ML062090368
| ML062090368 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/28/2006 |
| From: | Poison K Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML062090366 | List: |
| References | |
| BW060076 | |
| Download: ML062090368 (61) | |
Text
__
Exel_n
~xeionGeneTation Co npany. LLC Ni__ci BraidwoodStation July 28, 2006 BW060076 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington. ft C. 20555 - 0001 Braidwood Station, Unit 1 Facility Operating License Nos. NPF-72 NRC Docket No. STN 50-456
Subject:
Braidwood Station, Unit I Inservice Inspection Summary Report Enclosed is the post-outage summary report (Le., the 90 day report) for Inservice Inspection examinations conducted during the Braidwood Station, Unit 1 twelfth refueling outage (Al R12).
This report is submitted in accordance with the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, 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. Dale Ambler, Regulatory Assurance Manager, at (815) 417-2800.
Since rely, Keith ~~olson Site Vice President Braidwood Station
Enclosure:
Braidwood Station lSl Outage Report for Al Rl2
BRAIDWOOD STATION UNIT 1 INSERVICE INSPECTION
SUMMARY
REPORT FOR:
Interval 2, Period 3, Outage 1 A1R12 Outage STATION ADDRESS:
Braidwood Station 35100 S. Rt. 53 Suite 84 Braceville, Illinois 60407 UNIT 1 COMMERCIAL SERVICE DATE:
July 29, 1988 OWNERS ADDRESS:
Exelon Generation Co., LLC 300 Exelon Way Kennett Square PA 19348
Exek~n~
Braidwood Station Unit 1 A1R12 ISI Outage Report TABLE OF CONTENTS DESCRIPTION:
PAGE:
TITLE PAGE TABLE OF CONTENTS ii 1.0 INSPECTION INFORMATION 1-1 to 1-2 2.0 INSERVICE EXAMINATION
SUMMARY
2-1 to 2-4 3.0 INSERVICE/PRESERVICE COMPONENT DETAILED 3-1 to 3-53 EXAMINATION TABLES 4.0 NIS-1 FORM 4-1 to 4-3 (OWNERS REPORT FOR INSERVICE INSPECTION) 5.0 REPORT OF CONTAINMENT 5-1 to 5-5 DEGRADATION (IWE/IWL) 6.0 NIS-2 FORMS, Cover page pIus 32 pages of Attachments 6-1 to 6-33 (OWNERS REPORT FOR REPAIRS OR REPLACEMENTS)
Braidwood Station Unit 1 Al Rl 2 ISI Outage Report 1.0 INSPECTION INFORMATION 1.1 Summary Second Interval Inservice Inspections (ISI) of ASME Class 1, 2, and 3 components were conducted at Braidwood Station Unit 1 between November 19, 2003 to May 5, 2006, with the majority of these inspections being performed during the Braidwood Station Unit 1 twelfth refueling outage (A1R12). This outage is reflected in the Braidwood ISI schedule by the code 231 (Interval 2, Period 3, Outage 1).
The examinations were performed in accordance with the rules and regulations of Section Xl, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components, of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 1989 Edition, no addenda, pursuant to the requirements of Title 10, Part 50.55a of the Code of Federal Regulations (10CFR5O.55a).
The Containment Inspection Program was developed and implemented in accordance with the requirements and intent of Subsections IWE and IWL of ASME Section Xl, 1992 Edition through the 1992 Addenda, pursuant to the requirements of IOCFR5O.55a.
In addition to the ASME Section Xl requirements, certain NRC augmented lSl inspections were required during A1R12. The Braidwood Unit 1 augmented ISI examinations included:
a)
Examination of the Class 1 pressure boundary for leakage at nominal operating pressure, in accordance with Generic Letter 88-05.
b)
Bare Metal Visual examination of the Unit 1 pressurizer steam space nozzles in accordance with Braidwood Station response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors.
c)
Visual and volumetric examinations of pressure retaining components above the reactor vessel head and volumetric examination of reactor vessel head penetrations in accordance with First Revised NRC Order EA-03-009.
There were no significant findings associated with any of the augmented ISI examinations. Reports for these examinations have been submitted under separate transmittals when required.
1.2 Identification of Examination Requirements The Second Interval lSl Program contains the 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 NDE tables include the corresponding code category, item number, and component/weld population selection in conformance with examination requirements and intent of Subsection IWA, IWB, IWC, IWD, IWE, and IWF of Section Xl of the ASME Code. Program notes and relief requests and additional information are identified in the basis column.
Page 1-1
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Braidwood Station Unit 1 A1R12 ISI Outage Report 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-i, VT-2, VT-3, VT-iC, and VT-3C) 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. Personnel were certified to the requirements of the American Society for Non-destructive Testing SNT-TC-iA, 1984 Edition. The NDE procedures were developed and certified in conformance with ASME Section V and Xl, 1989 Edition, as applicable. In addition, ultrasonic examination personnel were qualified in accordance with ANSI/ASME CP-189, 1995.
Certified personnel performed and evaluated visual examinations (VT-i, 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-iA, 1984 Edition and/or ASME Section Xl 1989, as applicable.
Certified personnel performed and evaluated visual examinations (VT-i, VT-3, VT-i C and VT-3C) of Containment Structures. Personnel were certified to the requirements of the ANSI/ASNT CP-189, 1991 revision, and/or ASME Section Xl 1992 through 1992 Addenda, as applicable.
1.5 Witness and Verification of Examination The inservice inspections were witnessed and/or verified bythe 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 1-2
2.0 INSERVICE EXAMINATION
SUMMARY
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Braidwood Station Unit 1 A1R12 1St Outage Report The following is a summary of ASME Section XI, Risk Informed IS!, and augmented examinations performed during the Braidwood Station Unit i AiRi2 refueling outage.
Refer to the component detailed examination tabulations of Section 3.0 for additional information on specific welds, components, supports, snubbers and pressure test examinations and their respective results.
2.1 Inservice Weld/Component Summary Chemical & Volume Control (CV) 12 Feedwater (FW) i 5 Main Steam (MS) i 0 Reactor Coolant (RC) 16 Residual Heat Removal (RH) 1 Reactor Coolant (RY) 14 Steam Generator (SG) 4 Safety Injection (SI) 4 Essential Service Water (SX) i TOTALS 78
- 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.
2.2 Inservice Component Support Summary Number of SYSTEM EXAMINED Component Supports Containment Spray (CS)
Chemical & Volume Control (CV) 4 Feedwater (FW) 2 Reactor Coolant (RC) 8 Residual Heat Removal (RH) 4 Reactor Coolant (RY) i Safety Injection (SI) 25 Essential Service Water (SX) i TOTALS 50 containment ~..
(,~)
Page 2-i
2.3 Inservice Snubber Summary Exeloit Braidwood Station Unit 1 A1R12 ISI Outage Report Main Steam (MS) 8 7
Reactor Coolant (RC) 24 18 Residual Heat Removal (RH) 4 4
Reactor Coolant (RY) 10 10 Safety Injection (SI) 21 21 TOTALS 68 61 2.4 Inservice Pressure Test Summary 2.4.1 Pressure Test Test-Block Inspection Summary Summary of components contained in this table are those pressure test blocks that were examined for Section XI Inservice Inspection credit. Braidwood has adopted Code Case N-522 as previously approved for use in Regulatory Guide 1.147 Revision 13, Inservice Inspection Code Case Acceptability, ASME Section Xl, Division 1 for systems penetrating primary containment.
Process Sampling (PS) 2 1*
Safety Injection (SI) 2 i**
Plant Systems Pressurized During Mode 3 (ZZ) 1 & 2 4**
TOTALS ii
- Tests credited to the second period. Tests were completed after the AlRi 1 report was submitted.
- Portion of three test blocks (AOl Sl-000005-M04-02H, AOl ZZ-000005-M04-02A, and AOi ZZ-000005-M04-02B) were completed during AlRi 2, the remainder of these test blocks will be completed in AiRi3.
Chemical & Volume Control (~.,V) 1 1
Containment Fuel Pool CoolinQ O-L~)
2 2*
Page 2-2
Braidwood Station Unit 1 Al Ri 2 ISI Outage Report 2.4.2 Borated Bolting Inservice Inspection Summary Summary of components contained in this table are those insulated borated bolted connections that were examined for Section Xl Inservice Inspection credit.
Inspections on these connections are performed per the commitments in Relief Request 12R-i2, l2R-i3, and l2R-3O, as applicable, of the IS! Program Plan.
Number of Number of SYSTEM EXAMINED Connections Connections
_______________________ Examined by VT-2 Examined by VT-i Chemical & Volume Control 17 1
(CV)
Pressurizer (RY) 1 0
Reactor Coolant (RC) 13 0
Residual Heat Removal (RH) 12 1
TOTALS 43 2
2.5 Steam Generator (SG) Eddy Current Testing Summary In compliance with Braidwood Station Technical Specification (TS) 5.5.9, Steam Generator Tube Surveillance Program, and American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code Section Xl 1989 Edition, IWB 2500-i, Examination Category B-Q, Item Bi6.20, SG eddy current examinations were performed during the Braidwood Station Unit 1 Cycle 12 refueling outage (AiR12). In addition, the inspections were performed consistent with the Electric Power Research Institute (EPRI)
PWR Steam Generator Examination Guidelines, Revision 6, and Nuclear Energy Institute NE! 97-06, Steam Generator Program Guidelines, Revision 2.
The following inspections were performed during this outage.
100% full length bobbin coil eddy current in all four SGs 20% hot leg top of tubesheet (+1-3 inches) +PointTM eddy current in all four SGs 20% hot leg dents and dings ~ 2.0 volts ÷PointTM Diagnostic +PointTM eddycurrent based on bobbin coil eddy current results 100% Visual inspection of Previously Installed Tube Plugs 100% Visual Inspection of Newly Installed Tube Plugs The modes of tube degradation found during Al Ri2 were fan bar wear, lattice grid wear and foreign object wear.
As a result of the eddy current inspection of the SGs, a total of 28 tubes were removed from service by mechanical tube plugging. The 28 tubes were removed from service due to either having wear associated with secondary side foreign objects or were required to be removed from service in order to bound high flow locations where secondary side foreign objects could not be retrieved.
One tube in the 1A SG had tube wear greater than the TS plugging limit of ~ 40%.
Pursuant to TS 5.5.9.c, Inspection Results Classification, the lA SG was classified as inspection category C-2. No additional scope expansion was required since 100% full-length bobbin eddy current inspection was already being performed in the iA SG.
Page 2-3
Braidwood Station Unit 1 Al R12 1St Outage Report One tube in the lB SG had tube wear greater than the TS plugging limit of > 40%.
Pursuant to TS 5.5.9.c, Inspection Results Classification, the 1 B SG was classified as inspection category C-2. No additional scope expansion was required since 100% full-length eddy current inspection was already being performed in the lB SG.
There were no tubes containing wear greater than the TS plugging limit of ~ 40% in the 1 C and 1 D SGs. Pursuant to TS 5.5.9.c, Inspection Results Classification, the 1 C and 1 D SGs were classified as inspection category C-i.
There were no scanning limitations during the eddy current examinations. The table below, Equivalent Tube Plugging Level, provides the total tube plugging history and equivalent plugging levels to-date for the Braidwood Station, Unit 1 SGs. Note: The Braidwood Unit 1 steam generators were replaced during the Cycle 7 refueling outage (November 1998).
Equivalent Tube Plugging Level
~__________________________________________
1~*~
ui~
up.
- ~
Tubes Plugged at Factory 1
2 0
0 3
Tubes Plugged in A1RO8 1
0 0
0 1
Tubes Plugged inAiRlO 8
iO 3
0 2i Tubes Plugged inAiRil 0
2 2
1 5
Tubes Plugged inAlRl2 11 17 0
0 28 Total Tubes Plugged 21 31 5
1 58 Total Tubes Plugged (%)
0.32%
0.92%
0.08%
0.02%
0.22%
Note: Steam Generator Inspections Were Not Performed During Al R09.
Additional information concerning the steam generator eddy current inspection results can be obtained in the report submitted to the Nuclear Regulatory Commission as required byTechnical Specification 5.6.9.
Page 2-4
Braidwood Station Unit 1 A1R12 151 Outage Report 3.0 COMPONENT DETAILED EXAMINATION TABLES 3.1 Detailed Inservice Weld/Component Table(s):
The table for this section (Pages 3-5 to 3-22) lists the examinations performed for Section Xl Inservice and Augmented Inspection requirements for Class 1 and 2 welds and components. The general format of how the table is set-up is shown below. A description of the information contained in each column can be found in Section 3.5.
Section ~l 181 Identifier Line Relief Program Code Exam Actual Results Cat. Item Descri tion Number/EPN Request Notes Coverage Summary Exam Inspection Comments (A)
(B)
(C)
(D)
(E)
(F)
(G)
(H)
(I)
(K) 3.1.1 Detailed Preservice Weld/Component Table(s):
The table for this section (Page 3-23) lists the baseline examinations performed for Section XI Preservice Inspection requirements for Class 1 components replaced during A1R12. 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 3.5.
Section Xl ~ ISI Identifier Line Relief Program Code Exam Actual Results Lc~t.Item I
Description Number/EPN
~q~st Notes Covera e Summary Exam I Inspection Comments (A)
(B)
(C)
(D)
(E)
(F)
(G)
(H)
(I)
(K)
(J) 3.2 Detailed lnservice Component Support Table:
The table for this section (Pages 3-24 to 3-32) lists the examinations performed for Section Xl Inservice Inspection requirements for Class i and 2 component supports. The general format of how the table is set-up is shown below. A description of the information contained in each column can be found in Section 3.5.
Section Xi ISI Identifier Line Number/EPN Relief Program Exam Results Cat. Item Description Re uest Notes Summary Inspection Comments (A)
(B)
(C)
(D)
(E)
(G)
(I)
(K) li~
Page 3-i
Exekm Braidwood Station Unit 1 Al Ri 2 1St Outage Report 3.3 Detailed Inservice Snubber Table:
The table for this section (Pages 3-33 to 3-41) lists the examinations performed for Section Xl Inservice Inspection requirements for Class 1 and 2 snubbers. The general format of how the table is set-up is shown below. A description of the information contained in each column can be found in Section 3.5.
I Section XI ISI Identifier Line Number/EPN Relief Program Exam Results
~
Item Description Request Notes Summary I Inspection Comments (A)
(B)
(C)
(0)
(E)
(G)
(I)
(K)
(J) 3.3.1 Detailed Preservice Snubber Table:
The table for this section (Pages 3-42 to 3-43) lists the baseline examinations performed for Section XI Preservice Inspection requirements for Class 1 and 2 snubbers replaced during AlRi2. 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 3.5.
Section XI ISl identifier Line Number/EPN Relief Program Exam Results Cat. Item Description Request Notes Summary Inspection Comments (A)
(B)
(C)
(D)
(E)
(G)
(I)
(K)
(J) 3.4 Detailed lnservice Pressure Test Table(s):
The table for this section (Pages 3-44 to 3-48) lists the examinations performed for Section Xl Inservice and Augmented Inspection requirements for Class 1 and 2 pressure test blocks. The general format of how the table is set-up is shown below. A description of the information contained in each column can be found in Section 3.5.
[Section Xl ISI Identifier Relief Program Exam Results Cat. Item I Desc~p~on Re uest jj~tes Summary I
Inspection Comments (A)
(B)
(0)
(E)
(G)
(i)
(K)
(J)
Page 3-2
Exekit.
Braidwood Station Unit 1 A1R12 1St Outage Report 3.4.2 Borated Bolted Connection Inspections The table for this section (Pages 3-49 to 3-53) 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 3.5.
Relief Program Exam Results Reauest Notes Summary
~~----1 (D)
(E)
(G)
(I) 3.5 General Inservice Report Information 3.5.1 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 bythe IS! database.
(B)
This column contains the 151 Identifier that the IS! 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 IS! 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 IS! Program Plan note(s) that is associated with that Component. A complete copy of the Program note can be found in the IS! Program Plan.
(F)
This Column identifies the percentage of code coverage achieved for the associated 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.
Section Xl ISI Identifier
[çjte~j~scription I Inspection Comments (A)
(B)
(K)
(J)
Page 3-3
Braidwood Station Unit 1 Al Ri 2 lSI Outage Report 3.5.2 Report Abbreviations BMV Bare Metal Visual Inspection FUNCT Snubber Functional Test 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 3-4
Braidwood Station Unit 1 A1RI2 1St Outage Report Section 3.1 Detailed lnservice Inspection Weld I Component Listing (Page 1 of 18)
SYSTEM: Containment Spray System (CS)
I Section x~ I 1St Identifier
[Cat.__Item 10escriptio~~
Inspection Comments Line Number!EPN Relief Program
~
Exam Summary Actual I Exam Resu~J C-C C03.20 1CS-02-SWO1 360 DEGREE WELD 1CS1OAA-&
ED PIPE SADDLE 12R-15 NOTE 4 100 SUR PT NA!
Page 3-5
Exekit Braidwood Station Unit 1 A1R12 1St Outage Report Section 3.1 Detailed Inservice Inspection Weld / Component Listing (Page 2 of 18)
SYSTEM: Chemical & Volume Control System (CV)
~
~juneNumber/EPN
~
Inspection Comments A-A AOl 11 1 CV-05-03 1CVA3B-2~
NOTE 4 VT-2 VT-2 NA!
PIPE - ELBOW A-A ROi.il 1CV-05-04 1CVA3B-2~
NOTE 4 vT-2 VT-2 NA!
ELBOW - PIPE A-A AOl.11 1CV-05-05 1CVA3B-2~
NOTE 4 VT-2 VT-2 NA!
PIPE-ELBOW A-A A01.il 1CV-05-06 1CVA3B-2~
NOTE4 VT-2 VT-2 NA!
ELBOW - PIPE A-A ROill 1CV-05-13 1CVA3B-2 NOTE4 VT-2 VT-2 NA!
PIPE - ELBOW A-A A01.I1 1CV-05-14.01 1CVA3B-2 NOTE4 VT-2 VT-2 NA!
ELBOW - PIPE B-G-2 807.50 1CV-06-B1 1CV14GA-1.5 VT-i VT-i NA!
FLANGE BOLTING (4 STUDS)
B-G-2 807.50 ICV-06-B2 1CVI4GD-1.5 VT-i VT-I NA!
FLANGE BOLTING (4 STUDS)
A-A A01.11 1CV-11-06 1CVA6AA-2 NOTE4
/T-2 VT-2 NA!
PIPE - ELBOW A-A R0l.11 1CV-li-07 1CVA6AA-2 NOTE4 VT-2 VT-2 NA!
ELBOW - P!PE B-G-2 B07.50 1CV-16-Bi icvi4oc-i,5 VT-i VT-i NA!
FLANGE BOLTING (4 STUDS)
P-A P01.20 1CV-21-0l 1CVO1PA NOTE 4 50 VOL-E UT-35 NA!
1CVO1PA-i PUMP CASING-FLANGE NOTE 7 UT-45 NA!
_________UT-60L NA!
A-A P01.20 1CV-21-03 1CVO8AA-4 NOTE 4 93.5 VOL-E UT-35 NA!
ELBOW - ELBOW NOTE 7 UT-45 NRI UT-60L NA!
A-A P01.20 1CV-21-04 lCV08AA-4~
NOTE 4 98.7 VOL-E UT-35 NA!
ELBOW - PIPE NOTE 7 UT-45 NA!
UT-60L NA!
A-A R01.20 1CV-21-07 1CVO8AA-4 NOTE 4 50 VOL UT-45 NA!
VALVE 1CV8481A - PIPE NOTE 7 UT-60L NA!
A-A A01.20 1CV-21-08 1CVO8AA-4 NOTE 4 50 VOL-E UT-45 NA!
PIPE - TEE NOTE 7 UT-60L NA!
R-A R01.20 1CV-21-ii 1CV08AA-4~
NOTE4 100 VOL-E UT-45 NA!
ELBOW - PIPE NOTE 7 A-A P01.20 1CV-21-12 1CVO8AA-4 NOTE4 100 VOL-E UT-45 NA!
PIPE - ELBOW NOTE 7 A-A Aol 20 1CV-21-13 1CV08AA-4~
NOTE 4 100 VOL-E UT-45 NA!
ELBOW - PIPE NOTE 7 Page 3-6
Exekn.
Braidwood Station Unit 1 A1R12 1St Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 3 of 18)
SYSTEM: Chemical & Volume Control System (CV)
[~ct~~Number/EPNl 8t j~~m 1 ~
~
J Inspection Comments A-A P01.11 1AC-36-15 1CVA3AA-2~
NOTE4 VT-2 VT-2 NA!
PIPE - ELBOW A-A AOl.11 1 AC-36-1 6 1 CVA3AA-2~
NOTE 4 VT-2 VT-2 NP!
ELBOW - PIPE A-A P01.11 1AC-36-17 1cVA3AA-2~
NOTE 4 VT-2 VT-2 NA!
PIPE - ELBOW A-A P01.11 1AC-36-18 1CVA3AA-2~
NOTE 4 VT-2 VT-2 NA!
ELBOW
- PIPE A-A A0i.il lRc-37-i1 1CVA7AA-2 NOTE 4 VT-2 VT-2 NA!
PIPE - ELBOW P-A P01.11 1AC-37-12 iCVA7AA-2~
NOTE 4 VT-2 VT-2 NP!
ELBOW - PIPE C-C C03.30 1AHP-01-CVP-01 (A PUMPICVO1PA I2R-02 NOTE 4 100 VT-1 NP!
PUMP SUPPORT PAD I2R-lS 77.7 SUP NA!
Examination and coverage achieved in accordance with Relief Aequest 12A-02. Limitations for attachments CVP-2 and CVP-4 reduce liquid penetrant examination coverage to 77.7%
Page 3-7
Exet~n.
Braidwood Station Unit 1 AIR12 1St Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 4 of 18)
Section XI ISI Identifier Line Number!EPN Relief Item Description J,,,Request Program J Code Exam Notes
~verag~I,.Summary Actual Exam
~esu~J Inspection Comments A-A P01.11 1FW-01-19 1FWO3DD-l&
NOTE 4 100 VOL-E UT-45 NRI P01.18 PIPE-ELBOW NOTE7 A-A P01.11 1FW-01-20 1FWO3DD-16 NOTE 4 100 VOL-E UT-45 NA!
P01.18 ELBOW-PIPE NOTE7 A-A P01.11 1FW-Oi-33 1FW03DD-16~
NOTE 4 100 VOL-E UT-45 NP!
P01.18 PIPE-ELBOW NOTE7 P-A R01.11 1FW-03-04 1FWO3DB-16 NOTE4 100 VOL-E UT-45 NA!
P01.18 VALVE 1FWOO9B-P!PE NOTE 5 NOTE 7 UT-60 NA!
A-A P0111 1 FW-03-05 I FWO3DB-16 NOTE 4 100 VOL-E UT-45 NP!
P01.18 P!PE-P!PE NOTES NOTE 7 A-A P01.11 1FW-03-O5A 1FW03DB-16~
NOTE4 100 VOL-E UT-45 NP!
P01.18 PIPE-PENETRAT!ON(1PC-084)
NOTES NOTE_7 A-A P01.11 1FW-04-046 1FW03DC-16~
NOTE4 100 VOL-E UT-45 NA!
P01.18 PIPE-PIPE NOTE5 NOTE 7 A-A P01.11 1FW-04-05 1FWosDc-16 NOTE 4 100 VOL-E UT-45 NP!
P01.18 PIPE - PENETRATION (1Pc-o87)
NOTE 5 NOTE 7 A-A P01.11 1FW-04-17 1FwosDc-16 NOTE 4 100 VOL-E UT-45 NA!
P01.18 PIPE-ELBOW NOTE7 P-A P01.11 1FW-04-18 1FWO3DC-16 NOTE 4 100 VOL-E UT-45 NA!
P01.18 ELBOW-PIPE NOTE7 A-A P01.11 1FW-04-19 1FWO3DC-16° NOTE4 100 VOL-E UT-45 NA!
P01.18 PIPE-ELBOW NOTE7 A-A P01.11 1F\\N-05-29 1FW81BB-6 NOTE4 100 VOL-E UT-45 NPI P01.18 PIPE - TEE NOTES NOTE 7 UT-45 NA!
Two different examination frequencies (2.25 MHz and 5.0 MHz) were utilized.
P-A P01.11 1FW-05-31 1FW87CB-6~
NOTE 4 100 VOL-E UT-45 NP!
P01.18 TEE - PIPE NOTES NOTE 7 UT-45 NP!
Two different examination frequencies (2,25 MHz and 5.0 MHz) were utilized.
P-A P01.11 1FW-05-36 1FW87CB-6 NOTE4 100 VOL-E UT-45 NA!
P01.18 PIPE-l6~x6~
VESSELET NOTES NOTE 7 A-A P01.11 1FW-10-32 1FW87CC-6 NOTE4 100 VOL-E UT-45 NP!
P01.18 TEE - PIPE NOTES NOTE 7 UT-45 GEO Two different examination frequencies (2.25 MHz and 5.0 MHz) were utilized.
Page 3-8
Exekn.
Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.1 Detailed Inservice Inspection Weld / Component Listing (Page 5 of 18)
SYSTEM: Main Steam System (MS)
I ~I td~nfe jJne Number / EPN
~e!ief~
~~rc~9ram~~
Inspection Comments I
C-C C03.20 1MS-01-SWO8 TO SWO9 1MSO1AD-30.25
!2A-15 NOTE 4 100 (8) LUG ATrACH. FOP 1MSO8007S P-A P01.20 1MS-06-3O lMS13AB-8~
NOTE 4 100 PIPE - ELBOW NOTE 5 NOTE 7 P-A P01.20 1MS-06-31 1MS13AB-8 NOTE 4 100 ELBOW-PIPE NOTES NOTE 7 A-A P01.20 1MS-06-32 PIPE - ELBOW IMS13AB-&
NOTE 4 NOTE S NOTE 7 100 P-A AOl.20 IMS-06-33 ELBOW - PIPE 1MS13AB-8 NOTE 4 NOTE 5 NOTE 7 100 P-A P01.20 IMS-06-34 PIPE - ELBOW IMS13AB-8 NOTE 4 NOTE S NOTE 7 100 P-A P01.20 1MS-08-34 ELBOW-PIPE 1MS13AC-8 NOTE 4 NOTES NOTE 7 100 P-A P01.20 IMS-08-35 PIPE - ELBOW 1MS13AC-8 NOTE 4 NOTE 5 NOTE 7 100 P-A P01.20 1MS-08-36 ELBOW-PIPE 1MS13AC-8~
NOTE 4 NOTES NOTE 7 100 P-A AOl.20 1MS-08-37 PIPE - ELBOW 1MS13AC-8~
NOTE 4 NOTE S NOTE 7 100 SUP MT MT NP!
NP!
VOL-E UT-45 NP!
VOL-E UT-45 NP!
VOL-E UT-45 NP!
VOL-E UT-45 NP!
VOL UT-45 NA!
VOL-E UT-45 NP!
VOL-E UT-45 NA!
VOL-E UT-45 NA!
VOL-E UT-45 NA!
Page 3-9
Exek n.
Braidwood Station Unit 1 AIRI2 151 Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 6 of 18)
SYSTEM: Reactor Coolant System (RC)
- ti:~J~jjsj~zam LC0ve4mma4E~mJ1 Inspection Comments P-A P01.20 1 PC-02-04A THERMOWELL NOTE 4 VT-2 VT-2 NA!
BRANCH CONNECTION - THEPMOWELL P-A AOl.20 1PC-02-09 1PC29AB-10 NOTE 4 100 VOL-E UT-45L NP!
10 BPANCH NOZZLE - 27.5 PIPE A-A P01.20 1AC-03-21A THEPMOWELL NOTE 4 VT-2 VT-2 NP!
BRANCH CONNECTION - THEPMOWELL P-A P01.20 1PC-17-05 1RC24AA-4~
NOTE 4 100 VOL-E UT-45 NP!
PIPE - ELBOW P-A AOl.20 1PC-17-06 1PC24AA-4 NOTE 4 100 VOL-E UT-45 NP!
ELBOW - PIPE A-A P01.20 1PC-17-09 1RC24AA-4 NOTE4 100 VOL-E UT-45 NP!
ELBOW - PIPE P-A P01.20 1PC-17-1O lPC24AA-4~
NOTE 4 100 VOL-E UT-4S NP!
PIPE - PIPE A-A P01.20 1AC-17-11 1AC24AA-4~
NOTE 4 100 VOL-E UT-45 NP!
PIPE - ELBOW P-A AOl.20 1PC*17-13 lPC24AA-4~
NOTE 4 50 VOL-E UT-45 NP!
PIPE - VALVE 1AY022 P-A P01.20 1AC-23-01 1PC22AA-1.S NOTE 4 VT-2 VT-2 NP!
3Xl.S PEDUCEP - PIPE P-A P01.20 1PC-23-02 1PC22AA-1.5~
NOTE 4 VT-2 VT-2 NP!
PIPE - ELBOW P-A AOl.20 1PC-23-03 1RC22AA-1.S~
NOTE 4 VT-2 VT-2 NP!
ELBOW - PIPE P-A P01.20 1PC-23-04 lRC22AA-1.5~
NOTE 4 VT-2 VT-2 NP!
PIPE - ELBOW P-A P01.20 1PC-23-OS 1PC22AA-1.5~
NOTE 4 VT-2 VT-2 NP!
ELBOW
- PIPE A-A P01.20 1PC-27-O4AA 1PC22AA-1.5 NOTE 4 VT-2 VT-2 NA!
PIPE - ELBOW P-A P01.20 1PC-27-O5AA 1PC22AA-1.5 NOTE 4 VT-2 VT-2 NP!
ELBOW - PIPE P-A P01.20 1PC-27-O6AA 1AC22AA-i.5~
NOTE 4 VT-2 VT-2 NPI PIPE - ELBOW P-A P01.20 1PC-27-O7AA 1PC22AA-1.5~
NOTE 4 VT-2 VT-2 NP!
ELBOW - PIPE P-A P01.20 1PC-27-O8AA 1AC22AA-1.5~
NOTE4 VT-2 VT-2 NA!
PIPE - VALVE 1PC8045A P-A P01.11 1PC-29-01-03 1PC16AC-2~
NOTE4 VT-2 VT-2 NA!
PIPE - BRANCH CONNECTION Page 3-10
Exekn.
Braidwood Station Unit 1 A1R12 ISI Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 7 of 18)
SYSTEM: Reactor Coolant System (RC)
[~tion Xl I!Sl Identifier Line Number/ EPN Relief Program Code Exam Actual Results Item
,[~~criPtion
~j,~iequest__Notes
~f~rage__Summary Exam [
Inspection Comments P-A P01.11 1PC-29-0l-04 1RC16AD-2~
NOTE4 VT-2 VT-2 NA!
PIPE - BRANCH CONNECTION A-A P01.11 1PC-29-02-03 1RC16AC-2 NOTE4 VT-2 VT-2 NP!
ELBOW - PIPE P-A P01.11 1RC-29-02-04 1PC16AD-2 NOTE4 VT-2 VT-2 NRI ELBOW - PIPE P-A P01.11 1PC-29-03-03 1PC16AC-2 NOTE4 VT-2 VT-2 NP!
PIPE - ELBOW P-A P01.11 1RC-29-03-04 1PCl6AD-2~
NOTE4 VT-2 VT-2 NP!
PIPE - ELBOW P-A P01.11 1PC-29-04-03 1RC16AC-2 NOTE 4 VT-2 VT-2 NP!
ELBOW - PIPE P-A P01.11 1PC-29-04-04 1RC16AD-2 NOTE4 VT-2 VT-2 NP!
ELBOW - PIPE____________________________________________
A-A P01.11 1RC-29-05-03 1AC16Ac-2 NOTE 4 VT-2 VT-2 NP!
PIPE - ELBOW P-A P01.11 1PC-29-05-04 1AC16AD-2 NOTE 4 VT-2 VT-2 NP!
PIPE - ELBOW A-A P01.11 1RC-29-06-03 lPC16AC-2~
NOTE 4 VT-2 VT-2 NRI VALVE 1PC8038C - PIPE P-A P01.11 1PC-29-06-04 1PC16AD-2 NOTE 4 VT-2 VT-2 NP!
VALVE 1AC8038D - PIPE P-A P01.11 1RC-31-01 1PC14AB-2 NOTE 4 VT-2 VT-2 NP!
BRANCH CONNECTION - PIPE P-A P01.11 1AC-3l-02 1ACl4AB-2~
NOTE 4 VT-2 VT-2 NP!
PIPE - VALVE 1 PC8039B P-A P01.11 1PC-31-03 1AC14AB-2 NOTE 4 VT-2 VT-2 NA!
VALVE 1PC8039B - PIPE A-A P01.11 1PC-3l-04 lPCl4AB-2~
NOTE 4 VT-2 VT-2 NP!
PIPE - TEE P-A P01,11 1PC-3l-05 1PC14AB-2 NOTE 4 VT-2 VT-2 NA!
TEE - 2X.75~REDUCER P-A P01.11 1PC-3l-06 1PCl4AB-2~
NOTE4 VT-2 VT-2 NA!
TEE - PIPE P-A P01.11 1PC-3l-07 1PC14AB-2~
NOTE4 VT-2 VT-2 NA!
PIPE - VALVE 1 PC8037B P-A P01.20 1PC-31-08 1PC26A-Z NOTE4 VT-2 VT-2 NA!
BRANCH CONNECTION - PIPE P-A P01.11 1PC-36-o1 1PC14AA-2 NOTE4 VT-2 VT-2 NP!
BRANCH CONNECTION - PIPE Page 3-li
Exek:n.
Braidwood Station Unit 1 A1R12 1Sf Outage Report Section 3.1 Detailed Inservice Inspection Weld / Component Listing (Page 8 of 18)
SYSTEM: Reactor Coolant System (RC)
Section Xl IIS! Identifier I Line Number! EPN L~tem~J,~~riPtlon Inspection Comments P-A P01.11 1PC-36-02 1AC14AA-2 NOTE4 VT-2 VT-2 NP!
PIPE - ELBOW P-A P01.11 1RC-36-03 1PC14AA-2 NOTE4 VT-2 VT-2 NA!
ELBOW - PIPE P-A P01.11 1RC-36-04 1Ac14AA-2 NOTE 4 VT-2 VT-2 NP!
PIPE - VALVE 1AC8039A P-A P01.11 IPC-36-O5 IRC14AA-2 NOTE 4 VT-2 VT-2 NA!
VALVE 1PC8039A - PIPE P-A P01.11 1PC-36-06 1PC14AA-2° NOTE4 VT-2 VT-2 NP!
PIPE - TEE P-A P01.11 1AC-36-07 1PC14AA-2° NOTE 4 VT-2 VT-2 NRi TEE - 2X.75~REDUCER A-A P01.11 1PC-36-08 1PC14AA-2~
NOTE 4 VT-2 VT-2 NP!
TEE - PIPE P-A P01.11 1AC-36-09 IPC14AA-2 NOTE 4 VT-2 VT-2 NP!
PIPE - VALVE 1AC8037A P-A P01.11 1RC-36-20 1AC14AA-2 NOTE 4 VT-2 VT-2 NP!
PIPE-TEE P-A P01.11 1RC-36-22 lPC86AA-2~
NOTE 4 VT-2 VT-2 NA!
TEE-2Xl REDUCER P-A P01.11 1RC-37-01 1AC14AD-2 NOTE 4 VT-2 VT-2 NP!
BRANCH - PIPE P-A P01.11 IPC-37-02 1PCI4AD-2 NOTE 4 VT-2 VT-2 NA!
PIPE - ELBOW P-A P01.11 1PC-37-03 1PC14AD-2 NOTE 4 VT-2 VT-2 NA!
ELBOW
- PIPE P-A P01.11 1PC-37-04 1AC14AD-2~
NOTE4 VT-2 VT-2 NA!
PIPE - VALVE 1 RC8039D P-A P01.11 1PC-37-05 1AC14AD-2~
NOTE 4 VT-2 VT-2 NP!
VALVE 1 PC8039D - PIPE P-A P01.11 IPC-37-06 1PCl4AD-2~
NOTE 4 VT-2 VT-2 NP!
PIPE - TEE P-A P01.11 1AC-37-07 1PCl4AD-2~
NOTE 4 VT-2 VT-2 NA!
TEE - 2~X,7SREDUCER A-A P01.11 1RC-37-08 1AC14AD-2~
NOTE4 VT-2 VT-2 NA!
TEE - PIPE P-A P01.11 1PC-37-09 1PCl4AD-2~
NOTE 4 VT-2 VT-2 NP!
PIPE - VALVE 1 PC8037D P-A P01.11 1PC-41-O1AA 1PC16AA-2~
NOTE4 VT-2 VT-2 NP!
PIPE - BRANCH CONNECTION Page 3-12
Bcekn.
Braidwood Station Unit 1 A1R12 ISI Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 9 of 18)
SYSTEM: Reactor Coolant System (RC)
Section XI IS! Identifier I Line Number / EPN Item Description Inspection Comments P-A P01.11 1AC-4l-O1AB 1PC16AB-2 NOTE 4 VT-2 VT-2 NP!
PIPE - BRANCH CONNECTION P-A P01.11 1PC-4l-O2AA 1RC16AA-2 NOTE 4 VT-2 VT-2 NA!
ELBOW - PIPE A-A P01.11 1AC-4l-O2AB 1AC16AB-2 NOTE 4 VT-2 VT-2 NP!
ELBOW - PIPE P-A P01.11 1PC-41-03AA 1PCI6AA-2 NOTE 4 VT-2 VT-2 NP!
P!PE - ELBOW P-A P01.11 1AC-41-O3AB 1AC16AB-Z NOTE 4 VT-2 VT-2 NA!
PIPE - ELBOW P-A P01.11 1AC-41-O4AA 1Pc16AA-2~
NOTE 4 VT-2 VT-2 NP!
ELBOW - PIPE P-A R01.11 IPC-41-O4AB 1Pc16AB-2~
NOTE 4 VT-2 VT-2 NP!
VALVE 1PC8038B - PIPE P-A P01.11 1AC-41-O5AA 1AC16AA-2~
NOTE 4 VT-2 VT-2 NA!
PIPE - ELBOW P-A P01.11 1AC-41-O6AA lACl6AA-2~
NOTE 4 VT-2 VT-2 NP!
VALVE 1 PCSO38A - PIPE P-A P01.11 1PC-42-01 1PC14AC-2~
NOTE 4 VT-2 VT-2 NPI BRANCH CONNECTION - PIPE A-A P01.11 1PC-42-02 1PC14AC-2 NOTE 4 VT-2 VT-2 NP!
PIPE - ELBOW P-A P01.11 1PC-42-03 1PC14AC-2~
NOTE 4 VT-2 VT-2 NP!
ELBOW - PIPE A-A P01.11 1RC-42-04 lPC14AC-2~
NOTE 4 VT-2 VT-2 NP!
PIPE - VALVE 1 PC8039C A-A P01.11 1AC-42-05 1PCl4AC-2~
NOTE4 VT-2 VT-2 NP!
VALVE 1PC8039C
- PIPE A-A P01.11 1PC-42-06 1PC14AC-2~
NOTE 4 VT-2 VT-2 NP!
PIPE - TEE P-A P01.11 1PC-42-07 1PC14AC-2~
NOTE4 VT-2 VT-2 NP!
TEE - 2 X3/4 REDUCER A-A P01.11 1PC-42-08 1 PC1 4AC-2~
NOTE 4 VT-2 VT-2 NP!
TEE - PIPE P-A P01.11 1PC-42-09 1PC14AC-2~
NOTE4 VT-2 VT-2 NP!
PIPE - VALVE 1 PCBO37C P-A P01.11 IPC-42-lO 1PC14AC-2 NOTE4 VT-2 VT-2 NP!
PIPE - TEE A-A P01.11 1PC-42-11 1PC14AC-2~
NOTE 4 VT-2 VT-2 NP!
TEE - PIPE Page 3-13
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Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.1 Detailed Inservice Inspection Weld / Component Listing (Page 10 of 18)
SYSTEM: Reactor Coolant System (RC)
Section XI IS! Identifier Cat.
Item Description F Inspection Comments P-A P01.11 1PC-42-12 TEE - 2Xl REDUCER 1 PC14AC-2 6-G-1 B06.180 1ACP-Ol-PCP-PA-01 TO 24 PCO1PA 606.190 PCP MAIN FLANGE BOLT(0l TO 24)
NOTE 2 VT-1 VT-1 NP!
P-A P01.15 1PV-01-022 1ACO1R
!-600 NOZZLE - SAFE END (22 DEG.)
Bare metal visual examination in accordance with MAP 2003-039.
!2A-16 NOTE4 BMV BMV NA!
NP!
P-A P01.15 1PV-01-023 1RCO1R 1-600 SAFE END - NOZZLE (67 DEG.)
Bare metal visual examination in accordance with MAP 2003-039.
!2P-16 NOTE 4 BMV BMV P-A P01.15 1PV-O1-024 1PCO1P 1-600 SAFE END - NOZZLE (113 DEG.)
Bare metal visual examination in accordance with MAP 2003-039.
!2P-16 NOTE 4 BMV BMV NP!
P-A P01.15 1AV-0l-025 1RCO1R 1-600 NOZZLE - SAFE END (158 DEG.)
Bare metal visual examination in accordance with MRP2003-039.
12P-16 NOTE 4 BMV BMV NP!
P-A P01.15 1AV-01-026 1ACO1P 1-600 NOZZLE - SAFE END (202 DEG.)
Bare metal visual examination in accordance with MAP 2003-039.
12P-16 NOTE 4 BMV BMV NP!
P-A P01.15 1AV-01-027 1RCO1P 1-600 SAFE END - NOZZLE (247 DEG.)
Bare metal visual examination in accordance with MAP 2003-039.
I2R-16 NOTE 4 BMV BMV NP!
P-A P01.15 1AV-01-028 1PCOIA 1-600 SAFE END - NOZZLE (293 DEG.)
Bare metal visual examination in accordance with MAP 2003-039.
l2P-16 NOTE 4 BMV BMV NP!
P-A P01.15 1RV-01-029 1PCO1R 1-600 NOZZLE - SAFE END (338 DEG.)
Bare metal visual examination in accordance with MAP 2003-039.
12P-16 NOTE4 BMV BMV NPI B-E B04.13 1AV-02-!NSTA. NOZZLES 1ACO1A 1-600 Ax VESSEL INSTRUMENTATION NOZ.
VT-2 VT-2 NA!
B-G-l 606.10 1AV-03-NUTS (01 TO 54) 1PC01P 12R-19 VT-i VT-i CLOSURE HEAD NUTS (54 TOTAL)
Examined nuts 89-2-4014-51-27, 28, 29, 30, 32, 33, 34, 35, 36, 37, 38, 39, 40, 41, 42, 43, 44, 45 per original scope. Also examined 31 per request of Reactor Services to check for damage from stud detensioner.
NP!
B-G-1 806.30 IRV-03-STUDS(01 TO 54) 1RC01R VOL UT-0 NRI CLOSURE HEAD STUDS (54 TOTAL>
Examined studs in stud holes 23, 24, 25, 26, 27, 28, 29, 30, 31, 32, 33, 34, 35, 36, 37, 38, 39, and 40. Surface examination is no longer required per Code Case N-652 approved in Regulatory Guide 1.147, Revision 14.
8-G-1 606.50 1PV-03-WASHEPS 1PCO1R VT-i VT-i NA!
CLOSURE WASHERS (01 TO 54)
Examined 89-4401 4-51 Top Washers (89-A3-401 4-SI Bottom Washers) - 28, 29, 30, 31, 32, 33, 34, 35, 36, 37, 38, 39, 40, 41, 42, 43, 44, 45.
I Line Number / EPN NOTE 4 VT-2 VT-2 NAI Page 3-14
Exek; Braidwood Station Unit 1 A1R12 ISI Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 11 of 18)
SYSTEM: Reactor Coolant System (RC)
Section Xl lSl Identifier Cat.
Item Description Inspection Comments 8-0 816.20 1SG-0S-1RCO1BA TUBING 1PCO1BA ET ET STEAM GENERATOR TUBING See Section 2.5 of report for details of examination. Eleven tubes were plugged in this steam generator during A1P12.
IND.
B-Q 816.20 1SG-06-1PCO1BBTUBING1PCO1BB ET ET IND.
STEAM GENERATOR TUBING See Section 2.5 of report for details of examination. Seventeen tubes were plugged in this steam_generator during Al P12.
6-0 616.20 1SG-07-1PCO1BCTUB!NG1PCO1BC ET ET NRI STEAM GENERATOR TUBING See Section 2.5 of report for details of examination. No tubes were plugged in this generator during Al P12.
6-G-1 806.90 1SG-07-SGB-0i 1PCO1BC VT-i VT-i NP!
806.100 PRIMARY MANWAY (20 STUDS and NUTS) 100 VOL UT-70 NR!
806.110 UT-80L NP!
B-C-i 806.90 1SG-07-SGB-02 1RCO1BC VT-i VT-I NP!
806.100 PRIMARY MANWAY (20 STUDS and NUTS) 100 VOL UT-70 NP!
806.110 UT-80L NP!
8-0 816.20 1SG-08-1RCO1BDTUBING1PCO1BD ET ET NRI STEAM GENERATOR TUBING See Section 2.5 of report for details of examination. No tubes were plugged in this generator during Al P12.
B-C-i 806.90 1SG-08-SGB-01 1PCO1BD VT-I VT-I NP!
606.100 PRIMARY MANWAY (20 STUDS and NUTS) 100 VOL UT-70 NP!
806.110 UT-80L NRI B-C-i 806.90 1SG-08-SGB-02 1PCO1BD VT-I VT-I NP!
806.100 PRIMARY MANWAY (20 STUDS and NUTS) 100 VOL UT-70 NRI 806.110 UT-80L NP!
P-A P01.11 ISI-16-22.01 IRC3OAD-l.5° NOTE4 VT-2 VT-2 NPI VALVE 1S!89000 - PIPE A-A P01.11 1S1-16-23 lPC3OAD-1.5~
NOTE4 VT-2 VT-2 NP!
PIPE - 3X11/2REDUCER P-A P01.11 1S!-17-01 lPC30AB-1.5~
NOTE4 VT-2 VT-2 NP!
PIPE - 3X11/2REDUCER______
P-A P01.11 1SI-17-02 1PC30AB-1.5~
NOTE4 VT-2 VT-2 NP!
VALVE 1S18900B - PIPE A-A P01.11 1SI-31-Oi 1PC30AA-1.5~
NOTE 4 VT-2 VT-2 NP!
PIPE - REDUCER P-A P01.11 1S1-31-02 1PC30AA-1.5~
NOTE 4 VT-2 VT-2 NA!
VALVE 1SIS900A - PIPE I Line Number / EPN Page 3-15
Ecekn.
Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.1 Detailed Inservice Inspection Weld / Component Listing (Page 12 of 18)
SYSTEM: Residual Heat Removal System (RH)
~SectionXl IS! Identifier
- Cat, Item
~
Re!~ef
~Req I Program I Code I
~
J Exam SummaryI Actual Exam I Resu!
J
~ispection Comments C-C C03.20 1RH-05-21B&22 1PHO2AA-8 l2P-lO NOTE 4 100 SUP PT NP!
- PIPE 12R-1S____
Page 3-16
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Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 13 of 18)
SYSTEM: Reactor Coolant System (RY) ion Xl
~i Identifier
~Ie Number /EPN
~
S~
- ~I1j_~eS;~ry Inspection Comments P-A P01.11 1CV-02-13 1PYl8A-2~
NOTE 4 VT-2 VT-2 NP!
VALVE 1CV8377 - PIPE P-A P01.11 1CV-02-l4 lAY18A-2~
NOTE 4 VT-2 VT-2 NA!
PIPE - ELBOW P-A P01.11 1CV-02-15 1RY18A-2~
NOTE4 VT-2 VT-2 NP!
ELBOW - PIPE P-A P01.11 1CV-02-16 1PY18A-2 NOTE4 VT-2 VT-2 NP!
PIPE - ELBOW P-A A01.11 1CV-02-17 1PY18A-2 NOTE4 VT-2 VT-2 NP!
ELBOW - PIPE P-A P01.11 1CV-02-18 IRYI8A-2 NOTE 4 VT-2 VT-2 NA!
PIPE - ELBOW P-A P01.11 1CV-02-19 1PY18A-2 NOTE 4 VT-2 VT-2 NA!
ELBOW - PIPE B-B 602.11 1PZR-01-08E 1PYO1S NOTE 4 99.1 VOL UT-45 NP!
SHELL-UPPER HEAD UT-60 NP!
B-B 80212 1PZP-01-09D 1PYO1S NOTE 4 100 VOL UT-45 NP!
SHELL LONG SEAM UT-60 NP!
Per Note 2 of Table !WB-2500-i Category B-B, extent of exam length is twelve inches from the associated circumferential weld.
B-G-2 807.20 1PZP-01-B1 1PYO1S VT-i VT-l NP!
MANWAY BOLTING_(16 TOTAL)
B-E 604.20 1PZR-01-HEATEP PENET.1RYO1S BMV VT-2 IND.
PRESSURIZER HEATER PENETRATION Visual NRI VT-2 NP!
During insulation removal for bare metal visual examination of pressuizer surge nozzle (non-Section Xl examination), boric acid was identified (reference IA 480489). Leakage was at Penetration #52. Portion of Penetration #52 containing socket welded coupling was removed and replaced by a welded plug (WO 915754-03/ EC 360630). The removed material was for analysis.
Final VT-2 was performed during ascending Mode 3 walk down.
Reference Braidwood LEA 2006-001 -00 (June 26, 2006).
B-D 603.110 1PZR-0l-N1 1RYO1S
!2P-08 NOTE4 20 VOL UT-4S NP!
PRESSURIZER - SURGE NOZZLE UT-60 NP!
Two insulation panels providing approximately an 80 degree arc of accessibility were removed to identify source of boric acid on surge nozzle mirror insulation. Accessible portions of nozzle-ta-vessel weld were examined per Relief Request l2P-08.
B-D 603.120 1PZP-0l-N1 (NIP) 1PYO1S I2P-08 NOTE 4 40 VOL UT-SO NA!
PRESSURIZER - SURGE NOZZLE INNEA RADIUS UT-55 NA!
Two insulation panels providing approxima~eIyan 80 degree arc of accessibility were removed to identify source of boric acid on surge nozzle mirror insulation. Accessible portions of nozzle inner radius were examined in accordance with Relief Request 12R-08.
B-D 803.110 1PZA-01-N4A 1PYO1S NOTE 4 100 VOL UT-45 NA!
PPESSUP!ZER - SAFETY NOZZLE UT-60 NP!
B-D 603.120 IPZP-01-N4A (NIP>
IPYO1S NOTE 4 100 IPS UT-24 NA!
PPESSUAIZEP - SAFETY NOZZLE INNER RADIUS UT-6S NA!
UT-70 NP!
Page 3-17
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Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 14 of 18)
SYSTEM: Reactor Coolant System (RY)
[~tion XI IS! Identifier Line N Description
[Inspection Comments umber I EPN Relief Request Program Notes Code Coverage Exam Summary Actual Results Exam B-K 610.10 1PZP-0l-PSL-01, -02, -03, 1PYO1S I2P-09 NOTE 4 VT-i AND -04 SEISMIC SUPPORT LUG I2P-IS SUP NP!
Best effort VT-l and liquid penetrant examinations performed in accordance with Relief Request 12P-09.
achieved on PSL-1, PSL-2, and PSL-3 for liquid penetrant examination. PSL-4 is totally inaccessible (0°/
Approximatel
~coverage).
y21.4% coverage P-A P01.11 1PZP-Ol-SE-01 1PY11A-14 NOTE4 BMV BMV NP!
P01.15 PZR SURGE NOZZLE - SAFE END 1-600 Bare metal visual examination in accordance with MAP 2003-039.
P-A P01.15 1PZR-01-SE-02 1PY03AA-6~
NOTE 4 BMV BMV NP!
1-600 PZP SAFETY NOZZLE - SAFE END Bare metal visual examination every outage per NRC Bulletin_2004-01 commitment.
P-A AOl.15 1PZP-0l-SE-03 1RYO3AB-6 NOTE 4 BMV BMV NP!
1-600 PZR SAFETY NOZZLE - SAFE END Bare metal visual examination every outage per NRC Bulletin 2004-01_commitment.
P-A P01.15 1PZR-01-SE-04 1PYO3AC-6 NOTE 4 BMV BMV NP!
1-600 PZR SAFETY NOZZLE - SAFE END Bare metal visual examination every outage per NRC Bulletin 2004-01 commitment.
A-A P01.11 1PZR-Ol-SE-05 1PY01B-6~
NOTE 4 BMV BMV NP!
POllS PZR SPRAY NOZZLE - SAFE END 1-600 Bare metal visual examination every outage per NRC Bulletin 2004-01 commitment..
P-A P01.15 1PZP-01-SE-06 1PY02A-6~
NOTE 4 BMV BMV NP!
1-600 PZP RELIEF NOZZLE - SAFE END Bare metal visual examination every outage per NRC Bulletin 2004-01 commitment.
P-A P01.11 1AC-04-03 1RYllA-l4~
NOTE 4 37.5 VOL-E UT-45L NA!
14 BRANCH NOZZLE - 29 PIPE P-A P01.11 1PC-05-08 1PY11A-i4 NOTE4 100 VOL-E UT-45 NP!
PIPE - 14 NOZZLE BRANCH CONNECTION P-A P01.20 1 PC-32-01 1 PYO3AA-6 NOTE 4 81.9 VOL-E UT-45 NA!
SAFE END - ELBOW P-A P01.20 1RC-32-03 1PYO3AA-6 NOTE 4 SO VOL-E UT-45 NP!
PIPE - ELBOW UT-60L NPI P-A AOl.20 1AC-32-04 1PYO3AA-6 NOTE 4 99.3 VOL-E UT-45 NA!
ELBOW - PIPE B-G-2 807.50 1PC-32-B4 1PYO3BA-6~
VT-i VT-i NP!
FLANGED CONNECTION (12 STUDS)
Page 3-18
Ecekn.
Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 15 of 18)
SYSTEM: Steam Generator (SG)
Section Xl IS! Identifier Description Inspection Comments C-A C01.10 C-B C02.21 1SG-05-SGN-03 1PCO1BA AUX FW NOZZLE - STEAM DRUM LOWER SHELL NOTE 4 100 100 SUP VOL MT UT-45 UT-6O NP!
NP!
NP!
C-B CO2.21 1SG-05-SGN-O4 1RCO1BA FW NOZZLE - STEAM DRUM LOWER SHELL NOTE 4 100 95 SUP VOL MT UT-45 UT-60 NP!
NP!
NP!
C-B CO2.22 1SG-OS-SGN-O4 (NIP) 1RCO1BA FW NOZZLE - STEAM DRUM LOWER SHELL NIP NOTE 4 95 IRS UT-35 UT-40 UT-45 UT-59 UT-60 NP!
NA!
NP!
NP!
NP!
I Line Number I EPN 1 SG-05-SGC-06 1 PCO1 BA SHELL CONE - STEAM DRUM LOWER SHELL NOTE 4 100 VOL UT-45 NP!
UT-60 NRI Page 3-19
Bcekn.
Braidwood Station Unit 1 Al Ri 2 151 Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 16 of 18)
SYSTEM: Safety Injection System (SI)
Section Xl IS! Identifier I Line Number! EPN
[f~__ltem~j~~riPtion Inspection Comments B-G-2 807.70 1SI-03-1S1881 8A (BLT) 1 SIO5DA-6 1S18818A CHECK VALVE (16 BLT)
Bolting examined in-place and under tension.
A-A P01.16 lSl-05-23 1SI09BB-lO PIPE - ELBOW NOTE4 100 VOL UT-45 UT-60 NP!
NP!
A-A P01.16 1SI-O5-24 iSlO9BB-10~
ELBOW - PIPE NOTE 4 97.8 VOL UT-45 UT-60 NP!
P-A P01.11 lSl-10-2S 1SI18FC-2 PIPE - ELBOW NOTE 4 VT-2 VT-2 NP!
P-A P01.11 151-10-26.01 1S!18FC-2 ELBOW - PIPE NOTE4 VT-2 VT-2 NP!
P-A P01.11 1SI-18-23 1SIO8JB-i.S VALVE 1S!8810B-PIPE NOTE4 VT-2 VT-2 NP!
P-A P01.11 1SI-18-24 1SIO8JB-1.5 PIPE - ELBOW NOTE4 VT-2 VT-2 NA!
P-A P01.11 1SI-18-2S 1SIO8JB-1.S~
ELBOW - PIPE NOTE4 VT-2 VT-2 VT-2 NP!
NP!
P-A P01.11 1SI-18-26 1S!O8JB-1.5 PIPE - ELBOW NOTE 4 VT-2 P-A P01.11 1SI-19-01 1S!O8GA-1.5 BRANCH CONNECTION - PIPE NOTE4 VT-2 VT-2 NRI P-A P01.11 1SI-i9-06 1S!O8HA-2~
COUPLING - PIPE NOTE4 VT-2 VT-2 NP!
P-A P01.11 1SI-19-07 1SIO8HA-2~
PIPE - FLANGE NOTE4 VT-2 VT-2 NP!
P-A P01.11 1SI-19-08 1SIO8HA-2 FLANGE - PIPE NOTE4 VT-2 VT-2 NP!
P-A P01.11 1S1-19-14 1SIO8JA-1.S PIPE - ELBOW NOTE4 VT-2 VT-2 NP!
P-A P01.11 1SI-19-15 1SI08JA-l.5~
ELBOW - PIPE NOTE 4 VT-2 VT-2 NA!
P-A P01.11 lSl-19-l6 1SlO8JA-l.5~
PIPE - VALVE 1SI881OA NOTE 4 VT-2 VT-2 NRI P-A P01.11 131-19-17 1SIO8JA-l.5~
VALVE 1S18810A - PIPE NOTE4 VT-2 VT-2 NP!
P-A P01.11 1SI-19-18 1SI08JA-1.5~
PIPE - FLANGE NOTE 4 VT-2 VT-2 NP!
P-A P01.11 1SI-19-20 1SlO8JA-1.5~
PIPE - ELBOW NOTE4 VT-2 VT-2 NP!
P-A P01.11 lSl-19-22 1Sl08JA~1.5a PIPE - ELBOW NOTE4 VT-2 VT-2 NA!
NOTE 3 VT-i VT-i NA!
Page 3-20
Bcek~.n.
Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.1 Detailed lnservice Inspection Weld / Component Listing (Page l7of 18)
SYSTEM: Safety Injection System (SI)
Section XI IS! Identifier I Line Number!EPN f~tem Description Inspection Comments A-A P01.11 1S!-19-23 lSl08JA-1.5~
ELBOW - PIPE A-A P01.11 1Sl-19-24 1 SIO8JA-i.5 PIPE - ELBOW B-K 810.20 1S1-21-09 1SIO3DA-2 PIPE - PENETRATION (1AB-061)
NOTE 4 VT-2 VT-2 NA!
NOTE 4 VT-2 VT-2 NA!
Page 3-21
Bcekin.
Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 18 of 18)
SYSTEM: Essential Service Water System (SX) lnsp C-C
~ti~nxIjd~n~fier ection Comments C03.2O 1SX-11-SWO1 STANCHION
~j Line Number I EPN 1SXO9BA-1O WELDED TO ELBOW 1!i~t I2A-15 NOTE 4 j~~e 100 Summary SUP E~
Ecekn.
Braidwood Station Unit 1 A1Ri2 IS! Outage Report Section 3.1.1 Detailed Preservice Inspection Weld I Component Listing (Page 1 of 1)
SYSTEM: Reactor Coolant System (RY)
Section XI IS! Identifier I Line Number! EPN Description (Inspection Comments B-G-2 B07.50 1PC-32-B4 1RY03BA-6~
VT-i VT-l NP!
FLANGED CONNECTION (12 STUDS)
Replaced inlet flange studs on Valve S/N N56964-O0-Oi 09 to accommodate use of hydranuts. Preservice VT-i performed under WO 773388.
B-G-2 B07.S0 1PC-32-B5 1AY03BB-6~
VT-i VT-i NP!
FLANGED CONNECTION (12 STUDS)
Replaced inlet flange studs on Valve S/N N56964-OO-0054 to accommodate use of hydranuts. Preservice VT-i performed under WO 793798.
B-G-2 807.50 1PC-32-B6 1RY03BC-6~
VT-i VT-i NP!
FLANGED CONNECTION (12 STUDS)
Replaced inlet flange studs on Valve S/N NS6964-O0-0i 10 to accommodate use of hydranuts. Preservice VT-i performed under WO 781899.
Page 3-23
BceI~n.
Braidwood Station Unit 1 AIRI2 IS! Outage Report Section 3.2 Detailed Inservice Inspection Component Support Listing (Page 1 of 9)
SYSTEM: Containment Spray System (CS)
Section Xl JISI Identifier Line Number I EPN Item j~~ription
[Inspection Comments F-A FO1.20 1CS03017X 1CS02AB-10~
NOTE 8 VT-3 NRI (1) Strut F-A F01.20 1CS03019V 1CSO2AB-10 NOTE 8 VT-3 NP!
(1) Variable Spring Can As found Spring Can Setting: 1320#. Lower
Attachment:
Clamp, Rod, and Spring Can: (Direct Upper
Attachment:
Structural Attachment and Upper Rod Assy. (Remote Examination 8 away).
F-A FOl.20 1CSO3O21P 1CSO2AB-iO NOTE 8 VT-3 NP!
(1) Strut F-A F01.20 1CSO3O88X 1CS10AA-6~
NOTE 8 VT-3 NA!
Box F-A F01.20 1CS03089A 1CS10AA-6~
NOTE 8 VT-3 NP!
Anchor, integrally attached to pipe Component painted, no indication of distress.
Page 3-24
Bcekn.
Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.2 Detailed Inservice Inspection Component Support Listing (Page 2 of 9)
SYSTEM: Chemical & Volume Control System (CV)
Section XI IS! Identifier Line Number! EPN Cat.
Item Description Inspection Comments F-A F01.40 1CVO1PA 1CVO1PA NOTE 8 VT-3 NA!
1A CV PUMP, integrally attached to pump F-A F01.lO 1CV16012G 1CVA7AB-2 NOTE 8 VT-3 NA!
Box F-A F01.10 1CV16014X 1CVA7AB-2~
NOTE 8 VT-3 NP!
Box F-A FOlIO 1CV22006X ICV45B-2~
NOTE 8 VT-3 NP!
(1) Strut Note: Insulation removed for exam.
Page 3-25
Bcekn.
Braidwood Station Unit 1 A1R12 ISI Outage Report Section 3.2 Detailed Inservice Inspection Component Support Listing (Page 3 of 9)
Section XI IS! Identifier Cat.
Item Description Inspection Comments F-A FOl.20 1 FWO40I SR (1) Strut F-A F01.20 IFWOSO18X 1FWO3DD-l6 NOTE 8 VT-3 NPI Box IFW03DC-16 NOTE 8 VT-3 NP!
Page 3-26
Bcekn.
Braidwood Station Unit 1 A1R12 ISI Outage Report Section 3.2 Detailed Inservice Inspection Component Support Listing (Page 4 of 9)
SYSTEM: Reactor Coolant System (RC)
Section XI IS! Identifier Line Number!EPN Cat.
Item Description Inspection Comments F-A FOliO 1CVOSO14X (1) Strut F-A FOliO 1CVO9O61R Box F-A FOliO 1CVO9O71G U-Bolt F-A F01.10 1CV12004V (1) Variable Spring Can As Found Setting: 460 lbs.
F-A FOliO 1CV13004R 1PC16AC-2~
Box F-A F0i.40 1RCO1BA 1RCO1BA S.G A Insulation loosened / pulled back from upper lateral restraint in order to perfrom examination.
F-A F01.40 1RCO1P 1PCO1R REACTOR Perform in conjunction with MAP visual inspection of A and C cold legs and B and D hot legs.
F-A FOliO 1PCO2001V 1PC21AB-8 (1) Variable Spring Can NOTE 8 VT-3 NA!
NOTE 8 VT-3 VT-3 NP!
NA!
NOTE 8 VT-3 NP!
NOTE 8 VT-3 NP!
1 PC36A-3~
1PC14AC-2 1 PCi 4AC-2 1 PCi 6AA-2 NOTE 8 NOTE 8 NOTE 8 NOTE 8 VT-3 VT-3 VT-3 VT-3 NA!
NP!
NA!
NA!
Page 3-27
Ecekn.
Braidwood Station Unit 1 A1R12 ISI Outage Report Section 3.2 Detailed Inservice Inspection Component Support Listing (Page 5 of 9)
SYSTEM: Residual Heat Removal System (RH)
L~ctionXl
~!Slldenfier
~J~ine Number! EPN J!ief
~Pr gram 5ryjt8~
Inspection Comments F-A F01,20 1PC-068A 1PHO1BA-12 NOTE 8 VT-3 NA!
Anchor, integrally attached to pipe Outside Containment Anchor, integrally attached to pipe VT-3 NA!
Exam performed on 04/24/2006 was on the portion of the component located inside containment. Exam performed on 02/16/2006 was on portion of component located outside the containment.
F-A FO1.20 1RHO4O14C lAH03AB-8~
NOTE 8 VT-3 NP!
(2) Constant Spring Cans, IWA to pipe Spring can settings intolerance. Size 17 Constant Supports (2 Cans Trapeze Type), Load 955#, T.T. = 3, A.T. 11/16 up. Remote examination performed (25 away). Travel Setting acceptable.
F-A F01.20 1RHO4O17G 1AHO3AB-8 NOTE 8 VT-3 NA!
Box Remote examination performed (20 away).
F-A FOl.20 1SI18O8SX 1AHO3AA-8 NOTE 8 VT-3 NP!
(1) Strut Page 3-28
Bcek~n Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.2 Detailed Inservice Inspection Component Support Listing (Page 6 of 9)
SYSTEM: Reactor Coolant System (RY)
Section XI IS! Identifier Cat.
Item Description Line Number!EPN J Relief Program Notes Exam j~~ary Results Inspection Comments F-A F01.40 1PYO1S 1PYO1S NOTE 8 VT-3 NP!
All PZA_Supports Page 3-29
Ecek ~
Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.2 Detailed lnservice Inspection Component Support Listing (Page 7 of 9)
SYSTEM: Safety Injection System (SI)
[Section XI IS! Identifier
[f~~em Description (Inspection Comments F-A P01.10 1PB-061A Anchor,_integrally attached to pipe F-A F01.10 1PH02020R (2) Struts F-A FOliO 1RHO2O21R Box F-A FO1.1O 1RH02072X (1) Strut F-A FOliO 1RHO2100X Box F-A FOliO 1SIO1O22X
_____________ (1) Strut F-A FOliO 1SIO1O73X (1)Strut F-A F0i.20 1S!O3005C (1)Constant Spring Can Actual Setting = 5 1/2 F-A FOliO 1SIO4O15R (1) Strut F-A FO1.20 1S!06098X (1) Strut, integrally attached to pipe F-A FOliO 1S!O9014R (2) Struts F-A FOliO 1S1O9036X Box F-A F01.iO 1S113104G U-Bolt F-A F01.20 1S!l5002G Box and Strut F-A F01.20 1SI15006R Box F-A F01,20 lS!15008R (1) Strut F-A F01,20 1SI15O1OX (1) Strut F-A F01.20 iSIl5Ol5X Box F-A F01.20 1SI18O24X Box F-A P01.20 1SI18O5OX (1) Strut 1SIO3DA-Z NOTE 8 VT-3 NP!
1~O4D-8~
NOTE 8 VT-3 NP!
1SIO4D-8 NOTE 8 VT-3 NP!
lSl04B-12~
NOTE 8VT-3 NP!
1SIO4B-12 NOTE 8 VT-3 NP!
1SlO5DA-6~
NOTE 8 VT-3 NP!
NP!
1S!O5DA-6 NOTE 8 VT-3 iSlO5cA-8 NOTE 8 VT-3 NP!
1SIO5DB-6 NOTE 8 VT-3 NP!
1SIO1B-24 NOTE 8 VT-3 NP!
1SIO5DC-6 NOTE 8 VT-3 NP!
1SIOSDC-6° NOTE 8 VT-3 NPI 1SI03DA-2~
NOTE 8 VT-3 NA!
1 S!O2BA-6 NOTE 8 VT-3 NP!
lS!l3BA-6~
NOTE 8 VT-3 NA!
NOTE 8 VT-3 NAI 1Sll3BA-6~
NOTE 8 VT-3 NP!
1SI02BA-6~
NOTE 8 VT-3 NA!
NOTES VT-3 NA!
1SIO2BA-6 NOTE 8 VT-3 NP!
Page 3-30
Exekn.
Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.2 Detailed Inservice Inspection Component Support Listing (Page 8 of 9)
SYSTEM: Safety Injection System (SI)
Section Xl IS! Identifier Description (Inspection Comments F-A F0l.2O 1S118060P Box F-A FOliO 1SI21O14G Box F-A FO1.10 1S121021A Anchor, integrally attached to_pipe F-A FOliO 1S!21022X (1) Strut F-A F0l.l0 1S!23001G Box Box Support.
1 Sl02BA-6~
1 5108FA-3~
1 SIO8FA-3 1 S!O8E-3 1 SIO8FA-Y NOTE 8 NOTE 8 NOTE 8 NOTE 8 NOTE 8 VT-3 VT-3 VT-3 VT-3 VT-3 NP!
NA!
NP!
NA!
NP!
Page 3-31
Bcekn Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.2 Detailed Inservice Inspection Component Support Listing (Page 9 of 9)
SYSTEM: Essential Service Water System (SX)
[::
Insp F-A ion XI j~identifl~~
J~e Number!EPN ection Comments F0i.20 1SXO81O1X 1SXO9BA-iO (1) Strut, integrally attached to pipe Program NOTE 8 Sum~IL~j VT-3 NPI Page 3-32
Bcekn..
Braidwood Station Unit I A1R12 IS! Outage Report Section 3.3 Detailed lnservice Inspection Snubber Listing (Page 1 of 9)
SYSTEM: Chemical & Volume Control System (CV)
~S~ct Insp F-A It~iXl ection Corn FOliO
~I~cien~fier ments iCV16009S Snubber Line Number I EP~
- Iief IP~9ram1 1CVA7AB-2° I2P-14 Sry VT-3 Functional VT-3 Re~1 NRI NRI NA!
Page 3-33
Section 3.3 Detailed Inservice Inspection Snubber Listing (Page 2 of 9)
SYSTEM: Main Steam System (MS)
Bcekn.
Braidwood Station Unit 1 A1R12 ISI Outage Report Inspection Comments F-A P01.20 1MSO1O79S Snubber, integrally attached to pipe F-A P01.20 1MSO1O8SS Snubber, integrally attached to pipe 1MSO7AD-28 l2A-14 VT-3 Functional VT-3 NP!
NPI NP!
F-A P01.20 1MSO1O92AS Snubber, integrally attached to pipe 1MSO7AB-28°
!2P-14 VT-3 Functional VT-3 NP!
NP!
NP!
F-A P01.20 1MSO1O92BS Snubber, integrally attached to pipe 1MSO7AB-28 l2P-14 VT-3 Functional VT-3 NA!
NA!
NP!
P-A P01.20 1MSO1O97.S Snubber, integrally attached to pipe 1MS07AB-28 i2A-14 VT-3 Functional VT-3 NP!
NP!
NA!
F-A P01.20 1MSO11O1AS Snubber, integrally attached to pipe 1MSO7AC-28 12R-14 VT-3 Functional VT-3 NA!
NP!
NA!
Serial Number: 1625 F-A P01.20 1MSO11O1BS Snubber, integrally attached to pipe 1MSO7AC-28~
!2R-14 VT-3 NP!
Functional IND.
Functional NP!
VT-3 NA!
Snubber Serial Number 1534 failed to meetfunctional test acceptance criteria. Replaced by Serial Number 20006 under WO 899716-01 Functional Snubber, integrally attached to pipe VT-3 NA!
Snubber functional and post-installation VT-3 Completed.
F-A P01.20 1 MSO1 106S 1 MSO7AC-28~
Snubber, integrally attached to pipe 12R-14 VT-3 NP!
Functional NA!
VT-3 NA!
1MSO7AA-28 12R-14 VT-3 NPI Page 3-34
Ecekn.
Braidwood Station Unit 1 A1R12 ISI Outage Report Section 3.3 Detailed Inservice Inspection Snubber Listing SYSTEM: Reactor Coolant System (RC)
Section Xl IS! Identifier
[Cat.
Item Description (Inspection Comments P-A P01.10 1CV15O39AS Snubber Snubber functional and post-installation VT-3 completed.
Snubber Functional
!ND.
Functional NA!
VT-3 NA!
Snubber Serial Number 3128 failed to meet functional test acceptance criteria. Replaced by Serial Number 12538 under WO914213-01.
Skewed pipe attachment component identfied during visual examination (post test VT-3).
F-A P01.10 1CV15O39BS 1RC14A8-2~
12R-14 Functional NP!
Snubber VT-3 NP!
Snubber functional and post-installation VT-3 completed.
Snubber VT-3 IND.
Functional IND.
Functional NP!
VT-3 NP!
Snubber Serial Number 8052 failed to meet functional test acceptance criteria. Replaced by Serial Number 14610 under WO 914213-01.
Skewed pipe attachment component identfied durinq visual examination (post test VT-3).
F-A P01.10 1CV25002S 1PC14AD-2 12R-14 VT-3 Snubber Functional VT-3 NA!
NP!
NRI P-A P01.10 1ACO1006S 1RC21AA-8 12P-14 VT-3 NP!
Snubber Functional NP!
VT-3 NP!
F-A P01.10 1RCO1007S 1PC21AA-8 12R-14 VT-3 NP!
Snubber Functional NP!
VT-3 NP!
F-A P01.40 1RCO1 BA-A S.G A l2R-14 VT-3 NP!
Snubber F-A P01.40 IRC01BA-8 S.G A i2R-14 VT-3 NRI Snubber F-A P01.40 1PCO1BB-A S.G B 12A-14 VT-3 NP!
Snubber VT-3 NP!
Serial Number 23. VT-3 performed for WO 98108541 was post maintenance VT-3 after replacement of 1PCO1BB-B snubber, Both snubbers are_supplied from a common reservoir.
F-A P01.40 1PCO1BB-B S.G B 12P-14 Functional NP!
Snubber VT-3 NP!
Snubber functional and post-installation VT-3 completed.
VT-3 IND.
Snubber Functional VT-3 NA!
Snubber (Serial Number 14) was identfied as leaking fluid from the piston seal at power during the operating cycle prior to A1R12.
Leakage quantified as 25 dpm on 04/2012006.Snubber was replaced by Serial Number 06 under WO 98108541.
(Page 3 of 9) 1RC14AB-2 12P-i4 Functional NP!
VT-3 NP!
VT-3 IND.
Page 3-35
Bcek~n Braidwood Station Unit 1 A1R12 IS! Outage Report (Page 4 of 9)
Section 3.3 Detailed Inservice Inspection Snubber Listing SYSTEM: Reactor Coolant System (RC)
(SI Identifier Description (Inspection Comments F-A P01.40 1RCO1BC-A Snubber S.G C l2P-14 VT-3 NA!
Functional NP!
VT-3 NP!
Serial Number 12. Snubber functional test and post maintenance VT-3 examination F-A P01.40 1PCO1BC-B S.C C 12P-14 VT-3 NP!
Snubber F-A P01.40 1PCO1BD-A S.G D 12R-14 VT-3 NP!
Snubber F-A P01.40 1PCO1BD-B S,G C 12P-l4 VT-3 NP!
Snubber F-A P01.10 1ACO2006AS 1AC21AB-8 12P-14 VT-3 NA!
Snubber Functional IND.
Functional NA!
VT-3 NP!
Snubber (Serial Number 8666) failed to meet functional test acceptance criteria. Replaced by Serial Number 2S04 under WO 914208-01.
Functional Snubber VT-3 NA!
Snubber functional and post-installation VT-3_completed.
F-A P01.10 1PCO2006BS 1AC21AB-8
!2A-l4 VT-3 NA!
Snubber Functional NP!
VT-3 NA!
F-A P01.10 1PCO2007S 1PC21AB-8~
12A-14 VT-3 NA!
Snubber Functional NP!
VT-S NP!
P-A P01.10 1PC16114S 1RC22AA-1.5~
12R-14 VT-3 NP!
Snubber Functional NA!
VT-3 NA!
F-A P01.10 1RC16119S 1PC22AA-1.5~
12A-14 VT-3 NA!
Snubber Functional NP!
VT-3 NA!
F-A P01.10 1RC17O52S 1PC22AB-1.5~
l2P-l4 VT-3 NA!
Snubber Functional NA!
VT-3 NP!
P-A P01.10 1RC18O34AS 1PC22AC-1.5~
l2A-i4 VT-3 NA!
Snubber Functional NA!
VT-3 NP!
Serial No. 13044 P-A P01.10 1PC18034BS 1PC22AC-1.5~
12A-14 VT-3 NA!
Snubber Functional NRI VT-3 NPI SN. 13082 Section XI Cat.
Item Page 3-36
Ecekn.
Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.3 Detailed Inservice Inspection Snubber Listing (Page 5 of 9)
SYSTEM: Reactor Coolant System (RC)
Section Xl IS! Identifier Cat.
Item Description Inspection Comments F-A P01.10 1RY06057S Snubber Snubber functional and post-installation VT-3 completed.
Snubber VT-3 Functional VT-3 NP!
Snubber (Serial Number 329) was replaced with Serial Number 13518 under WO 915045-01.
F-A P01.10 1PYO6O91S 1PC26A-2~
l2P-14 Functional NP!
Snubber VT-S NP!
Snubber (Serial Number 8609) performance was identified as trending downward during Al All and was replaced with functionally tested spare snubber (Serial Number 9857) under WO 744327-01.
P-A P01.10 1RYO6153S 1PC24AB-4
!2P-i4 VT-3 NP!
Snubber Functional NA!
VT-3 NP!
1PC26A-2 I2P-14 Functional NP!
VT-3 NP!
Page 3-37
Exek; n, Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.3 Detailed Inservice Inspection Snubber Listing (Page 6 of 9)
SYSTEM: Residual Heat Removal System (RH)
Section XI IS! Identifier Item Description Inspection Comments F-A P01.10 1PHO2003S Snubber 1PHO1AB-12 12R-14 VT-3 NP!
Functional NP!
VT-3 NP!
F-A P01.10 1PHO2O13S Snubber 1PH0lAB-12~
!2P-14 VT-3 Functional VT-3 NA!
NP!
NP!
P-A P01.10 1PHO2O59S Snubber 1AH0lAA-12~
l2R-14 VT-3 Functional NP!
NP!
VT-3 NP!
P-A P01.20 1PHO8O15S 1RHO2AB-8~
l2P-14 VT-3 NP!
Snubber Functional NP!
VT-3 NP!
Page 3-38
Section 3.3 Detailed Inservice Inspection Snubber Listing (Page 7 of 9)
SYSTEM: Reactor Coolant System (RY)
Braidwood Station Unit 1 A1R12 IS! Outage Report Section XI IS! Identifier
[~~1j~escription (Inspection Comments F-A P01,10 1PYO6O12S Snubber F-A P01.10 1PY06022S Snubber 1AYO1B-6 12P-14 VT-3 Functional VT-3 NP!
NA!
NP!
F-A P01.10 1PY06029S Snubber 1RYO1B-6 12R-i4 VT-3 Functional VT-3 NA!
NP!
NP!
P-A P01.10 1RYO6O33S Snubber lPYO1B-6~
12P-14 VT-3 Functional VT-3 NP!
NP!
NP!
P-A P01.10 1RY06034S Snubber lRYOlB-6~
12P-14 VT-3 Functional VT-3 NP!
NP!
NP!
F-A P01.10 1RYO6O47S Snubber 1AY18A-2 12P-14 VT-3 Functional VT-3 NP!
NP!
NP!
P-A P01.10 1RYO611OS Snubber lPYO1B-6~
!2P-14 VT-3 Functional VT-3 NP!
NP!
NP!
F-A P01.10 1PYO6126S Snubber lPYOlAB-4~
!2R-14 VT-3 Functional VT-3 NP!
NP!
NP!
P-A P01.10 1PYO9005S Snubber 1RYO2B-3 12R-14 VT-3 Functional VT-3 NP!
NP!
NA!
P-A P01.10 1AYO9O77S Snubber 1PYO2B-3 12R-14 VT-3 Functional VT-3 NP!
NP!
NP!
1RYO1AB-4 I2P-14 VT-3 NA!
Functional NP!
VT-3 NP!
Page 3-39
Exek:ii.
Braidwood Station Unit I A1R12 IS! Outage Report Section 3.3 Detailed Inservice Inspection Snubber Listing (Page 8 of 9)
SYSTEM: Safety Injection System (SI)
Section XI IISI Identifier Line Number! EPN
[~tem j~~ffiption Inspection Comments F-A P01.10 1PHO2O19S iSl04D-8~
12P-14 VT-3 NP!
Snubber Functional NP!
VT-3 NP!
P-A P01.20 1AHO2O27S 1SI04C-8~
!2P-14 VT-3 NP!
Snubber Functional NP!
VT-3 NP!
F-A P01.10 1PHO2O66S 1SIA4B-8~
!2P-14 VT-3 NP!
Snubber Functional NA!
VT-3 NP!
P-A P01.10 1PHO2O67S 1SIO4D-8
!2P-14 VT-3 NP!
Snubber Functional NP!
VT-3 NP!
P-A P01.10 1PHO2O78S ISIA4B-8 12R-l4 VT-3 NP!
Snubber Functional NP!
VT-3 NP!
F-A P01.10 1PHO2083S ISlA4B-8~
12R-14 VT-3 NP!
Snubber Functional NP!
VT-3 NP!
P-A P01.20 1PH02206S 1SlA4A-8~
12P-14 VT-3 NP!
Snubber Functional NP!
VT-3 NP!
F-A NA 1SIO1003S 1Sl09BA-1O~
12P-14 VT-3 NP!
Snubber Functional NP!
VT-3 NP!
F-A P01.10 1SIO1O21S 1SIO5DA-6 12R-14 VT-3 NP!
Snubber Functional NP!
VT-3 NP!
F-A P01.20 1S!03003S 1SIO5CA-8 l2A-14 VT-3 NP!
Snubber Functional NP!
VT-3 NA!
F-A P01.20 1SIO3006S 1Sl05CA-8~
I2P-14 VT-3 NP!
Snubber Functional NA!
VT-3 NP!
P-A P01.20 1S103007S 1SlO5CA-8~
12R-14 VT-3 NAI Snubber Functional NP!
VT-3 NP!
P-A P01.20 1S103009S 1SI05CA-8~
12P-14 VT-3 NA!
Snubber Functional NA!
VT-3 NAI P-A P01.10 1S103018S 1SIO5DD-6 l2A-l4 VT-3 NP!
Snubber Functional NPI VT-3 NA!
Page 3-40
Exekn.
Braidwood Station Unit 1 Al Ri 2 IS! Outage Report Section 3.3 Detailed Inservice Inspection Snubber Listing (Page 9 of 9)
SYSTEM: Safety Injection System (SI)
Section XI IS! Identifier Item
~[f~ription (Inspection Comments P-A P01.10 1SIO3O24S Snubber F-A P01.10 1SIO4003S Snubber 1SIO9BB-iO 12P-14 VT-3 Functional VT-2 NA!
NPI NP!
P-A P01.20 1S109004S Snubber 1S!05CB-8~
12P-14 VT-3 Functional VT-3 NP!
NP!
NA!
F-A P01.20 iS!09009S Snubber 1SIO5CB-8°
!2R-14 VT-3 Functional VT-3 NP!
NP!
NP!
P-A P01.10 1S109020S Snubber 1SIO9Bc-1O l2R-14 VT-3 Functional VT-3 NA!
NP!
NP!
F-A P01.20 1S!O9043S Snubber lSIO5CB-8~
12R-14 VT-3 Functional VT-3 NP!
NP!
NP!
F-A P01.20 1S!18049S Snubber 1SIO2BA-6
!2P-14 VT-3 Functional VT-3 NP!
NP!
NP!
iSl09BD-1O~
12R-14 VT-3 NP!
Functional NP!
VT-3 NP!
Page 3-41
Exek~n.
Braidwood Station Unit 1 A1Ri2 IS! Outage Report Section 3.3.1 Snubber Preservice Inspection Listing (Page 2 of 2)
SYSTEM: Reactor Coolant System (RC)
Section XI IS! Identifier Line Number!EPN (Cat.
Item Description Relief Request Program Notes Exam Summary Results
)~spectionComments F-A P01.10 1CV15O39AS 1RCl4AB-2~
12P-14 Functional NP!
Snubber VT-3 NP!
Snubber functional and post-installation VT-3 completed.
P-A P01.10 1CV15O39BS lPCi4AB-2~
l2P-14 Functional NP!
Snubber VT-3 NP!
Snubber functional and post-installation VT-3 completed.
P-A P01.40 1RCO1 88-B S.C B l2P-14 Functional NP!
Snubber VT-3 NP!
Snubber functional and post-installation VT-3 completed.
P-A P01.10 1PCO2006AS 1RC21AB-8 l2R-14 Functional NP!
Snubber VT-3 NP!
Snubber functional and post-installation VT-3 completed.
P-A P01.10 1AYO6O57S 1RC26A-2 I2A-14 Functional NP!
Snubber VT-3 NP!
Snubber functional and post-installation VT-3 completed.
P-A P01.10 1RYO6O91S 1PC26A-2~
l2R-14 Functional NP!
Snubber Snubber (Serial Number 8609) performance was identified as trending downward during Al Al 1 and was replaced VT-3 with functiona NP!
lly tested spare snubber (Serial Number 9857) under WO 744327-01.
Page 3-43
Exekn.
Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.4.1 Detailed Inservice Inspection Pressure Test Test-Block Listing (Page 1 of 5)
SYSTEM: Containment Spray System (CS)
Section XI IS! Identifier
[Cat.
Item Description (Inspection Comments C-H C07.1O AO1CS-000003-M04-O1A C07.30 40 Month Period ASME Section Xl pressure Test.
C07.5O C07.70 Second period examination.
A number of minor packing leaks were identified (Information Only).
C-H CO7.1O AO1CS-000003-M04-O1B l2R-05 VT-2 ND.
C07.3O 40 Month Period ASME Section XI pressure Test.
!2R-1 3 CO7.5O CO7.70 Second period examination.
Nonactive boric acid ieak at bolted connection on Line 1CSO1AB-16 (reference IA 284476 and 291483). Gasket replacement performed under WO 697822.
C-H CO7.iO AO1CS-000003-MO4-O1C 12P-05 VT-2 NP!
CO7.3O 40 Month Period ASME Section Xl Pressure Test. The Test Pressure
!2R-13 C07.70 shall be those pressures developed when the Spray Additive Tank is pressurized with the nitrogen blanket. Use SNOOP or Ultraprobe to inspect nitrogen filled piping, valves and upper portion of Spray Additive Tank containing nitrogen blanket.
Second period examination.
l2R-13 Page 3-44
Bcekn.
Braidwood Station Unit 1 Al Ri 2 IS! Outage Report Section 3.4.1 Detailed lnservice Inspection Pressure Test Test-Block Listing (Page 2 of 5)
SYSTEM: Fuel Pool Cooling System (FC)
Section XI IS! Identifier
[~~~ltem Description
[Inspection Comments C-H C07.3O AO1FC-000001-M04-O1C C07.70 40 Month Period ASME Section Xl Pressure Test.
Second period examination.
C-H CO7.3O AO1PC-000001-MO4-O1D
CO7.7O 40 Month Period ASME Section Xl Pressure Test.
!2P-13 Second period examination.
12P-12 l2R-13 Page 3-45
Exekn Braidwood Station Unit 1 AiRi2 IS! Outage Report Section 3.4.1 Detailed Inservice Inspection Pressure Test Test-Block Listing (Page 3 of 5)
SYSTEM: Process Sampling System (PS)
Section XI ils! Identifier
~
Inspection Comments C-H C07.3O AO1PS-000009-MO4-OlE l2P-05 NOTE13 VT-2 NA!
C07.7O 40 Month Period ASME Section XI Pressure Test.
Relief Request l2P-47 submitted to address inaccessible piping.
Second period examination.
Initial review of May 2005 walk down revealed all sections of system were not examined by VT-2 method (Reference IA 338480). A subsequent risk evaluation was performed.
Access to 25 of piping could not be attained during second walk down in October 2005 (IA 387085), Relief Request !2P-47 submitted on 4/7/2006.
Page 3-46
Bce1c~n.
Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.4.1 Detailed Inservice Inspection Pressure Test Test-Block Listing (Page 4 of 5)
SYSTEM: Safety Injection System (SI)
Section XI IS! Identifier
~
Description Inspection Comments C-H C07.40 AO1SI-000005-M04-02H CO7.8O 10 Year Interval ASME Section Xl Pressure Test.
Portion completed in AlA 12, the balance of the test block will be performed during Al P13.
12R-05 NOTE13 VT-2 NPI 12R-12 NOTE17 12A-1 3 Page 3-47
Ecekn.
Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.4.1 Detailed Inservice Inspection Pressure Test Test-Block Listing (Page 5 of 5)
SYSTEM: Plant Systems Pressurized During Mode 3 (ZZ)
Section XI
!SI Identifier Cat.
Item Description Inspection Comments B-P 815.10 AO1ZZ-000005-M04-O1A 815.20 Periodic (each refueling outage) ASME Section Xl Pressure Test &
815.30 815.50
!2P-3O 815.60/70 12P-31 Class 1 system leakage test.
No Recordable Indications.
Information Only (10): Leakage past 1 PCO1 4 series head vent valve (reference IA 485050)
B-P 815.11 AO1ZZ-000005-MO4-02A
815.21 10 Year Interval ASME Section XI Pressure Test.
Freeze seal
!2R-12 NOTE14 815.31 required for Line 1CV45B.
l2P-l3 NOTE17 815.51
!2R-30 815.61/71 I2P-3i Portion_completed_in_A1A12,_the_balance_of the_test_block_will_be_performed_during_Al P13.
C-H CO7.2O AOl ZZ-000005-MO4-O2B l2R-05 NOTE13 VT-2 NA!
CO7.4O 10 Year Interval ASME Section Xl Pressure Test. All Code Class 2
!2P-12 NOTE17 Co7.8o Components inside Containment. VT-2 Visual Inspection of
!2P-13 components outside of Missle Barrier may be performed during Mode 1 if conditions permit.
Portion completed in Al P12, the balance of the test block will be performed during Al P13.
C-H CO7.1O AOl ZZ-000078-MO4-03A l2P-05 NOTE13 VT-2 NP!
CO7.3O 40 Month Period ASME Section Xl Pressure Test. All Code Class 2 12P-12 Co7.7o components inside containment. VT-2 Visual Inspection of l2R-13 components outside Missle Barrier may be performed during Mode 1 if conditions permit.
Class 2 and 3 systems examined during ascending Mode 3 walk down.
!2R-12 NOTE14
!2R-l3 NOTE17 Page 3-48
Bcek;n, Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.4.2 Detailed Inservice Inspection Borated Bolting Listing (Page 1 of 5)
SYSTEM: Chemical & Volume Control System (CV)
Section Xl IS! Identifier Description C-H CO7.3O lA-CV-b P-2-1 (C-H)
C07.40 FLANGED CONNECTION (8 STUDS) 12P-l 3 C-H C07.1O 1CVO4AB (C-H) l2P-i2 VT-2 C07.2O 1CVO4AB HX (28 STUDS)
!2P-13 NP!
C-H CO7.3O 1CV-lO P-i-i (C-H)
C07.4O FLANGED CONNECTION (8 STUDS)
!2R-13 VT-i NP!
Evidence of leakage (dry boric acid accumulation, (<1 Teaspoon) identhed at one stud. Component cleaned, VT-i Examination performed, with exception of minor surface rust no indication of degradation identhed. No evidence of leakage identified during post cleaning examination. Reference Issue Report Number 496436 for identification of indication in the Corrective Action Program.
B-P 815.50 PG-2546C-014 P-2-2 (B-P)
815.51 FLANGED CONNECTION (4 STUDS) 12P-13 C-H CO7.30 PG-2546C-O18 F-i-S (C-H) l2R-12 VT-2 NP!
CO7.4O FLANGED CONNECTION (4 STUDS) 12R-13 C-H CO7.3O PG-2546C-O2O P-i-i (C-H)
C07.4O FLANGED CONNECTION (4 STUDS) l2P-12 VT-2 NP!
12R-l3 Evidence Of DryBoric Acid at the packing on instrument valves 1 CVO9OC and 1 CVO91 C which attaches to the flanges within this Borated Bolted Connection. Not within the scope of borated bolted connections. However components were cleaned and inspected with no identified degradation. Reference Issue Report Numbers 495158 and 495163 for identification of valve packing leakage in the Corrective Action Program.
C-H C07.3O PG-2546C-O41 P-i-i (C-H) 12R-l2 VT-2 NP!
CO7.4O FLANGED CONNECTION (4 STUDS)
!2P-l3 C-H CO7.30 PG-2546C-063 P-i-i (C-H) 12P-l2 VT-2 NP!
CO7.4O FLANGED CONNECTION (4 STUDS)
!2R-13 Evidence Of Dry Boric Acid at the packing on instrument valves 1 CVO9OD and 1 CVO91 D which attaches to the flanges within this Borated Bolted Connection. Not within the scope of borated bolted connections. However components were cleaned and inspected with no identified degradation. Reference Issue Report Numbers 4951 6sand 495168 for identification of valve packing leakage in the Corrective Action Program.
C-H C07.3O PG-2546C-068 P-i (C-H) l2P-i2 VT-2 NP!
C07.40 FLANGED CONNECTION (4 STUDS) 12P-13 C-H C07.3O PG-2546C-076 P-1-3 (C-H) l2P-12 VT-2 NPI C07.4O FLANGED CONNECTION (8 STUDS) 12P-13 C-H C07.30 PG-2546C-083 PL-1-2 (C-H) l2P-l2 VT-2 NRI C07.4O FLANGED CONNECTION (8 STUDS) l2A-13 C-H C07.30 PG-2546C-089 FL-i-i (C-H)
C07.40 FLANGED CONNECTION (8 STUDS) l2A-12 VT-2 NP!
l2P-1 3 Evidence Of Dry Boric Acid at the packing on instrument valves 1CVO49D and 1CVO5OD which attaches to the flanges within this Borated Bolted Connection. Not within the scope of borated boltedconnections. However components were cleaned and inspected with no identified degradation. Peference Issue Peport Numbers 495174 and 495185 for identification of valve packing leakage in the Corrective Action Program.
C-H C07.30 PG-2546C-090 F-i-i (C-H) l2P-12 VT-2 NPI C07.40 FLANGED CONNECTION (8 STUDS) 12P-i3 B-P 816.50 PG-2546C-091 P-2-3 (8-P) 12P-12 VT-2 NP!
815.51 FLANGED CONNECTION (4 STUDS) l2A-13 C-H C07.30 PG-2546C-093 P-i (C-H)
C07.4O FLANGED CONNECTION (4 STUDS) 12P-12 VT-2 NP!
!2A-13 Inspection Comments 12P-12 VT-2 NP!
Page 3-49
Bcakn.
Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.4.2 Detailed Inservice Inspection Borated Bolting Listing (Page 2 of 5)
SYSTEM: Chemical & Volume Control System (CV)
Section XI IS! Identifier Item Description
[nspection Comments B-P 815.50 PG-2546C-101 P-2-3 (B-P) 815.51 FLANGED CONNECTION (4 STUDS) 12P-13 C-H C07.30 PG-2546C-lll F-1-2 (C-H) 12P-12 VT-2 NP!
CO7.40 FLANGED CONNECTION (8 STUDS) 12P-l3 Evidence Of Dry Boric Acid at the packing on instrument valves 1 CVO49A and 1 CVO5OA which attaches to the flanges within this Borated Bolted Connection. Not within the scope of borated bolted connections. However components were cleaned and inspected with no identifled degradation. Reference Issue Report Numbers 495191 and 495195 for identification of valve packing leakage in the Corrective Action_Program.
Page 3-50
E~fikfl Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.4.2 Detailed Inservice Inspection Borated Bolting Listing (Page 3 of 5)
SYSTEM: Pressurizer (PZR)
Section XI IS! Identifier
[~~.__Item Description
[ispection Comments B-P 815.20 1PZP-O1-Bl (B-P) 815.21 MANWAY BOLTING (16 TOTAL)
!2R-13 Page 3-51
Exekn.
Braidwood Station Unit 1 AiRi2 IS! Outage Report Section 3.4.2 Detailed Inservice Inspection Borated Bolting Listing (Page 4 of 5)
SYSTEM: Reactor Coolant System (RC)
Section Xl ISI Identifier
~
Item Description (Inspection Comments B-P 815.50 1PC-i9-B3(B-P) 12P-12 VT-2 815.51 FLANGED CONNECTION (4 STUDS) l2R-i3 B-P 815.50 1PC-2O-Bi (B-P)
815.51 FLANGED CONNECTION (4 STUDS) 12P-13 B-P 815.50 1RC-23-Bi (B-P) 12R-b2 VT-2 NP!
B15.51 FLANGED CONNECTION (4 STUDS) 12P-13 B-P 815.50 IPC-27-Bl (B-P) 12P-12 VT-2 NP!
815.51 FLANGED CONNECTION (4 STUDS) l2R-13 B-P 815.10 1RV-03-STUDS (01 TO 54, B-P) 12P-13 VT-2 NP!
815.11 CLOSURE HEAD STUDS (54 TOTAL) 12R-3l B-P Bi5.3O 1SG-O5-SGB-Oi (B-P) 12P-13 VT-2 NA!
815.31 PRIMARY MANWAY (20 STUDS) l2R-31 B-P 815.30 1SG-05-SGB-O2 (B-P) 12R-13 VT-2 NP!
815.31 PRIMARY MANWAY (20 STUDS) l2A-3l B-P 815.30 1SG-O6-SGB-O1 (B-P)
815.31 PRIMARY MANWAY (20 STUDS) 12R-3l B-P 815.30 1SG-O6-SGB-O2 (B-P) 12P-13 VT-2 NP!
815.31 PRIMARY MANWAY (20 STUDS) 12R-3l B-P 815.30 1SG-O7-SGB-Oi (B-P) 12P-13 VT-2 NP!
815.31 PRIMARY MANWAY (20 STUDS) 12R-31 Section Xl VT-i scheduled for A1P12. (IS!)
B-P 815.30 1SG-07-SGB-02 (B-P) 12A-13 VT-2 NA!
B15.31 PRIMARY MANWAY (20 STUDS) 12P-3l Section Xl VT-i scheduled for A1P12. (IS!)
B-P 815.30 1SG-08-SGB-Ol (B-P)
815.31 PRIMARY MANWAY (20 STUDS) 12P-31 Section Xl VT-b scheduled for A1P12. (IS!)
B-P 815.30 1SG-O8-SGB-02 (B-P) l2P-13 VT-2 NA!
815.31 PRIMARY MANWAY (20 STUDS) l2P-3i Section XI VT-i scheduled forAlPl2. (ISI) _____
NP!
Page 3-52
Ecekn.
Braidwood Station Unit 1 A1R12 IS! Outage Report Section 3.4.2 Detailed Inservice Inspection Borated Bolting Listing (Page 5 of 5)
SYSTEM: Residual Heat Removal System (RH)
Section XI Ils! Identifier
~
(Inspection Comments C-H C07.30 1 RHO1 MB (C-H)
C07.40 FLANGED CONNECTION (12 STUDS)
C-H CO7.3O 1RH-02 F-i-i (C-H)
C07.4O FLANGED CONNECTION (20 STUDS) l2R-12 12R-1 3 C-H CO7.30 C07.4O 1AH-O2 F-2-1 (C-H)
FLANGED CONNECTION (20 STUDS) 12R-12 12P-i3 VT-2 NP!
C-H C07.3O CO7.4O 1PH-02 P-4 (C-H)
FLANGED CONNECTION (8 STUDS) l2P-12 12A-13 VT-2 NP!
C-H CO7.3O CO7.4O 1RH-03 P-2 (C-H)
FLANGED CONNECTION (24 STUDS)
C-H CO7.3O CO7.4O 1PH-O5 F-i (C-H)
FLANGED CONNECTION (24 STUDS) 12P-12 12P-13 VT-2 NP!
C-H C07.3O 1 PH-OS P-2 (C-H)
C07.4O FLANGED CONNECTION (24 STUDS)
C-H C07.3O 1RH-05 F-3-1 (C-H)
CO7.4O FLANGED CONNECTION (12 STUDS) l2R-12 VT-2 12R-i 3 12R-l 2 12P-13 VT-2 VT-i NP!
IND.
NA!
Evidence of leakage (dry boric acid accumulation, (Approx. 1 Cup) identfied within the mechanical connection. Component cleaned, VT-i Examination performed, with exception of minor surface rust no indication of degradation identfied. No evidence of leakage identified during post cleaning examination. Reference IP Number 477836 for identification of indication in the Corrective Action Program.
Component was repaired (Bolting Retightened / Petorqued) on 04/13/2006 under WO 911750. No evidence of leakage or degradation identified during post repair exam.
C-H CO7.3O 1PH-06 P-i-i (C-H) 12R-12 VT-2 NP!
CO7.4O FLANGED CONNECTION (12 STUDS) 12R-i3 C-H CO7.3O 1PH-O7 P-2-1 (C-H) l2R-i2 VT-2 NA!
C07.4O FLANGED CONNECTION (20 STUDS) 12R-13 C-H C07.3O 1PH-07 P-3-i(C-H) 12P-12 VT-2 NP!
C07.4O FLANGED CONNECTION (20 STUDS) 12R-13 C-H CO7.7O 1PH6O6(C-H) 12R-12 VT-2 NP!
C07.80 1RH606 VLV (4 STUDS) l2P-13 12R-12 VT-2 NP!
Page 3-53