BW100010, Inservice Inspection Summary Report
| ML100330273 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 01/27/2010 |
| From: | Shahkarami A Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW100010 A2R14 | |
| Download: ML100330273 (106) | |
Text
Exelon, Exelon Generation Company, LLC www.exeloncorp.com Nuclear Braidwood Station 35100 South Route 53, Suite 84 BTaceville, IL 60407-9619 January 27, 2010 BW100010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Facility Operating License No. NPF-77 NRC Docket No. STN 50-457
Subject:
Braidwood Station, Unit 2 Inservice Inspection Summary Report Enclosed please find the post-outage summary report (i.e., 90 day report) for inservice inspection examinations conducted during Braidwood Station, Unit 2 Refueling Outage 14 (A2R1 4). 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. David Gullott, Regulatory Assurance Manager, at (815) 417-2800.
Respectfully, Amir Shahkarami Site Vice President Braidwood Station
Enclosure:
Braidwood Station ISI Outage Report for A2R1 4 cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - Braidwood Station Illinois Emergency Management Agency - Division of Nuclear Safety Y0-(-7 uLA.
BRAIDWOOD STATION UNIT 2 INSERVICE INSPECTION
SUMMARY
REPORT FOR:
Interval 3, Period 1, Outage 1 Interval 2, Period 3, Outage 3 A2R14 Outage STATION ADDRESS:
Braidwood Station 35100 S. Route 53 Suite 84 Braceville, Illinois 60407 UNIT 2 COMMERCIAL SERVICE DATE:
October 17, 1988 OWNER'S ADDRESS:
Exelon Generation Co., LLC 300 Exelon Way Kennett Square PA 19348
Exel0 kn Braidwood Station Unit 2 A2R14 ISI Outage Report TABLE OF CONTENTS DESCRIPTION:
PAGE:
TITLE PAGE TABLE OF CONTENTS 1.0 -
INSPECTION INFORMATION 1-1 to 1-3 2.0 INSERVICE EXAMINATION
SUMMARY
2-1 to 2-5 3.0 -
COMPONENT EXAMINATION RESULTS 3-1 to 3-52 4.0 -
REPORT OF CONTAINMENT 4-1 to 4-3 DEGRADATION (IWE) 5.0 -
FORM NIS-1 (OWNER'S REPORT FOR INSERVICE INSPECTION) 5-1 to 5-6 FOR ISI SECOND AND THIRD INTERVAL AND THIRD INTERVAL INSPECTION STATUS AFTER A2R14 6.0 -
FORM NIS-2, (OWNER'S REPORT FOR REPAIRS 6-1 to 6-34 OR REPLACEMENTS), Cover page plus 33 pages of Attachments ii
Exel an-Braidwood Station Unit 2 A2R14 ISI Outage Report 1.0 INSPECTION INFORMATION 1.1 Summary Third Interval Inservice Inspections (ISI) and Preservice Inspections (PSI) of ASME Class 1, 2, and 3 components were conducted at Braidwood Station Unit 2 from October 17, 2008 through November 1, 2009. The majority of these inspections were performed during the Braidwood Station Unit 2 fourteenth refueling outage (A2R14). This report also contains the results of the remaining Second Interval pressure tests that were not completed prior to submittal of the previous A2R1 3 outage report.
For the Third Interval, 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 remaining Second Interval 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, 1989 Edition, No Addenda, pursuant to the requirements of 10CFR 50.55a.
The Containment Inspection Program was 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 Xl requirements, certain NRC or industry augmented inspections were completed during A2R14. The Braidwood Unit 2 augmented examinations included:
a)
Examination of the Class 1 pressure boundary for leakage at nominal operating pressure, in accordance with Generic Letter 88-05.
b)
Examination of the 2A reactor coolant pump motor flywheel in accordance with Regulatory Guide 1.14 and Technical Specification 5.5.7.
c)
Examination of welds in accordance with Materials Reliability Project MRP-139 and MRP-146.
There were no significant findings associated with any of the augmented examinations.
Page 1-1
Exelkn-Braidwood Station Unit 2 A2R14 ISI Outage Report 1.2 Identification of Examination Requirements The Second and Third Interval ISI Programs contain the applicable Component Selection tables. These tables are presented in a tabular format consistent with the tables found in subsections IWB, IWC, IWD, IWE, and IWF-2500 of the ASME code. The Non-Destructive Examination (NDE) tables include the corresponding code category, item number, and component/weld population selection in conformance with examination requirements and intent of Subsection IWA, IWB, IWC, IWD, IWE, and IWF of Section 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 Xl Subsection IWB, IWC, IWD, and IWF are identified in the Braidwood Station Boundary Basis document, along with reference to the justification(s) for exempting the component/system.
1.4 ISI Program Implementation Braidwood Station personnel, or their designee, visually examined (VT-1, VT-2, and VT-3) and/or NDE examined (UT, PT, MT) ASME components.
The components examined comply with the ISI Program Schedule, Braidwood Station Technical Specifications (TS), and/or compliance with the ASME Section Xl Repair/Replacement Program. All ISI NDE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section Xl, Sub-article IWA-2200:
"Examination Methods".
Certified personnel performed and evaluated all NDE results. Personnel were certified to the requirements of the American Society for Non-destructive Testing SNT-TC-1A, 1984 Edition. The NDE procedures were developed and certified in conformance with ASME Section V and Xl,
,2001 Edition through 2003 Addenda, or approved alternatives (Performance Demonstration Initiative Program) as applicable. In addition, ultrasonic examination personnel were qualified inaccordance with ANSI/ASME CP-189,1995 Revision.
Certified personnel performed and evaluated visual examinations (i.e.,
VT-1, VT-2, and VT-3) of Class 1, 2, and 3 components and supports.
Personnel were certified to the requirements of the American Society for Non-destructive Testing SNT-TC-1A, 1984 Edition and ANSI/ASNT CP-189, 1995 Revision.
Certified personnel performed and evaluated examinations (UT, VT-1, and VT-3) of primary containment. Personnel were certified in accordance with the requirements of the ANSI/ASNT CP-1 89, 1995 Page 1-2
Exebk-Braidwood Station Unit 2 A2R14 ISI Outage Report Revision, and/or ASME Section XI 2001 through 2003 Addenda, as applicable.
1.5 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANII), L. Malabanan and R.
White. The inspectors are associated with Hartford Steam Boiler Inspection and Insurance Company of Connecticut, Chicago Branch, at 2443 Warrenville Rd., Suite 500, Lisle, Illinois 60532.
Page 1-3
Exemn Braidwood Station Unit 2 A2R14 ISl Outage Report 2.0 INSERVICE EXAMINATION
SUMMARY
The following is a summary of ASME Section Xl Class 1 and 2, Risk Informed ISI, and augmented examinations performed during the Braidwood Station Unit 2 A2R14 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 Main Steam (MS) 7 Reactor Coolant (RC) 27 Residual Heat Removal (RH) 1 Pressurizer (RY) 5 Safety Injection (SI) 1 TOTALS 42 Non-Section Xl Augmented examinations and Risk Informed ISI socket weld VT-2 examinations are not included in these counts but are contained in Section 3.1.1 of report.
2.2 Inservice Component Support Summary Loniainmeni spray (U*)
Chemical & Volume Control (CV) 7 Feedwater (FW) 25*
Main Steam (MS) 1 Reactor Coolant (RC) 11 Safety Injection (SI) 1 TOTALS 52 Includes sample expansion examinations.
Page 2-1
Exek~n-Braidwood Station Unit 2 A2R14 ISI Outage Report 2.3 Inservice Snubber Summary Chemical & Volume Control (CV) 15 4
Main Steam (MS) 4 2
Reactor Coolant (RC) 18 7
Residual Heat Removal (RH) 6 5
Reactor Coolant (RY) 9 5
Steam Generator Blowdown (SD) 6 2
Safety Injection (SI) 8 3
Essential Service Water (SX) 1 0
TOTALS 78 35 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 XI Inservice Inspection credit during A2R14.
Table 2.4.1-1 A2R14 Section XI Pressure Tests Auxiliary I-eedwater (AF-)
Plant Systems Pressurized During Mode 3 (ZZ)
I TOTALS 3
The components contained in Table 2.4.1-2 are pressure test blocks that were completed during the third period of the Second Interval but were not submitted under the previous A2R1 3 outage report because surveillances were either not closed out or were scheduled after the A2R13 90 Day Report was submitted.
Page 2-2
Exelrn Braidwood Station Unit 2 A2R14 ISI Outage Report Table 2.4.1-2 Second Interval Section XI Pressure Tests Completed Since Previous Report Auxiliary Feedwater (AF) 2 1
Component Cooling (CC) 2 1
Containment Spray (CS) 2 5
Fire Protection (FP) 2 1
Essential Service Water (SX) 2 2
TOTALS 10 2.4.2 Borated Bolting Inservice Inspection Summary The components contained in Table 2.4.2-1 are those insulated borated bolted connections that were examined for Section Xl Inservice Inspection credit. Inspections on these connections are performed per the ISI Program Plan.
Table 2.4.2-1 Borated Bolted Connections Chemical & Volume Control (CV) 22 2
Reactor Coolant/Pressurizer 14 0
(RC/RY)
Residual Heat Removal (RH) 15 1
TOTALS 51 3
2.5 Steam Generator Eddy Current Testing Summary 2.5.1 Steam Generator Eddy Current Testing Summary In accordance with Braidwood Station Technical Specification (TS) 3.4.19, "Steam Generator (SG) Tube Integrity," TS 5.5.9, "Steam Generator (SG) Program," and American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code Section Xl 2001 Edition through 2003 Addenda, IWB 2500-1, Examination Category B-Q, Item B16.20, SG eddy current examinations were performed during the Braidwood Station, Unit 2, fourteenth refueling outage (A2R14). In Page 2-3
Exarn-Braidwood Station Unit 2 A2R14 ISI Outage Report addition, the inspections were performed consistent with the Electric Power Research Institute (EPRI) "PWR Steam Generator Examination Guidelines," Revision 7, and Nuclear Energy Institute NEI 97-06, "Steam Generator Program Guidelines," Revision 2.
The following inspections were performed during this outage:
100% bobbin coil eddy current examination of all SGs excluding the Row 1 and Row 2 U-Bend regions. In the Row 1 and Row 2 U-Bend regions a 25% +PointTM inspection was performed as described below.
- 30% hot leg top of tubesheet (+ 4" to - 3"), +PointTM in all SGs.
30% hot leg bulges > 18 Volts and over expansions > 1.5 mils within the top 16.95 inches of the hot leg tubesheet in all SGs.
30% of the hot leg tubing within the tubesheet (+ 4" to - 18"), +Point in all SGs.
100% hot leg tubing within the tubesheet (+ 4" to - 18"), +PointTM of inservice tubes identified as having increased residual stress.
100% of the hot leg dents/dings > 2.0 volts contained in inservice tubes identified as having increased residual stress, +PointTM.
100% of the wear indications contained in inservice tubes identified as having increased residual stress, +PointM.
+PointTM inspection of all hot leg and cold leg tubesheet expansions transitions significantly outside the tubesheet. (Note: None were identified during A2R14).
+PointTM inspection of all pre-heater baffle plate expansions significantly above or below the baffle plate. (Note: None were identified during A2R14).
20% pre-heater baffle expansion +PointTM in the 2B SG.
25% hot leg dents/dings >3.0 volts +PointTM in all SGs.
25% Row 1 and Row 2 U-bends +PointTM in all SGs.
100% visual inspection of the previously installed and newly installed tube plugs in all SGs.
The modes of tube degradation found during the A2R14 SG inspection were anti-vibration bar (AVB) wear, pre-heater tube support plate wear and secondary side foreign object wear.
As a result of the eddy current inspection of the SGs, a total of six tubes were removed from service by mechanical tube plugging. Of the six tubes removed from service, one tube was plugged due to having AVB wear greater than or equal to the 40% through wall (TW) Technical Specification 5.5.9.c.1 acceptance criteria, and five tubes were preventatively plugged due to having wear from secondary side foreign objects, which were below the 40% TW Technical Specification 5.5.9.c.1 acceptance criteria.
There were no scanning limitations during the eddy current examinations.
Page 2-4
Exekm-Braidwood Station Unit 2 A2R14 ISI Outage Report Table 2.5-1 provides the tube plugging levels for each SG to date. Table 2.5-2 provides the total number of tubes plugged during A2R14 by degradation mode.
Table 2.5-.1 Equivalent Tube Plugging Level
_______________SG~2A_
SG2B
- SG2C~ SGO 2D
- Total, Tubes Previously Plugged 83 49 65 26 223 Tubes Plugged in A2R14 0
5 1
0 6
Total Tubes Plugged 83 54 66 26 229 Total Tubes Plugged (%)*
1.82%
1.18%
1.44%
0.57%
1.25%
- S-2A!
SG2*b SG 2C SO2D
- Total, Foreign Object Wear 0
4 1
0 5
Anti-Vibration Bar Wear 0
1 0
0 1
A2R14 Plugging Totals 0
5 1
0 6
Additional information concerning the steam generator eddy current inspection results can be obtained in the report submitted to the Nuclear Regulatory Commission as required by Technical Specification 5.6.9, "Steam Generator (SG) Tube Inspection Report."
Page 2-5
Exelkn Braidwood Station Unit 2 A2R14 ISI Outage Report 3.0 COMPONENT EXAMINATION RESULTS 3.1 Third Interval Inservice and Preservice Inspection Detailed Result Tables 3.1.1 Detailed Third Interval Inservice Weld/Component Table(s):
The table for this section (Pages 3-6 to 3-20) lists the examinations performed for Section XI Inservice and Augmented Inspection requirements for Class 1 and 2 welds and components for the Third ISI Interval. The general format of how the table is set-up is shown below. A description of the information contained in each column can be found in Section 3.3.
I Section Xl, 11 Identifier Line Relief Program Code Exam Actual Results Cat. Item Description Number/EPN Request Notes Coverage SummaryI Exam I Inspection Comments (A)
(B)
(C)
(D)
(E)
(F)
(G)
(H)
(I)
(K)
(J) 3.1.2 Detailed Third Interval Preservice Weld/Component Table(s):
The table for this section (Page 3-21) lists the baseline examinations performed for Section Xl Preservice Inspection requirements for Class 1 and Class 2 components replaced during A2R14. The general format of how the table is set-up is shown below. A description of the information contained in each column can be found in Section 3.3.
Section Xl ISI Identifier Line I Relief Program Code Exam Actual Results Cat. Item I Description Number/EPN I Request Notes Coverage Summary Exam Inspection Comments (A)
(B)
(C)
(D)
(E)
(F)
(G)
(H)
(i)
(K)
(J) 3.1.3 Detailed Third Interval Inservice Component Support Table:
The table for this section (Pages 3-22 to 3-28) lists the examinations performed for Section XI Inservice Inspection requirements for Class 1 and 2 component supports for the Third ISI Interval. The general format of how the table is set-up is shown below. A description of the information contained in each column can be found in Section 3.3.
ISection Xl ISI Identifier Line NumberEPN Relief Program Exam Result Cat. Item Description Request Notes Summary I Inspection Comments (A)
(B)
(C)
(D)
(E)
(G)
(I)
(K)
(J)
Page 3-1
Exekrn-Braidwood Station Unit 2 A2R14 ISI Outage Report 3.1.4 Detailed Third Interval Preservice Component Support Table:
The table for this section (Pages 3-29) lists the examinations performed for Section Xl Inservice Inspection requirements for a replaced Class 2 component support. 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 X ISI Identifier Line NumberEP Relief Program Exam esus Cat. Item Description I
Request Notes I Summary Inspection Comments (A)
(B)
(C)
(D)
(E)
(G)
(I)
(K)
(J) 3.1.5 Detailed Third Interval Inservice Snubber Table:
The table for this section (Pages 3-30 to 3-39) 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 3.3.
Section Xl ISI Identifier Line NumberEPN Relief Program Exam Iesus Cat. Item Description Request Notes Summary Inspection Comments (A)
(B)
(C)
(D)
(E)
(G)
(I)
(K)
(J) 3.1.6 Detailed Third Interval Preservice Snubber Table:
The table for this section (Pages 3-40 to 3-41) lists the baseline examinations performed for Section Xl Preservice Inspection requirements for Class 1 and 2 snubbers replaced during A2R14. 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 X' ISI Identifier Line Number/EPN Relief Program Exam Results Cat. Item Description Request Notes Summary I Inspection Comments (A)
(B)
(C)
(D)
(E)
(G)
(I)
(K)
(J)
Page 3-2
Exeknm Braidwood Station Unit 2 A2R14 ISI Outage Report 3.1.7 Detailed Listing of Third Interval System Pressure Tests The table for this section (Pages 3-42 to 3-43) lists the examinations performed for Section XI Inservice and Augmented Inspection requirements for Class 1 and 2 pressure test blocks credited to the Third ISI Interval. The general format of how the table is set-up is shown below.
A description of the information contained in each column can be found in Section 3.3.
iSection XlI iSI Ientifier Relief Program Exam Results Cat. Item Description Request Notes Summary Inspection Comments (A)
(B)
(D)
(E)
(G)
(I)
(K)
(J) 3.1.8 Detailed Borated Bolted Connection Table The table for this section (Pages 3-44 to 3-47) lists the examinations performed for Inservice Inspection pressure testing requirements of Section Xl Class 1 and 2 borated bolted connections. The general format of how the table is set-up is shown below. A description of the information contained in each column can be found in Section 3.3.
Section Xl ISI Identifier Relief Program Exam I Results Cat. Item Description Request Notes Summary Inspection Comments (A)
(B)
(D)
(E)
(G)
(I)
(K)
(J) 3.2 Detailed Listing of Second Interval System Pressure Tests The table for this section (Pages 3-48 to 3-52) lists the examinations performed for Section Xl Inservice and Augmented Inspection requirements for Class 1 and 2 pressure test blocks credited to the Second ISI Interval. The general format of how the table is set-up is shown below. A description of the information contained in each column can be found in Section 3.3.
SectionXll ISI Identifier Relief IProgram Exam I Results Cat. Item Description Request Notes Summary Inspection Comments (A)
(B)
(D)
(E)
(G)
(I)
(K)
(J)
Page 3-3
Exekon-Braidwood Station Unit 2 A2R14 ISl Outage Report 3.3 General Inservice Report Information 3.3.1 Report Column Descriptions (A) This column contains the Section Xl Category and Item identifiers for the specified component. There are special cases, like snubbers, where an "S" has been added to the end of the Section XI Item identifier. This was done to allow easy sorting of the snubber population by the ISI database.
(B)
This column contains the ISI Identifier that the ISI Program uses to distinguish components.
(C)
This column contains the line number or equipment piece number (EPN) associated with the component for identification.
(D) This column identifies the ISI Program Plan relief request(s) that is associated with that component. A complete copy of the relief request can be found in the ISI Program Plan.
(E)
This column identifies the ISI Program Plan note(s) that is associated with that component. A complete copy of the Program note can be found in the ISI Program Plan.
(F)
This column identifies the percentage of code coverage achieved for the associated surface or volumetric examination for that component.
(G)
This column summarizes the exams performed during this outage for the associated component.
(H) This column identifies actual exams performed during this outage for the associated component.
(I)
This column summarizes the results for exams performed during this outage for the associated component.
(J)
This row states inspection comments, when applicable, for the associated component.
(K) This column specifies the description of the associated component.
Page 3-4
Exe~n-Braidwood Station Unit 2 A2R14 ISI Outage Report 3.2.2 Report Abbreviations ATI Action Tracking Item BMV Bare Metal Visual Inspection ET Eddy Current (Steam Generator)
FUNCT Snubber Functional Test FSWOL Full Structural Weld Overlay GE/IND Geometry/Indication GEOM Geometry IND Indication IR Issue Report NRI No Recordable Indications MT Magnetic Particle Inspection PT Liquid Penetrant Inspection SUR Surface Exam TBD To Be Developed WO Work Order UT Ultrasonic Inspection VOL Volumetric Exam VOL-E Volumetric Exam of an Extended Volume VT Visual Inspection Page 3-5
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Containment Spray System (CS)
C-C C03.30 2CSP-01-CSP01, 02,03 2CS01PA NOTE 17 65.7 SUR PT NRI 2CS01 PA PUMP LUG 65.7 VT-1 NRI Limited liquid penetrant examination coverage, supplemented by VT-1 examination on each attachment. Relief request is required (less than 90% coverage achieved). Relief request for first period limited examination coverage is being tracked through ATI 894565-02.
Page 3-6
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Chemical & Volume Control System (CV)
~SectionXi Compoen ID Line Number "Reliefj Technical :CodeQ Required~ Actual Results~
Cat~
Description IReuests Notes Cov~erage Exa Exam R-A R01.11 2CV-05-03 2CVA3B-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.1 1 2CV-05-04 2CVA3B-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2CV-05-05 2CVA3B-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2CV-05-06 2CVA3B-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2CV-05-13 2CVA3B-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2CV-05-14 2CVA3B-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
RýA R01.11 2CV-11-06 2CVA6AA-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2CV-11-07 2CVA6AA-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-36-15 2CVA3AA-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-36-16 2CVA3AA-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-36-17 2CVA3AA-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-36-18 2CVA3AA-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-37-13 2CVA7AA-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-37-14 2CVA7AA-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 oerformed durinq ascending Mode 3/system leakage test.
Page 3-7
Exekmn.
Braidwood Station Unit 2 A2R14 IS[ Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Main Steam System (MS)
R-A R01.20 2MS-02-14 2MS01CD-30.25" 13R-01 NOTE 09 100 VOL-E UT-0 NRI VALVE 2MS001D - PIPE NOTE 17 UT-45 UT-70 Single-sided carbon steel examination. Zero degree performed to confirm no counterbore exists. Supplemental 70 degree shear wave due to single-sided access.
C-C C03.20 2MS-03-SW15 TO SW18 2MS01AA-30.25" NOTE 17 97.96 SUR MT NRI (4) LUG ATTACH. FOR 2MS05002C Coverage limited due to Support 2MS05006R.
R-A R01.20 2MS-04-62 2MS01CA-30.25" 13R-01 NOTE 09 100 VOL-E UT-0 NRI VALVE 2MS001A - PIPE NOTE 17 UT-45 Single-sided carbon steel examination. Zero degree performed to confirm no counterbore exists.
R-A R01.20 2MS-04-63 2MS01CA-30.25" 13R-01 NOTE 09 100 VOL-E UT-0 NRI PIPE - PIPE NOTE 17 UT-45 Zero degree performed to confirm no counterbore exists.
C-C C03.20 2MS-04-SW18 2MS07AA-28" NOTE 17 100 SUR MT NRI (1) LUG ATTACH. FOR 2MS01205X R-A R01.20 2MS-06-14 2MS01CB-32.75" 13R-01 NOTE 09 100 VOL-E UT-0 NRI VALVE 2MS001B - PIPE NOTE 17 UT-45 Single-sided carbon steel examination. Zero degree performed to confirm no counterbore exists.
RýA R01.20 2MS-08-14 2MS01CC-32.75" 13R-01 NOTE 09 100 VOL-E UT-45 NRI VALVE 2MS001C - PIPE NOTE 17 Single-sided carbon steel examination. Zero degree performed to confirm no counterbore exists. Supplemental 70 degree shear wave due to single-sided access.
Page 3-8
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)
R-A R01.20 2RC-06-02 2RC21AA-8" ELBOW - ELBOW Zero degree performed to confirm no counterbore exists.
13R-01 NOTE 17 100 VOL-E UT-45 NRI UT-60 R-A R01.20 2RC-06-03 2RC21AA-8" 13R-01 NOTE 17 100 VOL-E UT-0 NRI ELBOW - PIPE UT-45 UT-60 Zero degree performed to confirm no counterbore exists.
R-A R01.11 2RC-06-05 2RC21AA-8" 13R-01 NOTE 17 100 VOL-E UT-0 NRI PIPE - ELBOW UT-45 UT-60 Zero degree performed to confirm no counterbore exists.
R-A R01.11 2RC-06-06 2RC21AA-8" 13R-01 NOTE 17 100 VOL-E UT-0 NRI ELBOW - PIPE UT-45 UT-60 Zero degree performed to confirm no counterbore exists.
R-A R01.11 2RC-07-09 2RC28A-3" 13R-01 NOTE 17 93.5 VOL UT-0 NRI ELBOW - SWEEPOLET UT-45 UT-70 VT-2 NRI Not a Section Xl examination, performed per MRP-146. Zero degree exam performed to locate counterbore, none observed. Limited scanning in elbow intradose.
Bare metal VT-2 examination performed.
R-A R01.11 2RC-07-16 2RC37A-3" 13R-01 NOTE 17 93.5 VOL UT-0 NRI ELBOW - SWEEPOLET UT-45 UT-70 VT-2 VT-2 NRI Not a Section XI examination, performed per MRP-146. Zero degree exam performed to locate counterbore, none observed. Limited scanning in elbow intradose.
Bare metal VT-2 examination performed.
R-A R01.20 2RC-11-06 2RC04AB-12" 13R-01 NOTE 04 100 VOL-E UT-0 NRI PIPE - ELBOW NOTE 17 UT-45 Zero degree performed to confirm no counterbore exists.
R-A R01.20 2RC-11-07 2RC04AB-12" 13R-01 NOTE 04 100 VOL-E UT-0 NRI ELBOW - PIPE NOTE 17 UT-45 Zero degree performed to confirm no counterbore exists.
R-A R01.20 2RC-17-09 2RC24AA-4" 13R-01 NOTE 17 100 VOL-E UT-0 NRI PIPE - ELBOW UT-45 Zero degree performed to confirm no counterbore exists.
R-A R01.20 2RC-17-10 2RC24AA-4" 13R-01 NOTE 17 100 VOL-E UT-0 NRI ELBOW - PIPE UT-45 Zero degree performed to confirm no counterbore exists.
R-A R01.20 2RC-20-02 2RC22AD-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
Page 3-9
Exel n-Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)
Section XI
' Component ID IILine NumberW Relief Tech~nical ýCoie R~equired Actual Results' Cat Description~
Requests Not~es CoeaeExam Exam
[Co11-mmnts R-A R01.20 2RC-20-03 2RC22AD-1.5" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-20-04 2RC22AD-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-20-05 2RC22AD-1.5" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-20-36 2RC22AD-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-20-37 2RC22AD-1.5" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-20-38 2RC22AD-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-20-39 2RC22AD-1.5" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-20-40 2RC22AD-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
B-G-2 B07.50 2RC-23-B1 2RC22AA-1.5" SUR.
VT-1 NRI FLANGED CONNECTION (4 STUDS)
Performed Inservice VT-1 of bolted connection for 2FE-0418 during gasket replacement under WO# 1131570-01. Existing bolting was replaced with new material to minimize radiation exposure and hold time on freeze seal.
R-A R01.11 2RC-29-11 2RC16AC-2" 13R-01 NOTE 17 VT-2 NRI VALVE 2RC8038C - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-29-12 2RC16AC-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-29-13 2RC16AC-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-29-14 2RC16AC-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-29-15 2RC16AC-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
Page 3-10
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM:
Section X1 Component ID7
ý 'ine Number Relief Technical :Code Rlequired Actual Results Cat.
Deciptio Reqest Nts Coverage, Exam~ E xam COrnrmentas R-A R01.11 2RC-29-16 2RC16AC-2" 13R-01 NOTE 17 VT-2 NRI PIPE - BRANCH CONNECT.
VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-30-11 2RC13AB-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-30-12 2RC13AB-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-30-13 2RC13AB-2" 13R-01 NOTE 17 VT-2 NRI PIPE - TEE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-30-14 2RC13AB-2" 13R-01 NOTE 17 VT-2 NRI TEE - 2"X.75" REDUCER VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-30-15 2RC13AB-2" 13R-01 NOTE 17 VT-2 NRI TEE - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-30-16 2RC13AB-2" 13R-01 NOTE 17 VT-2 NRI PIPE - VALVE 2RC8040B VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-30-18 2RC13AC-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-30-19 2RC13AC-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-30-20 2RC13AC-2" 13R-01 NOTE 17 VT-2 NRI PIPE - TEE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-30-21 2RC13AC-2" 13R-01 NOTE 17 VT-2 NRI TEE - 2"X.75" REDUCER VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-30-22 2RC13AC-2" 13R-01 NOTE 17 VT-2 NRI TEE - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-31-01 2RC14AB-2" 13R-01 NOTE 17 VT-2 NRI BRANCH CONNECTION - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-31-02 2RC14AB-2" 13R-01 NOTE 17 VT-2 NRI PIPE-ELBOW VT-2 performed during ascending Mode 3/system leakage test.
Page 3-11
71:1 n7 Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)
R-A R01.11 2RC-31-03 2RC14AB-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-31-04 2RC14AB-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-31-05 2RC14AB-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-31-06 2RC14AB-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-31-07 2RC14AB-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-31-08 2RC14AB-2" 13R-01 NOTE 17 VT-2 NRI PIPE - VALVE 2fRC8039B VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-31-09 2RC14AB-2" 13R-01 NOTE 17 VT-2 NRI VALVE 2RC8039B - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-31-09A.01 2RC14AB-2" 13R-01 NOTE 17 VT-2 NRI PIPE - TEE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-31-09B.01 2RC14AB-2" 13R-01 NOTE 17 VT-2 NRI TEE - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-31-09C.01 2RC86AB-2" 13R-01 NOTE 17 VT-2 NRI TEE - 2"X1" REDUCER VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-31-10 2RC14AB-2" 13R-01 NOTE 17 VT-2 NRI PIPE - TEE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-31-11 2RC15AB-2" 13R-01 NOTE 17 VT-2 NRI TEE - 2"X.75" REDUCER VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-31-12.01 2RC14AB-2" 13R-01 NOTE 17 VT-2 NRI TEE - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.20 2RC-31-14 2RC26A-2" 13R-01 NOTE 17 VT-2 NRI BRANCH CONNECTION - PIPE VT-2 performed during ascending Mode 3/system leakage test.
Page 3-12
Exem n.
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)
Sctio~nXI Compone~nt I0/D Line Number Relief Technica[ Code
ýRequired Actual~
Results KCat.
Descriptionr, Requests Notes" Covierage 'Exam Exam R-A R01.20 2RC-31-15 2RC26A-2" 13R-01 NOTE 17 VT-2 NRI PIPE - VALVE 2RC8057 VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-37-07A.01 2RC14AD-2" 13R-01 NOTE 17 VT-2 NRI PIPE - TEE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-37-07B.01 2RC14AD-2" 13R-01 NOTE 17 VT-2 NRI TEE - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-37-07C.01 2RC14AD-2" 13R-01 NOTE 17 VT-2 NRI TEE - 2"X1" REDUCER VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-37-08 2RC14AD-2" 13R-01 NOTE 17 VT-2 NRI PIPE - TEE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-37-09 2RC14AD-2" 13R-01 NOTE 17 VT-2 NRI TEE - 2"X.75" REDUCER VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-37-10 2RC14AD-2" 13R-01 NOTE 17 VT-2 NRI TEE - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-37-11 2RC14AD-2" 13R-01 NOTE 17 VT-2 NRI
-PIPE - VALVE 2RC8037D VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-41-03 2RC16AA-2" 13R-01 NOTE 17 VT-2 NRI VALVE 2RC8038A - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-41-04 2RC16AA-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-41-05 2RC16AA-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-41-06 2RC16AA-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-41-07 2RC16AA-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-41-08 2RC16AA-2" 13R-01 NOTE 17 VT-2 NRI PIPE - BRANCH CONNECT.
VT-2 performed durinl ascendinq Mode 3/system leakaQe test.
Page 3-13
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)
R-A R01.11 2RC-41-11 2RC16AB-2" 13R-01 NOTE 17 VT-2 NRI VALVE 2RC8038B - PIPE VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-41-12 2RC16AB-2" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW VT-2 performed during ascending Mode 3/system leakage test.
R-A R01.11 2RC-41-13 2RC16AB-2" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE VT-2 performed during ascending Mode 3/system leakage test.
NA RG 1.14 2RCP-01-FLYWHEEL 2RCP01A NOTE 18 100 SUR PT NRI (PMP A)
RCP PUMP "A" FLYWHEEL NDE of 2A RCP flywheel completed during MMD overhaul under WO# 1202554.
B-G-2 B07.60 2RCP-01-PSB-PB-B1 2RC01PB NOTE 03 VT-1 VT-1 NRI PUMP SHAFT SEALS (12 BOLTS)
NOTE 16 VT-1 during RCP seal replacement under WO# 1259851.
B-G-1 B06.180 2RCP-01-RCP-PA-01 TO 2RC01PA NOTE03 100 VOL UT-0 NRI 24 RCP MAIN FLANGE BOLT (01 TO 24)
NOTE 15 UT of 2A RCP main flange cap screws in place. This satisfies the B-G-1 Item B6.180 volumetric interval requirement for the Unit 2 reactor coolant pumps per B-G-1 Note (3).
N-722 B15.090 2RV-01-022 N-722 2RC01R NOTE 14 Visual, VE BMV NRI NOZZLE - SAFE END (22 DEG.)
NOTE 17 MRP-139 Visual, VE examination after mirror insulation was removed. No pressure boundary leakage noted. Minor stain noted on surface of floor around base of NI detector, likely from past nozzle cover gasket leakage.
N-722 B15.090 2RV-01-025 N-722 2RC01R NOTE 14 Visual, VE BMV NRI NOZZLE - SAFE END (158 DEG.)
NOTE 17 MRP-139 Visual, VE examination after mirror insulation was removed. No pressure boundary leakage noted.
N-722 B15.090 2RV-01-026 N-722 2RC01R NOTE 14 Visual, VE BMV NRI NOZZLE - SAFE END (202 DEG.)
NOTE 17 MRP-139 Visual, VE examination after mirror insulation was removed. No pressure boundary leakage noted.
N-722 B15.090 2RV-01-029 N-722 2RC01R NOTE 14 Visual, VE BMV NRI NOZZLE - SAFE END (338 DEG.)
NOTE 17 MRP-139 Visual, VE examination after mirror insulation was removed. No pressure boundary leakage noted.
B-G-2 B07.10 2RV-03-74 CETNA 2RC01R SUR VT-1 NRI CLAMP BOLTING INCORE THERMOCOUPLE CLAMP (Pen. #74)
VT-1 performed prior to reassembly under WO# 1236929 during inspection of 2RV-03-RVLIS BOLTING (NORTH) AND 2RV-03-RVLIS BOLTING SOUTH.
Page 3-14
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)
B-G-2 B07.10 2RV-03-75 CETNA 2RC01R SUR VT-1 NRI CLAMP BOLTING INCORE THERMOCOUPLE CLAMP (Pen. #75)
VT-1 performed prior to reassembly under WO# 1236929 during inspection of 2RV-03-RVLIS BOLTING (NORTH) AND 2RV-03-RVLIS BOLTING SOUTH.
B-G-2 B07.10 2RV-03-76 CETNA 2RC01R SUR VT-1 NRI CLAMP BOLTING INCORE THERMOCOUPLE CLAMP (Pen. #76)
VT-1 performed prior to reassembly under WO# 1236929 during inspection of 2RV-03-RVLIS BOLTING (NORTH) AND 2RV-03-RVLIS BOLTING SOUTH.
B-G-2 B07.10 2RV-03-77 CETNA 2RC01R SUR VT-1 NRI CLAMP BOLTING INCORE THERMOCOUPLE CLAMP (Pen. #77)
VT-1 performed prior to reassembly under WO# 1236929 during inspection of 2RV-03-RVLIS BOLTING (NORTH) AND 2RV-03-RVLIS BOLTING SOUTH.
B-G-2 B07.10 2RV-03-78 CETNA 2RC01R SUR VT-1 NRI CLAMP BOLTING INCORE THERMOCOUPLE CLAMP (Pen. #78)
VT-1 performed prior to reassembly under WO# 1236929 during inspection of 2RV-03-RVLIS BOLTING (NORTH) AND 2RV-03-RVLIS BOLTING SOUTH.
NA 1-600 2RV-03-HEAD 2RC01R Visual, VE VT-2 NRI N-729-1 REACTOR HEAD SURFACE Opened doors and performed examination during descending Mode 3 GL 88-05 inspection and and ascending Mode 3 system leakage test.
B-G-2 B07.10 2RV-03-RVLIS BOLTING 2RC01R SUR VT-1 NRI (NORTH)
NORTH RVLIS ASSEMBLY VT-i performed prior to reassembly under BwMP 3300-075 in WO# 1236929-29.
B-G-2 B07.10 2RV-03-RVLIS BOLTING 2RC01R VT-1 VT-1 NRI (SOUTH)
SOUTH RVLIS ASSEMBLY VT-1 performed prior to reassembly under BwMP 3300-075 in WO# 1236929-29.
N-722 B15.120 2SG-01-2RC01BA DRAIN Visual, VE BMV NRI DRAIN LINE STEAM GENERATOR BOWL DRAIN LINE Performed examination during descending Mode 3 GL 88-05 inspections after mirror insulation was removed.
B-Q B16.20 2SG-01-2RC01BA 2RC01BA VOL ET NRI TUBING STEAM GENERATOR TUBING See Section 2.5 of report for details of examination, tube plugging was not required for this steam generator.
N-722 B15.120 2SG-02-2RCOIBB DRAIN Visual, VE BMV NRI DRAIN LINE STEAM GENERATOR BOWL DRAIN LINE CONNECTION Performed examination during descending Mode 3 GL 88-05 inspections after mirror insulation was removed.
Page 3-15
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RC)
B-Q B16.20 2SG-02-2RC01BB 2RC01BB VOL ET IND TUBING STEAM GENERATOR TUBING See Section 2.5 of report for details of examination, tube plugging was performed in the hot leg and cold leg ends of the following tubes:
Row 13, Column 38; Row 30, Column 56; Row 21, Column 65; Row 19, Column 67; Row 41, Column 45 N-722 B15.120 2SG-03-2RC01BC DRAIN Visual, VE BMV NRI DRAIN LINE STEAM GENERATOR BOWL DRAIN LINE Performed examination during descending Mode 3 GL 88-05 inspections after mirror insulation was removed.
B-Q B16.20 2SG-03-2RC01BC 2RC01BC TUBING STEAM GENERATOR TUBING VOL ET IND See Section 2.5 of report for details of examination, tube plugging was performed in the hot leg and cold leg ends of the following tube:
Row 10, Column 3 N-722 B15.120 2SG-04-2RC01BD DRAIN Visual, VE BMV NRI DRAIN LINE STEAM GENERATOR BOWL DRAIN LINE CONNECTION Performed examination during descending Mode 3 GL 88-05 inspections after mirror insulation was removed.
B-Q B16.20 2SG-04-2RC01BD 2RC01BD VOL ET NRI TUBING STEAM GENERATOR TUBING See Section 2.5 of report for details of examination, tube plugging was not required for this steam generator.
Page 3-16
Exeloin-Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Residual Heat Removal System (RH)
C-A C01.10 2RHX-01-2RHEC-01 (A 2RH02AA NOTE 17 VOL UT-45 NRI HX)
FLANGE - HX SHELL NOTE 30 N-706 Performed length resizing of Indication #2 previously recorded in Data Sheet A2R13-UT-016 during the A2R13 outage due to documented flaw size exceeding acceptance criterial of NC-5300 of ASME Section III 1974 Edition (reference Issue Report 979896).
Indication was documented as 0.500" long in A2R13, and was sized conservatively (applied 20% DAC recording criteria instead of ASME Section XI 50% criteria). Indication was resized using a 3/8" diameter 2.25 MHz 45 degree shear wave and a 3/8" 5.0 MHz 45 degree shear wave transducer. Indication was sized as 0.300" long with the 2.25MHz tranducer and 0.200" long using the 5.0 MHz transducer.
Reference 10/16/2009 memo from Jay Miller (Exelon Level III UT Examiner) to Brendan Casey (ISI Program Owner).
C-C C03.10 2RHX-01-2RHES-01 (A 2RH02AA NOTE 17 100 SUR PT NRI HX)
BOTTOM HEAD - SUPPORT SKIRT NOTE 29 N-700 Page 3-17
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Reactor Coolant System (RY)
B-K B10.10 2PZR-01-07 2RY01S NOTE 17 100 SUR MT NRI PRESSURIZER SUPPORT SKIRT ATT.
NOTE 29 N-700 Code Case N-700 applied.
B-B B02.11 2PZR-01-08A 2RY01S NOTE 17 95.57 VOL UT-0 NRI SHELL - LOWER HEAD UT-45 UT-60 Limitations due to weld pads.
B-B B02.12 2PZR-01-09A 2RY01S NOTE 17 100 VOL UT-0 NRI SHELL LONG SEAM UT-45 UT-60 Twelve inches of longitudinal seam weld.
B-G-2 B07.50 2RC-32-85 2RY03BB-6" SUR VT-1 NRI INLET FLANGE 2RY801OB (12 STUDS)
Performed VT-1 of 2RY801OB inlet flange hydranuts during valve replacement under WO# 991964-01.
B-G-2 B07.50 2RC-32-B6 2RY03BC-6" SUR VT-1 NRI INLET FLANGE 2RY8010C (12 STUDS)
Performed VT-1 of 2RY8010C inlet flange hydranuts during valve replacement under WO# 991965-01.
Page 3-18
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Safety Injection System (SI)
Sciond4~i XI Component ID
. LIine Number Relief
'Technical Co~de Required ýActual
~
esults Cat.
Descriptionj Requests Notes Coverage Exam
~1/2Exam~
R-A R01.11 2SI-20-04 2SI08JC-1.5" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-05 2SI08JC-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-06 2SIO8JC-1.5" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-07 2SI08JC-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-09 2SIO8JC-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - FLANGE Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-10 2SIO8JC-1.5" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-11 2SIO8JC-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-12 2SI08JC-1.5" 13R-01 NOTE 17 VT-2 NRI VALVE 2SI8810C - PIPE Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-13 2SI08JC-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - VALVE 2SI8810C Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-14 2SI08JC-1.5" 13R-01 NOTE 17 VT-2 NRI 2"X1.5" REDUCER - PIPE Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-15 2SI08HC-2" 13R-01 NOTE 17 VT-2 NRI COUPLING - 2"X11/2" REDUCER Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2S1-20-20 2SI08HC-2" 13R-01 NOTE 17 VT-2 NRI 2"X1.5" REDUCER - COUPLING Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-21 2SI08GC-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - 2"X11/" REDUCER Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-22 2SI08GC-1.5" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE Performed VT-2 durinq 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI proqram.
Page 3-19
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.1 Detailed Third Interval Inservice Inspection Weld Table SYSTEM: Safety Injection System (SI) jSect-ionXI C ompo 'nent ID~
LieNme Relief Techiiical Codes Required iActuial Results Cat~'.
Description
'Rqet oe oeaeExam Exam R-A R01.11 2SI-20-23 2SI08GC-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-24 2SI08GC-1.5",
13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-informed ISI program.
R-A R01.11 2SI-20-25 2SI08GC-1.5" 13R-01 NOTE 17 VT-2 NRI
. PIPE - ELBOW Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-27 2SI08GD-1.5" 13R-01 NOTE 17 VT-2 NRI COUPLING - PIPE Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-28 2SI08GD-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-29 2SI08GD-1.5" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-30 2SI08GD-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - ELBOW Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-31 2SI08GD-1.5" 13R-01 NOTE 17 VT-2 NRI ELBOW - PIPE Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
R-A R01.11 2SI-20-32 2SI08GD-1.5" 13R-01 NOTE 17 VT-2 NRI PIPE - 2"Xl 1/2" REDUCER Performed VT-2 during 2BwOSR 5.5.8.CV-8 for Risk-Informed ISI program.
B-G-2 B07.50 2SI-20-B2 2SI08HC-2" SUR VT-1 NRI FLANGED CONNECTION (8 STUDS)
Performed VT-1 of all bolting materials while connection was disassembled under WO# 1132409 to replace gasket.
Page 3-20
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.2 Detailed Third Interval Preservice Weld / Component Table SYSTEM: Reactor Coolant System (RC)
Section XI ~Component ID Line Number Relief Technical Code~
Required Actualq Results
>Cat.
ltemt Descrption RquestsNotes CoeaeEa Exam:W B-G-2 B07.50 2RC-23-B1 2RC22AA-1.5'"
SUR VT-1 NRI FLANGED CONNECTION (4 STUDS)
Preservice VT-1 of replacement bolting for connection 2RC-23-B1 disassembled under WO# 1131570-01.
Page 3-21
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Component Support Table SYSTEM: Containment Spray System (CS)
F-A F01.20 2CS03011X Strut Remote exam (15' away) performed using binoculars.
F-A F01.20 2CS03024R Strut Remote exam (20' away) performed using binoculars.
F-A F01.20 2CS03032V (1) Variable Spring Can F-A F01.20 2CS03084R Box F-A F01.20 2CS03086G Box F-A F01.20 2CS03097X Box F-A F01.20 2CS06033A Anchor, inteqrally attached to pipe 2CS02AA-10" VT-3 NRI 2CS02AB-10" VT-3 NRI 2CS1 OAA-6" 2CS02AA-1 0" 2CS10AA-6" 2CS10AA-6" 2CS06AA-6" VT-3 Vr-3 VT-3 VT-3 VT-3 NRI NRI NRI NRI NRI Page 3-22
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Component Support Table SYSTEM: Chemical & Volume Control System (CV)
Ke-ction XI IStIIdentifier Line Nu~mber' Relief Technical c
AtuaI Results
!Cat.'i~ >>
Ite Decrpto Requests Notes
~Exam F-A F01.10 2CV16031X 2CVA3B-2" VT-3 NRI Strut F-A F01.10 2CV16041R 2CVA3B-2" VT-3 NRI Box F-A F01.10 2CV16075R 2CVA3AB-2" VT-3 NRI Strut F-A F01.10 2CV16083R 2CVA3B-2" VT-3 NRI Strut F-A F01.10 2CV22005G 2CV45B-2" VT-3 NRI Box F-A F01.10 2CV22011X 2CV45B-2" VT-3 NRI Strut F-A F01.10 2CV22016A 2CV45B-2" VT-3 NRI Anchor Page 3-23
Exeoi n-Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Component Support Table SYSTEM: Feedwater System (FW)
F-A F01.20 2AF04069R 2FW81AB-6" VT-3 NRI Strut F-A F01.20 2AF04076X 2FW81 AB-6" VT-3 NRI Strut Sample expansion from 2AF07030X (reference IR 952591).
F-A F01.20 2AF05061R 2FW81AC-6" VT-3 NRI Rod F-A F01.20 2AF05063X 2FW81 AC-6" VT-3 NRI Strut Sample expansion from 2AF07030X (reference IR 952591).
F-A F01.20 2AF06039X 2FW81AA-6" VT-3 NRI Strut Sample expansion from 2AF07030X (reference IR 952591).
F-A F01.20 2AF07028V 2FW81AD-6" VT-3 NRI (2) Variable Spring Cans WELDED ATTACHMENTS PAINTED.
F-A F01.20 2AF07030X 2FW81AD-6" VT-3 IND Strut Pipe clamp was discovered loose and could be rotated on pipe due to clamp spacer being too long (reference IR 952591). Support corrected under WO# 1261700. Sample expansion performed on adjacent supports 2AF07031 R and 2PC076A as well as additional supports 2AF04076X, 2AF05063X, 2AF06039X, 2AF07040G, 2FW06006X, 2FW06015X, 2FW09012X, and 2FW09015X.
F-A F01.20 2AF07031R 2FW81 AD-6" VT-3 NRI Rod Sample expansion from 2AF07030X (reference IR 952591).
F-A F01.40 2AF07040G 2FW81AD-6" VT-3 NRI (2) Struts, Attached to Valve 2FW039D Sample expansion from 2AF07030X (reference IR 952591).
F-A F01.20 2FW02008R 2FW03DA-16" VT-3 NRI Slide Plate F-A F01.20 2FW02020X 2FW03DA-16" VT-3 NRI Box F-A F01.20 2FW03007V 2FW03DB-16" VT-3 NRI (1) Variable Spring Can F-A F01.20 2FW04008V 2FW03DC-16" VT-3 NRI (1) Variable Spring Can F-A F01.20 2FW05002R 2FW03DD-16" VT-3 NRI Strut F-A F01.20 2FW06006X 2FW87CA-6" VT-3 NRI Strut Sample expansion from 2AF07030X (reference IR 952591).
F-A F01.20 2FW06011X 2FW87CA-6" VT-3 NRI Strut Remote exam (10' away).
Page 3-24
Exelein-Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Component Support Table SYSTEM: Feedwater System (FW)
F-A F01.20 2FW06015X 2FW87CA-6" VT-3 NRI Strut Sample expansion from 2AF07030X (reference IR 952591).
F-A F01.20 2FW07015X 2FW87CB-6" VT-3 NRI Strut F-A F01.20 2FW07016V 2FW87CB-6" VT-3 NRI (1) Variable Spring Can Remote exam (7' away).
F-A F01.20 2FW08010R 2FW87CC-6" VT-3 NRI Box Remote exam.
F-A F01.20 2FW08011X 2FW87CC-6" VT-3 NRI Box Remote exam.
F-A F01.20 2FW08012R 2FW87CC-6" VT-3 NRI Strut Remote exam.
F-A F01.20 2FW09012X 2FW87CD-6" VT-3 NRI Strut Sample expansion from 2AF07030X (reference IR 952591).
F-A F01.20 2FW09015X 2FW87CD-6" VT-3 NRI Strut Sample expansion from 2AF07030X (reference IR 952591).
F-A F01.20 2PC-076A 2FW03DD-16" VT-3 NRI Anchor, Flued Head Sample expansion from 2AF07030X (reference IR 952591).
Page 3-25
t~xe1, 'n-Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Component Support Table SYSTEM: Main Steam System (MS)
F-A F01.20 2MS05002C 2MS01AA-30.25" VT-3 NRI (2) Constant Spring Cans, IWA to pipe Page 3-26
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Component Support Table SYSTEM: Reactor Coolant System (RC)
F-A F-A F-A F-A F-A F-A F-A F-A F-A F-A F-A F01.10 2CV06020C (1) Constant Spring Can F01.10 2RC01004V (1) Variable Spring Can F01.10 2RC04001V (1) Variable Spring Can F01.10 2RC16104X Box F01.10 2RC16116R Box F01.10 2RC17054X Box F01.10 2RC17056R Box F01.10 2RC18031G Box F01.10 2RC18033R Box F01.10 2RC19051G U-Bolt F01.10 2RC19053X Strut 2RC36A-3" 2RC21AA-8" 2RC21 BD-8" 2RC22AA-1.5" 2RC22AA-1.5" 2RC22AB-1.5" 2RC22AB-1.5" 2RC22AC-1.5" 2RC22AC-1.5" 2RC22AD-i.5" 2RC22AD-1.5" VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 NRI NRI NA NRI NRI NRI NRI NRI NRI NRI NRI Page 3-27
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.3 Detailed Third Interval Inservice Component Support Table SYSTEM: Safety Injection System (SI)
F-A F01.10 2RH02038X 2SIA48-8" VT-3 NRI Strut Page 3-28
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.4 Detailed Preservice Component Support Table SYSTEM:
F-A F01.20 2AF07030X 2FW81 AD-6" VT-3 NRI Strut Post maintenance VT-3 after corrective measures under WO# 1261700-01 were completed.
Page 3-29
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM: Chemical & Volume Control System (CV)
NA NA 2CV02005S Snubber NA NA 2CV03002S Snubber NA NA 2CV04002S Snubber DTPG-2-1 (INITIAL SAMPLE)
NA NA 2CV07033S Snubber NA NA 2CV07068S Snubber DTPG-2-2 (INITIAL SAMPLE)
F-A F01.10 2CV09063S Snubber NA NA 2CV12017S Snubber DTPG-2-1 (INITIAL SAMPLE)
NA NA 2CV24024S Snubber F-A F01.10 2CV25009S Snubber NA NA 2CV29036S Snubber NA NA 2CV31007S Snubber NA NA 2CV31020S Snubber NA NA 2CV40005S Snubber NA NA 2CV4001 1S Snubber DTPG-2-1 (INITIAL SAMPLE)
NA NA 2CV41002S Snubber 2CV1 OCB-3" 2CV10CA-3" 2CV10B-3" 2CV01 E-3" 2CV01 DC-3" 2CVA6AA-2" 2CV43BA-2" NOTE 01 VT-3 NOTE 01 VT-3 NOTE 01 VT-3 FT NOTE 01 VT-3 NOTE 01 VT-3 FT NOTE 01 VT-3 NOTE 01 VT-3 FT" NOTE 01 VT-3 NOTE 01 VT-3 NOTE 01 VT-3 NOTE 01 VT-3 NOTE 01 VT-3 NOTE 01 VT-3 NOTE 01 VT-3 FT NOTE 01 VT-3 NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI 2CV43BB-2" 2CVA7AA-2" 2CV15AC-.75" 2CV15DA-.75" 2CV15E-.75" 2CV14EC-2" 2CV14EC-2" 2CV14ED-2" Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-30
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM: Feedwater System (FW)
F-A F01.20 2FW02016S 2FW03DA-16" NOTE 01 VT-3 NRI Snubber F-A F01.20 2FW03015S 2FW03DB-16" NOTE 01 VT-3 NRI Snubber F-A F01.20 2FW05011AS 2FW03DD-16" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
F-A F01.20 2FW05011BS 2FW03DD-16" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
F-A F01.20 2FW05014S 2FW03DD-16" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
F-A F01.20 2FW05017S 2FW03DD-16" NOTE 01 VT-3 NRI Snubber
- FT NRI DTPG-2-2 (INITIAL SAMPLE)
F-A F01.20 2FW07004S 2FW87CB-6" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
F-A F01.20 2FW07005S 2FW87CB-6" NOTE 01 VT-3 NRI Snubber F-A F01.20 2FW07006S 2FW87CB-6" NOTE 01 VT-3 NRI Snubber F-A F01.20 2FW08005S 2FW87CC-6" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
F-A F01.20 2FW08006S 2FW87CC-6" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-31
Exietz Yn.
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM:
Main Steam System (MS)
F-A F01.20 2MS06007AS Snubber, integrally attached to pipe F-A F01.20 2MS06007BS Snubber, integrally attached to pipe F-A F01.20 2MS08007AS Snubber, integrally attached to pipe DTPG-2-3 (INITIAL SAMPLE)
F-A F01.20 2MS08007BS Snubber, integrally attached to pipe DTPG-2-3 (INITIAL SAMPLE) 2MS01AB-32.75" NOTE 01 VT-3 NRI 2MS01AB-32.75" NOTE 01 VT-3 NRI 2MS01AD-30.25" NOTE 01 VT-3 NRI FT NRI 2MS01AD-30.25" NOTE 01 VT-3 NRI IFT NRI Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1 220 and IWF-2500 tables Page 3-32
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM: Reactor Coolant System (RC)
Section XI 1181 Identifier/
'j, Line Number Relief Technical Actual Results tC It.
Item Descript ion Request's Notes Exam
'comments F-A F01.10 2CV02003S 2RC37A-3" NOTE 01 VT-3 NRI Snubber FT NRI DTPB-2-2 (INITIAL SAMPLE)
F-A F01.10 2CV12002S 2RC16AA-2" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
F-A F01.40 2RC01BA-A S.G. A NOTE 01 VT-3 NRI Snubber F-A F01.40 2RC01BA-B S.G. A NOTE 01 VT-3 NRI Snubber F-A F01.40 2RC01BB-A S.G B NOTE 01 VT-3 NRI Snubber F-A F01.40 2RC01BB-B S.G B NOTE 01 VT-3 NRI Snubber F-A F01.40 2RC01BC-A S.G C NOTE 01 VT-3 NRI Snubber F-A F01.40 2RC01BC-B S.G C NOTE 01 VT-3 NRI Snubber F-A F01.40 2RC01BD-A S.G D NOTE 01 VT-3 NRI Snubber FT NRI F-A F01.40 2RC01BD-B S.G D NOTE 01 VT-3 NRI Snubber F-A F01.10 2RC03007S 2RC21AC-8" NOTE 01 VT-3 NRI Snubber F-A F01.10 2RC04005S 2RC21AD-8" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
F-A F01.10 2RC16114S 2RC22AA-1.5" NOTE 01 VT-3 NRI Snubber FT MARG DTPG-2-1 (INITIAL SAMPLE) Snubber Serial Number 2419 met Functional Test Acceptance Criteria but showed exhibited marginal test results during the running drag test and was therefore replaced with Serial Number 42808. Pre-Service functional test was performed on snubber (S.N. 42808).
F-A F01.10 2RC16119S 2RC22AA-1.5" NOTE 01 VT-3 NRI Snubber NA NA 2RC1 7069S 2RC20AB-.75" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-1 (INITIAL SAMPLE)
Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-33
Exek n.
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM: Reactor Coolant System (RC)
NA NA 2RC1 8037S 2RC08AC-.75" NOTE 01 VT-3 NRI Snubber F-A F01.10 2RC19054S 2RC22AD-1.5" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-1 (INITIAL SAMPLE)
NA NA 2RC1 9060S 2RC20AD-.75" NOTE 01 VT-3 NRI Snubber Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-34
-Explon.
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM: Residual Heat Removal System (RH)
F-A F01.10 2RH02012S 2RHO1AB-12" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
F-A F01.10 2RH02013S 2RH01AB-12" NOTE 01 VT-3 NRI Snubber F-A F01.10 2RH02054S 2RH01AA-12" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
NA NA 2RH02215S 2RH26AB-.75" NOTE 01 VT-3 NRI Snubber FT NRI RETEST OF FAILURE FROM PREVIOUS TEST PERIOD (A2R13)
NA NA 2RH02218S 2RH26AB-.75" NOTE 01 VT-3 NRI Snubber FT MARG Due to marginal functional test results identified during previous refuel outage (A2R13), snubber with serial number 2968 was replaced with snubber with serial number 42817 during A2R14. Replaced snubber was functionally tested during A2R14. All acceptance criteria was met. Replacement snubber (serial number 42817) was subjected to pre-service testing prior to installation. Reference Work Order 1132740.
F-A F01.20 2RH08030S 2RH02AB-8" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-1 (INITIAL SAMPLE)
Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-35
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM: Reactor Coolant System (RY)
F-A F01.10 2RY05010S 2RY11A-14" NOTE 01 VT-3 NRI Snubber F-A F01.10 2RY06020S 2RY01B-6" NOTE 01 VT-3 NRI Snubber F-A F01.10 2RY06025S 2RY01B-6" NOTE 01 VT-3 NRI Snubber F-A F01.10 2RY06076S 2RY01B-6" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-3 ASME CLASS 1 NA NA 2RY06125S 2RY09AB-.75" NOTE 01 VT-3 NRI Snubber F-A F01.10 2RY09012S 2RY06A-3" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
F-A F01.10 2RY09078S 2RY06A-3" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
F-A F01.10 2RY09100S 2RY02B-3" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
F-A F01.10 2RY09101S 2RY06A-3" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
Note: Section XI Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-36
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM: Steam Generator Blowdown System (SD)
NA NA 2SD06030S Snubber NA NA 2SD06032S Snubber NA NA 2SD06037S Snubber NA NA 2SD12048S Snubber NA NA 2SD12063S Snubber DTPG-2-1 (INITIAL SAMPLE) 2SD01CE-2" NOTE 01 2SD01CE-2" NOTE 01 2SD01 CE-2" NOTE 01 2SD01CG-2" NOTE 01 2SD01CG-2" NOTE 01 VT-3 VT-3 VT-3 VT-3 VT-3 FT NRI NRI NRI NRI NRI NRI NA NA 2SD24078S 2SD01CD-2" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-37
Exe I,ýr Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM: Safety Injection System (SI)
F-A F01.20 2RH02027S Snubber F-A F01.10 2RH02061S Snubber F-A F01.10 2RH02069S Snubber DTPG-2-2 (INITIAL SAMPLE)
F-A F01.10 2RH02078S Snubber F-A F01.20 2SI09002S Snubber F-A F01.10 2SI09014AS Snubber DTPG-2-2 (INITIAL SAMPLE) 2SI04C-8" NOTE 01 2SI04D-8" NOTE 01 2SI04D-8" NOTE 01 VT-3 NRI VT-3 NRI VT-3 NRI FT NRI VT-3 NRI VT-3 NRI VT-3 NRI FT NRI 2SIA4B-8" 2S109BC-1 0" 2SI05DC-6' NOTE 01 NOTE 01 NOTE 01 F-A F01.10 2SI09014BS 2SI05DC-6" NOTE 01 VT-3 NRI Snubber FT NRI DTPG-2-2 (INITIAL SAMPLE)
NA NA 2SI16038S 2SI18EC-2" NOTE 01 VT-3 NRI Snubber Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-38
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.5 Detailed Third Interval Inservice Snubber Table SYSTEM: Essential Service Water System (SX)
F-A F01.20 2SX09038S 2SX07CB-10" NOTE 01 VT-3 NRI Snubber Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-39
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.6 Detailed Third Interval Preservice Snubber Table SYSTEM: Reactor Coolant System (RC)
F-A F01.10 2RC16114S 2RC22AA-1.5" NOTE 01 FT PASS Snubber VT-3 Existing snubber (PSA 1/4, Serial Number 2419) passed functional test with marginal results (reference IR 978918) and was proactively replaced with a tested spare (Serial Number 42808)..
Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-40
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.6 Detailed Third Interval Preservice Snubber Table SYSTEM:
Residual Heat Removal System (RH)
NA NA 2RH02218S 2RH26AB-.75" NOTE 01 FT PASS Snubber VT-3 NRI Existing PSA 1/4 snubber (Serial Number 2968) passed functional test with marginal results and was replaced with a new tested spare (Serial Number 42817).
Note: Section Xl Category numbers identified as "N/A" are exempt from IWF-1220 and IWF-2500 tables Page 3-41
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.7 Detailed Third Interval Pressure Tests SYSTEM: Auxiliary Feedwater System (AF)
SetonX bomponenti ID
-+K
- 4UtW t
Relief
~ Technical. Required Results Cat Ite Inspection Notes RV~1/2 equests Notes Exam ~
Com~ments C-H C07.10 A02AF-000005-M04-02C VT-2 NRI Period ASME Section Xl Pressure Test.
No recordable indication noted during VT-2 performed in conjunction with surveillances 2BwOSR 5.5.8.AF-4A and 2BwOSR 5.5.8.AF-4B.
Page 3-42
.Exqion-Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.7 Detailed Third Interval Pressure Tests SYSTEM: Plant Systems Pressurized During Mode 3 (ZZ)
Secio X1': Comp onent ID Reliefi Req ire Results B-P B15.10 A02ZZ-000005-M04-01A NOTE 22 VT-2 NRI Each Refueling Outage Generic Letter 88-05 Examinations Class 1:
NOTE 23 PMID 55141-03. Class 2 and 3: PMID96032-17.
System leakage test performed under WO# 1138072. No recordable indications noted.
C-H C07.10 A02ZZ-000078-M04-03A NOTE 22 VT-2 RI Period ASME Section Xl Pressure Test. All Class 2 components inside containment. VT-2 visual inspection of components outside Missile Barrier may be performed during Mode 1/3 if conditions permit. Valve in EX and LTD HX'ers when perform.
System leakage test performed under WO 01138410. Active pressure boundary leakage identified at valve 2CV8321A on the packing leak off line (ref. IR 00986349). Valve 2CV8321A, associated with the 2A Regenerative Heat Exchanger, isolated pending corrective actions.
Page 3-43
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.8 Detailed Borated Bolted Connection Table SYSTEM: Chemical & Volume Control System (CV)
Ca.
te Dscipin eqess ots Exam*
C-H C07.10 2A-CV-26 F-2-1 (C-H)
VT-2 NRI FLANGED CONNECTION (8 STUDS)
B-P B15.10 2CV-03-Bl (B-P)
VT-2 NRI FLANGED CONNECTION (4 STUDS)
C-H C07.10 2CV04AA (C-H)
VT-2 NRI 2CV04AA HX (28 STUDS)
Scope of examination included head to shell connection, inlet connection, and outlet connection.
C-H C07.10 2CV04AB (C-H)
VT-2 NRI 2CV04AB HX (28 STUDS)
Scope of examination included head to shell connection, inlet connection, and outlet connection.
C-H C07.10 2CV-21 F-1-1 (C-H)
VT-2 NRI FLANGED CONNECTION (8 STUDS)
.C-H C07.10 2CV-21 F-3-2 (C-H)
VT-2 NRI FLANGED CONNECTION (8 STUDS)
C-H C07.10 2CV-26 F-1-2 (C-H)
VT-2 NRI FLANGED CONNECTION (8 STUDS)
B-P B15.10 PG-2546C-214 F-2-2 (B-P)
VT-2' NRI FLANGED CONNECTION (4 STUDS)
C-H C07.10 PG-2546C-222 F-2-4 (C-H)
VT-2 NRI FLANGED CONNECTION (4 STUDS)
C-H C07.10 PG-2546C-241 F-1-1 (C-H)
VT-2 RI FLANGED CONNECTION (4 STUDS)
VT-3 NRI VT-2 NRI Less than 1 Teaspoon of dry boric acid residues identified at connection. Residues were not in contact with bolting in the as found condition. Connection is for Flow Orifice 2FE-01 60. Connection was cleaned and VT-3 was performed on bolting in the assembled condition. No evidence of degradation identified. Post cleaning VT-2 Exam performed. No leakage / degradation identified. Evaluation completed in accordance with ER-AP-331-1002. Reference Issue Report Number 981057.
C-H C07.10 PG-2546C-262 F-1-3 (C-H)
VT-2 NRI FLANGED CONNECTION (4 STUDS)
C-H C07.10 PG-2546C-262 F-2-2 (C-H)
VT-2 NRI FLANGED CONNECTION (4 STUDS)
C-H C07.10 PG-2546C-263 F-1 (C-H)
VT-2 NRI FLANGED CONNECTION (4 STUDS)
C-H C07.10 PG-2546C-269 F-1 (C-H)
VT-2 NRI FLANGED CONNECTION (4 STUDS)
C-H C07.10 PG-2546C-270 F-2-1 (C-H)
VT-2 NRI FLANGED CONNECTION (4 STUDS)
B-P 815.10 PG-2546C-271 F-2-3 (B-P)
VT-2 NRI FLANGED CONNECTION (4 STUDS)
C-H C07.10 PG-2546C-283 F-1 (C-H)
VT-2 NRI FLANGED CONNECTION (8 STUDS)
Page 3-44
_Exekrn.
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.8 Detailed Borated Bolted Connection Table SYSTEM: Chemical & Volume Control System (CV)
C-H C07.10 PG-2546C-285 F-1-3 (C-H)
VT-2 NRI FLANGED CONNECTION (4 STUDS)
C-H C07.10 PG-2546C-285 F-2-2 (C-H)
VT-2 NRI FLANGED CONNECTION (4 STUDS)
C-H C07.10 PG-2546C-289 F-1 (C-H)
VT-2 RI FLANGED CONNECTION (8 STUDS)
VT-3 NRI VT-2 NRI Less than 1 Teaspoon of dry boric acid residues identified at connection. Residues were not in contact with bolting in the as found condition. Connection is for Flow Orifice 2FE-0162. Connection was cleaned and VT-3 was performed on bolting in the assembled condition. No evidence of degradation identified. Post cleaning VT-2 Exam performed. No leakage / degradation identified. Evaluation completed in accordance with ER-AP-331-1002. Reference Issue Report Number 981011.
B-P 815.10 PG-2546C-301 F-2-2 (B-P)
VT-2 NRI FLANGED CONNECTION (4 STUDS)
C-H C07.10 PG-2546C-311 F-1-1 (C-H)
VT-2 NRI FLANGED CONNECTION (8 STUDS)
Page 3-45
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.8 Detailed Borated Bolted Connection Table SYSTEM: Reactor Coolant System (RC)
Sectio XI~
Component-ID, Relief iTechnical~ JActu~al Results ~
Cat. Item Desripton Rquets Ntes Exam B-P B15.10 2PZR-01-B1 (B-P)
VT-2 NRI MANWAY BOLTING (16 TOTAL)
B-P B15.10 2RC-20-B1 (B-P)
VT-2 NRI FLANGED CONNECTION (4 STUDS)
B-P B15.10 2RC-32-B4 (B-P)
VT-2 NRI FLANGED CONNECTION (12 STUDS)
B-P B15.10 2RC-32-B5 (B-P)
VT-2 NRI FLANGED CONNECTION (12 STUDS)
B-P B15.10 2RC-32-B6 (B-P)
VT-2 NRI FLANGED CONNECTION (12 STUDS)
B-P B15.10 2RV-03-STUDS (01 TO 54, B-P)
VT-2 NRI CLOSURE HEAD STUDS (54 TOTAL)
B-P B15.10 2SG-01-B1 (B-P)
VT-2 NRI 9A PRIMARY MANWAY (16 BOLTS)
B-P B15.10 2SG-01-B2 (B-P)
VT-2 NRI 9B PRIMARY MANWAY (16 BOLTS)
B-P B15.10 2SG-02-B1 (B-P)
VT-2 NRI 9A PRIMARY MANWAY (16 BOLTS)
B-P B15.10 2SG-02-B2 (B-P)
VT-2 NRI 9B PRIMARY MANWAY (16 BOLTS)
B-P B15.10 2SG-03-B1 (B-P)
VT-2 NRI 9A PRIMARY MANWAY (16 BOLTS)
B-P B15.10 2SG-03-B2 (B-P)
VT-2 NRI 9B PRIMARY MANWAY (16 BOLTS)
B-P B15.10 2SG-04-B1 (B-P)
VT-2 NRI 9A PRIMARY MANWAY (16 BOLTS)
B-P B15.10 2SG-04-B2 (B-P)
VT-2 NRI 98 PRIMARY MANWAY (16 BOLTS)
Page 3-46
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.1.8 Detailed Borated Bolted Connection Table SYSTEM: Residual Heat Removal System (RH)
SeG~--X--oponeiitID-Relief Technical Actual~
Results CtItm'escriton~
Requests Notes Exam CPomments
~
1W C-H C07.10 2RH01MA (C-H)
VT-2 NRI FLANGED CONNECTION (12 STUDS)
C-H C07.10 2RH-09 F-1 (C-H)
VT-2 NRI FLANGED CONNECTION (20 STUDS)
C-H C07.10 2RH-09 F-2 (C-H)
VT-2 NRI FLANGED CONNECTION (20 STUDS)
C-H C07.10 2RH-10 F-2-2 (C-H)
VT-2 NRI FLANGED CONNECTION (24 STUDS)
C-H C07.10 2RH-10 F-3-2 (C-H)
VT-2 NRI FLANGED CONNECTION (24 STUDS)
C-H C07.10. 2RH-10 F-4 (C-H)
VT-2 NRI FLANGED CONNECTION (8 STUDS)
C-H C07.10 2RH-11 F-1 (C-H)
VT-2 NRI FLANGED CONNECTION (12 STUDS)
C-H C07.10 2RH-12 F-1 (C-H)
VT-2 NRI FLANGED CONNECTION (12 STUDS)
C-H C07.10 2RH-12 F-2-1 (C-H)
VT-2 NRI FLANGED CONNECTION (12 STUDS)
C-H C07.10 2RH-12 F-3-1 (C-H)
VT-2 RI FLANGED CONNECTION (12 STUDS)
VT-3 NRI VT-2 NRI Less than 1 Teaspoon of dry boric acid residues identified at connection. Residues were not in contact with bolting in the as found condition. Components cleaned, VT-3 Exam performed on bolting in the assembled condition. No degradation identified. Condition evaluated in accordance with ER-AP-331-1002 as acceptable. Reference Issue Report 983679.
C-H C07.10 2RH-12 F-4-1 (C-H)
VT-2 NRI FLANGED CONNECTION (12 STUDS)
C-H C07.10 2RH-12 F-5 (C-H)
VT-2 NRI FLANGED CONNECTION (8 STUDS)
C-H C07.10 2RH-13 F-1 (C-H)
VT-2 NRI FLANGED CONNECTION (20 STUDS)
C-H C07.10 2RH-13 F-2 (C-H)
VT-2 NRI FLANGED CONNECTION (20 STUDS)
C-H C07.10 2RH-13 F-3-1 (C-H)
VT-2 NRI FLANGED CONNECTION (8 STUDS)
Page 3-47
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.2 Detailed Second Interval System Pressure Tests SYSTEM: Auxiliary Feedwater System (AF)
C-H C07.40 A02AF-000005-M04-02C C07.80 Completed under WO# 811707, no recordable indications noted.
12R-05 NOTE17 VT-2 NRI 12R-13 Page 3-48
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.2 Detailed Second Interval System Pressure Tests SYSTEM: Component Cooling System (CC)
Section XI Component ID.............
Technical Required RIlesults Ca.Item, Inspection Notes Requests Notes Exam lComiments C-H C07.40 A02CC-000005-M04-02A 12R-05 NOTE17 VT-2 NRI C07.80 12R-13 Completed under WO# 859669, no recordable indications noted.
Page 3-49
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.2 Detailed Second Interval System Pressure Tests SYSTEM: Containment Spray System (CS)
C-H C07.20 A02CS-000005-M04-02A 12R-05 NOTE17 VT-2 IND.
C07.40 12R-13 C07.60 C07.80 Leakage indication at bolted connection for eductor 2CS01SA (IR 745929);
Informational indications noted at packing on valves 2CS035A (IR 745858), 2CS009A (IR 746504), and targets from spillage associated with vent valve 2CS084A (IR 746502)
C-H C07.20 A02CS-000005-M04-02B 12R-05 NOTE17 VT-2 IND.
C07.40 12R-13 C07.60 C07.80 Indications of leakage noted at bolted connection at spool piece (IRs 749741 and 749747), and eductor 2CS01 SB (IR 749775);
Informational leakage noted at packing on valves 2CS009B (IR 749767), 2CS027B (IR 749719), 2SIO01B (IR 746508), 2CS01OB (IR 749752), and manifold valve 2FT-CS014 (IR 744395).
C-H C07.20 A02CS-000005-M04-02C 12R-05 NOTE17 VT-2 NRI C07.40 12R-13 C07.80 Completed under WO# 973414, no recordable indications noted.
C-H C07.40 A02CS-000005-M04-02D 12R-05 NOTE17 VT-2 NRI C07.80 12R-13 Completed under WO# 1106369-01; no recordable indications noted.
C-H C07.40 A02CS-000005-M04-02E 12R-05 NOTE17 VT-2 NRI C07.80 12R-13 Completed under WO# 1106370-01, no recordable indications noted.
Page 3-50
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.2 Detailed Second Interval System Pressure Tests SYSTEM: Fire Protection System (FP)
C-H C07.40 A02FP-000005-M04-02B C07.80 Completed under WO# 1035876-01, no recordable indications noted.
12R-05 NOTE17 VT-2 NRI 12R-13 Page 3-51
Braidwood Station Unit 2 A2R14 ISI Outage Report Section 3.2 Detailed Second Interval System Pressure Tests SYSTEM: Essential Service Water System (SX)
Sectionor X
O 1008752-01 Relief r
aTechnicaiRediuited Results Cat~Iem Inspection Notes~
Rquests Notes Ea Comnts "A'C C-H C07.40 A02SX-000005-M04-02G 12R-05 NOTE17 VT-2 NRI C07.80 12R-13 Completed under WO# 1008752-01, no recordable indications noted.
C-H C07.40 A02SX-000005-M04-02H 12R-05 NOTE17 VT-2 NRI C07.80 12R-1 3 Completed under WO# 1008752-01, no recordable indications noted.
Page 3-52
Exelon.
Braidwood Station Unit 2 A2R14 ISI Outage Report 4.0 REPORT OF CONTAINMENT DEGRADATION Containment inspections are performed in accordance with Subsection IWE (Requirements for Class MC and Metallic Liners of Class CC Components of Light-Water Cooled Power Plants) and Subsection IWL (Requirements for Class CC Components of Light-Water Cooled Power Plants) of ASME Section Xl, Division 1, with specified modifications and limitations in 10 CFR 50.55a. The following sections are included in the Inservice Inspection Summary report to meet the reporting conditions specified in 10CFR 50.55a(b)(2)(ix)(A)(1) through (3). A limited scope of IWE inspections was completed during A2R14. 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 A2R14 and thus there are no results to report.
4.1 A2R14 Containment Metal Liner Examinations (IWE)
Augmented Section Xl IWE examinations of the Class CC liner examinations for the Third Interval were performed in accordance with the requirements of ASME Section Xl, Table IWE-2500-1, Category E-C, Containment Surfaces Requiring Augmented Examination.
Exelon Procedures ER-AA-330-007, "Visual Examination of ASME Section Xl Class MC Surfaces and Class CC Liners" and ER-AA-335-018, "Detailed, General Visual, VT-1, VT-iC, VT-3 and VT-3C, Visual Examination of ASME Class MC and CC Containment Surfaces and Components" 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 scheduled augmented VT-1 and UT examinations of the Unit 2 containment liner plate, liner pitting was observed in the surfaces just below the moisture barrier (MB). The observed pitting resulted in metal loss of varying depths (reference IRs 978989 and 980924) with the maximum pit depth identified as 6/64".
Extent of condition:
The maximum pit depth measured was 6/64" and was limited to one location (Location 40-1) based on Detail Visual (VT-1) examination of approximately 65 feet of liner plate. The area was dry and did not appear to be active. The initial examination scope was expanded to approximately an additional 18 feet of MB.
The scope expansion was limited to three areas. These three areas were the only areas with newly identified degradation exceeding 10% metal loss within the A2R14 scope of augmented areas. Two areas were examined, each over a Page 4-1
Exelon.
Braidwood Station Unit 2 A2R14 ISI Outage Report length of approximately five feet. Additional expansion of these areas was discontinued based on measuring a maximum pit depth of 1/64" over the entire approximate five feet of expansion of each area. A third area was examined over a length of approximately seven feet. This examination length contained a maximum pit depth of 4/64" but was discontinued when the final three feet of expansion contained pit depths of less than or equal to 1/64".
The engineering evaluation of the three areas described above concluded that a sufficient length of MB was removed during A2R14 to examine surfaces below the MB without requiring any additional removal of the MB.
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 CZ1 1 in the year 2000.
Carbo Zinc CZ1 1 does not tolerate improper surface preparation and is not recommended for use unless white metal surface condition with a contoured surface profile is achieved. Since this strip of liner plate below the MB is not easily accessible, it is likely that the proper surface preparation was not attained at some of these locations. Furthermore, the liner plate surface may not have been completely dried (some moisture left in the wall) when the MB was replaced in 2000. As such, the liner most likely experienced a slow chronic corrosion rate prior to 2000. After MB was removed and replaced in 2000, the bulk of the liner corrosion observed probably occurred in the early years after the 2000 MB replacement. It has conservatively assumed that the corrosion rate had a linear progression over the past nine years since 2000. The new Service Level I coating applied in A2R14 was Keeler and Long 9600 Series, which does not require a white metal surface condition prior to application.
Evaluation of each area, and the result of the evaluation
[10CFR 50.55a(b)(2)(ix)(A)(2)]:
Since the indications of degradation (pitting) were similar in each area inspected, one engineering evaluation was performed to address all the documented indications since the corrosion leading to the degraded condition is the same contributor affecting the same component (liner plate).
An evaluation was performed to determine an acceptable minimum liner thickness. Since the minimum measured liner thickness found during A2R14 were greater than the minimum acceptable liner plate thickness determined by this evaluation, the liner plate conditions were found acceptable for all degradations found during A2R14. Additionally, an assessment was performed of locations where the measured liner plate thickness was less than the nominal liner thickness of 0.25". The purpose of this assessment was to evaluate the rate of metal loss. This assessment concluded that the liner plate will continue to perform its intended design function without repair or replacement until at least the next scheduled refueling outage when additional examinations are scheduled.
Page 4-2
Exel n-Braidwood Station Unit 2 A2R14 ISI Outage Report Description of Necessary Corrective Actions Completed
[110CFR 50.55a(b)(2)(ix)(A)(3)]:
Based on the results for the initial examination of 65 feet, approximately 18 additional feet of MB was removed to expose the liner plate below the moisture barrier in order to perform examinations by the VT-1 method. The maximum pitting depth was measured at 4/64" for the additional MB removed. The total amount of MB removed during A2R14 including augmented areas and expanded areas was approximately 80 feet.
The liner surfaces at all the exposed locations where the moisture barrier had been removed were prepared for a new protective Service Level I coating which was applied during A2R14.
Engineering Evaluation (EC 377614) was completed and supports acceptability of the liner.
A General Visual exam was performed on the remaining surfaces of the MB and no tears were found.
Portions of Class CC liner below the MB have been categorized as Category E-C (Augmented) in accordance with IWE-1242 and the ISI schedule.
Planned Actions for A2R15 Additional examinations in the first period of the Third Interval (outage A2R15) will be required of liner plate at three locations: 40-1, N-7 and 3-9. These areas are scheduled for the A2R1 5 refueling outage (April 2011) to perform VT-1 and UT examinations. This action is tracked through ATI #983972-02.
IR #983972 was initiated to create an A2R15 work order for MB removal in order to support VT-1 and UT examinations and the reapplication of Service Level I coating at locations 40-1, N-7 and 3-9. It was determined in the engineering evaluation that these three areas shall be examined prior to the next inspection period based on projected metal loss.
The liner plate will continue to perform its intended design function without any repair or replacement until at least A2R15 when VT-1 and UT examinations are scheduled.
Conclusions/Findings As evaluated under EC 377614, the Unit 2 containment liner plate is acceptable and remains capable of performing its intended design function without repair or replacement.
Additionally, the UT results at points for augmented areas are acceptable and will continue to be classified as augmented items and subject to subsequent examinations in A2R15.
Page 4-3
Exelkmn Braidwood Station Unit 2 A2R14 ISI Outage Report 5.0 NIS-1 FORM As required by IWA-6000 of Section XI, this section contains the Owner's Report for Inservice Inspections, Form NIS-1, for the inservice examination of Class 1 and Class 2 pressure retaining components. Two Form NIS-1 are included, one for the Second ISI Interval which is now completed, and one for the Third ISI Interval.
Page 5-1
FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 1. Owner Exelon Generation Company (EGC, LLC), 200 Exelon Way, Kennett Square, PA, 19348 (Name and Address of Owner)
- 2. Plant Braidwood Station, 35100 South Route 53, Suite 84, Braceville, Illinois 60450 (Name and Address of Plant)
- 3. Plant Unit 2
- 4. Owner Certificate of Authorization (if required)
Not Applicable
- 5. Commercial Service Date 10/17/1988
- 6. National Board Number for Unit N-197
- 7. Components Inspected See Section 3 of this report for all components (report is a total of 105 pages).
Component or Manufacturer Manufacturer State or National Appurtenance Or Installer or Installer Province No.
Board No.
Serial No.
See Section 2.4.1 and associated table for the remaining Class 2 pressure test blocks examined for the third period of the Second Interval ISI Program.
Page 5-2
FORM NIS-1 (Back)
- 8.
Examination Dates:
June 16, 2008 to October 16, 2008
- 9.
Inspection Period Identification:
3d Period, Second Interval - From July 29, 2005 through October 16, 2008
- 10.
Inspection Interval Identification:
2 nd Interval - From July 29, 1998 through October 16, 2008
- 11.
Applicable Edition of Section XI 1989 Edition Addenda No Addenda
- 12.
Date/Revision of Inspection Plan:
June 29, 2009 / Revision 1Of
- 13.
Abstract of Examination and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan.
See Attached Sections 2 and 3.
- 14.
Abstract of Results of Examinations and Tests.
See Attached Sections 2 and 3.
- 15.
Abstract of Corrective Measures.
See Attached Sections 2 and 3.
We certify that a) the statements made in this report are correct, b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xl, and c) corrective measures taken conform to the rules of the ASME Code, Section Xl.
Certificate of Authorization No. (if applicable)
Not Applicable Expiration Date Not Applicable Date
.Ja*ALaJ2lryc 1
20 10 Signed Exelon Nuclear Braidwood Station By ~
Owner~
Braidwood ISI 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 La-ti.-
to vo-1_o,',
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.
Commissions 1--3*
91Se -
o5 KI.
Ce Inspector's Signature Date 01 - I,t -
National Board, State, Province, and Endorsements 20 k ::
Page 5-3
FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 1. Owner Exelon Generation Company (EGC, LLC), 200 Exelon Way, Kennett Square, PA, 19348 (Name and Address of Owner)
- 2. Plant Braidwood Station, 35100 South Route 53, Suite 84, Braceville, Illinois 60450 (Name and Address of Plant)
- 3. Plant Unit 2
- 4. Owner Certificate of Authorization (if required)
Not Applicable
- 5. Commercial Service Date 10/17/1988
- 6. National Board Number for Unit N-197
- 7. Components Inspected See Section 3 of this report for all components (report is a total of 105 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 2RC01R Pressurizer Westinghouse 2101 U-199012 18696 2RY01S Steam Generator Westinghouse CDGT-21 11 N/A 20 2RC01BA Steam Generator Westinghouse CDGT-2112 N/A 21 2RC01BB Steam Generator Westinghouse CDGT-2113 N/A 22 2RC01BC Steam Generator Westinghouse CDGT-2114 N/A 23 2RC01BD Residual Heat Joseph Oat 2267-1 F U-199322 841 Removal Heat Corporation Exchanger 2RH02AA See Sections 3.1 through 3.1.8 and associated tables for the specific Class 1 and 2 component locations examined for the Third Interval ISI Program.
Page 5-4
FORM NIS-1 (Back)
- 8.
Examination Dates:
October 16, 2008 to November 1, 2009
- 9.
Inspection Period Identification:
- 10.
Inspection Interval Identification:
- 11.
Applicable Edition of Section Xl 1st Period, Third Interval - From October 16, 2008 through October 16, 2011 3d Interval - From October 17, 2008 through October 16, 2018 2001 Edition Addenda 2003 Addenda
- 12.
Date/Revision of Inspection Plan:
June 29, 2009 / Revision 1
- 13.
Abstract of Examination and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan.
See Attached Sections 2 and 3.
- 14.
Abstract of Results of Examinations and Tests.
See Attached Sections 2 and 3.
See Attached Sections 2 and 3.
- 15.
Abstract of Corrective Measures.
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
,J*'.JnV?
/,f3 20 /0 Signed Exelon Nuclear Braidwood Station By Braidwood ISI 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 periodlo-I (. - -IS to It-co-o9 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.
Inspector's Signature Date O.- \\
Commissions t'l138-157L,,
t 1,Z MaCý-
National Board, State, Province, and Endorsements 20 \\*
Page 5-5
Exekn-Braidwood Station Unit 2 A2R14 IS[ Outage Report Braidwood Unit 2 Non-Deferrable Inspection Status (Third Interval) After A2R14 per IWA-6220(f)
Code Category Code Item Number Total Number Selected Total Number Examined Current Percentage (Interval) in A2R14 Completed for Category B-A B1.30 1
0 0%
B1.40 1
0 B-B B2.11 2
1 B2.12 2
1 2/5 = 40%
B2.40 1
0 B-D B3.110 6
0 B3.120 6
0 0%
B3.140 8
0 B-K B10.10 1
1 1/3 = 33%
B10.20 2
0 B-N-1 B13.10 1
0 0
B-P B15.10 Every Outage 1
Not Applicable B-Q B16.20 Per Technical Specifications 4
Not Applicable C-A C1.10 4
0 C1.20 2
0 0%
C1.30 1
0 C-B C2.21 5
0 C2.22 1
0 C-C C3.10 1
1 C3.20 9
2 0%
C3.30 3
1.
C-H C7.10 38 1
1/38 =2.6%
D-A D1.10 6
2 D1.20 3
4 6/20 =30%
D1.30 1
0 D-B D2.10 26 0
0%
E-A E1.11 301 0
0%
E1.30 1
0 E-C E4.11 22 0
0%
F-A F1.10 167 44 F1.20 186 42 94/455 = 20.7%
F1.30 73 0
F1.40 29 8
L-A L1.11 2
0 0%
L-B L.2.10 966 0
0%
R-A Butt Welds 202 13 13/202 = 6%
Socket Welds 96 Welds Every Outage 123 Page 5-6
Exelkn.
Braidwood Station Unit 2 A2R14 ISI Outage Report 6.0 NIS-2 FORM (OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS)
SUMMARY
OF NIS-2 FORMS The following table provides the Class 1 and 2 ASME Section Xl repairs completed since the last outage report (A2R13). 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 AF Auxiliary Feedwater 1
CV Chemical & Volume Control 3
MS Main Steam 3
RC Reactor Coolant 4
SI Safety Injection 2
Total NIS-2 Forms 18 Associated NIS-2 Forms and associated Code Data Reports are attached (33 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
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Shaw/ Stone & Webster Address: 36400 South Essex Road, Wilmington, IL 60481
- 4.
Identification of System: AF (Auxiliary Feed Water) (Class 2)
Date 11/9/2009 Sheet 1 of 1 Unit:
2 IT Work Order #00951927J-01 Repair/Replacement Organization P.O., Job No., etc Type Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda Section Xl 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 1/8" Diameter Bolting for Not Recorded Unknown Not Bolted Not Recorded Removed No Spectacle Flange Bolted Applicable Connection Connection AF-28-F-3-4 AF-28-F-3-4 (Between Lines 2AF02ED-4" and 2FW06AD-4")
1 1/8"-8 Heavy Hex Nuts NOVA Machine Heat 251897 Not Cat ID 2009 Installed No Products/
Lot 50164202 Applicable 1394984-1 AUGE Trace Code UTC 2826963 Industrial 1 K75 Fasteners I1 1/8"-8 Threaded Rod NOVA Machine Lot 35534050 Not Cat ID 37102 1997 Installed No Products Heat Code Applicable UTC 2664926
___......._FA X
- 7.
Description of Work: Replaced existing bolting material associated with spectacle flange connection during replacement of existing gasket to address potential foreign material concerns. No reason was provided for the replacement of the existing bolting materials.
- 8.
Tests Conducted:
Hydrostatic El Pneumatic E] Nominal Operating Pressure [I Exempt 0 Other 0 Pressure Not Applicable psig Test Temp.
Not Applicable OF
- 9.
Remarks: Applicable material documentation for hex nuts was attached at the time of final review and is maintained on file.
CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.
Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable S i g ned 6 /,2,ý D.v'2..
ISI Coordinator Date
//
, 20e Owner or Owndr's Designee,,'4itle 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 3/25/2009 to 11/9/2009, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
I Inspe Date
- J
,tor's Signature Commissions IL1085 National Board, State, Province, and Endorsements Page 6-2 20 (1,c1
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI Owner
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Date 12/15/2009 Sheet 1 of 1 Unit:
2 Work Order #01117693-01 Repair/Replacement Organization P.O., Job No., etc
- 3.
Work Performed By: Shawl Stone & Webster Address: 36400 South Essex Road, Wilmington, IL 60481
- 4.
Identification of System: Chemical Volume and Control (CV) (Class 2)
Type Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME Section III 1974 Edition, Winter 1975 Addenda, No Code Cases Applicable Edition of Section Xl Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda Section Xl Code Cases used: None
- 6.
Identification of Components:
/
Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No.
Board No.
Identification Removed, or Stamped (Yes Installed or No)
Existing Valve Cover and Borg Warner Not Recorded Not Valve Not Recorded Removed Yes (Valve)
Body-to-Cover Seal Weld Applicable 2CV8368A Valve 2CV8368A I
Valve Cover from Spare BW/IP E081 P-1-1 Not Cat ID 19719-1 1998 Installed Yes (Valve)
Valve Assembly International, Inc./
(Valve)
Applicable UTC 2612225 Patriot Forge, Inc.
Heat 26536 (Bonnet)
Body-to-Cover Seal Weld Arcos Industries, Lot/Alloy Not Cat ID 8500-1 2004 Installed No Weld Electrode LLC CM8256 Applicable UTC 2715657 3/32" ER316/316L
..Body-to-Cover Seal Weld Arcos Industries, Lot/Alloy Not Cat ID 8512-1 2002 Installed No Valve 2CV8368A LLC DF7967 Applicable UTC 2670511
.* Weld Electrode l:'
1/8" ER316/316L
- 7.
Description of Work: Removed existing seal weld to provide access to valve internals for check valve inspection. After inspection was completed, the existing valve cover was replaced with a new one from obtained spare assembly from Byron Station and seal weld was reapplied. Seal weld wa.c examined by liquid penetrant in the finished condition.
- 8.
Tests Conducted:
Hydrostatic [] Pneumatic 0 Nominal Operating Pressure 0 Exempt [I Other 0 Pressure Nominal psig Test Temp. Nominal
°F
- 9.
Remarks: Valve was examined during the ascending Mode 3 walk down on 10/30/2009 after four hour hold time and was found acceptable. There is no specific instrumentation for monitoring system pressure or temperature for this valve. Applicable documentation for replacement valve cover (Form Jw) and seal weld filler materials was attached at the time of final review and is maintained on file.
A' qpv j I.
,h 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 Codegymbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed.)O,42dt4v144 ISI Coordinator Date 1211 20-_5j Owner or Owner'eDesignee, Titid CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 1/30/2009 to 12/15/2009, 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-Lx-ý Page 6 9 Commissions IL1085 National Board, State, Province, and Endorsements Inspector's Signature t -- _ & *--
^ _
R!N/QR M 9 8:.07797 FORM NPV-1 MANUFACTURERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES As Required by the Provisions of the ASME Code Rules (9
BW/IP International Inc. Valve Division
- 1. Manulacwredi.
701 First Street, Williamsport.. PA 17701 Order NoE-OSIP-1 (Narne f Address al Monmufmotur
- 2. Manufactured for Commonwealth Edison Co.,
P. 0. Box 767, Chicago, II*,der No345778:
XX970 (News ad Address) 60690
- 3. Owner Commonwealth Edison Company
- 4. Location of PiantCTEAM/CRIT, 555 South Joliet Rd., Bolingbrook, IL 60440
- 5. Pump oa Valve Identification 2" 1500# Y-Globe Piston Check Valve Valve Serial No.:
E-081P-1-1 (B~OP das@CvitpU0 Of $*"Is* lot WWhio equipment was designed)
() Drwn 6FCBl-05, R/C Pped BW/IP International, Inc. Valve Division (b) National Board No.
N/A Design Conditions 3600 i
900 Olt
,,-..-.,re" 0Tnp"
's B98.037 44 The miterial, design, consmtction, and workmanship compiles with ASME Cqde Section UL Class Edition sumAddends Dateuer 1975 N/A Edto Addnd DaeCse No.
6.
7.
(;')
uimk MMa Hterilm Spine. No.
- Mmajletl, Rmmrks
- a.
,.bgO5S Disc:
R/S 4331059 COCR/STL6 BW/IP Int'l, Inc. Pump Division S/N 6 (AoS 5387) 01*30*3eNMe (b)
F u
Body:
R/S 0303865 SA182-F316 BW/IP Int'l, Inc. Pump Division S /I 2 9
..2.9-Bonnet:
HT #26536 S A182-F316 Patriot Forge,-In TI
-I I
Page 6-4 "It
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 Address:
300 Exelon Way, Kennett Square, PA 19348
- 2.
Plant Name:
Braidwood Station Unit 2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Braidwood Station Mechanical Maintenance Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 4.
Identification of System: Chemical and Volume Control (CV) (Class 2 Portion of System)
Date 5/6/2009 Sheet 1 of 1 Work Order #011 69536-01 Repair Organization P.O., Job No., etc Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases Applicable Edition of Section Xl Utilized for Repairs or Replacements: 1989 Edition with No Addenda Section XI code Cases used: None
- 6.
Identification of Con ponents Repaired or Replaced and Replacement Components:
Name of Component Name of Manufacturer National Other Year Built
- Repaired, ASME Code Manufacturer Serial No.
Board No.
Identification Replaced, or Stamped (Yes Replacement or No)
Line 2CV06A-4" Not Recorded Not Recorded Not 2CV06A-4" Not Recorded Replaced No Bolted Connection Applicable CV-1 7-F-1 5/8"-11 Threaded Rod NOVA Heat 7404456 Not Cat ID 571385-1 2001 Replacement No Machine Lot 40062896 Applicable UTC 2657685 Products Trace Code F440 5/8"-11 Heavy Hex NOVA Heat 7220464 Not Cat ID 37029-1 2001 Replacement No Nuts Machine Lot 50002892 Applicable UTC 2689561 Products Trace Code M192
- 7.
Description of Work: Replaced existing bolting that was removed for VT-1 examination in accordance with the Boric Acid Corrosion Control Program.
- 8.
Tests Conducted:
Hydrostatic [J Pneumatic El Nominal Operating Pressure Z Other [] Pressure N/A psig Test Temp.
N/A OF
- 9.
Remarks: Section XI pressure testing not required. Applicable manufacturer's certifications were attached at the time of final review and are maintained on file.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI.
Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed i/r
-es.i4 SI Coordinator Date
_,20_
Owner or Owner'sq/Oesignee, TitlIf 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 10/15/2008 to 5/6/2009, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date
-m 1i
,200l Page 6-5
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1
Owner
- 2.
Plant Name:
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Shaw/ Stone & Webster Address: 36400 South Essex Road, Wilmington, IL 60481
- 4.
Identification of System: Chemical Volume and Control (CV) (Class 2)
Date 11/17/2009 Sheet 1 of 1 Unit:
2 Work Order #01136818-01 Repair/Replacement Organization P.O., Job No., etc Type Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME Section III 1971 Edition, Winter 1972 Addenda, No Code Cases Applicable Edition of Section Xl Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda Section Xl 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)
Internals from Valve Kerotest Not Recorded Not 2CV8345 Not Recorded Removed Yes.(Valve) 2CV8345 Applicable Internals (Disc) from Flowserve /
Valve: 12BLL Not Cat ID 30706-1 2009 Installed Yes (Valve) spare valve assembly Talley Metals Disc: 21792-17 Applicable UTC 2812606
- 7.
Description of Work: Valve did not appear to be passing flow (reference IR 776325). During corrective maintenance on valve, removed existing valve internals and replaced with internals from an available spare valve assembly.
- 8.
Tests Conducted:
Hydrostatic [I Pneumatic [I Nominal Operating Pressure 0 Exempt 0 Other 0 Pressure Not Apolicable psig Test Temp. Not Applicable OF
- 9.
Remarks: Section XI pressure testing is not applicale. Applicable documentation for replacement disk (Form NPV-1 for valve) was attached at the time of final review and is maintained on file.
CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed ISI Coordinator Date
/
'7.
2o_
Owner or Owner'?'Designee, Titlif CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 2/19/2009 to 11/17/2009, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
L-..
Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date it
-.20,*'9 Page 6-6
149330 FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES' As Required by the Provisions of the ASME Code,Section III, Division 1 3134
- g. i of 2 P1
- 1. Manufactured and certified by FlO:sm Corporadw., 1900 South Saunders St. Ralelah, NC 27603 Iname and address of N Coerflcatt Holderl
- 2. Manufactured for Exelon Business Sefvlces, An Exelon Company P.O. Box 805388 Chkago. IL 60680-5388 Ineme and address oa Purchaer)
- 3. Location of Installation Braidwood Station East of IL 53 1-1/2 miles South of RT 113 Braldwood, IL 60408 (name md address
- 4. Model No., Series No., of Type 1500 yGB Drawing Rev.
"I CRN N/A S. ASME Code,Section III, Division 1:
1971 WINThR 1972 2
N/A (adildoam (addenda detel Idel)
(Code Case nai
- 8. Pump or valve Valve Nominal inlet size 2
Outlet size 2
lift.)
I,
- 7. Material:
(a) valve Body SA182F316 Bonnet SA479-316 Disk SAZ79-3 Bolting N/A (bI) pump Casing Cover Bolting (a)
Carl.
Holders Serial No.
12BLL Board No.
N/A (a) 1d) godylcaaing BormeVr-over Serial Serial No.
No.
AS-93 30011-8
- Supplemental Informadon In the form of
- lists, ekerctree.
or drawings may be usad provided Iii size Is 8'lj x 11. (2) Informadon in items 1 through 4 on fills Oala ~epOfl Serial No.
21792-17
- Supplemental Information In the form of lists, sketchoo.'ar drawings may be used provided III atIsiz iWO/I x 11. 12) Inofrmation In Items I through 4 on this Data Report Is Included on each useet, (3) eard sheet Is numbered end the number of sheets Is recorded at the top of this form.
Page 6-7
142330O 138134 FORM NPV-1 (Back -
Pg. 2 of Certificate Holder's Serial No.
12BLL S. Design conditions 2580 psi 650
,F or valve pressure class 1500
- 9. Cold working pressure 3600 psi at 1007 S3960
- 10. Hydrostatic test psi. Disk differential telt pressure psi
- 11. Remarks S; O 4759, YOKE MATL SA10q H-ATS 21215-1 CERTlFICAllON OF DESIGN Design Specification'certified by L 1. EZekoye P.E. State PA Reg. no. 18379-E Design Report certifled by PE. State Reg. no.
CERTIFICATE OF COMPLIANCE We certify that the statements made In this report are correct and that this pump or valve conforms to the rules for construc tion of the ASME Code% Section 11, Division 1.
N Certificate of Authorization No.
N-1S62 Expires 11-26-09 Dat ame 17 Flwserv Corporation Signed
<I IN Cacilate Hhdduel authorkied ra0ftentadval CERTIFICATE OF INSPECTION 1, the undersign d, holding a valid commission issued by the National Board of Boi InLParessure Vessel Inspectors and the State or Province of NC e-nd employed b*y Y
.... of Hafltrd, 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 accordanca with the ASME Code, Section I1I, 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.
D a eSi n dC om m issions I 'C O atsf xe N U~ a S ~ n d ~
d
~
i I n s Z Y i afi d. Unb. arm d ar aw ern n and ati ;a 0 9 1 W. end M O.1 Page 6-$
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI
- 1.
Owner
- 2.
Plant Name:
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Braidwood Station Mechanical Maintenance Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 4.
Identification of System: Containment Spray (CS) (Class 2)
Date 1/13/2010 Sheet 1 of 1 Unit:
2 Work Order #01116328-01 Repair/Replacement Organization P.O., Job No., etc Type Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases Applicable Edition of Section XI Utilized for Repair/Replacement 2001 Edition with 2003 Addenda Section Xl Code Cases used: None
- 6.
Identification of Components:
Name of Name of Manufacturer National Other Year Built Corrected ASME Code Component Manufacturer Serial No.
Board No.
Identification Removed, or Stamped (Yes Installed or No) 3/4"-10 Flange Not Recorded Not Recorded Not 2CS01 PB Not Recorded Removed No Bolting at Applicable (Lines 2CS05AB-Containment Spray 6" 2CS12AB-6" Eductor 2CS01 PB 2CS06AB-61) 3A"-10 Heavy Hex NOVA Heat 442820 Not Cat ID 1394886-1 2008 Installed No Nuts Lot 50145022 Applicable UTC 2812226 3"-10 Threaded NOVA/
Heat 243162 Not Cat ID 37094-1 2007 Installed No Rod AUGE Industrial Lot 50102895 Applicable UTC 2779993 Fasteners LLC Trace 0K45 Heat 243162 UTC 2813226 2008 Lot 50146402 Trace 1Z59
- 7.
Description of Work: Bolted connection was identified as leaking (reference IR 749775). Removed bolting closest to source of leakage (nine bolts total) for VT-1 examination on 8/27/2009. No wastage was noted, but existing studs were replaced with new material per MA-MW-736-600 Bolted Connection Checklists.
- 8.
Tests Conducted:
Hydrostatic [] Pneumatic E] Nominal Operating Pressure [0 Exempt 0 Other [0 Pressure Not Applicable psig Test Temp. Not Aoolicable OF
- 9.
Remarks: Section XI pressure testing Is not applicable. Applicable documentation for the replacement threaded rod 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 Coder,,Pymbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed ISI Coordinator Date
/13
.20
- /-C Owner or Ow6er's Designd6, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 6/18/2009 to 1/13/2010, 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 Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Page 6-9 Date 1,.
20-1
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1.
Owner
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Date 1/4/2010 Sheet 1 of 1 Unit: -_2_
Work Order #01266547-01 Repair Organization P.O., Job No., etc Code Symbol Stamp: None Authorization No.: None Expiration Date: None
- 3.
Work Performed By: Braidwood Station Mechanical Maintenance Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 4.
Identification of System: Containment Spray (CS) (Class 2) 5 (a)
(b)
(c)
Applicable Construction Code: ASME Section I11 1974 Edition, Summer.1975 Addenda, No Code Case Applicable Edition of Section XI Utilized for Repair/Replacement 2001 Edition with 2003 Addenda 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 Bolting Material at Not Recorded Not Recorded Not Line 2CS01AA Not Removed No Line 2CS01AA Applicable Flange CS-1 8-F1 Recorded Flange CS-18-Fl 1"-8 Threaded Rod Flowserve Heat Not Cat ID 29929-1 1999 Installed No 649050 Applicable UTC 2053068 Trace Code E16 A99-01383 1"-8 Heavy Hex Nuts NOVA Machine Heat S66497 Not Cat ID 1394888-1 2004 Installed No Products/
Lot 50127428 Applicable UTC-2802671 Castle Metals
- 7.
Description of Work: Replaced existing bolting material for ease of reinstallation after performing VT-3 examination per Boric Acid Corrosion Control Program requirements. No degradation/wastage of existing bolting material was documented under VT-3 examination.
Tests Conducted:
Hydrostatic 0 Pneumatic [3 Nominal Operating Pressure [0 Exempt 0 Other 0 Pressure __
psig Test Temp.
F
- 9.
Remarks: Material certifications for replacement bolting materials were attached at the time of final review and is available on file.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and conforms to the rules of the ASME Code, Section Xl.
Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed I/LU q*
SI Coordinator Date 20._O.
Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of IL and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 10/25/2009 to 1/4/2010, 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, 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.
ILt A....
Commissions ILL 085 Inspector's Signature National Board, State, Province, and Endorsements Date ii-*
4
.20_19 Page 6-10
FORM NIS-2 OWNER'S REPORT FOR REPAIRPREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI
- 1.
Owner
- 2.
Plant Name:
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Braidwood Station Mechanical Maintenance Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 4.
Identification of System: Containment Spray (CS) (Class 2)
Date 10/2/2009 Sheet 1 of 1 Unit:
2 Work Order #01116334-01 Repair Organization P.O., Job No., etc Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME Section III 1974 Edition, Winter 1975 Addenda, No Code Case Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda Section XI Code Cases used: None
- 6.
Identification of Com onents Repaired or Replaced and Replacement Corn )onents:
Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No.
Board No.
Identification Removed, or Stamped (Yes Installed or No)
Bolting on Line Not Recorded Not Recorded Not Flanged Not Removed No 2CS01AB-16" Applicable Connections Recorded (2B CS Pump Suction CS-17-Fl and Soool Piece)
CS-17-F2 Replacement 1"-8 NOVA Machine Heat 226078 Not Cat ID 2005 Installed No Threaded Rod Products, Inc./
Lot 50058125 Applicable 39559-1 AUGE Industrial Trace Code UTC 2727841 Fasteners LLC X336
- 7.
Description of Work: Replaced existing bolts on suction spool piece during gasket replacement to correct identified leakage. Reference IRs 749741 and 749747 for initial identified condition. There was no reduction in cross sectional area documented on any of the existing bolting material during VT-3 examination completed on 8/27/2009.
- 8.
Tests Conducted:
Hydrostatic El Pneumatic El Nominal Operating Pressure [I Exempt 0 Other 0 Pressure psig Test Temp.
F
- 9.
Remarks: Material certification for replacement bolting material was attached at the time of final review and is available on file.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI.
Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable.
Signed..
4L 4
ISI Coordinator Date
/10 2
, 2009 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of IL and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 6/20/2009 to 10/2/2009, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
KL LCommissions Inspector's Signature National Board, State, Province, and Endorsements Date (*
,20 0 Page 6-11
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI Owner Exelon Generation Co., LLC Address: 300 Exelon Way, Kennett Square, PA 19348
- 2.
Plant Name:
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Shaw / Stone & Webster Address: 36400 South Essex Road, Wilmington, IL 60481
- 4.
Identification of System: MS (Main Steam) (Class 2)
Date 11/9/2009 Sheet 1 of 1 Unit:
2 Work Order #01233885-01 Repair/Replacement Organization P.O., Job No., etc Type Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME Section III 1974 Edition, No Addenda, No Code Cases Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda 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)
Main Steam 6" Relief Valve Dresser BR09658 Not Cat ID 1388667-1 1979 Removed/
Yes (Position 2MS01 5A Applicable UTC 2841841 Installed
- 7.
Description of Work: Relief valve was removed and sent to NWS Technologies for disassembly and inspection. Existing disc was replaced with a preoxidized X750 disc (Serial Number ACZ84, provided to NWS by Exelon). Per Purchase Order 451491, valve was reassembled and set pressure and seat tightness were verified using steam prior to shipment back to Braidwood. Valve was reinstalled into the same position as removed.
- 8.
Tests Conducted:
Hydrostatic 0 Pneumatic [I Nominal Operating Pressure 0 Exempt 0 Other [] Pressure Not Applicable psig Test Temp.
Not Agplicable
°F
- 9.
Remarks: Applicable documentation (Form NVR-1 for refurbished valve and Form N-2 for replacement disc) 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 Cod Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed ISI Coordinator Date I///,Lf. 20_.i Owner or Owr~r's Designd6, 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 8/19/2009 to 11/9/2009, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described In this Owner's Report In accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date f2-o
,20 Page 6-12
FORM NVR-1 REPORT OF REPAIR (
REPLACEMENT I OF NUCLEAR PRESSURE RELIEF DEVICES
- 1. Work performed by: NWS Technologies, LLC Purchase Order # 451491 131 Venture Boulevard, Spartanburg, SC 29306 151792
- 2. Work performed for. Exelon Corporation, Braidwood Station 3/4. Owner - name, address and Identification of nuclear power plant.
Exelon Corp. - Braidwood Station East of IL RT 53, 1-1/2 Miles South of RT 113-Braidwood IL 60408.
- 5. a: Repaired pressure relief device:
Main Steam Safety Valve b: Name of manufacturer Consolidated I Dresser c: Identifying nos.
3707R BROS (type)
(mt's d: Construction Code:
Section III (name/section/dlvlolon)
'668 SIN) n/a (NBO) steam 6"
(service)
(size) 1974 (edition) n/a n/a (addenda)
(Code Cases(s))
- 6. ASME Code Section XI applicable for Inservice Inspection:
- 7. ASME Code Section X1 used for repairs, replacements:
- 8. Construction Code used for repairs, replacements:
2001 (edition) 2001 (edition) 1974' (edition) 2003 (addenda) 2003 (addenda) n/a (addenda) 1979 (yr.bullt) 2 (Code Class) n/a (Code Case(s))
n/a (Code Case(s))
n/a (Code Case(s))
- 9. Design responsibilities: n/a
- 10. Opening pressure:
1205 psig Set-pressure adjustment made at NWS Technologies, LLC using steam
- 11. Description of work (Include name and Identifying number of replacement parts):" Disassembled, Inspected, installed preoxidized X750 disc, lapped nozzle seat and passivated seat area, cleaned, lubricated, assembled.
Certified set-pressure and seat tightness using steam.
- 12. Remarks: NWS Traveler # 09-291. Replacement disc s/n ACZ,4.
CERTIFICATE OF COMPLIANCE I,
Jason C. Gibson certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules.
National Board Certificate of Authorization No.
632 to use the "VR" stamp expires April 3, 2012.
National Board Certificate of Authorization No.
81 to use the "NR" stamp expires April 9. 2012.
ac, QA Engineer Date Repair Organization v Authorized representative Title v
r CERTIFICATE OF INSPECTION I,
Deryl Simpson holding a valid commission Issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of NC and employed by HSB of CT of Hartford, CT have inspected the repair, modification or replacement described In this report on o
and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section Xl of the of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described in this report. Futhermore, neither the undersigned nor my employer shall be liable In any manner for any personal Injury, property damage or loss of any kind arising from or connect it thi-m Lon.
_o-___o_
a_-___NS_#**_52 NB1,652A, B, N, NS NC # 1206 Date Insectoes Signature Commissions (NB (Ind endorsements), jurisdiction,& no.)
Page 6-13
FOW 4
N.
R TMW A1 HOLD'RV DATA REPOtRT FOR VNTgICAL NUCLEAR PARTS AND APPURT!NANCEW b4"'M§2845 9 As Roqaalmd by th PwVSoImS of tM AIME Cods, SesWon M Not to Exceed One Day's Production Pg. 1of 2
Druusor Valve Division; Dressr Equipment Group, Inc.
Interecton tHy. 167 @3225 North, Alexandria, Louisiana 71309
- 1. Manufadured and codified by (MM Amue aof tW NP"Cwtilk M i'f)
- 2. Manufactured for Commonwealth Edison Company P,O. Box ?87 Chicago. Illinois 60690-0767 (0118 ame 11adrom of pumfnw )
- 3. Location of installation Commonwealth Edison Co. Braidwood Sta. E.Of ILL. Rt. 63.11-1/2 M, S.Of RI. 113 BradwoodILL.60408 (1,41111S10 armows)I
- 4. Type OS430 S0637 (Inconel X,750)
NIA N/A 1999
-.( mSi2C.O.)
3W. 1110.
t)
ICRN I (y*V buiII)
- 5. AWSM('1e SbWi Il, DIivision 1:
1974 None 2
N/A (0060) saddftd"
)
1re) 1CodeCas fo
- 6. Fabricated in accordance with Consi. Spec. (Div. 2 only)
N/A Revision NIA Date N/A (noI
- 7. Remarks.
Nons
- 8. Nora. thickness ( in )
N/A. Min. design thickness ( in. )
NIA Dia. ID ( ft. & in. )
N/A Length overall ( ft. & in. )
N/A
- 9. When applicable, Certificate Holders Data Reports are attached for each item of this report:
Pon or Appurtenance Serial Number National Board No.
in Numerical Order Parl or Appurtenance Serial Number National Board No.
in Numerical Order (0)
(2)
(3)
(4)
(5)
(6)
(7)
(801 (10)
(12)
(13)
(14)
(18)
(17')
(20)
(21)
(22)
(24)
(25)
A(
A(Ac
- Z84 4.5 2Z85 Y.
Za88 WIC-i-4 2Zao IZ9I q-tw-*--- 4 426) j27)
(28)
(29)
(30)
(31)
(32)
(33)
(34)
(35)
(38)
(37)
(38)
(39)
(40)
(41)
(42)
(43)
(44)
(45)
(46)
(47)
(48)
(49)
(50) 4 4.
4.
.4-4.
4-.
10 Desig pfessure N/A psi Temp.
NIA IF Hydro Test pressure 2250 PSIG af(
Iep F
$I U00074tj oftiwiobori IV ft orm of 40sts kstore of eraigir "a be used pmv'ded I I I son is & 112 x 11, (2) rnfkvinalocn in 11um 2 and 3 on Mill Otat Repor awdm W o r'dc san ac,"eu 3)1
$NO' VnW 'al numWeW JIM " num~ CO sneer it IS=re At t" WOp Of Ons t
^' -A A I
U
S~u2845 9 FORM N.2 (Back -
Pg. 2 of 2
)
Certitficate Holdar's Serial Nos.
ACZ84, ACZ85
-theugh ACZ88, ACZ89, ACZ90 CERTIFICATION OF DESIGN Design speclfications certified by N/A P.E. State N/A Reg. No.
.I W
- ,..l.he*f
)
Design report' certified by N/A P.E. State NIA Reg. No N/A Wrie aw=ale)
CERTIFICATE OF COMPLIANCE We ceary that te statements made in this report are correct and that this ( these)
Disc conforms to the rules of construction of the ASME Code,Section III, Division 1.
NPT Certftte of Authorization No.
N.2434 Expires 5/20/2001 Oat Name SEE LINE I NOT Eetfista.te
/
,..l-'
I aun"nei,,
reproen*ratie )
CERTIFICATE OF INSPECTION I. the undesigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectors and Ihe State or Province of LOUISIANA and employed by H. & B. I. & t. Co.
of HARTFORD. CT have inspected these items descrbed in this Data Report on *[J,, I *,
. and state that to the best of my knowledge and beWief, the Cerf1cate Holder has fabncated these parts or appurtenances in accordance with the ASME Code, Section
)11: Division. Each part lisied has been authonzed for stamping on the date shown above By signing this cserUcaIe. neither the inspector nor his employer makes any warranty. expressed or implied, concerning the equipment described in Ma pata Report. Furthermore. neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage y loss of any kiV j
v*
f of connected with this insp*ction Date jll zr?1ij11 Signed-tt
.g'4,%.tL....
Commissions
,&.V5777",?
4"/."
t f Au~iv'9id Nu*uat' insrectiv I N1t 14 I ad1.i OiOoJ 1gWf"Is Ia" lstat aI twOV and nO I Page 6-15
.I V, U
U
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 11/9/2009 Address: 300 Exelon Way, Kennett Square, PA 19348 Sheet 1 of 1
- 2.
Plant Name:
Braidwood Station Unit:
2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 Work Order #01233886-01 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: MS (Main Steam) (Class 2) 5 (a)
Applicable Construction Code: ASME Section III 1974 Edition, No Addenda, No Code Cases (b)
Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c)
Section X1 Code Cases used: None
- 6.
Identification of Comp onents:
Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No.
Board No.
Identification Removed, or Stamped (Yes Installed or No)
Main Steam 6" Relief Valve Dresser BR09662 Not Cat ID 1388647-1 1979 Removed/
Yes (Position 2MS01 6A Applicable UTC 2839826 Installed
- 7.
Description of Work: Relief valve was removed and sent to NWS Technologies for disassembly and inspection. Existing disc was replaced with a preoxidized X750 disc (Serial Number ADE53, provided to NWS by Exelon). Per Purchase Order 451491, valve was reassembled and set pressure and seat tightness were verified using steam prior to shipment back to Braidwood. Valve was reinstalled into the same position as removed.
- 8.
Tests Conducted:
Hydrostatic [: Pneumatic [I Nominal Operating Pressure [0 Exempt 10 Other 0 Pressure NotADglicable psig Test Temp.
Not Applicable IF
- 9.
Remarks: Applicable documentation (Form NVR-1 for refurbished valve and Form N-2 for replacement disc) 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 ymbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed /J',*
(I.Q.Ce-SI Coordinator Date
///9
,20*_
Owner or Ownefs DesignetV~itle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 8/19/2009 to 11/9/2009, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report In accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
J'-
L*.*-
- Commissions lL1085 Inspector's Signature National Board, State, Province, and Endorsements Date
,20j Page 6-16
FORM'NVR-1 REPORT OF REPAIR 00 REPLACEMENT I OF NUCLEAR PRESSURE RELIEF DEVICES
- 1. Work performed by:
NWS Technologies, LLC Purchase Order# 451491 131 Venture Boulevard, Spartanburg, SC 29306
- 2. Work performed for. Exelon Corporation, Braidwood Station 3/4. Owner - name, address and Identification of nuclear power plant Exelon Corp. - Braidwood Station East of IL RT53, 1-1/2 Miles South of RT 113 Braidwood IL 60408
- 5. a: Repaired pressure relief device:
Main Steam b: Name of manufacturer.
Consolidated / Dresser c: Identifying nos.
Safety Valve 3707R BRO0 (type)
(m"*a d: Construction Code:
Section III (name/sectlon/dlvlslon)
IS s,
62 n/a steam 6"
N)
(NB#)
(service)
(size) 1974 n/a n/a (edition)
(addenda)
(Code Cases(s))
(I 1979 (yr.built) 2 Code Class)
S. ASME Code Section XI applicable for Inservice Inspection:
- 7. ASME Code Section Xl used for repairs, replacements:
- 8. Construction Code used for repairs, replacements:
2001 (edition) 2001 (edition) 1974 (edition) 2003 (addenda) 2003 (addenda) n/a (addenda) n/a (Code Case(s))
n/a (Code Case(s))
n/a (Code Case(s))
- 9. Design responsibilities: n/a
- 10. Opening pressure:
1190 psig Set-pressure adjustment made at NWS Technologies, LLC using steam
- 11. Description of work (Include name and Identifying number of replacement parts):
Disassembled, Inspected, Installed preoxidized X750 disc, lapped nozzle seat and passIvated seat area, cleaned, lubricated, assembled.
Certified set-:essure and seat ti2htness using steam.
- 12. Remarks: NWS Traveler # 09-292. Replacement disc s/n ADE53.
I CERTIFICATE OF COMPLIANCE I,
Jason C. Gibson certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules.
National Board Certificate of Authorization No.
632 to use the "yR' stamp expires April 3, 2012.
National Board Certificate of Authorization No.
81 to use the "NR" stamp expires April 9, 2012.
_4,*_9____
NWS Technologies, LLC e, C.......,
QA Engineer Date Reopir Omanization
(/Authorized reoresentatve Title r
v
. r...
CERTIFICATE OF INSPECTION I,
Deryl Simpson holding a valid commission Issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the Jurisdiction of NC and employed by HSB of CT of Hartford, CT have Inspected the repair, modification or replacement described In this report on Z
and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section XI of the of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described In this report Futhermore, neither the undersigned nor my employer shall be liable In any manner for any personal Injury, property damage or loss of any kind arising from or connec ith tiNs ction.
_/_r--____ISISNB
- 10652 A, B, N, NS NC # 1206 Date
/
InSctoas Signature Commissions (NB (Ind endorsements), Jurisdiction,& no.)
Page 6-17
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Page 6-19
~'J.
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I Certificate of Conforma c--
of wdk pwformd fw I
- m I
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI
- 1.
Owner
- 2.
Plant Name:
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Shaw/ Stone & Webster Address: 36400 South Essex Road, Wilmington, IL 60481 Date 11/912009 Sheet 1 of 1 Unit:
2 Work Order #01233884-01 Repair/Replacement Organization P.O., Job No., etc Type Code Symbol Stamp: None Authorization No.: None Expiration Date: None
- 4.
Identification of System: MS (Main Steam) (Class 2) 5 (a)
Applicable Construction Code: ASME Section III 1974 Edition, No Addenda, No Code Cases (b)
Applicable Edition of Section Xl Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda (c)
Section XI Code Cases used: None
- 6.
Identification of Corn ponents:
Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No.
Board No.
Identification Removed, or Stamped (Yes Installed or No)
Main Steam 6" Relief Valve Dresser BR09666 Not Cat ID 1388663-1 1979 Removed/
Yes (Position 2MS017A Applicable UTC 2839829 Installed.
- 7.
Description of Work: Relief valve was removed and sent to NWS Technologies for disassembly and inspection. Existing disc was replaced with a preoxidized X750 disc (Serial Number ADE49, provided to NWS by Exelon). Per Purchase Order 451491, valve was reassembled and set pressure and seat tightness were verified using steam prior to shipment back to Braidwood. Valve was reinstalled into the same position as removed.
- 8.
Tests Conducted:
Hydrostatic [I Pneumatic E] Nominal Operating Pressure [I Exempt [
Other 0 Pressure Not Applicable psig Test Temp.
Not Applicable OF
- 9.
Remarks: Applicable documentation (Form NVR-1 for refurbished valve and Form N-2 for replacement disc) 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 ymbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed "L -44 ISI Coordinator Date
/Z/'
2 0,0J Owner or Owner's Designee'ritle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel In'spectors and the State of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 8/19/2009 to 11/9/2009, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
,4
.(L Commissions IL-1085 Inspector's Signature National Board, State, Province, and Endorsements Date I -
202=9 Page 6-20
FORM NVR-1 REPORT OF REPAIR 1-REPLACEMENT G OF NUCLEAR PRESSURE RELIEF DEVICES 151792
- 1. Work performed by:
NWS Technologies, LLC Purchase Order # 451491 131 Venture Boulevard, Spartanburm, SC 29308
- 2. Work performed for. Exelon Corporation, Braldwood Station 3/4. Owner - name, address and Identification of nuclear power plant Exelon Corp. - Braidwood Station East of IL RT 53, 1-1/2 Miles South of RT 113 Braidwood IL 60408
- 5. a: Repaired pressure relief device:
Main Steam E b: Name of manufacturer Consolidated I Dresser c: Identifying nos.
vafet.
Valve 3707R BR09666 (type)
(mfrs SIN) d: Construction Code:
Section 1i1 1974
. (name/sectlon/dlision)
(edition)
- 6. ASME Code Section XI applicable for inservice inspection:
- 7. ASME Code Section XI used for repairs, replacements:
- 8. Construction Code used for repairs, replacements:
n(tn/a steam 6"
1979 lB)
(service)
(size)
(yr.built) nla nla 2
(addenda)
(Code Cases(s))
(Code Class) 2001 (edition) 2001 (editon) 1974 (edition) 2003 (addenda) 2003 (addenda) n/a (addenda) n/a (Code Case(s))
n/a (Code Case(s))
n/a (Code Case(a))
- 9. Design responsibilities:
nra
- 11. Description of work (include name and Identifying number of replacement parts):
Disassembled, Inspected, installed preoxidIzed X750 disc, lapped nozzle seat and passIvated seat area, replaced spring assembly (CEAR 09-80),
cleaned, lubricated, assembled. Certified set-pressure and seat tightness using steam.
- 12. Remarks: NWS Traveler # 09-293. Replacement Disc s/n ADE49. Spring s/n AELI 8, upper spring washer s/n AEL19, lower spring washer s/n AEL20.
CERTIFICATE OF COMPLIANCE I,
Jason C. Gibson certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code 'VR"' and "NR" rules.
National Board Certificate of Authorization No.
632 to use the '"VR" stamp expires April 3, 2012.
National Board Certificate of Authorization No.
81 to use the "NR" stamp expires April 9, 2012.
/ /jpe p NW8 Technologies, LLC 2--
- e.
QA Engineer Date Repair Organization V Authorized representative Title CERTIFICATE OF INSPECTION I,
Deryl Simpson holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of NC and employed by HSB of CT of Hartford, CT have inspected the repair, modification or replacement described In this report on,J-/S "o 2 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the of the ASME Code and the National Board Inspection Code '"VR" and "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described in this report. Futhermore, neither the undersigned nor my employer shall be I ble In any manner for any personal Injury, property damage or loss of any kind arising from or connect th i nspection.
NB #10052 A, B, N, NS NC # 1206 Date inspector's Signature Commlesione (NO (min endorsements), jurlsdlction,& no.)
Page 6-21
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FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI
- 1.
Owner Exelon Generation Co., LLC Address: 300 Exelon Way, Kennett Square, PA 19348
- 2.
Plant Name:
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Shaw / Stone & Webster Address: 36400 South Essex Road, Wilmington, IL 60481
- 4.
Identification of System: Reactor Coolant (RC) (Class 1)
Date 10/27/2009 Sheet 1 of 1 Unit:
2 Work Order #01277357-01 Repair Organization P.O., Job No., etc Type Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME Section III 1974 Edition, Summer 1974 Addenda, Code Cases 1644, N71, and N249 Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda Section XI Code Cases used: None
- 6.
Identification of Coi ponents Repaired or Replaced and Replacement Com ponents:
Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No.
Board No.
Identification Removed, or Stamped (Yes Installed or No)
PSA / Mechanical Pacific Scientific Serial Number Not 2RC16114S 1977 Removed No Snubber 2419 Applicable 2RC16114S PSA 1/4/4 Mechanical Basic-PSA Serial Number Not Cat ID 27625-1 2004 Installed No Snubber 42808 Applicable UTC 2807870
- 7.
Description of Work: Replaced existing mechanical snubber, which passed functional test with marginal results (reference Issue Report 978918),
with a new tested spare mechanical snubber. Post installation VT-3 examination was completed and satisfactory on 10/19/2009.
- 8.
Tests Conducted:
Hydrostatic C] Pneumatic C] Nominal Operating Pressure [I Exempt 0 Other 0 Pressure Not Required psig Test Temp. Not Required OF
- 9.
Remarks: Section Xl pressure testing is not applicable. Applicable material documentation for replacement mechanical snubber was attached at the time of final review and is maintained on file.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI.
Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed
.I..sL 6"
K ISI Coordinator Date 1o/z 7
, 20_9 Owner or Owner's Designee, "ltle 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 10/17/2009 to 10/27/2009, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
~
~Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements Date I
, 20.S n Page 6-24
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI
- 1.
Owner
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Westinghouse Electric Corporation Address: P. 0. Box 158, Madison, PA 15663
- 4.
Identification of System: Reactor Coolant/Steam Generator Date 11/2/2009 Sheet 1 of 1 Unit:
2 Work Order #01136183-02 Repair/Replacement Organization P.O., Job No., etc Type Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME Section III 1971 Edition, Summer 1972 Addenda, No Code Cases Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda 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) 2B Steam Generator Westinghouse Unknown Not 2RC01 BB Not Recorded Corrected No (Tubes)
Tubes Applicable Plugs in Hot Leg and Westinghouse Heat Not Cat ID 45903-1 Not Recorded Installed No Cold Leg End of Tubes:
Electric NX31188hk Applicable Corporation/
Westinghouse Row 13, Column 38 Tooling Serial Numbers RIR-CDE-Row 30, Column 56 Specialists, Inc 1 U461, 1 U462 2009-6 Row 21, Column 65 1 U463, I U464 Row 19, Column 67 1U465 Row 41, Column 45 (Hot Leg) 1 U466, 1 U467 1U468, 1 U469 1U470 (Cold Leg)
- 7.
Description of Work: Mechanically plugged steam generator tubes in the 2B steam generator based on eddy current test results.
- 8.
Tests Conducted:
Hydrostatic [I Pneumatic [] Nominal Operating Pressure 0 Exempt 0 Other 0 Pressure Not Reauired psig Test Temp. Not Required OF
- 9.
Remarks: Section Xl pressure testing is not applicable. Applicable material documentation for tube plugs was attached at the time of final review and is maintained on file.
CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed.
Det,,l.eý.
ISI Coordinator I
Date L4/2.
20Ž_9' Owner or Owner's Designee, bfritle CERTIFICATE OF-INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 10/21/2009 to 11/2/2009, 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.
Inspectors Signature Page 6-25 Commissions ILl 085 National Board, State, Province, and Endorsements Date I k,20 ý,c
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1
Owner
- 2.
Plant Name:
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Westinghouse Electric Corporation Address: P. 0. Box 158, Madison, PA 15663
- 4.
Identification of System: Reactor Coolant/Steam Generator Date 10/28/2009 Sheet 1 of 1 Unit:
2 Work Order #01136184-02 Repair Organization P.O., Job No., etc Type Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME Section III 1971 Edition, Summer 1972 Addenda, No Code Cases Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda Section XI Code Cases used: None
- 6.
Identification of Components Repaired or Replaced and Replacement Coin onents:
Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No.
Board No.
Identification Removed, or Stamped (Yes Installed or No) 2C Steam Generator Westinghouse Unknown Not 2RC01 BC Not Recorded Corrected No (Tubes)
Tubes Applicable Plugs in Hot Leg and Westinghouse Serial Not Cat ID 45903-1 Not Recorded Installed No Cold Leg End of Tube:
Electric Numbers:
Applicable Corporation/
1 U472 Westinghouse Row 10, Column 3 Tooling (Hot Leg)
RIR-CDE-Specialists, Inc.
1U471 2009-6 (Cold Leg)
Heat NX3188HK
- 7.
Description of Work: Mechanically plugged steam generator tube in the 2C steam generator based on eddy current test results.
- 8.
Tests Conducted:
Hydrostatic 0 Pneumatic [] Nominal Operating Pressure [0 Exempt 0 Other 0 Pressure Not Required psig Test Temp. Not Reouired IF
- 9.
Remarks: Section XI pressure testing is not applicable. Applicable material documentation for tube plugs was attached at the time of final review and is maintained on file.
CERTIFICATE OF COMPLIANCE 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 ISI Coordinator Date 20 Owner or Owndr's Designg, 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 10/21/2009 to 10/28/2009, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
J- -
Commissions IL1085 Inspector's'Signature National Board, State, Province, and Endorsements Date 20-U-Page 6-26
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI
- 1.
Owner
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Shaw / Stone & Webster Address: 36400 South Essex Road, Wilmington, IL 60481
- 4.
Identification of System: Reactor Coolant (RC) (Class 1)
Date 11/2/2009 Sheet 1 of 1 Unit:
Work Order #01131570-01 Repair/Replacement Organization P.O., Job No., etc Type Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Cases Applicable Edition of Section Xl Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda 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 Bolting Material at Not Recorded Not Recorded Not 2FE-0418 Not Recorded Removed No Flow Element 2FE-0418 Applicable 2RC-23-B1 (ISI Bolted Connection 2RC-23-B1_)
I 1 "-8 Heavy Hex Nuts NOVA Machine Heat S66497 Not Cat ID 2004 Installed No Products/
Lot 50127428 Applicable 1394888-1 Dyson Domestic UTC Nut Corp.
2802671 1"-8 Threaded Rod NOVA Machine Heat 28290 Not Cat ID 39990-1 1999 Installed No Products/
Lot 40085740 Applicable UTC 2683953 Nedschroef Trace H729 K
Corporation
- 7.
Description of Work: Removed existing bolting to replace gasket to correct boric acid leak. Existing bolting was replaced with new for expediency since line was isolated through a freeze seal. The existing and replacement bolting materials were inspected by VT-1 method per B-G-2 requirements.
- 8.
Tests Conducted:
Hydrostatic 0 Pneumatic - Nominal Operating Pressure [0 Exempt 0 Other 0 Pressure Not Required psig Test Temp. Not Reauired OF
- 9.
Remarks: Bolted connection was inspected during the system leakage test on 10/30/2009 and was acceptable. Applicable documentation for replacement bolting material was attached at the time of final review and is maintained on file.
CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.
Type Code ymbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed V oer-OA n s6,-
D ISI Coordinator Date
'K,//2-20 e_.9 Owner or OwnE's Designee~l'itle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 2/25/2009 to 11/2/2009, 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.
jl,*t"
Ins-Date Commissions IL1085 pector's Signature National Board, State, Province, and Endorsements Page 6-27
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI
- 1.
Owner
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Braidwood Station Mechanical Maintenance Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407 4,
Identification of System: Residual Heat Removal (RH) (Class 2)
Date 9/28/2009 Sheet 1 of 1 Unit: _2 Work Order #01131576-01 Repair Organization P.O., Job No., etc Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME Section I11 1974 Edition, Summer 1975 Addenda, No Code Case Applicable Edition of Section Xl Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda Section XI Code Cases used: None 6.
Identification of Components Repaired or Replaced and Replacement Components:
Name of Component Name of Manufacturer National Other Year Built Corrected ASME Code Manufacturer Serial No.
Board No.
Identification Removed, or Stamped (Yes Installed or No)
Bolting on Line Not Recorded Not Recorded Not Flanged Not Removed No 2RH01 CB Applicable Connections Recorded (2B RHR Pump Suction RH-13-Fl and Spool Piece)
RH-13-F2 Replacement 1-1/2"-6 NOVA Machine Heat 38218 Not Cat ID 2003 Installed No Threaded Rod Products, Inc./
Lot 50175614 Applicable 1429747-1 Nedschroef Trace Code UTC 2837110 Corporation 3D18 Replacement 1-1/2"-6 Heavy Hex Nuts NOVA Machine Products, Inc./
Dyson Corp.
Domestic Nut Heat 8965253 Trace Code 873A Heat 8965253 Trace Code 287A Not Applicable Cat ID 1394988-1 UTCs 2810789 and 2837112 Cat ID 1394988-1 UTC 2837113 2005 Installed No
- 7.
Description of Work: Replaced existing bolting during visual examination for the Boric Acid Corrosion Control program, reference IR 771506 for initial I
condition. No reduction in cross sectional area was documented on any existing bolting material under VT-3 examination completed on 7/24/2009.
- 8.
Tests Conducted:
Hydrostatic [I Pneumatic [I Nominal Operating Pressure [I Exempt [@
Other [] Pressure _
psig Test Temp.
0F
- 9.
Remarks: Material certifications for replacement bolting materials were attached at the time of final review and are available on file.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI.
Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed 6 lyxllw" a
ISI Coordinator Date 2/0At
,20 Owner or Owner's Designee, Title I
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 IL and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 5/15/2009 to 9/28/2009, 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.
Inspector's Signature Commissions a-it
- k. c'-.*
National Board, State, Province, and Endorsements IDate L.. -
20 OCC Page 6-28
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI
- 1.
Owner
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Shaw / Stone & Webster Address: 36400 South Essex Road, Wilmington, IL 60481
- 4.
Identification of System: Residual Heat Removal (RH) (Class 2)
Date 11/16/2009 Sheet 1 of 1 Unit:
2 Work Order #01185894-01 Repair/Replacement Organization P.O., Job No., etc Type Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME Section III 1971 Edition, Winter 1972 Addenda, No Code Cases Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda Section Xl 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)
Valve Yoke from Kerotest Not Recorded Not 2RH8734B Not Recorded Removed Yes (Valve) 2RH8734B Applicable Yoke from Spare Valve Flowserve Valve: 93BNC Not Cat ID 1969-1 2009 Installed Yes (Valve)
Assembly Yoke: 20681-2-7 Applicable UTC 2827242 (2" 1500# Class Y-Globe Valve)
- 7.
Description of Work: During corrective maintenance on valve, removed existing valve yoke and replaced with a new yoke from an available spare valve assembly.
- 1.
Tests Conducted:
Hydrostatic [I Pneumatic [] Nominal Operating Pressure 0 ExemptO Other 0 Pressure 170 psig TestTemp. 89
°F
- 9.
Remarks: Section XI pressure testing was performed and acceptable on 10/27/2009. Applicable documentation for replacement yoke (Form NPV-1 for valve) was attached at the time of final review and is maintained on file.
CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed 1$4t/ -d)
ý4 4'
ISI Coordinator Date i//
', 202.2 Owner or Owner' Designee, "r-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 Illinois and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 9/1/2009 to 11/16/2009, 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
(...,z Commissions IL1085 Inspector's Signature National Board, State, Province, and Endorsements flate
-*)
20 c*
Date 20 QI Page 6-29
144456 FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES' As Required by the Provisions of the ASME Code, Section !11, Division 1 Pg.. 1 of 2
- 1. Manufactured and certified by #:lOWSe'V8 Cor.oJtion. 1900 South Saunders St. Ralekih. NG 27603
{fim.
sir sd*.lu.4 N artiiats Holder)
- 2. Manufactured for r'elon Business Servles, An Exelon Company P.O. Box 805388 ailcago, IL 60680-S388 tnam and address of Prchual
- 3. Location of installation Braldwood Station East of IL 53.1-1/2 miles S"udi of RT 113 Braidwood, IL 60W8 rome and ddr %
- 4. Model No., Series No., or Type' Y
Drawing WC (If127 0 ".Rev.
- L CRN N/A
'5. ASME Coda, Section Il1, Division 1:
1971 WINTER 1972 1
N/A
- (edi air)("eddsne del WanI MCode Cue. mol
- 8. Pump or valve Valve Nominal inlet size 2
Outlet size 2
- 7. Material:
(a) valve Body SA182'F316 Bonnet SA479-316 Disk
- 5679016 Bolting NIA (b) pump Casing -
Cover Bolting (a8
- Cert.
Hotdeýr
' Serial No.
93BNC
-!4PNC 95BNC 96.'NC (b)
Nat'l Board No.
N/A NIA NIA N/A
- Supleentl Ifanatlfi n te fant f lsts sklules.or rawigs ay e wd plifsd
- 1) lla.8%a 1, () Iforatin I llaa 1thrugh4 o Ih Daa Rpor (ci Bodylr..lng Serial No.
AS-105 A65-106
,45-107 AS-108 BonnWCover NO.
.E102S2-33 E402S2-34 E402S2-35 E40252-36 Dik Serial No.
21450-S 21450-.6 21450-7 21450-8
- Supplemeantal Inlonmetion In fth fonmn of 11iW, sketchero or drawings may be used prmvled 11) aft is 8%/. x 11, 111) Information In Iterms I through 4 on this Data Report Is Included on each shaM 13) suah siftee is numbered a4 the rurn'et at sheeds Is ettuded, C tde lap adf ftrh..
m.
Page 6-30
- 144456 FORM NPV-1 (Back - Pg. 2 of.L '.)
Certificate Holder's Serial No. 93BC"hRU 96BNC
- 8. Design conditions 250 psi 650 OF or valve pressure class 1500 ps Ite rn rumma
- 9. Cold working pressure 3600 psi at IO01F t 5400 3960
- 10. Hydrostatic test 5ps Disk differential test pressure
'psi
- 11. Remarks. 5..
50713 YOKE: MATL: SA10S. HEAT: 20681-2 SIN 7 THRU 10 CERTIFICA71ON OF DESIGN L KE EZEKOVE PA 1B.379-E Design Specification certified by RE. State P
Rag. no.
Design Report certified by RON S. FARRELL.
RE. State NC Reg. no... 296.
CERTIFICATE OF COMPUANCE We certify that the statements mado In this report are correct and that this pump or valve conforms-to the rules for construction of the ASME Code, Section Il1, Division 1.
N Certificate of Authorization No.
N-1562 Expires 11-26-09 Date 62 1 Name Flowserve Corporation Sge (N Colfloste)
H
- v.
I M ftd ve)
CERTIFICATE, OF INSPECTION I, the undersigned, holding a valid commission Issued by the National Board of Boller an.Pressure Vessel. Inspectors and the State or Province of NC and employed by HSB
.I of Hartfoni. CT have Inspected the pump, or valve, described In this Data Report on 2*12. f.
I and stafe that to tho best 9f 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 connected with this Inspection.
Date IJ74&
Signed C omch~suions AX~ /5-1/17
'U..
5t~mflujNudesr Inap~ctwt INOfV. Dd. lined. endlsmonats) end aste or prov. and ne.l r-_
- nn 3
. rage 0-11
CUSTOMER:
SALES ORDER:
50713 UNE ITEM:
01 14 4A A 5 CD C'D 0)
VALVEASSEMBLY REPORT VALVE SIN BODY' ENWNET D=IS YOKE DIAPHRAGM STEM ASSY.
SPRING DISC CAP SPRING GUIDE 93 BNC AS-105 E40252-33 21450-5 20681-2-7 23135-1 #25-32 25430-1 HT12O7XK G13479 A14651 94 BNC A5-106 E40252-34 21450-6 20681-2-8 23135-1 #33-40
- 25430-1 HT1207XK G13479
.A14651 95 BNC A5-107 E40252-35 21450-7 20681-2-9 23135-1 #41-48 25430-1 HT1207XK G13479 A14651 96 BNC AS-108 E40252-36 21450-8 20681-2-10 23135-1 #49-56 25430-1 HT1207XK G13479 A14651 I
-N
FORM NIS-2 OWNER'S REPORT FOR REPAIRSOR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1.
Owner
- 2.
Plant Name:
Braldwood Station Unit 2 Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Braidwood Mechanical Maintenance Address: 35100 S. Route 53, Suite 84, Braceville, IL 60407
- 4.
Identification of System: Safety Injection (SI) (Class 2 Portion of System)
Date 5/15/2009 Sheet I of I Work Order #01146685-01 Repair Organization P.O., Job No., etc Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME Section III 1974 Edition, Summer 1975 Addenda, No Code Case Applicable Edition of Section Xl Utilized for Repairs or Replacements: 1989 Edition with No Addenda Section XI Code.Cases used: None Iaentificaton of C ponentJ Repaired or Heplacea ano IR placement LC ponens:-
Name of
- Repaired, ASME Code Name of Component Manufacturer Manufacturer National Other Identification Year Built Replaced, or Stamped (Yes Serial No.
Board No.
Replacement or No)
Bolting at Connection Unknown Not Recorded Not 2A-SI-22 Not Replaced No 2A-SI-22 on Recorded Recorded Line 2SI01 B-24 5I8"-11 Heavy Hex Nuts NOVA Machine Heat 7220464 Not Cat ID 37029-1-1 2005 Replacement No Products Lot 50002892 Applicable UTC 2689581 Corporation Trace M1 92 518"-11 Threaded Rod NOVA Machine Heat 7404456 Not Cat ID 571385-1 2002 Replacement No Products Lot 40062898 Applicable UTC 2657685 Corporation' Trace F440
- 7.
Description of Work: Replaced existing bolting with new mate rial as part of corrective actions from leak Identified under Issue Report 785928.
- 8.
Tests Conducted:
Hydrostatic [3 Pneumatic [3 Nominal Operating Pressure [3 Other [3 Pressure Not Applicable psig Test Temp. Not Applicable OF
- 9.
Remarks: Applicable material certifications were attached at the time of final review and are on file.
CERTIFICATE OF COMPLIANCE We certify that the statements made In the report are correct and this replacement conforms to the rules of the ASME Code, Seconl.
Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed AL-
- i.
ISI Coordinator Date
.20__..
Owner or Owner's signee, Title 4V CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of IL and employed by.HSBCT of CT have Inspected the components described In this Qwner's Report during the period 7/10/2008 to 5/15/2009, 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-examinatlons 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.
3, Lu-Inspector's Signature Commissions IL1085 National Board, State, Province, and Endorsements OatA -- i' L%*
gn. q3 Date -S-1 Le.
Page 6-33
FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI
- 1.
Owner
- Exelon Generation Co., LLC Address:
300 Exelon Way, Kennett Square, PA 19348
- 2.
Plant Name:
Braidwood Station Address: 35100 S. Rte. 53, Suite 84, Braceville, IL 60407
- 3.
Work Performed By: Shaw / Stone & Webster Address: 36400 South Essex Road, Wilmington, IL 60481
- 4.
Identification of System: Safety Injection (SI)
Date 10/24/2009 Sheet 1 of 1 Unit:
2 Work Order #1033803-01 Repair Organization P.O., Job No., etc Type Code Symbol Stamp: None Authorization No.: None Expiration Date: None 5
(a)
(b)
(c)
Applicable Construction Code: ASME/ANSI 831.1 1973 Edition, 1975 Addenda, No Code Cases Applicable Edition of Section XI Utilized for Repair/Replacement: 2001 Edition with 2003 Addenda Section XI Code Cases used: None
- 6.
Identification of Components Repaired or Replaced and Replacement Components:
Name of Name of Manufacturer National Other Identification Year Built Corrected ASME Code Component Manufacturer Serial No.
Board No.
Removed, or Stamped (Yes Installed or No) 2" X 1" Pipe Not Recorded Not Recorded Not Cat ID 7483-1 Not Recorded Installed No Reducer Upgraded to SR Applicable UTC 2827979 Couplings per Exelon Power Labs Inspection
_144811 2" Seamless Sandvik/
Heat 512741 Not Cat ID 26883-1 2007 Installed No Pipe Pennsylvania Applicable UTC 2807097 Extruded Pipe Cnmnanv ER308/308L Arcos Industries, Lot/Alloy Number Not Cat ID 8497-1 UTC 2007 Installed No Weld Rod LLC CT8659 Applicable 2791121 (3/32" Diameter)
I I
I III ER308/308L Arcos Industries, Lot/Alloy Number Not Cat ID 8513-1 UTC 2003 Installed No Weld Rod LLC DF7995 Applicable 2702660 (1/8" Diameter)
- 7.
Description of Work: Modified line 2SI99G-1" under EC 365548 which involved removing 1" check valve 2SI8969F from line 2SI99F-1" and 1/2" drain tap valve 2SI8969G and replacing them with several manually operated ball valves. Part of the modification installed a 2" diameter section of pipe in order to increase available volume for collecting condensate from line 2S199F-1". Although this portion of the system was not installed as ASME Section III Class 2, the function of the system is Section Xl Class 2 as defined in the Braidwood Station Third Interval ISI Program Boundary Basis Document Section 4.2.41.
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Tests Conducted:
Hydrostatic 0 Pneumatic El Nominal Operating Pressure El Exempt [I Other 0 Pressure 60 psig Test Temp. 58 OF
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Remarks: Section Xl pressure testing is only applicable to piping and fittings greater than 1" NPS and was performed in the fabrication shop prior to final field installation. Applicable material documentation for replacement 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 replacement conforms to the rules of thePSME Code, Section Xl.
Type Code Symbol Stamp: Not Applicable Certificate of Authorization No.: Not Applicable Signed 181 u-ISI Coordinator Date
/__,2-_, 2001?
Owner or Owners Designe6,Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of and employed by HSBCT of CT have inspected the components described in this Owner's Report during the period 3/11/2009 to 10/14/2009, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
. Commissions _n/*/)w Inspector's SiLeture National Board, State, Province, and Endorsements Date
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