16 where additional exam inations are scheduled.

Description of Necessary Corrective Actions Completed

[10CFR 50.55a(b)(2)(ix)(A)(3)]:

Corrective Actions Completed During A1R15 As previously discussed, approximately an additional 50' of liner plate directly below the MB was examined beyond the original scope using the VT-1 (Detailed Visual) method after the MB was removed. Ultrasonic thickness readings were performed near two areas with the 10/64" metal loss, to document actual liner plate thicknesses in the vicinity of these pitted areas. This evaluation was completed to provide justification for the acceptability of the liner plate at its thinnest location and provided assurances that additional margin exists for operation until A1R16 without repair or replacement activities.

The liner surfaces at all the exposed locations where the moisture barrier had been removed were prepared for Keeler and Long 9600 series coating used for Level I coating in containment that was applied during A1R15 along with a new Cerafibre and newly installed MB. A new MB was installed at all areas where the MB was removed. VT-3 exam was performed after all repairs were made on the entire MB and no cracks were Page 5-2

Braidwood Station Unit 1 A1R15 lSI Outage Report found to allow water intrusion. Portions of Class CC liner below the MB have been categorized as Category E-C in lSI schedule.

Proposed Actions for A1R16 VT-1 (Detailed Visual) and UT examinations are scheduled in A1R16 refueling outage to inspect the condition of the liner plate at the two locations with the most metal loss (10/64"). Examinations are scheduled for all areas of liner below the MB not inspected during A1R14 or A1R15.

Conclusions/Findings Based on the conclusions of the evaluation (Engineering Change Number 381781) performed to address the degradation identified during A1 R15, the liner plate containing the degraded conditions below the Moisture barrier (MB) in Unit 1 containment as identified during A1R15 is acceptable and capable of performing its intended design function until A1R16.

Page 5-3

Braidwood Station Unit 1 A1R15 lSI 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 (A1R14). 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 2 MS Main Steam 3 RC Reactor Coolant 7 RH Residual Heat Removal 1 SI Safety Injection 4 1 SX Essential Service Water 1

• When more than one Code Class exists (Le., valve located at Class break between Class 1 and 2), higher Class is used.

Total NIS-2 Forms 19 Associated NIS-2 Forms and associated Code Data Report are attached (35 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 11/1812010 Address: 300 Exelon Way. Kennett Square. PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Rte. 53. Suite 84. Braceville. IL 60407 Work Order #01218005-01 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 1111974 Edition. Winter 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 ASMECode 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 1CV8368B Valve 1CV8368B Body-to-Cover Seal Weld Arcos Industries, LoVAlloy Not Cat ID 8500-1 2007 Installed No Weld Electrode LLC CT8660 Applicable UTC2808606 3132" ER3161316L Heat 7::l4A1A

7. Description of Work: Removed existing seal weld to provide access to valve intemals for check valve inspection. After inspection was completed, the existing valve cover was reinstalled and a new seal weld was reapplied. Seal weld was examined by liquid penetrant In the finished condition.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Exempt ~

Other 0 Pressure _ _ pslg Test Temp. _ of

9. Remarks: Seal welds are exempt from Section XI pressure test requirements per IWA-4540(b)(B), however the valve was examined during the ascending Mode 3 walk down on 11/412010 after four hour hold time and was found acceptable. Applicable documentation for replacement 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 CodeJjymbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed '1'::>/l?t1d.<u:L<is'~ lSI Coordinator Date /1/tt3 .2010 Owner or Owner' esignee, Ti CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boller 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 2/10/2010 to 11/1812010. 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.

t1tU'd t? dtL

-...,V,..,L-""'ln-s-p""'ec-t-o""'r'-S-=S..,..lg-n-a-tu.Lre.J::::.IWILtf:.I&,+---------------

Commissions IJg 7920 AdJt*, /1.. -0 ZZf?'j--k:.

National Board, State, Province, and Endorsements

,20 If)

Page 6-2

FORM NI5-2 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 1/31/2011 Address: 300 Exelon Way. Kennett Square. PA 19348 Sheet 1 of 2

2. Plant Name: Braidwood Station Unit: _1_

Mdress: 35100 S. Rte. 53, Suite 84. Braceville, IL 60407 Work Order 001227470-01 Repair Organization PO., 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 and Volume Control) (Class 2) 5 (a) Applicable Construction Code: Valve: ASME Section III 1971 Edition, Winter 1972 Addenda, No Code Cases Piping: ASME Section 1111974 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 Como< nents:

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

Globe Valve 1CV8345 and Not Recorded Not Recorded Not 1CV8345 Not Recorded Removed Yes associated piping and U- Applicable Support bolt 1CV011OG 2" Globe Valve Flowserve 96BNC Not Cat 10 1969-1 2009 Installed Yes Corporation Applicable UTC 2827245 2" Seamless Pipe Sandvik Heat 505112 Not Cat 10 32352-1 2005 Installed No Materials WOlLot Applicable UTC 2847874

<;1<;dAA U-Bolt for 2" Pipe Bergen Power None Not Cat 10 24580-1 2006 Installed No Applicable UTC 2741727 5/8"-11 Heavy Hex Nuts Nova Machine Heat 87064 Lot Not Cat 1047197-1 1999 Installed No Products 50134197 Applicable UTC2805986

7. Description of Work: Replaced existing globe valve which leaked by seats. Existing u-bolt for Support 1CV011 OG was damaged during disassembly and was replaced. Socket welds were examined by liquid penetrant method.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 181 Exempt 0 Other 181 Pressure ~ psig Test Temp. ~ of

9. Remarks: Section XI pressure testing was performed during RPV loop fill and was acceptable on 11412010. Applicable material documentation for all components (Form NPV-1), materials, and 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 t3VLfLUU1..44-rJ Owner or Own~ignee:rwe

?~ lSI Coordinator 1/3/

Date _-'--_ _, 20-U 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 41212010 to 1/3112011, 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, conceming the examinations and corrective measures descnbed 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_..,.-~;.-::=-.::===- 0~85~-:-::~..,.-=---:-

Commissions 7""":":-!I,=:L.!::l __ -:-::~..,.-_ _..,.-_

Inspector's Signature National Board, State, Province, and Endorsements Date \ -~ \ ,20 i Page 6-3

FORM NI5-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI Owner Exelon Generation Co.. LLC Date 1/31/2011 Address: 300 Exelon Way. Kennett Square. PA 19348 Sheet 2 of 2

3. Plant Name: Braidwood Station Unit _1_

Address: 35100 S. Rte. 53. Suite 84. Braceville. IL 60407 Work Order #91227470-01 Repair Organization P.O.. Job No.. etc

3. Work Performed By: Shaw I Stone & Webster 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: (Chemical and Volume Control) (Class 2) 5 (a) Applicable Construction Code: Valve: ASME Section III 1971 Edition. Winter 1972 Addenda. No Code Cases Piping: ASME Section 1111974 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) 1/8" ER 30&l308L Bare Arcos LotDT8780 Not Cat 10 8513-1 2007 Installed No Welding Rod Industries. Heat 735456 Applicable UTC 2802006 LLC 3132" ER 30&l308L Bare Arcos Lot CT8816 Not Cat 10 8497-1 2008 Installed No Welding Rod Industries. Heat 735657 Applicable UTC 2812499 LLC Page 6-4

144456 FORM Npv., CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES*

As Required by the Provisions of the ASME Code. Section 1M. Division , 2 Pg.' o f _

1. MenufKtured Ind certified by FIowserve Ccrpcntion, 1900 South 5aU1ders St. R!Ie!gh. He 27603

, 1 _ llIeI ~ of N Cer1lIcate .....,1

2. Manuf8c:iured for ExeIon BusIness 5ervIa!s, M eceton ConpnY P.O. Box 805388 0lk3g0. IL 60680-5388 I . - oM . . . . of ""v.-I

3. Locltion of instlllition Braidwood Station East d It 53 1-1{2 miles SCMh d RT 113 Braidwood, n. 60408 e - .... ~

1500 Y-G.OBE Drawing W=I>9909-( l lt72577034AeY. L=--_ _ eRN _N.:../" _

4. Model No., Seri.. No.. or Type S. ASME Code. Section Ill, Division 1: 1971 1 NIA I...... ~I

8. Pump or velve _V_ahle~ Nominal inlet size _ _..;.2..,.'_ _ Dud. size _ _...;:.2,...-_ _

lln.1 On.1

7. M**rial:

(., velva Body SA182-F316 Bonnet SM19-316 Dig SA17H16 Bolting NIA lb' pump Casing Cover Bolting II'

, Cert.

HoIder'I lbl NeI'l Board

~Ing lei SerlM ldl a-.tJCo_

' Serief leI 0lIll Serial

, serwNo. MD. MD. No. No.

--- .. =

938NC 918NC Nt" NtA NlA N/A AS-IOS AS-I06 AS-I07 AS-I08

,E40252-33 E402S2-34 E40252-3S

~36 21150-S 21450-6 21450-7 21450-8 ....

Page 6-5

144456 FORM NPV-1 (~ck - Pg. 2 of _2_ ')

Certificlte Holder', Serial . No. ' 93BNC THRU 968NC _

8. Design conditiona __ 2580

~~=- __ psi _ _~6_SO==:--_ <If or velve prenure clas' ...;1""5...;00"-- _

!pr.....1 II_pl'-.

9. Cold working prenure __3_600...;;.-,-___ psi at l00"F

10. Hydrostatic telt psi. Disk differential test prenure 3960 ......... psi

11. Remarks: .. S.~Qf>.'.il.SO~7ulU13i.._ _

yPI(f: MArL: SAlOS. HEAT: 20681-2 SIN 7 MY 10 CERTFlCATlON Of DESIGN Cesign Specification certified by -:L-::-IKE--::-:~:::"":""-OVE---------------_ P.E. State PA Reg. no. 18379-E _

Design Report certified by __RON=:.:.:::S:.;.F:.,:ARRB.l===-- _ P.E. State .-.:.::;:NC:..- Reg. no. .028656 CER~TE Of COMPlIANCE We certify that the atltementll made in this report are correct and that this pump or velye conform. to the rules for construction of the ASME Code, Section Ill, Diyislon 1.

N Certificlta of Authorlzltlon No. N-_l_S62 Expires __1_1-_2~6-09:-----~--------

Name Rowsente Corpantt1on

~~~~~=------ Signed~

~-~

<:::::7'~F""'--::"::""":=r.::c~~

-~""l;;;;_w----

fN~HokIarI , \ (-..."'-""'1 CERTFlCATE, Of lNSPECnON I, tha undersigned, hold/ng a valid comminion issued by the National Board of Boiler snd Prenur. Vessel, Inspectors and the State or Province of NC and emplo~ by HS8 cr

'i4itO /0, of Hartford, cr

" have inapectad the pump. or valve, described in this Dlta Repor1 on and at.e that to the best of mv knowledge and belief. the Certificate Holder has constructed this pump, 'or valye.

in 1CC0rdance with the ASME Code. Sec:tion iii, Division 1.

BV ligning thie certifICate neither the inspector nor hi. amployer makes anv warranty. exprened or implied. concerning the compo~entdeacribed in this Data Report. Furthermore, neither the inspector nor his employer shall be liable in anv maMer for any personal injury or property damage or a Ion of anv kind arising from or connected with thi. inlpection. ",

~

Page 6-6.

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 Date 10/2812010 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order 1101362511-01 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: MS (Main Steam) (Class 2) 5 (a) Applicable Construction Code: ASME Section 11I1974 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 Id enti fIcatlon 0 f Comp< nents:

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

Main Steam Safety Consolidated! Not Recorded Not Valve 1MS016D Not Removed Yes (Position 1MS016D) Dresser Applicable Recorded Main Steam Safety Valve Consolidated! BR09605 Not Cat 10 1445340-1 1977 Installed Yes Dresser Applicable UTC 2867307

7. Description of Work: Replaced existing safety valve which was stuck open during A1F36 outage. Replacement valve was initially a Byron Station spare and was refurbished at NWS Technologies under Purchase Order 4542~ !4t- 113t12P1/

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 121 Exempt 0 Other Gil Pressure 1087 psig Test Temp. ~ of

9. Remarks: Applicable documentation (Form NVR-1 for refurbished 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 this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed ,tSrurv?4t;L.~. tc<-~vr lSI Coordinator Date k",!:ze .20k;J Owner or Own r:s Designee,ttitle 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 8116/2010 to 102812010, 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. conceming the examinations and corrective measures described in this Owner's Report. Furthermore. neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

___~_~_~--::1~._-_~-:==-L Commissions IL1085 Inspector's Signature N,'7a-:t7"'io-'n!.:al;-!;B:;:oa=!lL.rd'7.-:S:::ta-t:""e-,=P-ro-v7"'inc-e.-a-n-d:'-:E=-n-d7'"o-rs-em-e-n":"ts-Date II - t - .20~

Page 6-7

FORM NVR-1 REPORT OF REPAIR III REPLACEMENT [J OF NUCLEAR PRESSURE RELIEF DEVICES

1. Work performed by. NWS Technologies, LLC Purchase Order ' _ _4_54_204 _

131 Venture Boulevard, Spartanburg, SC 29306

2. Work performed for: ExeIon* Byron Nuclear Station 314. Owner - name, addteu and identification of nuclear power plant Exeton, Byron Nuclear Station 4450 N. German Church Road Byron, IL 61010

5. a: Repaired pressure relief device: ~Mal~n=Stea;,.;;;,;;;;,,;.;m...;;sate='""ty...:.V.;:;;aIYe;.;.;:..--------------

b: Name of manufacturer. ....;:Con=so=Hd;;:;;at;:;:;ed.;..;..;/Dc;; .;re8.;:; :; ;:ser,;:; . . _

c: Identifying nos.

3701R (type)

BROMOS (mfr'1 SIN) - nla (NBlJ) steam (MMce) 6" (Ilze) 77 (yr.built) d: Construction Code: ASME sectlon III 1974 nil nil 2

(~) (edIlIon) (1cldInda) (Code C81N(a>> (CodeClla)

6. ASME Code Section XI applicable for inservlce inspection: 2001 2003 nla (edIIIon) (8ddenda) (Code Caae(1>>

7. ASME Code section XI used for repairs. replacements: 2001 2003 nla (ecIliDn) (eddeftde) (Code e-(a>>

8. ConatnJctlon Code used for repelrs. replacements: 1974 nla nla (dIon) (eddenda) (Code CMe(1>>

9. Design responsibllitiel: .;.;nI;.;;a _

10. OpenIng pntI8W1t: 1190 Psig set-pressure adjuetment made at NWS Technologies, LLC using steam

11. DeIcrtptton rA work (Inc:Iudt MIM end ideI""'" number 01 ~!*lI>: DiIasIembIed, lapped disc and nozzle, inspected, cleaned, lubricated, reassembled, setjl!!!!U!! & tiQtrtn!!! certified.

12. Remerks: No per!! rep!!ced. NWS Traveter.1Q-151. Valve ahlpp!ns to Braidwood Station.

C A I, . Jason C. Gibson certify that to the best of my knowledge and befief the statements made in thiS report are c:orrect and the repair, modJtIcatlon or replacembl of the pressure reIlef 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. 832 to use the "VR" stamp expires April 3, 2012.

National Board C8rtlficat8 of AuthorIzation No. 81 to use the "NR" stamp expires Apr!19.2012.

~ NWS Techno!ogl!!, LLC ~. <:!... c9-- Manager, QA Date RepaIr 0rganizaII0n AuthoriZed ~ TIlle CERTIfICATE Of INSPECTION I. Chart.. F. TO!A!I Jr. holding a valid commission issued by The National Board of Boiler and Pressure Vesselinspec:lors and certificate of competency issued by the jurisdiction of North C.roIlna and employed by H.rtford Steam Boller of CT have inspected the repair. modification or replacement described in this report on this repair, modification or replacement has Iii8i1

n. WI) and state that to the best of my knowtedge and belief.

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. Futherrnore, neither the undersigned nor my employer shall be llabla In any manner for any personat injury, property damage or loss of any kind arising from or connected* is i .

,Into Ne , 8482, At N, I Net 1073 7 De" Commlselona (NS (ind endorsemen.... jurildictlon.& no.)

Page 6-8

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 11/1812010 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Ate. 53, Suite 84, Braceville, IL 60407 Work Order #01336747-01 Repair/Replacement Organization P.O., Job No., etc

3. Work Performed By: Shaw / Stone &Webster Type Code Symbol Stamp: None Address: 36400 S. Essex Road, Wilmington, IL 60481 Authorization No.: None Expiration Date: None

4. Identification of System: MS (Main Steam) (Class 2) 5 (a) Applicable Construction Code: ASME Section 11I1974 Edition, Summer 1974 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. Identi ication of Corne< nents:

Name of Component Name of Manufacturer National Other Year Built Corrected ASMECode Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No) 1MS017C Main Steam Not Recorded Not Recorded Not Valve 1MS017C Not Removed No Safety Valve Applicable Recorded Inlet flange bolt Threaded Rod (1 318"-8) Nova Machine Heat 57748 Not Cat 1037106-1 2009 Installed No Products/ Lot 50183185 Applicable UTC 2844900 Unus Products, Trace Code Inc. 3L37

7. Description of Work: Replaced existing inlet flange bolt which was stuck/damaged dUring disassembly.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Exempt 181 Other 0 Pressure Not Applicable psig Test Temp. Not Applicable of

9. Remarks: Applicable documentation for replacement bolting material was attached at the time of final review and is maintained on file.

CERTIFICATE OF COMPUANCE 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 ymbol Stamp: Not Applicable Certificate of Authorization No.: Not ApplicablE!

Signed ..:h:::.~?!J&.~t:J:::.~~~~~_ _-'.§J...QQ!m:!i!m:..-_ Date /1fa ,20it:L 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 8117/2010 to 11/1812010, 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.

---

,7"9-"d~~::;;...z;.~I?~~-:-'---'-"~'-----------

~liSPElCtOf'ssGi~

Commissions If.} $ 7£ zt> AAJ6/-/l ~()ZZP?- JZ National Board, State, Province, and Endorsements Date - (If ,20.../J!..

Page 6-9

FORM NI8-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner  : Exelon Generation Co., LLC Date 1/31/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Ate. 53, Suite 84, Braceville, IL 60407 Work Order #01371174-01 Repair/Replacement Organization P.O., Job No., ete

3. Work Perfonned 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: MS (Main Stearn) (ClaSS 2) 5 (a) Applicable Construction Code: ASME Section 1111974 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 ComP< nants:

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

Main Stearn 6" Relief Valve Dresser BR09605 Not Cat 10 1388647-1 19n Removed Yes (Position 1MS016D) Applicable UTC2839826 6* Main Stearn Safety Relief Dresser BR09645 Not Cat 10 1445882-1 19n Installed Yes Valve Applicable UTC 2869793

7. Description of Work: existing relief valve was removed and sent to NWS Technologies for disassembly and inspection, replaced with a tested spare relief valve.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 181 Exempt 0 Other 181 Pressure 1072.2 psig Test Temp. 559.1 OF

9. Remarks: Valve and connection were examined by VT-2 on 11/412010 and found acceptable. Applicable documentation (Fonn NVR-1 for refurbished valve) was attached at the time of final review and is maintained on file.

CERnFICATE OF COMPUANCE I certify that the statements made in the report are correct and this contonns to the requirements of the ASME Code,Section XI.

Type C o d ! : :Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed ~~ lSI Coordinator Date 113t .20g Owner or Owne Designee, r CERnFICATE 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 periocl9l2812010 to 113112010, and state that to the best of my knowledge and belief, the Owner has pertonned 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 imp/ied, concerning the examinations and corrective measures described in this Owner's Report. Furthennore, 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 1L1085 Inspector's Signature N'-;-a~tion;--l-a~'~Boa:-'rd-:-,-::S::':'ta-::te-,-::P::-ro-v-:-inc-e,-a-nd-:-::E:-ndo-;--rs-em-e-n-;-ts-Date \ -~\ 20..l.i..

Page 6-10

161985 FORM NVR*1 REPORT OF REPAIR !If REPLACEMENT [J OF NUCLEAR PRESSURE RELIEF DEVICES

1. Work performed by: NWS Technologies, LLC Purchase Order '_46_5_34_1 _

131 Venture Boulevard. Spartanburg. SC 29306

2. Work performed for. Exelon Corporation. Braidwood Station 3/4. Owner

• name. address 8nd 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 retlef device: ~Ma~In;:::s-team=-s-a;.;.;te;,,;jtyr..v-a-tv-e------------- -

b: Name of manufacturer.

c: Identifying nos. Consolidated

.................... 1Dresser _/---,

=.;0.0...;_....,;=-_ _

3707R BR09845....!!!!.. steam 6" 1977 (type) (mfr'1 SIN) (NBI) (service) (size) (yr.built) d: Construction Code: ASME /11I/1 1974 nla nla 2 (nameisectlOnldlvlsion) (edition) (adde.m) (Code Clsea(l>> (Code c....)

6. ASME Code Section XI applicable for inservice inspection: 2001 2003 nla (edition) (addenda) (Code Cue(1>>

7. ASME Code section XI used for repairs. replacements: 2001 2003 nla (edition) (eddenda) (Code Case(I>>

8. Construction Code used for repairs. replacements: 197.- nla nla (edition) (addenda) (Code Cue(S>>

9. Design responsibilities: ..;.;nI;.;;;8;....._r l

10':'Openlng pressure: 1190 psIA J set-pressure adjustment made at NWS Technotogies. LLC using steam

11. Description of work (Include neme end identifying number of repIecement parts): Disassembled. Inspected, 18pped and preoxidized the disc seat. lapped and passivated the nozzle seat, rep!aced guide, hofder, spring assy, lower ring pin. Cleaned and lubrtcated as required. certified set-preesure and seat tightness using steam.

12. Remarks: NWS Traveler'10-192. Repalced holder. guide. SprinS BSSY. lower ring pin.

CERnFICATE OF COMPLIANCE I. Jason C. Gibson certify that to the best of my knowledge al"ld 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. 20012 National Board Certificate of AuthoriZation No. 81 to use the "NR" stamp expires April 9. 20012 l'I"he,.

&t:

NWS Technologl.., LLC Repeil Organiutlon

!}~ C. 61 _

~uthorized representative Manager, QA rltle CERnFICATE OF INSPECTION I, Chari.. F. Toes.1 Jr. holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdietlon of North Carolina and employed by Hartford Steam Boller of CT of Hartford, CT have inspected the repair, modification or replacement described in this report on 11?t:1i t:£>k> 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, conceming this repair. modification or replacement described in this report. Furthermore. neither the undersigned nor my employer shall be liable in any manner for any nal injury, property damage or loss of any kind arising from or connected . . i~.: spe . ~ "\

}I1/f/ltt) ~ .~. '1 NB "8462, A, N, I Net 1073

, lOa' In ct r: S nltu Commlsaionl (NB (ina endorsements). JUrisdlctlon,& no.)

Page 6-11

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

1. Owner Exelon Generation Co., LLC Date 1/27/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit _1_

Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #00528957*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 11I1974 Edition, Summer 1975 Addenda, No Code Cases Valves: ASME Section 1111974 Edition, Summer 1976 Addenda (b) Applicable Edition of Section XI Utilized for RepairlReplacement 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None

6. Identification of Components Reoaired or Reolaced and Reolacement Comoonents:

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

Unit 1 Reactor Head Vent Unknown Not 1RC014A through Not Removed No Unknown Valves (1 RC014A, Applicable 1RC0140 Recorded 1RC014B, 1RC014C and Une 1RC0310A-1" 1RC0140) and associated piping Solenoid Valve Valcor Valve Serial Not Cat 101397111-1 Not Installed No Assemblies Engineering Numbers 58, Applicable UTC 2701665 and Recorded Corporation 59, 60, and 61 2701666 3132" ER308l308L Arcos Industries, Heat 735857 Not Cat 108497-1 2008 Installed No LLC Lot CT8816 Applicable UTC 2812499 Control 8816

7. Description of Work: Replaced existing reactor head vent manifold valves (which leaked by seats) with solenoid valve assemblies which were reworked by Valcor. Field welds were examined by liquid penetrant method.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Exempt 181 Other 181 Pressure Not Reauired psig Test Temp. Not Required of

9. Remarks: Section XI pressure testing is not required per IWA-4540(b)(6), but were examined by VT-2 during the system leakage test on 11/412010.

Applicable documentation for replacement solenoid valves and weld filler material was attached at the time of final review and is maintained on file.

CERTlFlCATE OF COMPUANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ~ME Code, Section . Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed '1'6, l . . . ,Cd... I r in Date IIL 7 , 20.!.L Owner or Owner's esignee, 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 412212010 to 1/27/2011, 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.

_____;;;*bk:

J

=;;...._L~~(===== Commissions -:-:-;--"c=:l:-:10:-'8...5 <--:--:::--:--=-_:--_---:-=--:-_ _-:-_

Inspector's Signature National Board, State, Province, and Endorsements Date I - 'Z' - ,20---1'

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

1. Owner Exelon Generation Co., LLC Date 1/27/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Ate. 53, Suite 84, Braceville, IL 60407 Work Order #00528957*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: Piping: ASME Section 11I1974 Edition, Summer 1975 Addenda, No Code Cases Valves: ASME Section 11I1974 Edition, Summer 1976 Addenda (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 Comoonents Reoaired or Reolaced and Reolacement Comoonents:

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

Unit 1 Reactor Head Vent Unknown Not 1RC99OO4G Not RemOved No Unknown Line Support Applicable Line 1RC031DA-1" Recorded 1RC99OO4G 3132" E7018 Weld ESAB Heat M902234 Not Cat 108491-1 2010 Installed No Electrode Lot 2H012D04 Applicable UTC 2870136 Control M"'/V)A 3A" X 518" X 4" Flat Bar Gerdau HeatJG5757 Not Cat 10 30483-1 2008 Installed No Stock Ameristeel Applicable UTC 2822259 2 Y2" X 2 W X y.." Square Independence HeatC50373 Not Cat 10 1446497-2 2009 Installed No Tubing Bar Stock Tube Corporation Applicable UTC 2870694

7. Description of Work: Removed existing support to assist with replacement of reactor head vent manifold valves.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Exempt f8I Other f8I Pressure Not Required psig Test Temp. Not Required of

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

CER11FICATE OF COMPUANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ME Code.Section XI. Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed I r Date 1/27 ,20..JI-CER11F1CATE OF INSERVICE INSPEC110N 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 412212010 to 1/27/2011, and state that to the best of my knowiedge 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, conceming the examinations and corrective measures described in this Owner's Report. Furthermore. neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_____ ;tL::=:.....".Jl~_~\.d..L~"-'::.::::====_

Inspector's Signature Commissions.-:--:--I""L:-o:1::'085 National Board, State, Province, and Endorsements Date l ~ '1-:0. ,20.-..!..l Page 6-13

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 1/27/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Rte. 53. Suite 84, Braceville, IL 60407 Work Order #00528957-03 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: Piping: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases Valves: ASME Section 1111974 Edition, Summer 1976 Addenda (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 Comoonents Reoalr . ed or ReOlaced I and ReOlacement I Comoonents:

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

Unit 1 Reactor Head Vent Unknown Not 1RC99008G Not Removed No Unknown Une Support Applicable Line 1RC031DA-1" Recorded 1RC99008G 3/32" E7018 Weld ESAB Heat M902234 Not Cat 10 8491-1 2010 Installed No Electrode Lot 2H012004 Applicable UTC 2870136 Control 34" X 5/8" X 4" Flat Bar Gerdau HeatJG5757 Not Cat 1030483-1 2008 Installed No Stock Ameristeel Applicable UTC 2822259 2 112" X 2 112" X W Square Independence HeatC50373 Not Cat 101446497-2 2009 Installed No Tubing Bar Stock Tube Corporation Applicable UTC 2870694

7. Description of Work: Removed existing support to assist with replacement of reactor head vent manifold valves.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Exempt t8I Other t8I Pressure Not Reouired psig Test Temp. Not Reouired of

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

CEAllFICATE 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 ~q~ lSI Coordinator Date;fzl ,20!L...

Owner or Owne Designee. itle CEAllFlCATE OF INSERVICE INSPEcnON 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 412212010 to 1/27/2011, 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_*..,..,...----JL~\..~u..-!:::::===:::::._ Commissions.-;-::-'I"':L:-':10:"85

.......-:-::~_=:-...,..... _ _...,...,:--:--_ _-:--_

Inspector's Signature National Board, State, Province, and Endorsements Date ,20LL Page 6-14

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 1/27/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Rte, 53, Suite 84, Braceville, IL 60407 Work Order #00528957-04 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: Piping: ASME Section 1111974 Edition, Summer 1975 Addenda, No Code Cases Valves: ASME Section 1111974 Edition, Summer 1976 Addenda (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 Reolaced and Reolacement Comoonents:

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

Unit 1 Reactor Head Vent Unknown Not 1RC99007G Not Removed No Unknown Line Support Applicable Line 1RC031 DA*1" Recorded 1RC99007G 3132" E7018 Weld ESAB Heat M902234 Not Cat 10 8491*1 2010 Installed No Electrode Lot 2H012D04 Applicable UTC 2870136 Control

"~I~I/V'"

7. Description of Work: Removed and reapplied hex nut tack welds on support in order to assist with replacement of reactor head vent manifold valves.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Exempt 181 Other 181 Pressure Not Required psig Test Temp. Not Required of

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

CER11FICATE 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 I. Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed ~71-Owner or Owner' I IC r in Date I'lL 7 ,20..!L CER11F1CATE OF INSERVICE INSPECll0N 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 412212010 to 1/27/2011, 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;::::...:-"':--=l~-:::"-=~l::J~L""""-====------------- Commissions.-:-~I""L",:10:"8...5<-,-..,,... _

Inspector's Signature National Board. State. Province. and Endorsements Date l-Page 6-15

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 1211312010 Address: 300 Exelon Way. Kennett Square. PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Rte. 53. Suite 84. Braceville. IL 60407 Work Order #01293926-01 Repair Organization P.O.. Job No.. etc

3. Work Performed By: Shaw / Stone & Webster Type Code Symbol Stamp: None Address: 38400 S. Essex Road. Wilmington IL, 60481 Authorization No.: None Expiration Date: None

4. Identification of System: Reactor Coolant/Steam Generator 5 (a) Applicable Construction Code: ASME Section III 1986 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 Comoonents Repalr . ed or RePlacedandRieplacement I Comoonents:

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

Cap Screws for Adaptor Boeing Unknown Not 1RC01BD-8 Not Recorded Removed No 1RC01BD-8 Applicable (1 B Steam Generator Snubber)

'4" *20 Hex Head Cap NOVA Machine Heat 8092338 Not Cat 10 2009 Installed No Screws Products. Inc. Applicable 1396239-1 Lot 50177876 UTC 2840134

7. Description of Work: Replaced mounting cap screws on steam generator snubber. Reason for replacement was not documented in work order.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Exempt S Other 181 Pressure Not Required psig Test Temp. Not Required of

9. Remarks: Post installation VT-3 examination was completed and acceptable on 1011012010. Applicable material documentation for cap screws was attached at the time of final review and is maintained on file.

CERTlFlCATE 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  :/3~.~::.tt 151 Coordinator Date all 3 I

.20/0 Owner or Owne Designee. itle CERllFICATE OF INSERVICE INSPECll0N 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 HS8CT of CT have inspected the components described in this Owner's Report during the period 312212010 to 1211312010. 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. conceming the examinations and corrective measures described in this Owner's Report. Furthermore. neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

(/1  ;;J ;(,)/;/ /0;;' / L-L"I,Z 7. (Y/- 'iJ:. AJ6 792 i: AN 8r .",,'(,-.~", '2'-*"7%"':;~'; 'pec"':;?- t:-or' ' :{-:-=S' :"i~-~.r. r.:;. tu' ' ;~- ~~......<<

.'-/---------------

. Commissions NatiOfl~:ilt:' Province. and Endorsements Date II'1 .20/0 --

Page 6-16

FORM NI8-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner : Exelon Generation Co., LLC Date 1/30/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: ...L Address: 35100 S. Ate. 53, Suite 84, Braceville,lL 60407 Work Order 1t01375122=01 Repair/Replacement Organization P.O., Job No., etc

3. Work Performed By: Shaw 1 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 (Steam Generator) (SG) (Class 1) 5 (a) Applicable Construction Code: ASME Section 11I1974 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) 1RC01 BA Lateral Not Recorded None Not 1RC01 BA Unknown Corrected No Support (Shim Pack) Applicable Lateral Support

\12"-13 SA-193 Grade B7 NOVA Machine Heat 10061010 Not Cat 10 24979-1 2010 Installed No Threaded Rod Products Lot 50222374 Applicable UTC 2870288

\12" Thick SA-36 Plate SSAB Heat EOI222 Not cat 10 2010 Installed No Applicable 1446244-1 UTC 2870351

~'-13 SA-194 Grade 6 NOVA Machine Heat 516788 Not SI#796031 1999 Installed No HAaVV HAll Nuts Lot RIN AQQ..tl113Q

~'-13 AlSA 194 Grade NOVA Machine Heat 361170 Not cat 10 37027-1 2009 Installed No 2H H.... vv HAY NIlt!cl Int lITe Description of Work: During examination of the shim pack bolting on 1RC01 BA steam generator to address extent of condition from inspection findings at Byron Station, sheared and potentially dlamaged bolting was discovered (reference IR 1121593 and 1121928). Shim packs were repaired using guidance provided through EC 361691. Shim material (exempt from repair/replacement per IWA-4120(b)(6) was also replaced dUring this repair.

7. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Exempt 181 Other 181 Pressure Not Regujred psig Test Temp. Not Required OF

8. Remarks: A VT-3 examination was performed after bolting was tightened (10120I2010) and again during ascending Mode 3 walk down (11/412010) after attaining nominal operating temperature.

CERl1F1CATE OF COMPUANCE 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 ApplicalJle Signed ~J4 Owner or Owne (j. ~

Designee, 151 Coordinator Date If 3( ,20.!.L.

CERl1F1CATE OF INSEAVICE INSPECll0N 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 1011012010 to 1/3012011, 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-=-~~;;:=:Q~L.=====--

Inspector's Signature Commissions ~ ~ I National Board, State, Province, and Endorsements Page 6-17

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 1/2812011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order 1t01375464-Ql Repair/Replacement Organization P.O., Job No., etc

3. Work Perlormed 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 (Steam Generator) (SG) (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:

Name of Component Name 01 Manufacturer National Other Year Built Corrected ASMECode Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No) 1RCOl BC Lateral Not Recorded None Not lRC01BC Unknown Corrected No Support (Shim Pack) Applicable Lateral Support Descnption of Work: Dunng examinatIon 01 the shim packs on 1RCOl BC steam generator, the upper right nut on the (South-West) shIm pack was loose (reference IR 1121934). The 3 remaining bolts and nuts were tight and intact. Tightened existing steam generator lateral support shim pack bolting that was discovered loose during visual inspection.

7. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Exempt I8J Other I8J Pressure Not Required psig Test Temp. Not Required of

8. Remarks: A VT-3 examination was performed after bolting was tightened (1011512010) and again during ascending Mode 3 walk down (11/412010) after attaining nominal operating temperature.

CERllF1CATE 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 Certificate of Authorization No.: Not Applicabl~

Signed ~'6.I...(J.&t.1.l::J~~~'/-:-J~~':£J.::::-_..&!.~lm!!:J!i1QI:--Date 1/2t!, 20 / /

CERllFICATE 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 10110/2010 to 1/2812011, 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, conceming the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_ _ _--=i:....* _---..,...:L-:::::::...:l~I~.==_ Commissions -u.- \;t \. 0'-2;) .s;.

Inspector's Signature National Board, State, Province, and Endorsements Date ,20-U,...

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 1/2512011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1 Plant Name: Braidwood Station Unit 1 Work Order #01224658-01 Address: 35100 S. Rte. 53, Suite 84. Braceville, IL 60407 Repair Organization PO.. Job No., etc

3. Work Performed By: Shaw 1 Stone & Webster Code Symbol Stamp: None Address: 36400 S. Essex Road. Wilmington, IL 60481 Authorization No.: None Expiration Date: None

4. Identification of System: Residual Heat Removal (RH) Class 1 system 5 (a) Applicable Construction Code: ASME Section 1111974 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 XI Utilized for Repairs or Replacements: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None

6. Identification of Compc nents Repaired or Reolaced and Reolacement Comoonents:

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

PSA-3 Mechanical Snubber ITT Grinnell SIN 9657 Not 1RH02047S 1981 Replaced No 1RH02047S Applicable PSA-3 Mechanical Snubber Basic-PSA Inc. SIN 41624 Not Cat 10 27676-1 1999 Replacement No Applicable UTC 2052207

7. Description of Work: Proactively replaced existing snubber after A1R15 functional testing, Existing snubber passed functional test in A 1R14 (reference IR 902853) and again in A 1R15, but performance was degrading. The replacement snubber was functionally tested prior to installation.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Other 0 Pressure Not Applicable psig Test Temp. Not Aoolicable of Remarks: VT-3 exam of snubber was performed after reinstallation on 10111/2010. Applicable Manufacturer's Data Report was attached at the time of final review and is maintained on file.

CERnFlCATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the;PME Code,Section XI. Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed '-i.JMIz..dd..rut: L~"J lSI Coordinator Date 1/2'::,2011-Owner or Owner's Designee?htle CERnFlCATE OF INSERVICE INSPECnON 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 412012010 to 112512011, 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 emptoyer makes any warranty, expressed or implied, conceming the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

___..,.- L--".,..._~ __

Inspector's Signature

__';;;....;===_ Commissions . ,. -,. -'I" L-,:10~85~~_--:::-

National Board, State, Province, and Endorsements Date 1-2:;;;:_ ,20_\,_

Page 6-19

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 1/27/2011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 2

2. Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Rte. 53, SUIte 84, Braceville, IL 60407 Work Order 1#00609949-01 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 1 and 2) 5 (a) Applicable Construction Code: Valve: ASME Section III 1971 Edition, Winter 1972 Addenda, No Code Cases Piping: ASME Section 1111974 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 Comoc nents:

Name of Component Name of Manufacturer National Other Identification Year Built Corrected ASMECode Manufacturer Serial No. Board No. RemOVed. or Stamped (Ves Installed or No)

Check Valve 1S18819C and Not Recorded Not Recorded Not 1S18819C Lines Not Removed Yes associated piping Applicable 1S118EC-2" and Recorded 1SI18FC-2" 2" Y-Piston Check Valve Flowserve 72BQV Not Cat 1024010-1 2010 Installed Yes Corporation Applicable UTC 2869753 2" Socket Weld Flange WA Heat Not Cat 1030443-1 2010 Installed No International 3737ANE1 Applicable UTC 2869983 2" Seamless Pipe Sandvik Heat 505112 Not Cat 1032352-1 2005 Installed No Materials WOllot Applicable UTC 2829918

<:;1 r:;AAA 3/32" ER316L (for valve Arcos LotCM8256 Not Cat 10 850Q-1 2004 Installed No cover seal weld) Industries, LLC Applicable UTC 2715657

7. Description ofWooc Replaced existing check valve and associated piping as part of a corrective action (reference ATI164897-09). Socket welds were examined by liquid penetrant method.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure C\SI Exempt 0 Other C\SI Pressure Class 2: 870 / Class 1: 2239.8 psig Test Temp. Class 2: 95 6 / Class 1: 549.32 of

9. Remarks: Section XI pressure testing for Class 2 was performed and acceptable on 10117/2010 in conjunction with 1BwVSR TRM 2.5.c.3. Class 1 system leakage test was performed and acceptable on 11/412010. Applicable material documentation for all components (Form NPV-1). materials.

and associated weld filler materials was attached at the time of final review and is maintained on file.

CER11FICATE 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 ~~'90'~

Owner or Owner'* Designee. Titl 1$1 Coordinator Date 1/?1 ,20.!L CERllFICATE OF INSERVICE INSPECll0N 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 911612010 to 1/27/2011, 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~:::;~~L:..:L--====::::::.._

Inspector's Signature Commissions.--:-:-~IL ...1 ":'0""85""""""'_",..-...."...---____,,:__----

National Board. State. Province, and Endorsements Page 6-20 Date \ 'J...j- .20....e,.

FORM NI8-2 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 1/27/2011 Address: 300 Exelon Way. Kennett Square. PA 19348 Sheet 2 of 2

3. Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Ate. 53. Suite 84. Braceville. Il60407 Work Order #00609949-01 Repair Organization P.O.* Job No.. etc

3. Work Performed By: Shaw / Stone & Webster Type Code Symbol Stamp: None Address: 35100 South Route 53. Suite 84. Braceville. Il60407 Authorization No.: None Expiration Date: None

4. Identification of System: SI (Safety Injection) (Class 1 and 2) 5 (a) Applicable Construction Code: Valve: ASME Section III 1971 Edition. Winter 1972 Addenda. No Code Cases 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 ASMECode Manufacturer Serial No. Board No. Identification Removed. or Stamped (Yes Installed or No) 1/8" ER 3OB/308l Bare Arcos lot OT8780 Not Cat 10 8513-1 2007 Installed No Welding Rod Industries. Heat 735456 Applicable UTC2802006 llC 3132" ER 30B/308l Bare Arcos lot CT8816 Not Cat 10 8497-1 2008 Installed No Welding Rod Industries. Heat 735857 Applicable UTC 2812499 llC Control 8816 3132" ER 308I308l Bare Arcos lotCT9023 Not Cat 10 8497-1 2008 Installed No Welding Rod Industries. Heat 737880 Applicable UTC2830005 ILC 1/8" ER 30B/308l Bare Arcos lot 0-9077 Not Cat 10 8513-1 2009 Installed No Welding Rod Industries. Heat 249076 Applicable UTC2844829 IIC Cnntrnl Q(l77 i11.w~q*~zP{/

1-- L.L~--

t\ 1V ll.\

Page 6-21

160671 FORM NPV-1 CERT1FICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES*

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

1. Manufactured and certified by FIowserve Corporation, 1900 South saunders St Raleigh, He 27603 INltll. and .ddr... of N C..llflc.t. Holder)

2. Manufactured for fxelon Business 5ervices, An ExeIon Company P.O. Box 8OS388 Clago, Il60680-5388 In.m. and addr... of PulcIl....1

3. Location of installation Braidwood Station East of It S3 1-1/2 miles South of RT 113 Braidwood, Il60408

~ (n.m. and add,...)

4. Model No.* Series No.* or TVpe 1500# CHECK VAlVE Drawing 09-56242-01 Rev. 0 CRN _N.....I_A _

5. ASME Code,Section III, Division 1:

1971 .; WINTER1~ 1 NIA

(.dltlon) Icl...1 ICod. C... no.)

6. Pump or valve Valve /

J Nominal inlet size _ _-.,;:2:J!1J....-__ Outlat size _ _-,;2;;.,...._ _

lin. I / lin.1

7. Material:

la) valve Body SA182-F316 Bonnet SAI82-F316 Disk SA479-316 Bolting N/A Ib) pump Casing Cover Bolting

(.1 (bl (el (d) (e) celt. Nat'l Body/Casing Bonnet/Cover Oisll:

Holder'.

Serial No.

Board No.

Serial No.

.; Serial /

No.

Serial No.

./

N/A A8-9 93n3-14 33617-6-1

• Supplemental information in the form of Iista. mlCb** or drewinga may be uud provided 111 size ia 8'f.z IC 11, (2) Information In itams 1 through 4 on this Data Report Is Included on each sheet. (3) each sheet is numbered and b number of sheets is recorded at b lOp of this form.

Page 6-22

180671 2

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

Certificate Holder's Serial No. 7_2_BQV _

2580 650 "F or valve pressure class .,;1;,;;5;,;;00;.;;;.. _

8. Design conditions psi lp"all.llel It_patatufal

9. Cold working pressure 3600 psi at 10O"F S400 psi. Disk differential test pressure 3960 _

10. Hvdrostatic test psi

11. Remarks: S.D. 56242-01 CER11FICATION OF DESIGN Design Specification certified by _L_I_ke __ Ezekoye-....;.----------------- P.E. State PA Reg. no. 18379-f Design Report certified by ...:.;:Robert==..:.A.::..:S;:.:izel::::.:m.::lOI:;:.re=- _ P.E. State NC Reg. no. 029425 CER11FICATE 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 Ill. Division 1.

N CertifICate of Authorization No. N_-1_56_2 Expires _1_1-_2_6-_1_2 _

Date 1/.. ./1,0 Name FIowserve Corporation IN Catllflcata HoI'" Sl. . . . s=<:f 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 ProviflCe of NC and employed by HS8 cr

~ P. of Hartford, cr have inspected the pump, or valve, described in this Data Report on 9(0 , and state that to the best of mv knowledge and belief. the Certificate Holder has constructed this pump. or valve.

in accordance with the ASME Code,Section III. Division 1.

BV signing this certificate neither the inspector nor his emplover makes any warranty. expressed or implied. concerning the component described in this Data Report. Furthermore. neither the inspector nor his emplover 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 I { INart. Bd. Unci. endoraamantal and ltala or prC/V. and no.1 Page 6-23 3

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

1. 0Nner Exelon Generation Co., LLC Date 1/2612011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 2 Plant Name: Braidwood Station Unit:..L Address: 35100 S. Ate. 53. Suite 84, Braceville, IL 60407 Work Order !tQ1281799-91 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 1 and 2) 5 (a) Applicable Construction Code: Valve: ASME Section 1111971 Edition. Winter 1972 Addenda, No Code cases Piping: ASME section III 1974 Edition. SLfTlmer 1975 Addenda. No Code cases (b) Applicable Edition of Section XI Utilized for RepairlAeplacement: 2001 Edition with 2003 Addenda (c) section XI Code cases used: None

6. Identification of Como< nents:

NameofCompooent Name of Manufacturer National Other Identification Year Built Corrected ASMECode Manufacturer Serial No. Board No. Removed. or Stamped (Yes Installed or No)

Check Valve 1SI8819B and Not Recorded Not Recorded Not 1SI8819B Not Removed Yes associated piping Applicable Unes 1SI18EB-2" Recorded

~nd 1SI1AFR-?"

2" Y*Piston Check Valve Flowserve 44BPM Not Cat 10 24010-1 2009 Installed Yes Corporation Applicable UTC 2859487 2" Socket Weld Flange Western Forge Heat 249217 Not cat 1030443-1 2010 Installed No

& Flange Co. Lot 10791

~ ~, .. Applicable UTC2869560 2" Seamless Pipe Sandvik Heat 505112 Not Cat 1032352*1 2005 Installed No Materials WOIlot Applicable UTC 2829998 Technology 515468 3132" ER316L (for valve Arcos LotCM8256 Not CatiD 8500-1 UTC 2004 Installed No cover seal 'N9kI) Industries, LLC Applicable 2715657 7.

DescriptIon of Work: Replaced existing check valve and assocl8ted ptptng as part of a troubleshooting effort. Socket welds were examined by liquid penetrant method.

8. Tests Conducted: Hydrostatic 0 PneLmatic 0 Nominal Operating Pressure 181 Exempt 0 Other 181 Pressure Class 2: 870 / Class 1: 2239.8 psig Test Temp. Class 2; 95.6/ Class 1: 549.32 OF

9. Remarks: Section XI pressure testing for Class 2 was performed and acceptable on 10t'1712010 in conjooctlon with 1BwVSR TAM 2.5.c.3. Class 1 system leakage test was performed and acceptable on 11/412010. Applicable material docLmentation for all components (Form NPV-1). materials.

and associated 'N9kI filler materials was attached at the time of finaJ review and is maintained on file.

CERTIFICATE OF COIIPUANCE We certify that the statements made in the report are cooect 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 lJ/UfwLMk(£ 0Nner or Owne(s t~i!f?

ignee. TItle lSI Coordjoator Date //2(,

.2O-lL CERTIFICATE OF INSERVtCE 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 Qwne(s Report during the period 911612010 to 1/2612011, and state that to the best of my knowledge and belief. the Owner has performed examinations and taken corrective measures described in this Qwne(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 Qwne(s Report. Furthermore. neither the Inspector nor his employer shall be liable in any manner for any persorI8l injury or roperty damage or a loss of any kind arising from or connected with this inspection.

__---:~--:__7L_=:...-:-~--:...---.-;;;~=-----------

Inspecto(s Signature Commisslons.~~IL':.l1;::085ll>L7'-:::::-:--=--:~_~::--:---:--

National Board, State, Province, and Endorsements Page 6-24 Date \. 'l.L.t- 20 I

FORM NI5-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner  : Exelon Generation Co., LLC Date 1/2612011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 2 of 2

3. Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Ate. 53, Suite 84, Braceville, IL 60407 Work Order #91281799-01 Repair Organization P.O., Job No., etc

3. Work Performed By: Shaw / Stone & Webster 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: SI (safety Injection) (Class 1 and 2) 5 (a) Applicable Construction Code: Valve: ASME Section III 1971 Edition, Winter 1972 Addenda, No Code Cases Piping: ASME Section 1111974 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 ASMECode Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No) 1/8" ER 308I308L Bare Arcos Lot OT8780 Not Cat 10 8513-1 2007 Installed No Welding Rod Industries, Heat 735456 Applicable UTC2802006 LLC 3/32" ER 308I308L Bare Arcos LotCT8816 Not Cat 108497*1 2008 Installed No Welding Rod Industries, Heat 735857 Applicable UTC 2812499 LLC 3/32" ER 308I308L Bare Arcos LotCT9023 Not Cat 10 8497*1 2008 Installed No Welding Rod Industries, Heat 737880 Applicable UTC2830005 Il~

1/8" ER 308I308L Bare Arcos LotCT9023 Not Cat 10 8513-1 2009 Installed No Welding Rod Industries, Heat 737880 Applicable UTC 2828327 1Ir.

~ I!Zf.,/zd/

cl L-v--lt-- \\ 'UL \ \"

Page 6-25

15.5949 FORM NPV-1 CERTIACATE 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 Aowserve Corporation. 1900 South Saunders St. Raleigh, He 27603

. (n_. . .., oddr... 01 !II Cerllft_. Hol.,.,

2. Manufactured for Exelon Business Services, An Exelon Company P.O. Box 805388 Chicago. IL 60680-5388

. 1 _ end oddr... of Purch....'

3. Location of installation Braidwood Station East of IL S3 1-1/2 miles South of RT 113 Braidwood, IL 60408

4. Model No., Series No., or Type 1500# CHECK VALVE Drawing 09-54152-01 Rev. o CRN _N..:../A _

5. ASME Code, Sec:tion lit, Division 1: 1971 .I WINTER 1972 1

- - - " ' - I*.,""h"'-lan-,---L --....;;;I.;...;.d-'-"_;;;,;..;...;;;.".;;.;I.;...;.,;;....-- ----IC....:I~:.... .- ' - - -

N/A

-'-""-'---,t""coo..,-.c"".-.-no-.-)-

6. Pump or valve Valve Nominal inlet size _ _-:?2=-:-_ _ Outlet size _ _......,;;2:;..,-_ _

lin.' lin.1

7. Material: .J ..; /

(a) valve Body SA182-F316 Bonnet SA182-F316 Disk SA479-316 Bolting N u IA u.:l.-_ _

lbl pump Casing Cover Bolting _

Cal Cbl leI Idl Cel Celt. Nat'l BodvlCasing BonnetICover Disk Holder's Board Serial Serial Serial Serial No. Nil. No. No. ../ No.

f/ 44BPM N(A A8-5 93723-6 33617-1-1

• Suppf.emantal information in the form of In, stratchell, or draw....gs may be uaed p;ovided maize is elk x 11, (21 information in itema 1 mroullh 4 on mia Data Report is included on each sheet, (31 each sheet is numberad and 1tla number of shaetll is recorded at me lop of mis form.

Page 6-26

155949 2

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

1/

Certificate Holder's Serial No. 44_B_PM _

2580 650 Of' or valve pressure class ...:1:.:5;,;00:..=.. _

8. Design conditions psi (pr.......1 It om per.UJf 01

9. Cold working pressure 3600 psi at l00"F 5400 3960 1O. Hydrostatic test psi. Disk differential test pressure psi

11. Remarks: :2S~.O:!.:..,-,S4~1.:=S~2 _

CERTIFICATION OF DESIGN Design Specification certified by _L_I_ke_E_zk_oye.:....:. _ P.E. State PA Reg. no.

16379-E Design Report certified by ....:,.Ron=:;:,.:S::,:.:,.:F:,.:arr::;.:.;eII==- _ P.E. State --"N:.;:::C_ Reg. no. 028656 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.

Expires __1_1_-_2_6-09~--------------

o N Certificate of Authorization No. N--_l_S_62 Date Name _Aow __serve Corpo....;,=ra~tio~*,..n~.,...,.,""'""" ---: Signed IN Conlficale Holderl 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 He and employed by HSB CT

_ _....., of Hartford, CT have inspected the pump. or valve. described in this Data Report on

~(>t ~e <:.o~tf ' and state that to the best of my knowledge and belief. the Certificate Holder has constructed this pump, or valve.

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 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 conn!'cted with this inspection.

Date .,'~8 [0,\ Sign~~t2 lAUlt\OfI~lns_1 CommisSions INort. Bd.UncI. ondoro_ontll ond stale or prov. ond no.)

Page 6-27

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

1. Owner Exelon Generation Co., LLC Date 1/2512011 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 2 Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #01224737*01 Repair Organization PO.. Job No., etc

3. Work Performed By: Shaw 1 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 1 and 2) 5 (a) Applicable Construction Code: Valve: ASME Section III 1971 Edition, Winter 1972 Addenda, No Code Cases Piping: ASME Section 1111974 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 0 fC omp<nents:

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

Check Valve 1SI88190 and Not Recorded Not Recorded Not 1SI88190 Not Recorded Removed Yes associated piping Applicable 2" Y*Piston Check Valve Flowserve 48BQD Not Cat 10 24010-1 2010 Installed Yes Corporation Applicable UTC 2865588 2" Socket Weld Flange Western Forge Heat 249217 Not Cat 10 30443-1 2010 Installed No

& Flange Co. Lot 10791 Applicable UTC 2869560 r.l'lt1AGMA 2" Seamless Pipe Sandvik Heat 505112 Not Cat 10 32352*1 2005 Installed No Materials WO/Lot Applicable UTC2829998 Technology 515468 3/32" EA316L (for valve Arcos LotCM8256 Not Cat 10 8500-1 2004 Installed No

' : . cover seal weld) Industries, LLC Applicable UTC 2715657

'F

7. Description of Work: Replaced existing check valve and associated piping as part of a troubleshooting effort. Socket welds were examined by liquid penetrant method.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 181 Exempt 0 Other 181 Pressure Class 2: 8701 Class 1: 2239.8 psig Test Temp. Class 2: 95.61 Class 1: 549.32 of

9. Remarks: Section XI pressure testing for Class 2 was performed and acceptable on 10117/2010 in conjunction with 1BwVSR TAM 2.5.c.3, Class 1 system leakage test was performed and acceptable on 11/412010. Applicable material documentation for all components (Form NPV-1), materials, and 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 t&t4UuL-f1; U~

Owner orowne;sesignee, Tit0 lSI Coordinator Date /Il?

I

,20---'-L 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 911612010 to 1/2512011, 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 roperty damage or a loss of any kind arising from or connected with this inspection.

___-:--_....,:;\.tL~:---xl:::::~::::..:::lt....:::::=====-----------

Inspectors Signature Commissions IL1085 N*7a-:t7'"io-'na~I~Bo~a'-rd'7",-::S::-ta-:t-e-,P::'r-o-v7'"inc-e-,-a-n-:d-::E::-nd--:-o-rs-em-e-n'7"ts-Page 6-28 Date

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 1/2512011 Address: 300 Exelon Way, Kennett Square. PA 19348 Sheet 2 of 2

3. Plant Name: Braidwood Station Unit _1_

Address: 35100 S. Ate. 53, Suite 84, Braceville, Il 60407 Work Order #01224737-01 Repair Organization P.O., Job No., etc

3. Work Performed By: Shaw I Stone & Webster Type Code Symbol Stamp: None Address: 35100 South Route 53, Suite 84, Braceville, Il60407 Authorization No.: None Expiration Date: None

4. Identification of System: SI (Safety Injection) (Class 1 and 2) 5 (a) Applicable Construction Code: Valve: ASME Section III 1971 Edition, Winter 1972 Addenda. No Code Cases Piping: ASME Section 1111974 Edition, Summer 1975 Addenda. No Code Cases (b) Applicable Edition of Section XI Utilized for RepairlReplacement 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 ASMECode Manufacturer Serial No. Board No. Identification Removed. or Stamped (Yes Installed or No) 1/8" ER 30B/308l Bare Arcos lot DT8780 Not Cat 10 8513-1 2007 Installed No Welding Rod Industries. Heat 735456 Applicable UTC2802006 llC 3132" ER 3OB/308l Bare Arcos lot CT8816 Not Cat 108497*1 2008 Installed No Welding Rod Industries. Heat 735657 Applicable UTC 2812499 llC 3132" ER 308I308l Bare Arcos lotCT9023 Not Cat 108497-1 2008 Installed No

) Welding Rod 1/8" ER 3OB/308l Bare Industries.

I I Arcos r.

Heat 737880 lot CT9023 Applicable Not UTC2830005 Cat 108513-1 2009 Installed No Welding Rod Industries. Heat 737880 Applicable UTC 2828327 ILC i l~Lt~__

1{"J.y I t \

Page 6-29

15 S43 0 FORM NPV-' 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 Aowserve Corporation. 1900 South Saunders St Raleigh. NC 27603 (nama end add.... 01 N Caruflca,a Holdar)

2. Manufactured for Exe/on Business Services, An Exelon Company P.O. Box 805388 O1icago, Il 60680-5388 (noma end adelta.. of Purch....'

3. Location of installation

\:II' Braidwood Station East of Il 53 1;1/2 miles South of RT 113 Braidwood. Il 60408 lnama end add.a..)

4. Model No., Series No., or Type 1500# atE(]( VAlVE Drawing 09-56242-01 Rev. .:.0 _ CRN _N...:.,/A _

5. ASME Code,Section III, Division 1:

1971 WINTER 1972 1 N/A ladition) (addenda datal lcl..., ICoda ea.. no.!

6. Pump or valve Valve Nominal inlet size 2 Outlet size 2 lin.! lin.!

7. Material:

Body SA182-F316 Bonnet SA182-F316 Disk SA479-316

/Bolting uNu./A3-._ _

(a) valve (b) pump Casing Cover Bolting _

la)

Cert.

Holder's Ibl Nat" Board leI Body/Casing serial Idl BClnnet!Cover serial J (e)

Disk serial /

SefiaiNo. j No. No. /

No. No. . "

048BQO N/A AB-6 93723-11 33617-1-20

• Supplemental infonnation in Ihe fonn of listlI, sketch.., or drawings may be used provided (11 size is 8'/2 x 11, 121 information in items 1 through 4 on Ihis Date Report is included on each sheet, 131 each sheet is numbered and Ihe number of sheet. is recorded al Ihe top of Ihis fonn.

Page 6-30

158430 2

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

Certificate Holder's Serial No. 4_8_BQO _

2580 650 Of or valve pressure class -=1:.;5:.;OO:.;;,..__......~/ _

8. Design conditions psi - v IpnrlSure' (temperature'

9. Cold working pressure __3_6_00 '-"".....

/ psi at 100"f S400 3960

10. Hydrostatic test psi. Disk differential test pressure psi

11. Remarks:  ::!S~.O:!:.:....:5:c6=2:.:4.e:2 _

CERTIFICATION OF DESIGN Design Speciflcation certified by _L_I_ke_Ez_e_koy....:._e _ P.E. State _-:-::__ PA Reg. no. 18379-E Design Report certified by ....:.;:R::::obert=~A.=_=Si:::*z::::emor==e _ P.E. State NC Reg. no. 029425 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.

e 'EL..~~.~.:

N Certificate of Authorization No. N_-_1_S6_2 Expires _1_1_-_2_6-_1_2 _

Aowserve Corporation Name ..;,.,.,.-=-~-:-~":"'"':------

IN Cenlf1cllle Holderl Sign" 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 cr

_ _ _...... - - of Hartford, cr have inspected the pump, or valve, described in this Data Report on 6/2 y 0 It , and state that to the best of mv knowledge and belief. the CertifICate Holder has constructed this pump, or valve.

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 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 lAultlorlud Nude. Inspeclorl Page 6-31

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 1127/2011 Address: 300 Exelon Way. Kennett Square. PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Ate. 53. Suite 84. Braceville. IL 60407 Work Order #01294185-01 Repair Organization P.O.. Job No.. etc

3. Work Performed By: Shaw I 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 Valve: ASME Section III 1971 Edition, Winter 1972 Addenda, No Code Cases (b) Applicable Edition of Section XI Utilized for RepairlReplacement: 2001 Edition with 2003 Addenda (c) Section XI Code Cases used: None

6. Identification of Come< nents:

Name of Component Name of Manufacturer National Other Year Built Corrected ASMECode Manufacturer Serial No. Board No. Identification RemOVed. or Stamped (Yes Installed or No)

Existing 2" Globe Valve and Not Recorded Not Recorded Not 1SI8952C (Valve) Not Removed Yes (Valve)

Associated Piping Applicable Line 1SI79GA-2" Recorded 2" Globe Valve Flowserve 93BQW Not Cat 10 30706-1 2010 Installed Yes Corporation Applicable UTC 2869749 2" Schedule 40 Sandvik Heat 512741 Not Cat 1026883-1 2007 Installed No Seamless Pipe Materials WOILot Applicable UTC 2807097

<:;2021/';

3132" Diameter Arcos Heat 737880 Not Cat 10 8497-1 2008 Installed No ER 308L Weld Rod Industries. LLC Lot CT9023 Applicable UTC2830005 Control 9023 1/8" Diameter Arcos Heat 249076 Not Cat 10 37029-1 2009 Installed No ER 308/308L Industries. LLC Lot D-90n Applicable UTC 2689561

~nntml r:1077

7. Description of Work: Removed existing valve and piping because Instrument Maintenance suspected pipe was plugged causing instrument indication errors in Safety Injection accumUlator.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 181 Exempt 0 Other 181 Pressure ~ psig Test Temp. Ambient OF

9. Remarks: Section XI pressure testing was performed and acceptable on 11/212010. instrument for specific temperature is not available. Applicable material documentation for all components (Form NPV-1). materials. and associated weld filler materials was attached at the time of final review and is maintained on file.

CERllF1CATE OF COMPUANCE 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 Signedtiutzdaa, Owner or Owner' Designee, TI 90* C~ lSI COordinator Date .

/hz .20lL.....

CERllF1CATE 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 4121/2010 to 1/27/2011. 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. conceming the examinations and corrective measures described in this Owner's Report Furthermore. neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_ _ _ _ _:k:..' ...:-...,..,.-x.C'--...:.::..l.=,"

Inspector's Signature

.===-----------r"l=="l~rrT' Page 6-32 Commissions ..,.----!I.L1~O!ll8~5--:-------------

National Board. State. Province. and Endorsements n"t.. - Jf - ?O I,

161186 FORM NPV-' CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES*

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

1. Manufactured and cartified by Rowserve Corporation, 1900 South saunders st. Raleigh, Nt 27603 Inama ..d ""eka.. 01 N Cardllcata Holdarl

2. Manufactured for Exelon Business Services, An ExeIon Company P.O. Box 805388 Chicago, IL 60680-5388 inam. . .d acldr_ Of Purcnuar)

3. location of installation Braidwood St.atk:in. East of It S3 1-1/2 miles South of RT 113 Braidwood, It 60408 1/ lnama ..d eddr...'

4. Model No.* Series No., or Type 1500# CH~ VAl.VEDrawin~905IS I W-o-ttMMt-~~. / J CRN _N..;./A _

5. ASME Code.Section III, Division 1: 1971,/ WINTER 19n ...,/ 2 N/A ledldon' ieddenda dote' ----"icf""'_-"",- - - ..:..:l.':':"-:-::iC~Od"""""Caee-no"""J--

6. Pump or valve Valve Nominal inlet size 2 / Outlet lize _ _ ~2~_ _

IIn.1 Un.)

7. Material: v Bonnet SA479-316J ./

(al valve Body SA182-F316 Dilk SA479-316 Bolting .N

...I...A......_ _

(bl pump Casing Cover Bolting _

(al (bl (e) (dl (el Celt. Na,'1 Body/Caling 8onnelICover DIsII:

Board Serial serial Serial Holde.... /

serial No. No. No.

I No.

./ NO./

93BQW N/A A7-SB 33619-1-2 33619-1-1

• Supplemenllll information itt lhe fonn of I., sketches. or drawings may be UI8d provided 111 size

• e'l, x 11. (21 information itt Item, 1 IIIrough 4 on lIIis o.ta Report is Included on eadt sheet, (31 eadt sheet Is numbered and lhe number of sh.... Is recorded at lila top of lIIis fonn.

Page 6-33

161166 2

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

Certificate Holder's Serial No. 9_3_SQ-..W -

2580 650 "F or valve pressure class ..;1::.::500:.:::.:::.- _

8. Design conditions psi Ipr.....' (temper.IUr.'

9. Cold working pressure 3600 psi at 100"F 3960

10. Hydrostatic test psi. Disk differential test pressure psi

11. Remarks: *

!S~.Ot.:. ..::l58~S82i!!:... _

yoKE- Material SAlas; HeatlS1N K456+1

. CERnFICAOON OF DESIGN Design SpecifICation certified by _L_I_ke_Ezekoye_--:. _ P.E. State PA _ Reg. no. 18379-E Design Report certified by _...:N/;:z.;.A;..-. _ P.E. State .....;N,;,;I.;.;A:..- Reg. no. ..INII.J,aA _

CERnFICATE OF COMPlIANCE We certify that the statementl 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 Auth . ation No. N_-_l_S62 Expires ....;;;.::........:...:;..;;~~~::;IO""~"."--.....- - - -

Date Name _Rowserve Corporation-=.",.,..,..."""""-.--:'=""""-:- _

(N Cartlflc** Hollier' CERnFICATE OF INSPECnON 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 cr

¥¥o~ ~ of Hartford, CT have inspected the pump. or valve. described in this Data Report on and state that to the best of my knowledge and belief, the CertifICate Holder has constructed this pump, or valve.

in acco dan 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 0/+ Signed Commissions NuN?

Page 6-34 3

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI Owner Exelon Generation Co.* LLC Date 1/25/2011 Address: 300 Exelon Way. Kennett Square. PA 19348 Sheet 1 of 1 Plant Name: Braidwood Station Unit 1 Work Order #01377039-01 Address: 35100 S. Rte. 53. Suite 84, Braceville. IL 60407 Repair Organizalion PO.. Job No.* etc

3. Work Perlormed 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: Safety Injection (SI) Class 1 system 5 (a) Applicable Construction Code: ASME Section 1111974 Edition. Summer 1974 Addenda. Code Cases: 1644 Revision 7, 1682. 1683, 1685.

1686, 1651. 1728, 1729, 1734. N*180 and N*l08 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 2001 Edition with 2003 Addenda (c) Seclion XI Code Cases used: None

6. Identification of Como< nents Reoaired or Replaced and Replacement Components:

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

PSA-3 Mechanical Snubber ITT Grinnell SIN 15517 Not 1S109015S2 1981 Replaced No lS109015S2 Applicable PSA-3 Mechanical Snubber Basic-PSA Inc. SIN 20643 Not Cat 10 27883*1 1982 Replacement No Applicable UTC 2635990

7. Description of Work: Existing snubber failed A 1R15 functional testing (reference Issue Report 1124493). Snubber is one of two installed on a trapeze type support. The failure of the existing snubber was evaluated under EC 381733 and was determined to be a result of grease degradation due to isolated excessive heat on the back end of the snubber. Additional snubber sample expansion was perlormed. The replacement snubber was functionally tested prior to installation.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Other 0 Pressure Not Applicable psig Test Temp. Not Applicable OF

9. Remarks: VT-3 exam of snubber was perlormed after reinstallation on 10/1212010. 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 replacement conforms to the rules of the SME Code,Section XI. Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed ...&.~~!:ta..~...J;;;.~r:..J=::.~';;J:.:"--_ _.E2!.~!ll!!!:!SWlJL-_Date / /2'5' , 201 e

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 10111/2010 to 1/25/2011, and state that to the best of my knowledge and belief, the Owner has perlormed 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, conceming the examinations and corrective measures described in this Owner's Report. Furthermore. neither the Inspector nor his empioyer 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.;::=:..: :=:==-- _ Commissions -:--:--""'L:-'1':f0""8S"'-:-"._---::::-- -,...,::- _

Inspector's Signature National Board, State, Province, and Endorsements Date \ - 2. s;- , 20~

Page 6-35

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: 3/29/2010 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1

2. Plant Name: Braidwood Station Unit: _1_

Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #01156907-05 Repair/Replacement Organization P.O., Job No., etc

3. Work Performed By: Braidwood 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: SX (Essential Service Water) (Class 2) 5 (a) Applicable Construction Code: ASME Section III 1974 Edition, Summer 1974 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 ASMECode Manufacturer Serial No. Board No. Identification Removed, or Stamped (Yes Installed or No)

Support 1SX09067G Not Recorded Not Recorded Not 1SX09067G Not Recorded Removed! No Applicable Installed 3132" E7018 Electrode ESAB Heat 90115 Not Cat 108491-1 2009 Installed No Applicable UTC2847019

7. Description of Work: Removed existing support which prevented removal of annubar 1FE-SX115 in order to perform preventative maintenance cleaning of annubar. Upon completion of annubar installation, reattached existing support members by welding. Support is exempt from Section XI visual examination requirements, finished welds were examined by NF-5222 visual inspection upon support restoration.

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Exempt 181 Other 0 Pressure Not Applicable psig Test Temp. Not Applicable OF

9. Remarks: Applicable material documentation for weld electroce 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 tJA..W~-ie' £~ lSI Coordinator Date 3)2.1 ,20 l D Owner or 0 er's oe;;gee: 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 Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 11/19/2009 to 3129/2010, 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.

___-,--3l~_.,JL~~(..::! .~. . =======_

Inspector's Signature Commissions-,-,......-'I""L""'10~8..,5<-.,--:::-_~--:

National Board, State, Province, and Endorsements Date ~ -'3.l 20 \ -

Page 6-36