ML072120484
| ML072120484 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 07/10/2007 |
| From: | Exelon Generation Co, Exelon Nuclear |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| BYRON 2007-0055 | |
| Download: ML072120484 (68) | |
Text
BYRON Exekn..
UNIT 2 Nuclear B2R13 Spring 2007 Outage INSERVICE INSPECTION
SUMMARY
REPORT For Inspection Activities from October 12, 2005 to May 3, 2007 Commercial Service Date August 21, 1987 Document Completion Date July 10, 2007 Exelon Generation Company (EGC, LLC) 4300 Winfield Rd Warrenville, IL 60555 Byron Nuclear Power Station 4450 North German Church Rd.
Byron, IL 61010
BYRON UNIT 2 Exeln.
B2R13 Nuclear INSERVICE INSPECTION
SUMMARY
REPORT I SECTION SECTION DESCRIPTION PAGES!
I
ICover Page I
1 I
8 I
I ii JTable of Contents I
1 I
I 1.0 IReport Introduction I
6 I
2.0 Examination Summary Tables (SI - Weld / Component Listing (SI
- Bolts, Pumps, and Valves Listing PSI
- Weld / Component Listing PSI - Bolts, Pumps, and Valves Listing ISI
- Pressure Tests (SI
- Component Supports IS)
- Snubbers PSI - Snubbers 21 4
1 1
12 10 11 3.0 IStatus of Examination Completion for the Program Plan 1
1 I
4.0 IForm NIS-1: Preservice and Inservice Examinations I
58 1
1 5.0 IForm NIS-2: Repairs / Modifications 1
101 I 6 0 C(S) Re ort 2nd IWL 5-Year Containment p
Penetration Concrete Surveillance Reportl 5
I 2PC064M Conditions Found I
I 21 I
TOTALPAGESINREPORTJ 246 I I
BYRON STATION UNIT 2 REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT
1.0 INTRODUCTION
lnservice inspections of American Society of Mechanical Engineers (ASME) Class 1, 2, 3, CC, and MC components were conducted at Byron Station Unit 2 from October 12, 2005 through May 3, 2007. The majority of these inspections were performed during the thirteenth refueling outage (B2R13) from April 2 through May 3-, 2007.
The examinations were performed in compliance with the rules and regulations of ASME Section Xl, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components, (applicable edition and addenda), pursuant to the requirements of 10 CFR 50.55a, Codes and Standards.
This summary report meets the requirements of ASME Code, IWA-6000 for the inspection of Class 1 and 2 components and piping. Class CC and MC components in the Containment Inservice Inspection (CISI) program are included when examination results require reporting as specified in 10 CFR 50.55a. See 7.0 in this section for a listing of referenced documents.
The Nondestructive Examination (NDE) Inservice Inspection (ISI) Program Plan for Class 1, 2, and 3 components was developed in accordance with the requirements and intent of Section Xl Subsections (WA, IWB, IWC, IWD, IWE, IWF and IWL, 2001 Edition, through the 2003 Addenda.
In addition to the ASME Section Xl requirements of examination, certain Nuclear Regulatory Commission (NRC) augmented ISI inspections were required. The Byron Station Unit 2 augmented (SI examination requirements include:
a) Class 1 pressure boundary for leakage at nominal operating pressure, in accordance with NRC Generic Letter 88-05, Boric Acid Corrosion ofCarbon Steel Reactor Pressure Boundaty Components in PWR Plants; b) Class 2 and 3 pressure boundary for leakage at nominal operating pressure, in accordance with NUREG 0737, Clarification of TMI Action Plan Requirements; Note: Specific requests for relief were developed and submitted for the NRCs review when the code and/or augmented requirement(s) were deemed to be impractical, results in excessive hardship, or an alternative examination method is determined as more suitable for the particular component.
1.1 Identification of Examination Requirements The Section 7.0 of the ISI Program Plan contains the examination program tables.
These tables are presented in a tabular format consistent with the tables found in Subsections IWB, IWC, IWD, (WE, IWF, and IWL-2500 of the ASME Code. The examination tables include the corresponding code category, item number, and component/weld selection in conformance with examination requirements and intent of Subsection (WA, IWB, IWC, IWD, IWE, IWF, and IWL of Section Xl of the ASME Code.
Section 1.0 Page 1 of 6
BYRON STATION UNIT 2 REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT For Class 1, 2, and certain non-class piping components, the requirements of Risk Informed Inservice Inspection (RI-IS)) are followed using EPRI TR112657 and Table 1 of ASME Code Case N-578-1.
1.2 Identification of Exempted Components ASME Class 1, 2, and 3 components, or parts of components, that are not included in the examination tables and that are exempt from examination, as specified in Section XI Paragraphs IWB, IWC, and IWD-1200, Components Exempt from Examination, and Tables IWB-2500-1, IWC-2500-1, and IWD-2500-i, are identified in the NDE Program Plan in conjunction with technical justification(s) for exempting the component/system.
Class 1 or 2 piping welds exempted by IWB and IWC-1200 are not included in the RI-ISI program. Previous selection and examination exemptions identified in Tables IWB and IWC-2500-1 for Examination Categories B-F, B-J, C-F-i, and C-F-2, are not allowed under the requirements of the RI-IS) program. With the adoption of RI-(SI, welds evaluated as Risk Category 6 or 7 are not required to be subject to examination.
1.3 Implementation of the (SI Program Exelon Nuclear, or its designee, visually examined ASME components utilizing the following test methods: VT-i, VT-2, and VT-3. The components examined comply with the (SI Program Schedule, Byron Station Technical Specifications, and/or comply with the ASME Section Xl Repair/Replacement Program.
Certified personnel performed and evaluated visual examinations (i.e., VT-i, VT-2, and VT-3) of Class 1, 2, and 3 components, and supports. Exelon Nuclear personnel certification procedures comply with the requirements of ANSI/ASNT CP-189, 1995 Edition and ASNT SNT-TC-1A, 1984 Edition.
Certified personnel performed and evaluated all NDE. Personnel were certified to the requirements of the ASNT SNT-TC-1A, 1984 Edition. Additionally, ultrasonic examiners were certified in accordance with ANSI/ASNT CP-1 89, 1995 Revision.
The NDE procedures were developed and certified in conformance with ASME Section V and Xl as applicable.
All ISI NDE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section Xl, Subarticle IWA-2200 Examination Methods. For components incorporated into the RI-ISI program, the guidance for the examination volume for a given degradation mechanism is provided by the EPRI Topical Report while the guidance for the examination method is provided by Code Case N-578-1.
Section 1.0 Page 2 of 6
BYRON STATION UNIT 2 REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT 1.4 Second and Third 10-Year Inspection Intervals The ~
fuel cycle for Unit 2 encompasses a time span of October 12, 2005 to May 3, 2007. Activities that occurred prior to January 16, 2006 were performed during the Third Inspection Period of the Second Inspection Interval. Activities that occurred on or after January 16, 2006 were performed during the First Inspection Period of the Third Inspection Interval.
1.5 Significant Section XI Activities During B2R1 3 During the refueling outage, the Alloy 600 pressurizer safe-end welds were overlaid with PWSCC resistant Alloy 690 material. Full structural weld overlays on the surge, spray, relief, and safety nozzles were completed. Baseline (PSI) examinations were performed on the overlays using qualified procedures, equipment, and personnel.
The weld overlays allowed the performance of qualified examinations to meet the requirements specified in MRP-139.
The 2nd 10-year inspection of the reactor vessel was completed during B2R13. The performance of this examination in the First Inspection Period of the Third Inspection Interval was authorized with Relief Request 13-01 (ML062280606). The personnel, equipment, and procedures used for these examinations are qualified in accordance with EPRIs Performance Demonstration Initiative (PDI). The B2R1 3 examinations comply with the requirements of ASME Section XI, Appendix VIII, 2001 Edition, as specified by 10CFR5O.55a(b)(2)(xxiv).
1.6 ASME Section Xl Code Cases The following code cases are incorporated into the current Byron Station ISI Program and were utilized during the ~
fuel cycle.
N-460 Alternative Examination Coverage for Class 1 and Class 2 Welds.
N-566-2 Corrective Action for Leakage Identified at Bolted Connections.
N-624 Successive Inspections.
The following code cases were used in the examination of the Unit 2 reactor vessel and associated safe-end welds.
N-6 13-1 Ultrasonic Examination of Penetration Nozzles in Vessels, Examination Categoiy B-D, Item Nos. B3. 10 and B3.90, Reactor Nozzle-to-Vessel Welds, Figs. IWB-2500-7(a), (b), and (c).
N-648-1 Alternative Requirements for Inner Radius Examinations of Class 1 Reactor Vessel Nozzles.
N-695 Qualification Requirements for Dissimilar Metal Piping Welds.
Section 1.0 Page 3 of 6
BYRON STATION UNIT 2 REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT The following code case is used for the implementation of the risk-informed program as described in relief request 13R-02.
N-578-1 Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B.
Portions of the following cases were utilized as described in relief request l3R-08 for the full structural weld overlays applied to the pressurizer safe-end welds:
N-504-2 Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping.
N-638-1 Similar and Dissimilar Metal Welding Using Ambient Temperature Machine c3TAW Temper Bead Technique.
Repair/replacement activities that occurred prior to January 16, 2006 were in the Second Inspection Interval under the 1989 Edition of the ASME Code.
1.7 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANII): Greg FeigeI, Jeff Hendricks, and Lee Malabanan.
These inspectors are associated with Hartford Steam Boiler Inspection and Insurance Company of Connecticut, Chicago Branch, at 2443 Warrenville Rd., Suite 500, Lisle, Illinois 60532.
2.0 EXAMINATION SUMMARIES The following section lists the summaries of examinations performed during the refueling cycle. Refer to Section 2.0 for each summary table for information or for specific tests and examinations conducted during this term.
Welds & Components Summaries Inservice Inspection - Weld / Component Listing Inservice Inspection - Bolts, Pumps, and Valves Listing Preservice Inspection - Weld / Component Listing Preservice Inspection - Bolts, Pumps, and Valves Listing System Pressure Test Summaries Component Support Examination Summary Component Snubber Test Summary 3.0 UNIT 2 EXAMINATION COMPLETION STATUS A summary table of the examination status of Class 1, 2, and 3 components is contained in Section 3.0.
Section 1.0 Page 4 of 6
BYRON STATION UNIT 2 REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT 4.0 FORM NIS-1 DATA SHEETS ASME Form NIS-2, Owners Report for Inservice Inspections, were filed during the cycle for Unit 2. See Section 4.0 for the reports.
5.0 FORM NIS-2 DATA SHEETS ASME Form NIS-2, Owners Report for Repairs or Replacements, were filed during the cycle for Unit 2. See Section 5.0 for the reports.
6.0 CONTAINMENT ISI PROGRAM Reportable conditions were identified for Class CC and Class MC components during this fuel cycle. The reporting requirements in 10CFR5O.55a (b)(2)(viii)(E) and (b)(2)(ix)(A) are applicable for this summary report. See Section 6.0 for these condition reports.
7.0 REFERENCED DOCUMENTS 7.1 Code of Federal Regulations, Title 10 Energy Part 50, Domestic Licensing of Production and Utilization Facilities 50.55a, Codes and Standards 7.2 American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section V, Nondestructive Examination, 2001 Edition, through 2003 Addenda.
Section Xl, Rules for lnservice Inspection of Nuclear Power Plant Components, 1989 Edition (for 2nd Inspection Interval repair/replacement activities).
Section XI, Rules for Inservice Inspection ofNuclear Power Plant Components, 2001 Edition, through 2003 Addenda (for all 3Id Inspection Interval activities).
7.3 American National Standards Institute / American Society for Nondestructive Testing ANSI/ASNT CP-1 89, 1995 Edition, Standard for Qualification and Certification of Nondestructive Testing Personnel 7.4 American Society for Nondestructive Testing ASNT Recommended Practice No. SNT-TC-1A, 1984 Edition, Personnel Qualification and Certification in Nondestructive Testing Section 1.0 Page 5 of 6
BYRON STATION UNIT 2 REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT 7.5 Miscellaneous NRC Documents Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants.
NUREG 0737, Clarification of TM! Action Plan Requirements.
7.6 Electric Power Research Institute Material Reliability Program Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-139) July 14, 2005.
Topical Report TR1 12657 Revision B-A, Revised Risk-Informed Inservice Inspection Procedure, December 1999.
Section 1.0 Page 6 of 6
7/10/2007 ExeI~n~
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Chemical & Volume Control System (CV)
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A~ieTI A~j~ii~red
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f~e~uit~
Cat.
Description Requests Notes Coverage Exam Exam Comments R-A R120 2CV98C-8/C03 2CV98C-8 l3R-02 C5.11 100 VOL-E UT NRI Pipe. Elbow 131-01 131-02 OBS13-119 R-A R1.20 OBS13-120 2CV98C-8/C04 Elbow - Pipe 2CV98C-8 I3IR-02 C5.11 100 VOL-E 13T-01 131-02 UT NRI R-A R1.11 OBS13-005 2CVA3B-2/W-70 Pipe
- Elbow 2CVA3B-2 13R-02 B9.40 131-01 131-02 VT-2 VT-2 NAI A-A Pill OBS13-006 2CVA3B-2,W-71 Elbow - Pipe 2CVA3B-2 13A-02 B9.40 l3T-01 131-02 VT-2 VT-2 NRI A-A P1.11 OBS13-007 2CVA3B-2/W-72 Pipe - Elbow 2CVA3B-2 13R-02 B9.40 13T-01 13T-02 VT-2 VT-2 NAI R-A P1.11 OBS13-008 2CVA3B-2/W-73 Elbow - Pipe 2CVA3B-2 13R-02 B9.40 131-0 1 131-02 VT-2 VT-2 NAt R-A P1.11 OBS13-009 2CVA3B-2/W-80 Pipe - Elbow 2CVA3B-2 13A-02 B9.40 131-01 131-02 VT-2 VT-2 NRI A-A P1.11 OBS13-010 2CVA3B-2/W-81 Elbow - Pipe 2CVA3B-2 13R-02 B9.40 131-0 1 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS13-011 2CVA5AA-2iW-06 Pipe - Elbow 2CVA5AA-2 13R-02 B9.40 131-0 1 131-02 VT-2 VT-2 NRI A-A P1.11 OBS13-012 2CVA5AA-2,W-07 Elbow - Pipe 2CVA5AA-2 13P-02 B9.40 131-0 1 131-02 VT-2 VT-2 NPI P-A P1.11 OBS13-013 2CVA6AA-2/W-04 Pipe - Elbow 2CVA6AA-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt 1
7/10/2007 Exek.tin Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Chemical & Volume Control System (CV)
Sechon XI Component ID
Line p Relief Technical Code Requfreci~Actu&-
Results Cat Description Requests Notes Coverage Exam Exam
___~
-~---
__i*
Comments P-A P1.11 2CVA6AA-21W-05 2CVA6AA-2 13A-02 B9.40 VT-2 VT-2 NAI Elbow - Pipe l3T-01 131-02 OBS13-014 A-A P1.11 OBS13-050 2CVA7AA-21W-06 Pipe - Elbow 2CVA7AA-2 13P-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt P-A P1.11 OBS13-051 2CVA7AA-2/W-07 Elbow - Pipe 2CVA7AA-2 13A-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt A-A P1.11 OBS13-052 2CVA7AA-2/W-08 Pipe - Elbow 2CVA7AA-2 13P-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt 2
7/10/2007 Exekit Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section Xl Component ID Line Number Relief Technical Code Required Actual Results Description Requests Notes f~overageExam Exam comments A-A P1.11 2FWO3DB-16/C01 2FWO3DB-16 13A-02 C551 100 VOL-E UT NAI P1.18 Valve-Pipe l3T-01 131-02 OBS13-127 A-A A1.11 2FWO3DB-16/C02 2FWO3DB-16 13A-02 C5.51 100 VOL-E UT NAt P1.18 Pipe-PIpe 13T-01 131-02 OBS13-128 A-A P1.11 2FWO3DB-16!C03 2FWO3DB-16 13A-02 C5.51 100 VOL-E UT NAt P1.18 Pipe-Pipe 131-01 131-02 OBS13-129 P-A P1.11 2FWO3DB-16/C04 2FWO3DB-16 13A-02 C5.51 100 VOL-E UT NPI P1.18 Pipe
- Penetration 131-01 131-02 OBS13-130 P-A P1.11 2FWO3DC-16/C01 2FWO3DC-16 13A-02 C5.51 100 VOL-E UT NAI P1.18 Valve-Pipe 131-01 131-02 OBS13-132 A-A A1.11 2FWO3DC-16/C02 2FWO3DC-16 13A-02 C5.51 100 VOL-E UT NAt P1.18 Pipe - Penetration 131-01 131-02 OBS13-133 P-A P1.11 2FW81BC-6/C07 2FW81BC-6 13A-02 C5.51 100 VOL-E UT NAt P1.18 Pipe - Tee 13T-01 131-02 OBS13-134 P-A P1.11 2FW87CC-6/C01 2FW87CC-6 13A-02 C5.51 100 VOL-E UT NPI P1.18 Aeducer-Tee 131-01 131-02 OBS13-135 A-A P1.11 2FW87CC-6/C02 2FW87CC-6 13A-02 C5.51 100 VOL-E UT NAt P1.18 Tee-Pipe 131-01 131-02 OBS13-136 A-A P1.11 2FW87CC-6/C03 2FW87CC-6 l3A-02 C5.51 100 VOL-E UT NAI P1.18 Pipe
- Pipe 131-01 131-02 OBS13-137 3
7/1012007 E,ceIc~~n_
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Main Steam System (MS)
Section Xl Component ID Line Number Relief Technical Code Required Actual Results Cat.
De5~1ptbo1~
Requests Notes Coverage Exam Exam Comments A-A Al 20 2MS01AA-30 25/Cot 2MSO1AA-3025 13A-02 C5.51 100 VOL-E UT NAI Nozzle - Elbow 131-01 131-02 OBS13-158 P-A P1.20 2MSO1AA-30.25/C06 2MSO1AA-30.25 13A-02 C5.51 100 VOL-E UT NAI Elbow - Pipe 131-01 131-02 OBS13-159 4
7/10/2007 ExeI~,n..
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Pressurizer (PZR)
Section Xl Component ID Line Number Relief Technical Code Required Actual Results
~~DescrlptIon Requests Notes Coverage Exam Exam Comments B-D B3.110 2RY-01-S/PN-O1 2AY-O1-S 13R-12 40 VOL UT NAI Surge Nozzle OBS13-160 Scan reduced on nozzle side due to configuration.
Scan from head side reduced by nozzle transition and obstructed by PZP heater penetrations.
B-D B3.120 2AY-01-S/PN-01-NIA 2AY-01-S 100 VOL UT NAt Surge Nozzle Inner Padius OBS13-161 5
7/10/2007
- ExIl Byron Station UnIt 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
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Description Requests Notes Coverage Exam lExam Comments A-A P1.20 2ACO1AA-29/J06 2ACO1AA-29 13A-02 B9.40 VT-2 VT-2 NAI SOL - Thermowell 13T-01 13T-02 OBS13-015 P-A P1.15 2PC-01-P/APVS-A Fl 2AC-01-P 13A-02 65.10 100 VOL UT NAt APV Nozzle Safe-End HL Loop D 13T-01 13T-02 OBS13-100 No ID surface indications seen with ET.
A-A P1.15 2PC-01-A/APVS-B Fl 2AC-01-A l3A-02 B5.10 100 VOL UT NPI APV Nozzle Safe-End CL Loop D 13T-01 13T-02 OBS13-101 No ID surface indications seen with ET.
A-A P1.15 2PC-01-A/APVS-C Fl 2AC-01-A 13P-02 B5.10 100 VOL UT NPI RPV Nozzle Safe-End CL Loop C 13T-01 13T-02 OBS13-102 No ID surface Indications seen with ET.
R-A P1.15 2PC-01-P/APVS-D El 2AC-01-A 13A-02 B5.10 100 VOL UT NAI APV Nozzle Safe-End HL Loop C 13T-01 I3T-02 OBS13-103 No ID surface indications seen with ET.
A-A P1.15 2AC-01-R/APVS-E Fl 2PC-01-A 13A-02 65.10 100 VOL UT NAI PPV Nozzle Safe-End HL Loop B 13T-01 I3T-02 OBS13-104 No ID surface indications seen with ET.
A-A P1.15 2AC-O1-R/APVS-F Fl 2PC-01-P l3P-02 B5.10 100 VOL UT NAI APV Nozzle Safe-End CL Loop B 13T-01 I3T-02 OBS13-105 No ID surface indications seen with ET.
A-A P1.15 2PC-01-R/RPVS-G Fl 2AC-01-P 13P-02 B5.10 100 VOL UT NPI APV Nozzle Safe-End CL Loop A l3T-01 l3T-02 OBS13-106 No ID surface indications seen with ET._______________________
A-A P1.15 2AC-O1-PJAPVS-H Fl 2AC-O1-A 13A-02 B5.10 100 VOL UT NPI APV Nozzle Safe-End HL Loop A 13T-01 13T-02 OBS13-107 No ID surface indications seen with ET.
6
7/10/2007 Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section Xl
~ComponentID Line Number Relief Technical Code RequIred Actual Results
~~Descrlption Requests Notes Coverage Exam Exam Comments A-A Al 20 2ACO3AA-27 5/JO2A 2PCO3AA-27 5 I3A-02 B9.40 VT-2 VT-2 NAI SOL - Therm owell t3T-01 13T-02 OBS13-016 A-A P1.20 OBS13-017 2ACO3AA-27.5/J04 SOL - Thermowell 2ACO3AA-27.5 I3P-02 B9.40 13T-01 13T-02 VT-2 VT-2 NPI A-A P1.20 OBS13-026 2AC13AA-21W-01 SOL - Pipe 2AC13AA-2 13P-02 69.40 131-01 131-02 VT-2 VT-2 NAt A-A P1.20 OBS13-027 2AC13AA-2/W-02 Pipe - Tee 2PC13AA-2 t3A-02 69.40 131-01 131-02 VT-2 VT-2 NAI P-A P1.20 OBS13-028 2AC13AA-2/W-03 Tee - Reducer 2PC13AA-2 l3A-02 69.40 131-01 13T-02 VT-2 VT-2 NAI A-A P1.20 OBS13-029 2AC13AA-2/W-04 Tee - Pipe 2PC13AA-2 I3P-02 B9.40 I3T-0l 131-02 VT-2 VT-2 NAt P-A P1.20 OBS13-030 2PC13AA-21W-05 Pipe - Valve 2AC13AA-2 13R-02 69.40 131-01 13T-02 VT-2 VT-2 NAt A-A P1.20 OBS13-031 2AC13AB-2/W-01 SQL - Pipe 2AC13AB-2 t3A-02 69.40 l3T-01 13T-02 VT-2 VT-2 NAI A-A P1.20 OBS13-032 2AC13AC-2iW-0l SQL - Pipe 2AC13AC-2 13A-02 B9.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.20 OBS13-033 2AC13AD-2/W-0l SOL - Pipe 2PC13AD-2 I3A-02 69.40 13T-01 131-02 VT-2 VT-2 NPI A-A P1.11 OBS13-036 2AC14AA-2/W-01 SOL - Pipe 2AC14AA-2 13P-02 69.40 131-01 131-02 VT-2 VT-2 NAI 7
7/10/2007 Exekn..
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section XI Component ID Line Number Relief Technical Code Required Actual Results Description Requests Notes Coverage Exam Exam Comments A-A P1.11 2RC14AA-2/W-O1A 2RC14AA-2 13P-02 B9.40 VT-2 VT-2 NAI Pipe - Tee 131-01 131-02 OBS13-037 A-A A1.11 OBS13-038 2AC14AA-2iW-O1B Tee - Aeducer 2AC14AA-2 13A-02 B9.40 13T-01 l3T-02 VT-2 VT-2 NAt A-A P1.11 OBS13-039 2AC14AA-21W-O1C Tee - Pipe 2AC14AA-2 I3A-02 B9.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.11 OBS13-040 2AC14AA-2,W-02 Pipe - Elbow 2PC14AA-2 l3P-02 69.40 13T-Ol 131-02 VT-2 VT-2 NAt A-A A1.11 OBS13-041 2AC14AA-21W-03 Elbow - Pipe 2PC14AA-2 13A-02 69.40 131-0 1 131-02 VT-2 VT-2 NAt A-A P1.11 OBS13-042 2AC14AA-2iW-04 Pipe
- Elbow 2RC14AA-2 l3R-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt A-A P1.11 OBS13-043 2PC14AA-2/W-05 Elbow - Pipe 2AC14AA-2 13A-02 B9.40 131-0 1 131-02 VT-2 VT-2 NAI P-A P1.11 OBS13-044 2AC14AA-2/W-06 Pipe - Valve 2AC14AA-2 I3A-02 B9.40 131-01 13T-02 VT-2 VT-2 NPI A-A P1.11 OBS13-045 2AC14AA-2/W-07 Valve - Pipe 2PC14AA-2 13A-02 69.40 13T-01 131-02 VT-2 VT-2 NAI A-A P1.11 OBS13-046 2AC14AA-2,W-08 Pipe - Tee 2PC14AA-2 13A-02 B9.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.11 OBS13-047 2AC14AA-2,W-09 Tee - Aeducer 2AC14AA-2 13P-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt 8
7/10/2007 ExeI~n..
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section XI Component ID
~LIneNumber RelIef Technical Code Required Actual Results Cat.
Descrlption Requests Notes Coverage Exam Exam Comments A-A P111 2AC14AA-2iW-10 2AC14AA-2 13A-02 69.40 VT-2 VT-2 NRI Tee - Pipe 131-01 131-02 OBS13-048 A-A P1.11 OBS13-049 2AC14AA-2/W-11 Pipe - Valve 2AC14AA-2 13A-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt A-A P1.11 OBS13-053 2AC16AA-2iW-03 Valve - Pipe 2RC16AA-2 I3A-02 69.40 13T-01 131-02 VT-2 VT-2 NAt A-A Al.1l OBS13-054 2PC16AA-2/W-04 Pipe - Elbow 2AC16AA-2 13A-02 69.40 13T-0l 131-02 VT-2 VT-2 NRI P-A P1.11 OBS13-055 2PC16AA-2/W-05 Elbow - Pipe 2RC16AA-2 13A-02 B9.40 131-01 131-02 VT-2 VT-2 NRI P-A P1.11 OBS13-056 2AC16AA-2/W-06 Pipe - Elbow 2AC16AA-2 13P-02 B9.40 131-01 I3T-02 VT-2 VT-2 NAI A-A P1.11 OBS13-057 2AC16AA-2/W-07 Elbow - Pipe 2PC16AA-2 13P-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI R-A P1.11 OBS13-058 2AC16AB-2,W-04 Pipe - Elbow 2RC16AB-2 l3P-02 B9.40 13T-0l 13T-02 VT-2 VT-2 NAt A-A P1.11 OBS13-059 2PC16AB-2/W-05 Elbow - Pipe 2AC16AB-2 I3A-02 B9.40 13T-0l 13T-02 VT-2 VT-2 NPI P-A P1.20 OBS13-024 2PC16AC-2/W-08 Pipe
- SQL 2AC16AC-2 I3A-02 69.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.20 OBS13-025 2AC16AD-2/W-01 Valve - Pipe 2AC16AD-2 13A-02 69.40 131-01 131-02 VT-2 VT-2 NAt 9
7/10/2007
- ExeI~
n_
Byron Station Unit 2 B2R13 1St Outage Report Weld I Component Outage Summary SYSTEM:
Section XI ComponentID Line Number Relief Technical Code Required Actual
~Results
~
DescrIption Requests Notes Coverage Exam Exam Comments A-A Pill 2AC21AA-8/J07 2RC21AA-8 I3R-02 B9.1l 100 VOL-E UT NRI Pipe - Elbow 131-01 131-02 QBS13-138 A-A P1.11 QBS13-139 2PC21AA-8/J08 Elbow - Pipe 2AC21AA-8 I3A-02 B9.ll 13T-01 131-02 100 VOL-E UT NPI P-A P1.11 OBS13-140 2PC21AA-8/J09 Pipe - Elbow 2AC21AA-8 13A-02 B9.1l 131-01 131-02 100 VOL-E UT NAt P-A P1.11 OBS13-141 2AC21AA-8/J10 Elbow - Pipe 2RC21AA-8 l3A-02 B9.11 I3T-0l 131-02 100 VOL-E UT NAt A-A P1.20 OBS13-020 2AC22AA-1.5/W-0l SQL - Pipe 2AC22AA-1.5 13P-02 69.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.20 OBS13-021 2AC22AA-1.5/W-05 Elbow - Pipe 2AC22AA-1.5 t3A-02 B9.40 131-01 131-02 VT-2 VT-2 NPI A-A P1.20 OBS13-022 2PC22AC-1.5/W-01 SQL - Pipe 2AC22AC-1.5 13A-02 B9.40 131-01 131-02 VT-2 VT-2 NAt P-A R1.20 OBS13-023 2PC22AC-1.5/W-06 Pipe - Tee 2AC22AC-1.5 I3A-02 69.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.20 QBS13-018 2PC22AD-1.5/W-01 SQL - Pipe 2PC22AD-1.5 I3A-02 B9.40 I3T-01 131-02 VT-2 VT-2 NAI A-A P1.20 OBS13-019 2AC22AD-15/W-08 Pipe - Tee 2AC22AD-l.5 13R-02 B9.40 131-01 131-02 VT-2 VT-2 NPI P-A P1.20 QBS13-034 2AC26A-2/W-01 SQL - Pipe 2RC26A-2 l3R-02 B9.40 13T-01 131-02 VT-2 VT-2 NAI 10
7/1012007 Ex Byron Station UnIt 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section Xl__~omponentID Line Number Relief Technical Code Required Actual Results r~t.
Description
-~
Requests Notes coverage Exam Exam Comments P-A Al 20 2AC26A-2fW-02 2AC26A-2 l3A-02 89.40 VT-2 VT-2 NRI Pipe - Valve 131-01 131-02 QBS13-035 A-A P1.11 2AC3OAA-1.51W-01 2AC3OAA-1.5 Valve - Aeducer 13P-02 69.40 VT-2 VT-2 NPI 131-01 131-02 OBS13-079 11
7/10/2007 Exek! n_
Byron Station Unit 2 B2R13 ISI Outage Report Weld / Component Outage Summary SYSTEM:
Residual Heat Removal System (RH)
Section Xl Component ID Line Numb&
Reflef Technlcal Code
~qulred 1~tu&
Results
~~DescrlptIon Requests Notes Coverage Exam Exam Comments R-A R1.20 2RH12A-8/C17 2RH12A-8 13R-02 C5.11 100 VOL-E UT NRI Pipe - Elbow 31-01 31-02 OBS13-117 12
7/10/2007 ExeI~n..
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section Xl Component ID Line Number Relief
- Technical Code Required Actual Results Cat.
Description Requests Notes Coverage Exam Exam Comments B-N-3 813.70 2PC-01-R/CQPESUPP 2AC-0l-A VT-3 VT-3 NRI STAUCT Core Support Structure OBS13-082 B-N-2 B13.50 2AC-01-AIINT ATTACH 2AC-0l-A VT-i VT-3 NAt BELTLINE Interior Attachment Within-Beltline OBS13-080 B-N-2 B13.60 2AC-0l-A/INT ATTACH 2AC-01-A VT-3 VT-3 NAt NONBELT Interior Attachment Non-Beltline OBS13-081 B-N-i 813.10 2PC-01-R/APV 2AC-01-P VT-3 VT-3 NAt INTEPIOP APV Interior Surfaces OBS13-083 B-D 83.90 2AC-01-A/PPVN-A 2PC-01-A 94 VOL UT IND Nozzle - Shell OBS13-084
- 1) 1.50°,2) 2.00, 3)1.75°,2) 3.25°,1)1.00, and
- 1) 2.25 Mid-wall indications, acceptable per code. Aef: B2A13-AIA-01.
Scan obstructed by nozzle geometry.
B-D B3.100 2PC-01-AIAPVN-A-NIA 2PC-01-R N-648-1 EVT-1 EVT-1 NAt APV Nozzle Inner Radius OBS13-085 6-D B3.90 2AC-01 -P/PP VN-B 2AC-01-A 94 VOL UT IND Nozzle - Shell QBS13-086 5)1.50, 3) 2.00, 2) 2.25, 1) 2.50, 2) 3.00°,and 1) 5.25 Mid-waIl indications, acceptable per code. Aef: B2A13-AIP-02. Scan obstructed by nozzle geometry.
B-D B3.l00 2AC-Ol-R/APVN-B-NIA 2AC-01-A N-648-1 EVT-1 EVT-i NRI APV Nozzle Inner Padius OBS13-087 B-D 63.90 2AC-0l-A/APVN-C 2PC-01-P 94 VOL UT IND Nozzle - Shell QBS13-088 1)1.00, 1) 1.25, 6)1.50, 1) 1.75, 7)2.00°,4)2.50, 2)3.00, 1)3.25°,and 1)3.50 Mid-wall indications, acceptable percode. Pef:
B2P13-PIR-03. Scan obstructed by nozzle geometry.
B-D B3.100 2AC-0l-RIAPVN-C-NIA 2PC-01-A N-648-l EVT-1 EVT-1 NAt APV Nozzle Inner Padius OBS13-089 B-D B3.90 2AC-01-PiPPVN-D 2PC-01-A 94 VOL UT IND Nozzle - Shell QBS13-090 3)1.50°,1) 2.00, 2)2.25°,2) 2.75°,1) 3.25°,and
- 1) 4.00° Mid-wall indications, acceptable per code. Pef: B2A13-AIP-04. Scan obstructed by nozzle geometry.
13
7/10/2007
- Ecekn~
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
SectIon Xl Component ID Line Number Relief Technical Code Required Actual Results
~
Description Requests Notes Coverage Exam Exam Comments B-D B3 100 2RC-01-A/PPVN-D-NIR 2AC-01-R N-648-l EVT-l EVT-1 NAI PPV Nozzle Inner Padius QBS13-091 B-D B3.90 2AC-01-A/APVN-E 2AC-01-A 94 VOL UT IND Nozzle - Shell OBS13-092 1)1.50°,2)1.75, 1)2.50°,and 1) 4.00°Mid-wall indications, acceptable per code. Aef: B2R13-RIP-05. Scan obstructed by nozzle geometry.
B-D B3.100 2PC-01-P/APVN-E-NIP 2AC-01-A N-648-1 EVT-1 EVT-1 NRI APV Nozzle Inner Padius QBS13-093 B-D B3.90 2PC-01-AIAPVN-F 2PC-01-A 94 VOL UT IND Nozzle - Shell OBS13-094 1)1.25, 1)1.50, 1)1.75°,3)2.00, 2) 2.50°,and 3)3.00 Mid-waIl indications, acceptable per code. Aef: B2P13-AIP-06. Scan obstructed by nozzle geometry.
B-D B3.100 2AC-01-P/PPVN-F-NIR 2AC-01-A N-648-1 EVT-l EVT-1 NAP RPV Nozzle Inner Aadius OBS13-095 B-D B3.90 2PC-0l-AJAPVN-G 2AC-01-A 94 VOL UT IND Nozzle - Shell OBS13-096 1)1.25, 5)1.50, 2)1.75, 2) 2.25°,2) 2.50, and 1) 4.00°Mid-wall indications, acceptable per code. Aef: B2A13-AIA-07. Scan obstructed by nozzle geometry.
B-D 63.100 2AC-0l-A/RPVN-G-NIR 2AC-01-A N-648-l EVT-1 EVT-l NAJ PPV Nozzle Inner Aadius QBS13-097 B-D B3.90 2PC-0l-A/APVN-H 2PC-01-P 94 VOL UT IND Nozzle - Shell OBS13-098 2)1.50, 4) 2.00, 1) 2.50°,2)2.75°,1) 3.00, 2) 4.00, and 1) 5.00°Mid-wall indications, acceptable per code.
Pef: B2A13-AIA-08. Scan obstructed by nozzle geometry.
B-D 63.100 2AC-01-PJAPVN-H-NIP 2PC-01-A N-648-1 EVT-1 EVT-1 NAt APV Nozzle Inner Padius OBS13-099 B-A B1.30 2PC-0l-R/WA-07 2PC-01-P 99 VOL UT Al Shell
- Flange OBS 13-1 12
- 1) 0.50 and 1) 0.60°Mid-waIl indications, acceptable per code. Pef: B2A13-AIA-l0.
B-A B1.21 2AC-O1-R,WA-16 2PC-0l-P 100 VOL UT NPI Lower Head Meridian Weld OBS13-108 Scan obstructed by bottom mounted instrumentation nozzles. Coverage per PDI single-sided access qualifications.
14
7/10/2007 eI4~,n Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section XI ~OrnpOneflI ID
~Line Number Relief Technical Code Required ~ActuaI Results cat.
DescriptIon Requests Notes Coverage Exam Exam Comments B-A 61.11 2AC-01-R/WA-l8 2RC-01-A Shell - Shell OBS13-109 1)0.60°and 1)1.10 Mid-wall indications, acceptable per code. Aef: B2P13-PIA-09.
B-A B1.11 2AC-0l-R/WA-29 2AC-01-P 13A-15 Shell
- Shell OBS13-110 Scan obstructed by core support lugs.
B-A 81.11 2AC-0l-AWP-34 Shell - Shell 100 VOL UT IND 79 VOL UT NAI 2AC-01-A 100 VOL UT NRI OBS13-111 15
7/10/2007 ExeI~n..
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Xl Component ID Line Number Relief Technical Code
~Iequhed~Actu~
Resu Cat.
Description Requests Notes Coverage Exam Exam Comments R-A Al 20 2RYO1B-6/J08 2AYO1B-6 13A-02 B9.1l 100 VQL-E UT NAt Elbow - Pipe 131-0 1 131-02 QBS13-148 A-A P1.11 QBS13-146 2PV11A-14/J08 Pipe - Pipe 2AV11A-14 13A-02 B9.11 100 VQL-E 131-01 131-02 UT NAt A-A P1.11 OBS13-001 2AY18A-2/W-01 Valve - Pipe 2AY18A-2 I3A-02 69.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.11 OBS13-002 2AY18A-2/W-02 Pipe - Elbow 2AY18A-2 13A-02 B9.40 131-01 31-02 VT-2 VT-2 NAI A-A P1.11 QBS13-003 2AY18A-2/W-03 Elbow - Pipe 2AY18A-2 13A-02 B9.40 131-0 1 131-02 VT-2 VT-2 NAt A-A A1.1l OBS13-004 2AY18A-2,W-04 Pipe
- WOL 2AY18A-2 13A-02 B9.40 131-01 l3T-02 VT-2 VT-2 NRI 16
7/10/2007
- ExeI~n..
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section Xl Component ID Line Number Relief TechnIcal Code Required 1Actual Results
~Cat.
Descrlptlon
Requests Notes Coverage Exam Exam Comments C-B C2.21 2AC-01-BAJSGN-02 2RC-01-BA 100 SUAF MT NAI Feedwater Nozzle 100 VOL UT NPI OBS13-149 Aef: IA 00614558 C-B C2.22 2AC-01-BA/SGN-02-NIA 2AC-01-BA VOL UT NAI Feedwater Nozzle NIP OBS13-150 17
7/10/2007 Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Safety Injection System (SI)
Section Xl Component ID Line Number Relief Technical Code Required Actual Results
~~~~Descrlptlon Requests Notes Coverage Exam Exam Comments A-A P1.20 2SIO5AB-8/C01 2SIO5AB-8 l3A-02 C5.ll 100 VQL-E UT NRI Tee - Elbow 131-01 131-02 OBS13-121 P-A P1.11 OBS13-060 2SIO8HA-2/W-01 Aeducer - Coupling 2SIO8HA-2 t3P-02 B9.40 13T-0l 131-02 VT-2 VT-2 NPI P-A P1.11 OBS13-061 2SIO8HA-2/W-02 Coupling - Pipe 2SIO8HA-2 t3A-02 B9.40 13T-0l 131-02 VT-2 VT-2 NAI A-A P1.11 OBS13-062 2SIO8HA-2/W-03 Pipe
- Flange 2SIO8HA-2 t3P-02 69.40 l3T-01 131-02 VT-2 VT-2 NAI A-A P1.11 CBS13-063 2SIO8HA-2/W-04 Flange - Pipe 2SIO8HA-2 l3A-02 B9.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.11 OBS13-064 2SIO8HA-2/W-05 Pipe - Coupling 2SIO8HA-2 13A-02 B9.40 131-01 131-02 VT-2 VT-2 NRI P-A P1.11 OBS13-065 2SIO8HA-2/W-06 Coupling - Peducer 2SIO8HA-2 13P-02 69.40 131-0 1 131-02 VT-2 VT-2 NAt P-A P1.11 OBS13-066 2SIO8JA-1.5/W-01 Peducer - Pipe 2SIO8JA-1.5 I3A-02 69.40 131-0 1 131-02 VT-2 VT-2 NAI P-A P1.11 QBS13-067 2SIO8JA-1.5/W-02 Pipe - Elbow 2SIO8JA-1.5 l3A-02 69.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.11 OBS13-068 2SIOSJA-1.5/W-03 Elbow - Pipe 2SIO8JA-1.5 I3P-02 B9.40 I3T01 131-02 VT-2 VT-2 NAI P-A Rl.11 OBS13-069 2SIO8JA-1.51W-04 Pipe - Elbow 2SIO8JA-1.5 I3A-02 69.40 131-01 I3T-02 VT-2 VT-2 NAI 18
7/10/2007 ExeI~n_
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Safety Injection System (SI)
Section_Xl__Component ID Line Number Relief Technical Code Required Actual Results DescriptIon Requests Notes Coverage Exam Exam
~mmentS P-A Pill 2SIO8JA-1 5/W-05 2SIO8JA-1.5 13A-02 B9.40 VT-2 VT-2 NAt Elbow - Pipe 131-01 13T-02 OBS13-070 A-A P1.11 OBS13-071 2SIO8JA-1.5,W-05A Pipe - Valve 2SIO8JA-1.5 I3A-02 69.40 131-01 131-02 VT-2 VT-2 NAt P-A P1.11 OBS13-072 2SIO8JA-1.5iW-05B Valve - Pipe 2SIO8JA-1.5 l3A-02 69.40 131-01 131-02 VT-2 VT-2 NPI P-A P1.11 OBS13-073 2SIO8JA-1.5iW-06 Pipe - Elbow 2SI08,JA-1.5 i3A-02 B9.40 131-01 13T-02 VT-2 VT-2 NPI P-A P1.11 CBS13-074 2SIO8JA-1,51W-07 Elbow - Pipe 2SIO8JA-1.5 13P-02 69.40 l3T-01 I3T-02 VT-2 VT-2 NAI A-A P1.11 CBS13-075 2SIO8JA-1.5/W-10 Pipe - Flange 2SIO8JA-1.5 l3P-02 B9.40 13T-01 131-02 VT-2 VT-2 NAt A-A P1.11 CBS13-076 2S108JA-1.5/W-l1 Flange - Pipe 2SIO8JA-1.5 13A-02 69.40 13T-01 131-02 VT-2 VT-2 NPI A-A P1.11 CBS13-077 2S1O8JA-1.5/W-14 Pipe - Coupling 2SIO8JA-1.5 l3A-02 69.40 131-01 l3T-02 Vr-2 VT-2 NPI A-A P1.11 CBS13-078 2SIO8JA-1.5/W-15 Coupling - Pipe 2SIO8JA-1.5 l3A-02 B9.40 131-01 131-02 VT-2 VT-2 NAI P-A P1.20 OBS13-122 2S134A-8/C01 Tee - Pipe 2St34A-8 l3A-02 C5.ll 131-01 131-02 100 VOL-E UT NAI P-A P1.20 CBS13-123 2S134A-8/C23 Pipe - Elbow 2S134A-8 l3A-02 C5.1l 131-01 131-02 100 VOL-E UT NPi 19
7/10/2007 ExeI~n_
Byron Station UnIt 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Safety Injection System (SI)
Section Xl Component ID Line Number Relief Technical Code Required Actual Results cat.
Description
-~____________
Requests Notes Coverage Exam Exam Comments A-A P1.20 2S134A-8/C24 2S134A-8 13P-02 C5 11 100 VOL-E UT NPI Elbow - Pipe l3T-01 I3T-02 CBS13-124 A-A P1.20 CBS13-115 2S182AA-12/C04 Pipe - Elbow 2SI82AA-12 13P-02 C5.l1 13T-01 131-02 100 VOL-E UT NAI P-A P1.20 OBS13-116 2S182AA-12/C05 Elbow - Pipe 2Sl82AA-12 13P-02 C5.1l 13T-01 131-02 100 VCL-E UT NAt 20
7/10/2007 e
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Essential Service Water System (SX)
SectionXI~omponentID Line Number Relief
~
-- - i
~ctu~j~
- i~uits cat.
Description Requests Notes Coverage Exam Exam Comments C-C C3.20 2SXO7FA-16/C1OA 2SXO7FA-16 NA 98 SURF MT NAI Closure Plate 2PC-14 CBS13-126 Penetration side obstructed by welded ID plate.
21
7/10/2007 Exek,n~
Byron Station Unit 2 B2R13 ISI Outage Report Bolts, Pumps, and Valves Outage Summary SYSTEM:
Reactor Pressure Vessel (RPV) je~ionxi n~ji~~
Theii~i~JT~inical Actuat 1Results
~
j~~DescrIptlon Requests Notes Exam Comments B-G-1 66.10 2PC-0i-R/N01-N18 VT-l NPI PPV Closure Head Nuts VT-i NPI CBS13-155 B-G-1 B6.10 CBS13-155 2AC-0i-P/N19-N36 APV Closure Head Nuts VT-i VT-i NAI NPI B-G-1 B6.10 CBS13-155 2RC-01-P/N37-N54 PPV Closure Head Nuts VT-i VT-i NPI NAP B-G-1 66.20 CBS13-157 2RC-01-R/S01-S18 PPV Closure Head Studs UT NPI B-G-1 66.20 OBS13-157 2AC-01-R/S19-S36 PPV Cksure Head Studs UT NAt B-G-1 B6.20 CBS13-157 2AC-Oi-R/S37-S54 APV Closure Head Studs UT NPI 1
7/1012007
- Exek~n_
Byron Station UnIt 2 B2R13 ISI Outage Report Bolts, Pumps, and Valves Outage Summary SYSTEM:
SectionXlCornponentlo
llTe1A Cat.
It~
DescrIption Requests Notes Exam Comments B-G-2 B7.50 2PYO3BA-6/FLG 1-12 VT-i NAI Piping Flange Bolting VT-i NRI CBS13-164 2007-298:_Nuts, tool marks noted. 2007-300: Studs.
B-M-2 Bi2.50 2AY8O1OA/PNT SUPF VT-3 NAP Valve Body interior CBS13-167 Disassembled under WO 00886405.
2
7/10/2007 Exek)n Byron Station Unit 2 B2R13 ISI Outage Report Bolts, Pumps, and Valves Outage Summary SYSTEM:
Section Xl Component ID Relief
~fechnIcal Actual Results L Cat.
it~r~Description Requests Notes Exam Lcomments B-G-2 6730 2AC-01-BC/BLT 1-32 VT-i NAP SG Manway Studs and Nuts CBS13-151 B-G-2 B7.30 2AC-01-BD/BLT 1-32 VT-i NAP SG Manway Studs and Nuts CBS13-152 3
711012007
~
Byron Station Unit 2 B2R13 ISI Outage Report Bolts, Pumps, and Valves Outage Summary SYSTEM:
Safety Injection System (SI)
Section XI Component ID Relief Technical Actual Results
- cat.
Item Description Requests Notes Exam Comments B-G-2 B7.50 2SPO8JA-1.5/FLG 1-4 VT-i NAt Piping Flange Bolting CBS13-165 Disassembled under WC00971151. Mechanical Joint MJ-82C.
B-G-2 B7.50 2SIO8JB-1.5/FLG 1-4 VT-i NPI Piping Flange Bolting CBS13-166 Disassembled under WC00971152. Mechanical Joint MJ-78.
B-G-2 B7.70 2S18818C/BLT 1-16 VT-i NAI Valve Studs, Nuts, Bushings, and Washers CBS13-162 Disassembled under WO 00927431.
B-M-2 B12.50 2S18818C/INTSUPF VT-3 NAI Valve Body Interior CBS13-163 Disassembled under WC00927431.
4
BYRON Exekn..
UNIT 2 Nuclear B2R13 Spring 2007 Outage INSERVICE INSPECTION
SUMMARY
REPORT For Inspection Activities from October 12, 2005 to May 3, 2007 Commercial Service Date August 21, 1987 Document Completion Date July 10, 2007 Exelon Generation Company (EGC, LLC) 4300 Winfield Rd Warrenville, IL 60555 Byron Nuclear Power Station 4450 North German Church Rd.
Byron, IL 61010
BYRON UNIT 2 Exeln.
B2R13 Nuclear INSERVICE INSPECTION
SUMMARY
REPORT I SECTION SECTION DESCRIPTION PAGES!
I
ICover Page I
1 I
8 I
I ii JTable of Contents I
1 I
I 1.0 IReport Introduction I
6 I
2.0 Examination Summary Tables (SI - Weld / Component Listing (SI
- Bolts, Pumps, and Valves Listing PSI
- Weld / Component Listing PSI - Bolts, Pumps, and Valves Listing ISI
- Pressure Tests (SI
- Component Supports IS)
- Snubbers PSI - Snubbers 21 4
1 1
12 10 11 3.0 IStatus of Examination Completion for the Program Plan 1
1 I
4.0 IForm NIS-1: Preservice and Inservice Examinations I
58 1
1 5.0 IForm NIS-2: Repairs / Modifications 1
101 I 6 0 C(S) Re ort 2nd IWL 5-Year Containment p
Penetration Concrete Surveillance Reportl 5
I 2PC064M Conditions Found I
I 21 I
TOTALPAGESINREPORTJ 246 I I
BYRON STATION UNIT 2 REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT
1.0 INTRODUCTION
lnservice inspections of American Society of Mechanical Engineers (ASME) Class 1, 2, 3, CC, and MC components were conducted at Byron Station Unit 2 from October 12, 2005 through May 3, 2007. The majority of these inspections were performed during the thirteenth refueling outage (B2R13) from April 2 through May 3-, 2007.
The examinations were performed in compliance with the rules and regulations of ASME Section Xl, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components, (applicable edition and addenda), pursuant to the requirements of 10 CFR 50.55a, Codes and Standards.
This summary report meets the requirements of ASME Code, IWA-6000 for the inspection of Class 1 and 2 components and piping. Class CC and MC components in the Containment Inservice Inspection (CISI) program are included when examination results require reporting as specified in 10 CFR 50.55a. See 7.0 in this section for a listing of referenced documents.
The Nondestructive Examination (NDE) Inservice Inspection (ISI) Program Plan for Class 1, 2, and 3 components was developed in accordance with the requirements and intent of Section Xl Subsections (WA, IWB, IWC, IWD, IWE, IWF and IWL, 2001 Edition, through the 2003 Addenda.
In addition to the ASME Section Xl requirements of examination, certain Nuclear Regulatory Commission (NRC) augmented ISI inspections were required. The Byron Station Unit 2 augmented (SI examination requirements include:
a) Class 1 pressure boundary for leakage at nominal operating pressure, in accordance with NRC Generic Letter 88-05, Boric Acid Corrosion ofCarbon Steel Reactor Pressure Boundaty Components in PWR Plants; b) Class 2 and 3 pressure boundary for leakage at nominal operating pressure, in accordance with NUREG 0737, Clarification of TMI Action Plan Requirements; Note: Specific requests for relief were developed and submitted for the NRCs review when the code and/or augmented requirement(s) were deemed to be impractical, results in excessive hardship, or an alternative examination method is determined as more suitable for the particular component.
1.1 Identification of Examination Requirements The Section 7.0 of the ISI Program Plan contains the examination program tables.
These tables are presented in a tabular format consistent with the tables found in Subsections IWB, IWC, IWD, (WE, IWF, and IWL-2500 of the ASME Code. The examination tables include the corresponding code category, item number, and component/weld selection in conformance with examination requirements and intent of Subsection (WA, IWB, IWC, IWD, IWE, IWF, and IWL of Section Xl of the ASME Code.
Section 1.0 Page 1 of 6
BYRON STATION UNIT 2 REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT For Class 1, 2, and certain non-class piping components, the requirements of Risk Informed Inservice Inspection (RI-IS)) are followed using EPRI TR112657 and Table 1 of ASME Code Case N-578-1.
1.2 Identification of Exempted Components ASME Class 1, 2, and 3 components, or parts of components, that are not included in the examination tables and that are exempt from examination, as specified in Section XI Paragraphs IWB, IWC, and IWD-1200, Components Exempt from Examination, and Tables IWB-2500-1, IWC-2500-1, and IWD-2500-i, are identified in the NDE Program Plan in conjunction with technical justification(s) for exempting the component/system.
Class 1 or 2 piping welds exempted by IWB and IWC-1200 are not included in the RI-ISI program. Previous selection and examination exemptions identified in Tables IWB and IWC-2500-1 for Examination Categories B-F, B-J, C-F-i, and C-F-2, are not allowed under the requirements of the RI-IS) program. With the adoption of RI-(SI, welds evaluated as Risk Category 6 or 7 are not required to be subject to examination.
1.3 Implementation of the (SI Program Exelon Nuclear, or its designee, visually examined ASME components utilizing the following test methods: VT-i, VT-2, and VT-3. The components examined comply with the (SI Program Schedule, Byron Station Technical Specifications, and/or comply with the ASME Section Xl Repair/Replacement Program.
Certified personnel performed and evaluated visual examinations (i.e., VT-i, VT-2, and VT-3) of Class 1, 2, and 3 components, and supports. Exelon Nuclear personnel certification procedures comply with the requirements of ANSI/ASNT CP-189, 1995 Edition and ASNT SNT-TC-1A, 1984 Edition.
Certified personnel performed and evaluated all NDE. Personnel were certified to the requirements of the ASNT SNT-TC-1A, 1984 Edition. Additionally, ultrasonic examiners were certified in accordance with ANSI/ASNT CP-1 89, 1995 Revision.
The NDE procedures were developed and certified in conformance with ASME Section V and Xl as applicable.
All ISI NDE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section Xl, Subarticle IWA-2200 Examination Methods. For components incorporated into the RI-ISI program, the guidance for the examination volume for a given degradation mechanism is provided by the EPRI Topical Report while the guidance for the examination method is provided by Code Case N-578-1.
Section 1.0 Page 2 of 6
BYRON STATION UNIT 2 REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT 1.4 Second and Third 10-Year Inspection Intervals The ~
fuel cycle for Unit 2 encompasses a time span of October 12, 2005 to May 3, 2007. Activities that occurred prior to January 16, 2006 were performed during the Third Inspection Period of the Second Inspection Interval. Activities that occurred on or after January 16, 2006 were performed during the First Inspection Period of the Third Inspection Interval.
1.5 Significant Section XI Activities During B2R1 3 During the refueling outage, the Alloy 600 pressurizer safe-end welds were overlaid with PWSCC resistant Alloy 690 material. Full structural weld overlays on the surge, spray, relief, and safety nozzles were completed. Baseline (PSI) examinations were performed on the overlays using qualified procedures, equipment, and personnel.
The weld overlays allowed the performance of qualified examinations to meet the requirements specified in MRP-139.
The 2nd 10-year inspection of the reactor vessel was completed during B2R13. The performance of this examination in the First Inspection Period of the Third Inspection Interval was authorized with Relief Request 13-01 (ML062280606). The personnel, equipment, and procedures used for these examinations are qualified in accordance with EPRIs Performance Demonstration Initiative (PDI). The B2R1 3 examinations comply with the requirements of ASME Section XI, Appendix VIII, 2001 Edition, as specified by 10CFR5O.55a(b)(2)(xxiv).
1.6 ASME Section Xl Code Cases The following code cases are incorporated into the current Byron Station ISI Program and were utilized during the ~
fuel cycle.
N-460 Alternative Examination Coverage for Class 1 and Class 2 Welds.
N-566-2 Corrective Action for Leakage Identified at Bolted Connections.
N-624 Successive Inspections.
The following code cases were used in the examination of the Unit 2 reactor vessel and associated safe-end welds.
N-6 13-1 Ultrasonic Examination of Penetration Nozzles in Vessels, Examination Categoiy B-D, Item Nos. B3. 10 and B3.90, Reactor Nozzle-to-Vessel Welds, Figs. IWB-2500-7(a), (b), and (c).
N-648-1 Alternative Requirements for Inner Radius Examinations of Class 1 Reactor Vessel Nozzles.
N-695 Qualification Requirements for Dissimilar Metal Piping Welds.
Section 1.0 Page 3 of 6
BYRON STATION UNIT 2 REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT The following code case is used for the implementation of the risk-informed program as described in relief request 13R-02.
N-578-1 Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B.
Portions of the following cases were utilized as described in relief request l3R-08 for the full structural weld overlays applied to the pressurizer safe-end welds:
N-504-2 Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping.
N-638-1 Similar and Dissimilar Metal Welding Using Ambient Temperature Machine c3TAW Temper Bead Technique.
Repair/replacement activities that occurred prior to January 16, 2006 were in the Second Inspection Interval under the 1989 Edition of the ASME Code.
1.7 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANII): Greg FeigeI, Jeff Hendricks, and Lee Malabanan.
These inspectors are associated with Hartford Steam Boiler Inspection and Insurance Company of Connecticut, Chicago Branch, at 2443 Warrenville Rd., Suite 500, Lisle, Illinois 60532.
2.0 EXAMINATION SUMMARIES The following section lists the summaries of examinations performed during the refueling cycle. Refer to Section 2.0 for each summary table for information or for specific tests and examinations conducted during this term.
Welds & Components Summaries Inservice Inspection - Weld / Component Listing Inservice Inspection - Bolts, Pumps, and Valves Listing Preservice Inspection - Weld / Component Listing Preservice Inspection - Bolts, Pumps, and Valves Listing System Pressure Test Summaries Component Support Examination Summary Component Snubber Test Summary 3.0 UNIT 2 EXAMINATION COMPLETION STATUS A summary table of the examination status of Class 1, 2, and 3 components is contained in Section 3.0.
Section 1.0 Page 4 of 6
BYRON STATION UNIT 2 REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT 4.0 FORM NIS-1 DATA SHEETS ASME Form NIS-2, Owners Report for Inservice Inspections, were filed during the cycle for Unit 2. See Section 4.0 for the reports.
5.0 FORM NIS-2 DATA SHEETS ASME Form NIS-2, Owners Report for Repairs or Replacements, were filed during the cycle for Unit 2. See Section 5.0 for the reports.
6.0 CONTAINMENT ISI PROGRAM Reportable conditions were identified for Class CC and Class MC components during this fuel cycle. The reporting requirements in 10CFR5O.55a (b)(2)(viii)(E) and (b)(2)(ix)(A) are applicable for this summary report. See Section 6.0 for these condition reports.
7.0 REFERENCED DOCUMENTS 7.1 Code of Federal Regulations, Title 10 Energy Part 50, Domestic Licensing of Production and Utilization Facilities 50.55a, Codes and Standards 7.2 American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section V, Nondestructive Examination, 2001 Edition, through 2003 Addenda.
Section Xl, Rules for lnservice Inspection of Nuclear Power Plant Components, 1989 Edition (for 2nd Inspection Interval repair/replacement activities).
Section XI, Rules for Inservice Inspection ofNuclear Power Plant Components, 2001 Edition, through 2003 Addenda (for all 3Id Inspection Interval activities).
7.3 American National Standards Institute / American Society for Nondestructive Testing ANSI/ASNT CP-1 89, 1995 Edition, Standard for Qualification and Certification of Nondestructive Testing Personnel 7.4 American Society for Nondestructive Testing ASNT Recommended Practice No. SNT-TC-1A, 1984 Edition, Personnel Qualification and Certification in Nondestructive Testing Section 1.0 Page 5 of 6
BYRON STATION UNIT 2 REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT 7.5 Miscellaneous NRC Documents Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants.
NUREG 0737, Clarification of TM! Action Plan Requirements.
7.6 Electric Power Research Institute Material Reliability Program Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-139) July 14, 2005.
Topical Report TR1 12657 Revision B-A, Revised Risk-Informed Inservice Inspection Procedure, December 1999.
Section 1.0 Page 6 of 6
7/10/2007 ExeI~n~
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Chemical & Volume Control System (CV)
~
I~
~
A~ieTI A~j~ii~red
~ii~i~
f~e~uit~
Cat.
Description Requests Notes Coverage Exam Exam Comments R-A R120 2CV98C-8/C03 2CV98C-8 l3R-02 C5.11 100 VOL-E UT NRI Pipe. Elbow 131-01 131-02 OBS13-119 R-A R1.20 OBS13-120 2CV98C-8/C04 Elbow - Pipe 2CV98C-8 I3IR-02 C5.11 100 VOL-E 13T-01 131-02 UT NRI R-A R1.11 OBS13-005 2CVA3B-2/W-70 Pipe
- Elbow 2CVA3B-2 13R-02 B9.40 131-01 131-02 VT-2 VT-2 NAI A-A Pill OBS13-006 2CVA3B-2,W-71 Elbow - Pipe 2CVA3B-2 13A-02 B9.40 l3T-01 131-02 VT-2 VT-2 NRI A-A P1.11 OBS13-007 2CVA3B-2/W-72 Pipe - Elbow 2CVA3B-2 13R-02 B9.40 13T-01 13T-02 VT-2 VT-2 NAI R-A P1.11 OBS13-008 2CVA3B-2/W-73 Elbow - Pipe 2CVA3B-2 13R-02 B9.40 131-0 1 131-02 VT-2 VT-2 NAt R-A P1.11 OBS13-009 2CVA3B-2/W-80 Pipe - Elbow 2CVA3B-2 13A-02 B9.40 131-01 131-02 VT-2 VT-2 NRI A-A P1.11 OBS13-010 2CVA3B-2/W-81 Elbow - Pipe 2CVA3B-2 13R-02 B9.40 131-0 1 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS13-011 2CVA5AA-2iW-06 Pipe - Elbow 2CVA5AA-2 13R-02 B9.40 131-0 1 131-02 VT-2 VT-2 NRI A-A P1.11 OBS13-012 2CVA5AA-2,W-07 Elbow - Pipe 2CVA5AA-2 13P-02 B9.40 131-0 1 131-02 VT-2 VT-2 NPI P-A P1.11 OBS13-013 2CVA6AA-2/W-04 Pipe - Elbow 2CVA6AA-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt 1
7/10/2007 Exek.tin Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Chemical & Volume Control System (CV)
Sechon XI Component ID
Line p Relief Technical Code Requfreci~Actu&-
Results Cat Description Requests Notes Coverage Exam Exam
___~
-~---
__i*
Comments P-A P1.11 2CVA6AA-21W-05 2CVA6AA-2 13A-02 B9.40 VT-2 VT-2 NAI Elbow - Pipe l3T-01 131-02 OBS13-014 A-A P1.11 OBS13-050 2CVA7AA-21W-06 Pipe - Elbow 2CVA7AA-2 13P-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt P-A P1.11 OBS13-051 2CVA7AA-2/W-07 Elbow - Pipe 2CVA7AA-2 13A-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt A-A P1.11 OBS13-052 2CVA7AA-2/W-08 Pipe - Elbow 2CVA7AA-2 13P-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt 2
7/10/2007 Exekit Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section Xl Component ID Line Number Relief Technical Code Required Actual Results Description Requests Notes f~overageExam Exam comments A-A P1.11 2FWO3DB-16/C01 2FWO3DB-16 13A-02 C551 100 VOL-E UT NAI P1.18 Valve-Pipe l3T-01 131-02 OBS13-127 A-A A1.11 2FWO3DB-16/C02 2FWO3DB-16 13A-02 C5.51 100 VOL-E UT NAt P1.18 Pipe-PIpe 13T-01 131-02 OBS13-128 A-A P1.11 2FWO3DB-16!C03 2FWO3DB-16 13A-02 C5.51 100 VOL-E UT NAt P1.18 Pipe-Pipe 131-01 131-02 OBS13-129 P-A P1.11 2FWO3DB-16/C04 2FWO3DB-16 13A-02 C5.51 100 VOL-E UT NPI P1.18 Pipe
- Penetration 131-01 131-02 OBS13-130 P-A P1.11 2FWO3DC-16/C01 2FWO3DC-16 13A-02 C5.51 100 VOL-E UT NAI P1.18 Valve-Pipe 131-01 131-02 OBS13-132 A-A A1.11 2FWO3DC-16/C02 2FWO3DC-16 13A-02 C5.51 100 VOL-E UT NAt P1.18 Pipe - Penetration 131-01 131-02 OBS13-133 P-A P1.11 2FW81BC-6/C07 2FW81BC-6 13A-02 C5.51 100 VOL-E UT NAt P1.18 Pipe - Tee 13T-01 131-02 OBS13-134 P-A P1.11 2FW87CC-6/C01 2FW87CC-6 13A-02 C5.51 100 VOL-E UT NPI P1.18 Aeducer-Tee 131-01 131-02 OBS13-135 A-A P1.11 2FW87CC-6/C02 2FW87CC-6 13A-02 C5.51 100 VOL-E UT NAt P1.18 Tee-Pipe 131-01 131-02 OBS13-136 A-A P1.11 2FW87CC-6/C03 2FW87CC-6 l3A-02 C5.51 100 VOL-E UT NAI P1.18 Pipe
- Pipe 131-01 131-02 OBS13-137 3
7/1012007 E,ceIc~~n_
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Main Steam System (MS)
Section Xl Component ID Line Number Relief Technical Code Required Actual Results Cat.
De5~1ptbo1~
Requests Notes Coverage Exam Exam Comments A-A Al 20 2MS01AA-30 25/Cot 2MSO1AA-3025 13A-02 C5.51 100 VOL-E UT NAI Nozzle - Elbow 131-01 131-02 OBS13-158 P-A P1.20 2MSO1AA-30.25/C06 2MSO1AA-30.25 13A-02 C5.51 100 VOL-E UT NAI Elbow - Pipe 131-01 131-02 OBS13-159 4
7/10/2007 ExeI~,n..
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Pressurizer (PZR)
Section Xl Component ID Line Number Relief Technical Code Required Actual Results
~~DescrlptIon Requests Notes Coverage Exam Exam Comments B-D B3.110 2RY-01-S/PN-O1 2AY-O1-S 13R-12 40 VOL UT NAI Surge Nozzle OBS13-160 Scan reduced on nozzle side due to configuration.
Scan from head side reduced by nozzle transition and obstructed by PZP heater penetrations.
B-D B3.120 2AY-01-S/PN-01-NIA 2AY-01-S 100 VOL UT NAt Surge Nozzle Inner Padius OBS13-161 5
7/10/2007
- ExIl Byron Station UnIt 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
~
~
~
~
Description Requests Notes Coverage Exam lExam Comments A-A P1.20 2ACO1AA-29/J06 2ACO1AA-29 13A-02 B9.40 VT-2 VT-2 NAI SOL - Thermowell 13T-01 13T-02 OBS13-015 P-A P1.15 2PC-01-P/APVS-A Fl 2AC-01-P 13A-02 65.10 100 VOL UT NAt APV Nozzle Safe-End HL Loop D 13T-01 13T-02 OBS13-100 No ID surface indications seen with ET.
A-A P1.15 2PC-01-A/APVS-B Fl 2AC-01-A l3A-02 B5.10 100 VOL UT NPI APV Nozzle Safe-End CL Loop D 13T-01 13T-02 OBS13-101 No ID surface indications seen with ET.
A-A P1.15 2PC-01-A/APVS-C Fl 2AC-01-A 13P-02 B5.10 100 VOL UT NPI RPV Nozzle Safe-End CL Loop C 13T-01 13T-02 OBS13-102 No ID surface Indications seen with ET.
R-A P1.15 2PC-01-P/APVS-D El 2AC-01-A 13A-02 B5.10 100 VOL UT NAI APV Nozzle Safe-End HL Loop C 13T-01 I3T-02 OBS13-103 No ID surface indications seen with ET.
A-A P1.15 2AC-01-R/APVS-E Fl 2PC-01-A 13A-02 65.10 100 VOL UT NAI PPV Nozzle Safe-End HL Loop B 13T-01 I3T-02 OBS13-104 No ID surface indications seen with ET.
A-A P1.15 2AC-O1-R/APVS-F Fl 2PC-01-P l3P-02 B5.10 100 VOL UT NAI APV Nozzle Safe-End CL Loop B 13T-01 I3T-02 OBS13-105 No ID surface indications seen with ET.
A-A P1.15 2PC-01-R/RPVS-G Fl 2AC-01-P 13P-02 B5.10 100 VOL UT NPI APV Nozzle Safe-End CL Loop A l3T-01 l3T-02 OBS13-106 No ID surface indications seen with ET._______________________
A-A P1.15 2AC-O1-PJAPVS-H Fl 2AC-O1-A 13A-02 B5.10 100 VOL UT NPI APV Nozzle Safe-End HL Loop A 13T-01 13T-02 OBS13-107 No ID surface indications seen with ET.
6
7/10/2007 Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section Xl
~ComponentID Line Number Relief Technical Code RequIred Actual Results
~~Descrlption Requests Notes Coverage Exam Exam Comments A-A Al 20 2ACO3AA-27 5/JO2A 2PCO3AA-27 5 I3A-02 B9.40 VT-2 VT-2 NAI SOL - Therm owell t3T-01 13T-02 OBS13-016 A-A P1.20 OBS13-017 2ACO3AA-27.5/J04 SOL - Thermowell 2ACO3AA-27.5 I3P-02 B9.40 13T-01 13T-02 VT-2 VT-2 NPI A-A P1.20 OBS13-026 2AC13AA-21W-01 SOL - Pipe 2AC13AA-2 13P-02 69.40 131-01 131-02 VT-2 VT-2 NAt A-A P1.20 OBS13-027 2AC13AA-2/W-02 Pipe - Tee 2PC13AA-2 t3A-02 69.40 131-01 131-02 VT-2 VT-2 NAI P-A P1.20 OBS13-028 2AC13AA-2/W-03 Tee - Reducer 2PC13AA-2 l3A-02 69.40 131-01 13T-02 VT-2 VT-2 NAI A-A P1.20 OBS13-029 2AC13AA-2/W-04 Tee - Pipe 2PC13AA-2 I3P-02 B9.40 I3T-0l 131-02 VT-2 VT-2 NAt P-A P1.20 OBS13-030 2PC13AA-21W-05 Pipe - Valve 2AC13AA-2 13R-02 69.40 131-01 13T-02 VT-2 VT-2 NAt A-A P1.20 OBS13-031 2AC13AB-2/W-01 SQL - Pipe 2AC13AB-2 t3A-02 69.40 l3T-01 13T-02 VT-2 VT-2 NAI A-A P1.20 OBS13-032 2AC13AC-2iW-0l SQL - Pipe 2AC13AC-2 13A-02 B9.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.20 OBS13-033 2AC13AD-2/W-0l SOL - Pipe 2PC13AD-2 I3A-02 69.40 13T-01 131-02 VT-2 VT-2 NPI A-A P1.11 OBS13-036 2AC14AA-2/W-01 SOL - Pipe 2AC14AA-2 13P-02 69.40 131-01 131-02 VT-2 VT-2 NAI 7
7/10/2007 Exekn..
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section XI Component ID Line Number Relief Technical Code Required Actual Results Description Requests Notes Coverage Exam Exam Comments A-A P1.11 2RC14AA-2/W-O1A 2RC14AA-2 13P-02 B9.40 VT-2 VT-2 NAI Pipe - Tee 131-01 131-02 OBS13-037 A-A A1.11 OBS13-038 2AC14AA-2iW-O1B Tee - Aeducer 2AC14AA-2 13A-02 B9.40 13T-01 l3T-02 VT-2 VT-2 NAt A-A P1.11 OBS13-039 2AC14AA-21W-O1C Tee - Pipe 2AC14AA-2 I3A-02 B9.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.11 OBS13-040 2AC14AA-2,W-02 Pipe - Elbow 2PC14AA-2 l3P-02 69.40 13T-Ol 131-02 VT-2 VT-2 NAt A-A A1.11 OBS13-041 2AC14AA-21W-03 Elbow - Pipe 2PC14AA-2 13A-02 69.40 131-0 1 131-02 VT-2 VT-2 NAt A-A P1.11 OBS13-042 2AC14AA-2iW-04 Pipe
- Elbow 2RC14AA-2 l3R-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt A-A P1.11 OBS13-043 2PC14AA-2/W-05 Elbow - Pipe 2AC14AA-2 13A-02 B9.40 131-0 1 131-02 VT-2 VT-2 NAI P-A P1.11 OBS13-044 2AC14AA-2/W-06 Pipe - Valve 2AC14AA-2 I3A-02 B9.40 131-01 13T-02 VT-2 VT-2 NPI A-A P1.11 OBS13-045 2AC14AA-2/W-07 Valve - Pipe 2PC14AA-2 13A-02 69.40 13T-01 131-02 VT-2 VT-2 NAI A-A P1.11 OBS13-046 2AC14AA-2,W-08 Pipe - Tee 2PC14AA-2 13A-02 B9.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.11 OBS13-047 2AC14AA-2,W-09 Tee - Aeducer 2AC14AA-2 13P-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt 8
7/10/2007 ExeI~n..
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section XI Component ID
~LIneNumber RelIef Technical Code Required Actual Results Cat.
Descrlption Requests Notes Coverage Exam Exam Comments A-A P111 2AC14AA-2iW-10 2AC14AA-2 13A-02 69.40 VT-2 VT-2 NRI Tee - Pipe 131-01 131-02 OBS13-048 A-A P1.11 OBS13-049 2AC14AA-2/W-11 Pipe - Valve 2AC14AA-2 13A-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt A-A P1.11 OBS13-053 2AC16AA-2iW-03 Valve - Pipe 2RC16AA-2 I3A-02 69.40 13T-01 131-02 VT-2 VT-2 NAt A-A Al.1l OBS13-054 2PC16AA-2/W-04 Pipe - Elbow 2AC16AA-2 13A-02 69.40 13T-0l 131-02 VT-2 VT-2 NRI P-A P1.11 OBS13-055 2PC16AA-2/W-05 Elbow - Pipe 2RC16AA-2 13A-02 B9.40 131-01 131-02 VT-2 VT-2 NRI P-A P1.11 OBS13-056 2AC16AA-2/W-06 Pipe - Elbow 2AC16AA-2 13P-02 B9.40 131-01 I3T-02 VT-2 VT-2 NAI A-A P1.11 OBS13-057 2AC16AA-2/W-07 Elbow - Pipe 2PC16AA-2 13P-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI R-A P1.11 OBS13-058 2AC16AB-2,W-04 Pipe - Elbow 2RC16AB-2 l3P-02 B9.40 13T-0l 13T-02 VT-2 VT-2 NAt A-A P1.11 OBS13-059 2PC16AB-2/W-05 Elbow - Pipe 2AC16AB-2 I3A-02 B9.40 13T-0l 13T-02 VT-2 VT-2 NPI P-A P1.20 OBS13-024 2PC16AC-2/W-08 Pipe
- SQL 2AC16AC-2 I3A-02 69.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.20 OBS13-025 2AC16AD-2/W-01 Valve - Pipe 2AC16AD-2 13A-02 69.40 131-01 131-02 VT-2 VT-2 NAt 9
7/10/2007
- ExeI~
n_
Byron Station Unit 2 B2R13 1St Outage Report Weld I Component Outage Summary SYSTEM:
Section XI ComponentID Line Number Relief Technical Code Required Actual
~Results
~
DescrIption Requests Notes Coverage Exam Exam Comments A-A Pill 2AC21AA-8/J07 2RC21AA-8 I3R-02 B9.1l 100 VOL-E UT NRI Pipe - Elbow 131-01 131-02 QBS13-138 A-A P1.11 QBS13-139 2PC21AA-8/J08 Elbow - Pipe 2AC21AA-8 I3A-02 B9.ll 13T-01 131-02 100 VOL-E UT NPI P-A P1.11 OBS13-140 2PC21AA-8/J09 Pipe - Elbow 2AC21AA-8 13A-02 B9.1l 131-01 131-02 100 VOL-E UT NAt P-A P1.11 OBS13-141 2AC21AA-8/J10 Elbow - Pipe 2RC21AA-8 l3A-02 B9.11 I3T-0l 131-02 100 VOL-E UT NAt A-A P1.20 OBS13-020 2AC22AA-1.5/W-0l SQL - Pipe 2AC22AA-1.5 13P-02 69.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.20 OBS13-021 2AC22AA-1.5/W-05 Elbow - Pipe 2AC22AA-1.5 t3A-02 B9.40 131-01 131-02 VT-2 VT-2 NPI A-A P1.20 OBS13-022 2PC22AC-1.5/W-01 SQL - Pipe 2AC22AC-1.5 13A-02 B9.40 131-01 131-02 VT-2 VT-2 NAt P-A R1.20 OBS13-023 2PC22AC-1.5/W-06 Pipe - Tee 2AC22AC-1.5 I3A-02 69.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.20 QBS13-018 2PC22AD-1.5/W-01 SQL - Pipe 2PC22AD-1.5 I3A-02 B9.40 I3T-01 131-02 VT-2 VT-2 NAI A-A P1.20 OBS13-019 2AC22AD-15/W-08 Pipe - Tee 2AC22AD-l.5 13R-02 B9.40 131-01 131-02 VT-2 VT-2 NPI P-A P1.20 QBS13-034 2AC26A-2/W-01 SQL - Pipe 2RC26A-2 l3R-02 B9.40 13T-01 131-02 VT-2 VT-2 NAI 10
7/1012007 Ex Byron Station UnIt 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section Xl__~omponentID Line Number Relief Technical Code Required Actual Results r~t.
Description
-~
Requests Notes coverage Exam Exam Comments P-A Al 20 2AC26A-2fW-02 2AC26A-2 l3A-02 89.40 VT-2 VT-2 NRI Pipe - Valve 131-01 131-02 QBS13-035 A-A P1.11 2AC3OAA-1.51W-01 2AC3OAA-1.5 Valve - Aeducer 13P-02 69.40 VT-2 VT-2 NPI 131-01 131-02 OBS13-079 11
7/10/2007 Exek! n_
Byron Station Unit 2 B2R13 ISI Outage Report Weld / Component Outage Summary SYSTEM:
Residual Heat Removal System (RH)
Section Xl Component ID Line Numb&
Reflef Technlcal Code
~qulred 1~tu&
Results
~~DescrlptIon Requests Notes Coverage Exam Exam Comments R-A R1.20 2RH12A-8/C17 2RH12A-8 13R-02 C5.11 100 VOL-E UT NRI Pipe - Elbow 31-01 31-02 OBS13-117 12
7/10/2007 ExeI~n..
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section Xl Component ID Line Number Relief
- Technical Code Required Actual Results Cat.
Description Requests Notes Coverage Exam Exam Comments B-N-3 813.70 2PC-01-R/CQPESUPP 2AC-0l-A VT-3 VT-3 NRI STAUCT Core Support Structure OBS13-082 B-N-2 B13.50 2AC-01-AIINT ATTACH 2AC-0l-A VT-i VT-3 NAt BELTLINE Interior Attachment Within-Beltline OBS13-080 B-N-2 B13.60 2AC-0l-A/INT ATTACH 2AC-01-A VT-3 VT-3 NAt NONBELT Interior Attachment Non-Beltline OBS13-081 B-N-i 813.10 2PC-01-R/APV 2AC-01-P VT-3 VT-3 NAt INTEPIOP APV Interior Surfaces OBS13-083 B-D 83.90 2AC-01-A/PPVN-A 2PC-01-A 94 VOL UT IND Nozzle - Shell OBS13-084
- 1) 1.50°,2) 2.00, 3)1.75°,2) 3.25°,1)1.00, and
- 1) 2.25 Mid-wall indications, acceptable per code. Aef: B2A13-AIA-01.
Scan obstructed by nozzle geometry.
B-D B3.100 2PC-01-AIAPVN-A-NIA 2PC-01-R N-648-1 EVT-1 EVT-1 NAt APV Nozzle Inner Radius OBS13-085 6-D B3.90 2AC-01 -P/PP VN-B 2AC-01-A 94 VOL UT IND Nozzle - Shell QBS13-086 5)1.50, 3) 2.00, 2) 2.25, 1) 2.50, 2) 3.00°,and 1) 5.25 Mid-waIl indications, acceptable per code. Aef: B2A13-AIP-02. Scan obstructed by nozzle geometry.
B-D B3.l00 2AC-Ol-R/APVN-B-NIA 2AC-01-A N-648-1 EVT-1 EVT-i NRI APV Nozzle Inner Padius OBS13-087 B-D 63.90 2AC-0l-A/APVN-C 2PC-01-P 94 VOL UT IND Nozzle - Shell QBS13-088 1)1.00, 1) 1.25, 6)1.50, 1) 1.75, 7)2.00°,4)2.50, 2)3.00, 1)3.25°,and 1)3.50 Mid-wall indications, acceptable percode. Pef:
B2P13-PIR-03. Scan obstructed by nozzle geometry.
B-D B3.100 2AC-0l-RIAPVN-C-NIA 2PC-01-A N-648-l EVT-1 EVT-1 NAt APV Nozzle Inner Padius OBS13-089 B-D B3.90 2AC-01-PiPPVN-D 2PC-01-A 94 VOL UT IND Nozzle - Shell QBS13-090 3)1.50°,1) 2.00, 2)2.25°,2) 2.75°,1) 3.25°,and
- 1) 4.00° Mid-wall indications, acceptable per code. Pef: B2A13-AIP-04. Scan obstructed by nozzle geometry.
13
7/10/2007
- Ecekn~
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
SectIon Xl Component ID Line Number Relief Technical Code Required Actual Results
~
Description Requests Notes Coverage Exam Exam Comments B-D B3 100 2RC-01-A/PPVN-D-NIR 2AC-01-R N-648-l EVT-l EVT-1 NAI PPV Nozzle Inner Padius QBS13-091 B-D B3.90 2AC-01-A/APVN-E 2AC-01-A 94 VOL UT IND Nozzle - Shell OBS13-092 1)1.50°,2)1.75, 1)2.50°,and 1) 4.00°Mid-wall indications, acceptable per code. Aef: B2R13-RIP-05. Scan obstructed by nozzle geometry.
B-D B3.100 2PC-01-P/APVN-E-NIP 2AC-01-A N-648-1 EVT-1 EVT-1 NRI APV Nozzle Inner Padius QBS13-093 B-D B3.90 2PC-01-AIAPVN-F 2PC-01-A 94 VOL UT IND Nozzle - Shell OBS13-094 1)1.25, 1)1.50, 1)1.75°,3)2.00, 2) 2.50°,and 3)3.00 Mid-waIl indications, acceptable per code. Aef: B2P13-AIP-06. Scan obstructed by nozzle geometry.
B-D B3.100 2AC-01-P/PPVN-F-NIR 2AC-01-A N-648-1 EVT-l EVT-1 NAP RPV Nozzle Inner Aadius OBS13-095 B-D B3.90 2PC-0l-AJAPVN-G 2AC-01-A 94 VOL UT IND Nozzle - Shell OBS13-096 1)1.25, 5)1.50, 2)1.75, 2) 2.25°,2) 2.50, and 1) 4.00°Mid-wall indications, acceptable per code. Aef: B2A13-AIA-07. Scan obstructed by nozzle geometry.
B-D 63.100 2AC-0l-A/RPVN-G-NIR 2AC-01-A N-648-l EVT-1 EVT-l NAJ PPV Nozzle Inner Aadius QBS13-097 B-D B3.90 2PC-0l-A/APVN-H 2PC-01-P 94 VOL UT IND Nozzle - Shell OBS13-098 2)1.50, 4) 2.00, 1) 2.50°,2)2.75°,1) 3.00, 2) 4.00, and 1) 5.00°Mid-wall indications, acceptable per code.
Pef: B2A13-AIA-08. Scan obstructed by nozzle geometry.
B-D 63.100 2AC-01-PJAPVN-H-NIP 2PC-01-A N-648-1 EVT-1 EVT-1 NAt APV Nozzle Inner Padius OBS13-099 B-A B1.30 2PC-0l-R/WA-07 2PC-01-P 99 VOL UT Al Shell
- Flange OBS 13-1 12
- 1) 0.50 and 1) 0.60°Mid-waIl indications, acceptable per code. Pef: B2A13-AIA-l0.
B-A B1.21 2AC-O1-R,WA-16 2PC-0l-P 100 VOL UT NPI Lower Head Meridian Weld OBS13-108 Scan obstructed by bottom mounted instrumentation nozzles. Coverage per PDI single-sided access qualifications.
14
7/10/2007 eI4~,n Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section XI ~OrnpOneflI ID
~Line Number Relief Technical Code Required ~ActuaI Results cat.
DescriptIon Requests Notes Coverage Exam Exam Comments B-A 61.11 2AC-01-R/WA-l8 2RC-01-A Shell - Shell OBS13-109 1)0.60°and 1)1.10 Mid-wall indications, acceptable per code. Aef: B2P13-PIA-09.
B-A B1.11 2AC-0l-R/WA-29 2AC-01-P 13A-15 Shell
- Shell OBS13-110 Scan obstructed by core support lugs.
B-A 81.11 2AC-0l-AWP-34 Shell - Shell 100 VOL UT IND 79 VOL UT NAI 2AC-01-A 100 VOL UT NRI OBS13-111 15
7/10/2007 ExeI~n..
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Xl Component ID Line Number Relief Technical Code
~Iequhed~Actu~
Resu Cat.
Description Requests Notes Coverage Exam Exam Comments R-A Al 20 2RYO1B-6/J08 2AYO1B-6 13A-02 B9.1l 100 VQL-E UT NAt Elbow - Pipe 131-0 1 131-02 QBS13-148 A-A P1.11 QBS13-146 2PV11A-14/J08 Pipe - Pipe 2AV11A-14 13A-02 B9.11 100 VQL-E 131-01 131-02 UT NAt A-A P1.11 OBS13-001 2AY18A-2/W-01 Valve - Pipe 2AY18A-2 I3A-02 69.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.11 OBS13-002 2AY18A-2/W-02 Pipe - Elbow 2AY18A-2 13A-02 B9.40 131-01 31-02 VT-2 VT-2 NAI A-A P1.11 QBS13-003 2AY18A-2/W-03 Elbow - Pipe 2AY18A-2 13A-02 B9.40 131-0 1 131-02 VT-2 VT-2 NAt A-A A1.1l OBS13-004 2AY18A-2,W-04 Pipe
- WOL 2AY18A-2 13A-02 B9.40 131-01 l3T-02 VT-2 VT-2 NRI 16
7/10/2007
- ExeI~n..
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Section Xl Component ID Line Number Relief TechnIcal Code Required 1Actual Results
~Cat.
Descrlptlon
Requests Notes Coverage Exam Exam Comments C-B C2.21 2AC-01-BAJSGN-02 2RC-01-BA 100 SUAF MT NAI Feedwater Nozzle 100 VOL UT NPI OBS13-149 Aef: IA 00614558 C-B C2.22 2AC-01-BA/SGN-02-NIA 2AC-01-BA VOL UT NAI Feedwater Nozzle NIP OBS13-150 17
7/10/2007 Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Safety Injection System (SI)
Section Xl Component ID Line Number Relief Technical Code Required Actual Results
~~~~Descrlptlon Requests Notes Coverage Exam Exam Comments A-A P1.20 2SIO5AB-8/C01 2SIO5AB-8 l3A-02 C5.ll 100 VQL-E UT NRI Tee - Elbow 131-01 131-02 OBS13-121 P-A P1.11 OBS13-060 2SIO8HA-2/W-01 Aeducer - Coupling 2SIO8HA-2 t3P-02 B9.40 13T-0l 131-02 VT-2 VT-2 NPI P-A P1.11 OBS13-061 2SIO8HA-2/W-02 Coupling - Pipe 2SIO8HA-2 t3A-02 B9.40 13T-0l 131-02 VT-2 VT-2 NAI A-A P1.11 OBS13-062 2SIO8HA-2/W-03 Pipe
- Flange 2SIO8HA-2 t3P-02 69.40 l3T-01 131-02 VT-2 VT-2 NAI A-A P1.11 CBS13-063 2SIO8HA-2/W-04 Flange - Pipe 2SIO8HA-2 l3A-02 B9.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.11 OBS13-064 2SIO8HA-2/W-05 Pipe - Coupling 2SIO8HA-2 13A-02 B9.40 131-01 131-02 VT-2 VT-2 NRI P-A P1.11 OBS13-065 2SIO8HA-2/W-06 Coupling - Peducer 2SIO8HA-2 13P-02 69.40 131-0 1 131-02 VT-2 VT-2 NAt P-A P1.11 OBS13-066 2SIO8JA-1.5/W-01 Peducer - Pipe 2SIO8JA-1.5 I3A-02 69.40 131-0 1 131-02 VT-2 VT-2 NAI P-A P1.11 QBS13-067 2SIO8JA-1.5/W-02 Pipe - Elbow 2SIO8JA-1.5 l3A-02 69.40 131-01 131-02 VT-2 VT-2 NAI A-A P1.11 OBS13-068 2SIOSJA-1.5/W-03 Elbow - Pipe 2SIO8JA-1.5 I3P-02 B9.40 I3T01 131-02 VT-2 VT-2 NAI P-A Rl.11 OBS13-069 2SIO8JA-1.51W-04 Pipe - Elbow 2SIO8JA-1.5 I3A-02 69.40 131-01 I3T-02 VT-2 VT-2 NAI 18
7/10/2007 ExeI~n_
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Safety Injection System (SI)
Section_Xl__Component ID Line Number Relief Technical Code Required Actual Results DescriptIon Requests Notes Coverage Exam Exam
~mmentS P-A Pill 2SIO8JA-1 5/W-05 2SIO8JA-1.5 13A-02 B9.40 VT-2 VT-2 NAt Elbow - Pipe 131-01 13T-02 OBS13-070 A-A P1.11 OBS13-071 2SIO8JA-1.5,W-05A Pipe - Valve 2SIO8JA-1.5 I3A-02 69.40 131-01 131-02 VT-2 VT-2 NAt P-A P1.11 OBS13-072 2SIO8JA-1.5iW-05B Valve - Pipe 2SIO8JA-1.5 l3A-02 69.40 131-01 131-02 VT-2 VT-2 NPI P-A P1.11 OBS13-073 2SIO8JA-1.5iW-06 Pipe - Elbow 2SI08,JA-1.5 i3A-02 B9.40 131-01 13T-02 VT-2 VT-2 NPI P-A P1.11 CBS13-074 2SIO8JA-1,51W-07 Elbow - Pipe 2SIO8JA-1.5 13P-02 69.40 l3T-01 I3T-02 VT-2 VT-2 NAI A-A P1.11 CBS13-075 2SIO8JA-1.5/W-10 Pipe - Flange 2SIO8JA-1.5 l3P-02 B9.40 13T-01 131-02 VT-2 VT-2 NAt A-A P1.11 CBS13-076 2S108JA-1.5/W-l1 Flange - Pipe 2SIO8JA-1.5 13A-02 69.40 13T-01 131-02 VT-2 VT-2 NPI A-A P1.11 CBS13-077 2S1O8JA-1.5/W-14 Pipe - Coupling 2SIO8JA-1.5 l3A-02 69.40 131-01 l3T-02 Vr-2 VT-2 NPI A-A P1.11 CBS13-078 2SIO8JA-1.5/W-15 Coupling - Pipe 2SIO8JA-1.5 l3A-02 B9.40 131-01 131-02 VT-2 VT-2 NAI P-A P1.20 OBS13-122 2S134A-8/C01 Tee - Pipe 2St34A-8 l3A-02 C5.ll 131-01 131-02 100 VOL-E UT NAI P-A P1.20 CBS13-123 2S134A-8/C23 Pipe - Elbow 2S134A-8 l3A-02 C5.1l 131-01 131-02 100 VOL-E UT NPi 19
7/10/2007 ExeI~n_
Byron Station UnIt 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Safety Injection System (SI)
Section Xl Component ID Line Number Relief Technical Code Required Actual Results cat.
Description
-~____________
Requests Notes Coverage Exam Exam Comments A-A P1.20 2S134A-8/C24 2S134A-8 13P-02 C5 11 100 VOL-E UT NPI Elbow - Pipe l3T-01 I3T-02 CBS13-124 A-A P1.20 CBS13-115 2S182AA-12/C04 Pipe - Elbow 2SI82AA-12 13P-02 C5.l1 13T-01 131-02 100 VOL-E UT NAI P-A P1.20 OBS13-116 2S182AA-12/C05 Elbow - Pipe 2Sl82AA-12 13P-02 C5.1l 13T-01 131-02 100 VCL-E UT NAt 20
7/10/2007 e
Byron Station Unit 2 B2R13 ISI Outage Report Weld I Component Outage Summary SYSTEM:
Essential Service Water System (SX)
SectionXI~omponentID Line Number Relief
~
-- - i
~ctu~j~
- i~uits cat.
Description Requests Notes Coverage Exam Exam Comments C-C C3.20 2SXO7FA-16/C1OA 2SXO7FA-16 NA 98 SURF MT NAI Closure Plate 2PC-14 CBS13-126 Penetration side obstructed by welded ID plate.
21
7/10/2007 Exek,n~
Byron Station Unit 2 B2R13 ISI Outage Report Bolts, Pumps, and Valves Outage Summary SYSTEM:
Reactor Pressure Vessel (RPV) je~ionxi n~ji~~
Theii~i~JT~inical Actuat 1Results
~
j~~DescrIptlon Requests Notes Exam Comments B-G-1 66.10 2PC-0i-R/N01-N18 VT-l NPI PPV Closure Head Nuts VT-i NPI CBS13-155 B-G-1 B6.10 CBS13-155 2AC-0i-P/N19-N36 APV Closure Head Nuts VT-i VT-i NAI NPI B-G-1 B6.10 CBS13-155 2RC-01-P/N37-N54 PPV Closure Head Nuts VT-i VT-i NPI NAP B-G-1 66.20 CBS13-157 2RC-01-R/S01-S18 PPV Closure Head Studs UT NPI B-G-1 66.20 OBS13-157 2AC-01-R/S19-S36 PPV Cksure Head Studs UT NAt B-G-1 B6.20 CBS13-157 2AC-Oi-R/S37-S54 APV Closure Head Studs UT NPI 1
7/1012007
- Exek~n_
Byron Station UnIt 2 B2R13 ISI Outage Report Bolts, Pumps, and Valves Outage Summary SYSTEM:
SectionXlCornponentlo
llTe1A Cat.
It~
DescrIption Requests Notes Exam Comments B-G-2 B7.50 2PYO3BA-6/FLG 1-12 VT-i NAI Piping Flange Bolting VT-i NRI CBS13-164 2007-298:_Nuts, tool marks noted. 2007-300: Studs.
B-M-2 Bi2.50 2AY8O1OA/PNT SUPF VT-3 NAP Valve Body interior CBS13-167 Disassembled under WO 00886405.
2
7/10/2007 Exek)n Byron Station Unit 2 B2R13 ISI Outage Report Bolts, Pumps, and Valves Outage Summary SYSTEM:
Section Xl Component ID Relief
~fechnIcal Actual Results L Cat.
it~r~Description Requests Notes Exam Lcomments B-G-2 6730 2AC-01-BC/BLT 1-32 VT-i NAP SG Manway Studs and Nuts CBS13-151 B-G-2 B7.30 2AC-01-BD/BLT 1-32 VT-i NAP SG Manway Studs and Nuts CBS13-152 3
711012007
~
Byron Station Unit 2 B2R13 ISI Outage Report Bolts, Pumps, and Valves Outage Summary SYSTEM:
Safety Injection System (SI)
Section XI Component ID Relief Technical Actual Results
- cat.
Item Description Requests Notes Exam Comments B-G-2 B7.50 2SPO8JA-1.5/FLG 1-4 VT-i NAt Piping Flange Bolting CBS13-165 Disassembled under WC00971151. Mechanical Joint MJ-82C.
B-G-2 B7.50 2SIO8JB-1.5/FLG 1-4 VT-i NPI Piping Flange Bolting CBS13-166 Disassembled under WC00971152. Mechanical Joint MJ-78.
B-G-2 B7.70 2S18818C/BLT 1-16 VT-i NAI Valve Studs, Nuts, Bushings, and Washers CBS13-162 Disassembled under WO 00927431.
B-M-2 B12.50 2S18818C/INTSUPF VT-3 NAI Valve Body Interior CBS13-163 Disassembled under WC00927431.
4
7/10/2007 Exekn~
Byron Station UnIt 2 B2R13 ISI Outage Report Weld I Component Outage Summary (Preservice Inspections)
SYSTEM:
Section Xl Component ID Line Number Relief Technical Code Required Actual Results~
Cat.
Item Description Requests Notes Coverage Exam Exam Comments NJA N/A 2AYO1C-4/JO1S 2AYO1C-4 l3R-08 VOL UT NAI Aeducer - Spray Nozzle Overlay Baseline exam for full structural weld overlay. 100% coverage in circ. direction and 100% in axial direction.
N/A N/A 2AY-01-S/PN-0i-F1S 2AY-0l-S 13R-08 VCL UT NPI Surge Nozzle-Safe End Overlay Baseline exam for full structural weld overlay. 100% coverage in circ. direction and 100% in axial direction.
N/A N/A 2AY-01-S/PN-02-F2S 2AY-01-S l3P-08 VOL UT NAt Spray Nozzle-Safe End Overlay Baseline exam for full structural weld overlay. 100% coverage in circ. direction and 100% In axial direction.
N/A N/A 2AV-01-S/PN-03-F3S 2AY-0i-S 13A-08 VOL UT NPI PCRV Nozzle-Safe End Overlay Baseline exam for full structural weld overlay. 100% coverage in circ. direction and 100% in axial direction.
N/A N/A 2PY-Ol-S/PN-04-F4S 2PY-Oi-S 13A-08 VOL UT IND Safety A Nozzle-Safe End Overlay Baseline exam for full structural weld overlay. 2 laminar indications, accept. Aejectable assumed planar flaws under laminars. Accepted by IWB-3600 evaluation. 99.5% coverage in circ. direction and 99.2% in axial direction.
N/A N/A 2RY-Oi-S/PN-05-F5S 2PY-01-S 13P-08 VOL UT IND Safety B Nozzle-Safe End Overlay Baseline exam for full structural weld overlay.
1 laminar indication, accept. Aejectable assumed planar flaw under laminar. Accepted by IWB-3600 evaluation. 98.3% coverage In circ. direction and 98.4% in axial direction.
N/A N/A 2AY-Oi-S/PN-06-F6S 2PY-01-S 13P-08 VOL UT IND Safety C Nozzle-Safe End Overlay Baseline exam for full structural weld overlay. 4 laminar indications, accept. 3 with rejectable assumed planar flaws under laminars.
Accepted by IWB-3600 evaluation. 94.3% coverage in circ. direction and 93.5% in axial direction.
N/A N/A 2PYO2A-6/JO1S 2RYO2A-6 l3A-08 VOL UT IND POAV Nozzle - Elbow Overlay Baseline exam for full structural weld overlay. 1 laminar indication, accept.
Pejectable assumed planar flaw under laminar. Accepted by IWB-3600 evaluation. 97.7% coverage in circ. direction and 98.0% in axial direction.
N/A N/A 2AYO3AA-6/J01 S 2AYO3AA-6 i3A-08 VOL UT NPI Safety A Nozzle-Safe End - Elbow Overlay Baseline exam for full structural weld overlay. 100% coverage in circ. direction and 100% in axial direction.
N/A N/A 2PYO3AB-6/JO1S 2AYO3AB-6 13A-08 VOL UT NRI Safety B Nozzle-Safe End - Elbow Overlay Baseline exam for full structural weld overlay. 100% coverage in circ. direction and 100% in axial direction.
N/A N/A 2AYO3AC-6/JO1S 2PYO3AC-6 I3P-08 VOL UT IND Safety C Nozzle-Safe End - Elbow Overlay Baseline exam for full structural weld overlay.
1 laminar indication, accept. Assumed planar flaw under laminar acceptable. 98.7%
coverage in circ. direction and 98.5% in axial direction.
N/A N/A 2PY11A-14/JO1S 2AY11A-14 l3A-08 VOL UT NPI Surge Nozzle Safe End - Pipe Overlay Baseline exam of full structural weld overlay. 100% coverage in circ. direction and 100% in axial direction.
1 7/10/2007
7/1012007 Exek n_
Byron Station Unit 2 B2R13 ISI Outage Report Detailed Inservice Inspection Bolts, Pumps, and Valves Listing (PSI)
SYSTEM: Reactor Coolant System (RY)
SeCtIOn XI 1~ompo~
__T~ii;~__
~
Cat item
~DescrIPtIon jflequests Notes Exam Comments B-G-2 B7.50 2RYO3BA-6/FLG 1-12 VT-i NRI Piping Flange Bolting Baseline exam for 2RY801 OA replacement.
Page 1-1 7/10/2007
7/1012007 Exel~,n_
Byron Station Unit 2 B2R13 ISP Outage Report Pressure Test Outage Summary SYSTEM:
Auxiliary Feedwater System (AF)
SectIon Xi Component ID Relief TechnIcal RequIred Results Requests Notes Exam Comments C-H C7.10 2-AF-2-1 13T-04 VT-2 NRI C-H C7.10 2-AF-2-2 131-04 VT-2 NAt 1
7/10/2007
7/1012007 ExeIc~n~
Byron Station Unit 2 B2R13 PSI Outage Report Pressure Test Outage Summary SYSTEM:
Containment Spray System (CS)
Section XI Component ID Relief Technical Required Results Cat.
Item Requests Notes Exam Comments C-H C7.iO 2-CS-2-1 131-04 VT-2 NAP C-H C7.10 2-CS-2-2 13T-04 VT-2 NAP 2
7/10/2007
711012007 ExeI ~,n_
Byron Station Unit 2 B2R13 PSI Outage Report Pressure Test Outage Summary SYSTEM:
Chemical & Volume Control System (CV)
Section Xl Component ID Relief Technical Required Results Cat.
Item eta Notes Exam Comments C-ti C7.10 2-CV-2-1 13T-04 VT-2 NAP C-H C7.10 2-CV-2-10 13T-04 VT NAP C-H C7.10 2-CV-2-2 P3T-04 VT-2 NPI C-H C7.10 2-CV-2-3 P3T-04 VT-2 NAt C-H C7.10 2-CV-2-4 Boric Acid present on 2CV8355A, B, C, D and 2CV061 l3T-04 VT-2 NAI C-N C7.10 2-CV-2-5 Boric Acid identified in IRs 606399 and 606391 131-04 VT-2 NAI C-H C7.10 2-CV-2-6 I3T-04 VT-2 NAt c-H C7.10 2-CV-2-7 l3T-04 VT-2 NAI 3
7/10/2007
7/1012007 Exekin.
Byron Station UnIt 2 B2R13 ISI Outage Report Pressure Test Outage Summary SYSTEM:
Fuel Pool Cooling System (AF)
Section XI fComponent ID Relief
~TechnicaI Required Results Cat. i~T Requests Notes Exam Comments C-H C7 10 2-FC-2-1 13T-04 VT-2 NPI 4
7/10/2007
7/10/2007 ExeI~
n_
Byron Station Unit 2 B2R13 151 Outage Report Pressure Test Outage Summary SYSTEM:
Section Xl Component ID Relief Technical Required Results I
Cat.
~
Requests Notes Exam Comments C-H C7.10 2-FW-2-2 l3T-04 VT-2 5
7/10/2007
7/1012007 Exek,n_
Byron Station Unit 2 B2R13 PSI Outage Report Pressure Test Outage Summary SYSTEM:
Main Steam System (MS)
Section Xl ComponentID Relief Technical Required Results Cat.
item~~~
Requests Notes Exam Comments C-H C7.iO 2-MS-2-1 t3T-04 VT-2 NAI C-H C7.10 2-MS-2-2 131-04 VT-2 NAt 6
7/10/2007
7/10/2007 ExeIcbn..
Byron Station Unit 2 B2R13 PSI Outage Report Pressure Test Outage Summary SYSTEM: Off Gas System (OG)
SectIon Xl cornponent~
~Rel~
~T~hnicai Requ~r~ ResuI~
eat. It~1 Requests Notes Exam I
Comments C-H C7.10 2-CG-2-1 131-04 VT-2 NAP 7
7/10/2007
7/10/2007 ExeI~n Byron Station Unit 2 B2R13 ISP Outage Report Pressure Test Outage Summary SYSTEM:
Process Sampling System (PS)
Section XI Component ID Relief Jf~nic&
Requfred Results
~at.
~
Reques~ Notes Exam Comments C-H C7 10 2-PS-2-3 13T-04 VT-2 NAI C-H C7.10 2-PS.2-4 i3T-04 VT-2 NAP C-H C7.10 2-PS-2-5 13T-04 VT-2 NAI C-H C7.10 2-PS-2-6 13T-04 VT-2 NAt 8
7/10/2007
Pressure Test Outage Summary Exelon..
Byron Station Unit 2 B2R13 ISI Outage Report SYSTEM:
Essential Service Water System (SX)
C-HC7.10 2-SX-2-i 13T-04 VT-2 NRI C-H C7.10 2-SX-2-2 13T-04 VT-2 NRI 7/1012007 12 7/10/2007
7/1 012007 Exek,n Byron Station Unit 2 B2R13 ISI Outage Report Component Support Outage Summary SYSTEM:
Chemical & Volume Control System (CV)
Section XI Component ID Line Number Relief Technical Actual Results eat.
Item
- Description Requests Notes Exam Comments F-A F1.20 2CVO5B-8/2CV47010X SEISMIC All welds painted 2CVO5B-8 VT-3 NAP F-A Fl.20 2CVO5CB-6/2CV0801 6X SEISMIC All welds painted 2CVO5CB-6 VT-3 NAP F-A F1.20 2CVA1A-6/2CV-CP1A ANCHOR Weld Is painted. Penetration 2AB-i30.
2CVA1A-6 VT-3 NAP F-A F1.10 2CVA5AA-2/2CV15030X SEISMIC 2CVA5AA-2 VT-3 NAt F-A Fl.10 2CVA5AA-2/2CV1 5031 X SEISMIC 2CVA5AA-2 VT-3 NAI F-A Fib 2CVA5AA-2/2CV15043X SEISMIC 2CVA5AA-2 VT-3 NRI F-A Fi.10 2CVB7A-3/2CV06007V VAAIABLE AS-FOUND COLD SETTING = 479 ~
East/4 2CVB7A-3 62 lbs. West VT-3 NAt 3
7/10/2007 Exek~n_
Byron Station Unit 2 B2R13 ISP Outage Report Component Support Outage Summary SYSTEM:
SecflonXl component ID
~LineNumb~
- Reilef Technical
- Actual~~
Results I
1~!J~°t95Exam Comments F-A Fl.20 2FWO3DA-16/2FW02008X 2FWO3DA-16 SEISMIC 4
7/10/2007 ExeI4~)n Byron Station Unit 2 B2R13 ISP Outage Report Component Support Outage Summary SYSTEM:
Main Steam System (MS)
Section XI
~ComponentID Line Number Relief
~TechnicaI Actual Results Cat Item__~escnptIon
-_J Requests Notes Exam j
Comments F-A Fl 20 2MSO1AC-32-3/4/2MS07002C 2MSO1AC-32-3/4 VT-3 CONSTANT 5
7/loi2oo7 EXek3 Byron Station Unit 2 B2R13 ISP Outage Report Component Support Outage Summary SYSTEM:
Section XI Component ID Line Number Relief Technical Actual Results Cat.
Item Description Requests Notes Exam Comments F-A F1.40 2AC-01-BAJS SG A SUPPORT Minor corrosion, no degradation.
2AC-01-BA VT-3 NAt F-A F1.40 2RC-01-PA/L1 RCPUMPASUPPOAT 2AC-01-PA VT-3 NAI F-A Fl.40 2AC-01-PA/L2 AC PUMP A SUPPORT 2AC-01-PA VT-3 NAI F-A F1.40 2RC-01-PAIL3 AC PUMP A SUPPORT 2AC-01-PA VT-3 Nfl 6
7/10/2007 Exek!~n.
Byron Station Unit 2 B2R13 1St Outage Report Component Support Outage Summary SYSTEM:
Residual Heat Removal System (RH)
Section XI
~ComponentID
~LIneNumb~
ReU~-
- T~hrilcaI~tu&
Res~s -
~
ests Notes Exam Comments F-A F1.20 2RHO3AA-8/2RH-CP1A 2RHO3AA-8 VT-3 NRI ANCHOR 7
7/10/2007 ExeI~in_
Byron Station Unit 2 B2R13 PSI Outage Report Component Support Outage Summary SYSTEM:
SectIon XI Component ID Line Number Relief Technical Actual Results Cat.
Item DescriptIon Requests Notes Exam Comments F-A Fl.10 2RYO1B-6/2AY06027X SEISMIC Only 90% of the support is accessible (back side of pressurizer)
F-A Fib 2AYO1B-6/2RYO61O1C 2AYO1B-6 CONSTANT Fl.10 2AYO2B-3/2AY09077S SNUBBER F-A VT-3 NAP VT-3 NAI 2AYO2B-3 VT-3 SR F-A Fl.l0 2AYO2B-3/2AYO9100S 2AVO2B-3 VT-3 SNUBBER SR 8
7/1012007 Exeic~n Byron Station Unit 2 B2R13 PSI Outage Report Component Support Outage Summary SYSTEM:
Safety Injection System (SI)
Section Xl Component PD Line Number Relief Technical Actual Results Cat Item Description Requests Notes Exam Comments F-A Fl.20 2SIO2BA-6/2S118A050X 2SIO2BA-6 SEISMIC All welds painted. 10 - Minor rust on bolting (no degradation)
F-A Fl.20 2SIO2BA-6/2SI 1 8A051X 2SIO2BA-6 SEISMIC All welds painted.
F-A Fl.20 2SIO2BA-6/2S1 18A052X SEISMIC All welds painted F-A ANCHOR F-A SNUBBER Trapeze Snubber, both cold settings 3-3/4~
F-A SEISMIC F-A SEISMIC F-A SEISMIC F-A SEISMIC F-A SNUBBER F-A SNUBBER VT-3 NRI VT-3 NAP 2SPO2BA-6 VT-3 2S104B-l2 VT-3 NAI 2SIO5DC-6 DBL SR VT-3 NRI 2SIO8JA-l -1/2 2SIO8JA-1-1/2 2Sl08,JA-l -1/2 2SIO8JA-1-l/2 2SIO8JC-l-1/2 2SIO8JC-l -1/2 vr-3 vr-3 vr-3 VT-3 VT-3 VT-3 NRI NAI NRI NRI NAt NAP SR SR 9
7/10/2007 ExeIt~~n..
Byron Station Unit 2 B2R13 PSI Outage Report Component Support Outage Summary SYSTEM:
Essential Service Water System (SX)
Section Xl Component ID Line Number Relief Technical Actual Results Cat.
item Description Requests Notes Exam Comments F-A F1.20 2SXO6FA-10/2SX06029A ANCHOR 2SXO6FA-b0 VT-3 NAI F-A Fl.20 2SXO9BA-lO/2SX08027X SEISMIC 2SXO9BA-l0 VT-3 NR1 F-A Fl.20 2SXO9BB-10/2SX09072X SEISMIC 2SXO9BB-lO VT-3 NRI 10
7/10/2007
- E~k~n_
Byron Station Unit 2 Byron Station Outage B2R13 Snubber Outage Summary (Page 1 of 11)
SYSTEM:
Auxiliary Feedwater System (AF)
SectIon Xl ComponentID
______Line Number Relief Technical Actual Results Descript I
-~
Requests Notes j~am Comments F-A Fl.20 2FW87BA-3/2FW14002S 2FW87BA-3 VT-3 NAt SNUBBER SR FT PASS F-A F1.20 2FW87BB-3/2FW12001S 2FW87BB-3 VT-3 NA1 SNUBBER SR Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 1
7/10/2007 xelfl_
Byron Station Unit 2 Byron Station Outage B2R13 Snubber Outage Summary (Page 2 of 11)
SYSTEM:
Containment Spray System (CS)
Section Xl Component ID tine Number Relief Technical Actual Results ftoescnption_- __iI 11L_
RequestsNoteeExam~
Comments F-A Fl.20 2CSO2AA-b0/2CSO3AO12S 2CSO2AA-bO VT-3 SNUBBER SR Note: Section Xl Category numbers N/A-ed are exempt from IWF-1 220 and IWF-2500 tables 2
7/1012007 ExeI~n Byron Station Unit 2 Byron Station Outage B2R13 Snubber Outage Summary (Page 3 of 11)
SYSTEM:
Chemical & Volume Control System (CV)
Section Xl Component ID Line Number Relief TechnIcal Actual Results C
Item Descnplion~
Requests Notes
~m Comments F-A Fl.20 2CVO5CB-6/2CV0801 iS 2CVO5CB-6 VT-3 NAI SNUBBER SR FT PASS F-A F1.20 2CVO5CB-6/2CV08013S 2CVO5CB-6 VT-3 SNUBBER SR NA NA 2CV1OCA-3/2CV03009S 2CV1OCA-3 VT-3 NAP SNUBBER SR FT PASS NA NA 2CV14EB-2/2CV36006S 2CV14EB-2 VT-3 NAP SNUBBER SR FT PASS NA NA 2CV14EC-2/2CV40009S 2CV14EC-2 SNUBBER SR FT PASS NA NA 2CV15E-3/4/2CV31020S 2CV15E-3/4 VT-3 NAP SNUBBER SR FT PASS NA NA 2CV16BD-3/412CV64025S 2CV16BD-3/4 VT-3 SNUBBER SR FT PASS NA NA 2CV43BC-2/2CV1 3034S 2CV43BC-2 VT-3 SNUBBER SR FT NRP F-A Fl.10 2CVA7AA-2/2CV25012S 2CVA7AA-2 VT-3 NAP SNUBBER SR FT PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 3
7/10/2007 Snubber Outage Summary (Page 4 of 11)
Exekm..
Byron Station UnIt 2 Byron Station Outage B2R13 SYSTEM:
Section XI Component ID TUne Number TReIPef ITechnical ual
- ~esufts -
cat Item Description 1
-~
j~~equestsNotes Exam Comments F-A F1.20 2FWO3DA-16/2FW02012S SNUBBER F-A Fl.20 2FWO3DD-1 612FW05022S SNUBBER F-A Fl.20 2FW87CA-6/2FW06002S SNUBBER F-A Fl.20 2FWB7CA-6/2FW06005S SNUBBER F-A Fl.20 2FW87CA-612FW06008S SNUBBER Failed 2FW06002S Expansion Sample F-A F1.20 SNUBBER Failed 2FW06002S Expansion Sample Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 4
2FWO3DA-16 SA VT-3 FT NRI PASS 2FWO3DD-16 SR VT-3 FT NAt PASS 2FW87CA-6 SR VT-3 FT NAP FAIL 2FW87CA-6 SR VT-3 FT NAP PASS 2FW87CA-6 SR VT-3 FT NAt PASS 2FW87CC-6 VT-3 NR1 SR FT PASS
7/10/2007 ExeI~n_
Byron Station Unit 2 Byron Station Outage B2R13 Snubber Outage Summary (Page 5 of 11)
SYSTEM:
Main Steam System (MS)
Sect XI Component ID i.ine Number R&Ie~
~TechniceI Actual Results Cat.
Item Description I
Requests Notes Exam Comments F-A SNUB 2MSO1AD-30 25/2MS08007-S1 2MSO1AD-30.25 DBL VT-3 NAP SNUBBER SR FT PASS F-A SNUB 2MSO1AD-30.25/2MS08007-S2 2MSO1AD-30.25 DBL VT-3 NAP SNUBBER SR FT PASS F-A SNUB 2MSO7AA-28/2MSO1 074-Si 2MSO7AA-28 DBL VT-3 NAt SNUBBER SR FT PASS Failed 2FW06002S Expansion Sample F-A SNUB 2MSO7AA-28/2MS01074-S2 2MSO7AA-28 DBL VT-3 NAP SNUBBER SR FT PASS Failed 2FW06002S Expansion Sample F-A Fl.20 2MSO7AA-28/2MSO1 079S 2MSO7AA-28 VT-3 NAP SNUBBER SR FT PASS F-A SNUB 2MSO7AD-28/2MS01083-Sl 2MSO7AD-28 DBL VT-3 NAt SNUBBER SR FT PASS F-A SNUB 2MSO7AD-28/2MS01083-S2 2MSO7AD-28 DBL VT-3 NRI SNUBBER SR FT PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-l220 and IWF-2500 tables 5
7/10/2007 Exel ~n_
Byron Station Unit 2 Byron Station Outage B2R13 Snubber Outage Summary (Page 6 of 11)
SYSTEM:
Reactor Coolant System (RQ.l Section XI ComponentID Line Number Relief TechnIcal Actual Results cati~e~
~
~
~
Notes Exam
Comments F-A Fl.40 2ACO1BA-2A/2ACO1BA-A 2RCO1BA-2A SNUBBER SR F-A Fl.40 2RCO1BA-2A/2RCO1BA-B 2RCO1BA-2A VT-3 NAP SNUBBER SR F-A F1.40 2RCO1BB-2B/2RCO1BB-A 2RCO1BB-2B VT-3 NAP SNUBBER SR Evidence of leakage on reservoir tubing atthreaded connection. PR# 611687 written to address situation.
F-A Fl.40 2ACO1BB-2B/2ACO1BB-B 2RCO1BB-2B VT-3 SNUBBER SR F-A Fl.40 2RCO1BC-2C/2RCO1BC-A 2RCO1BC-2C VT-3 NAP SNUBBER SR FT PASS F-A Fl.40 2RCO1 BC-2C/2ACO1 BC-B 2RCO1 BC-2C VT-3 NAt SNUBBER SR Evidence of leakage on reservoir tubing at threaded connection. IA# 611689 written to address situation.
F-A Fl.40 2ACO1BD-2C/2RCO1BD-A 2RCO1BD-2C VT-3 SNUBBER SR F-A Fl.40 2RCO1 BD-2C/2RCO1 BD-B 2RCO1 BD-2C VT-3 NAP SNUBBER SR NA NA 2RCO8AC-3/4/2RC18003S 2RCO8AC-3/4 SNUBBER SR FT PASS F-A Fl.l0 2RC14AC-2/2CV09028S 2RC14AC-2 SNUBBER SR FT PASS F-A Fl.10 2AC16AD-2J2CV14001S 2AC16AD-2 VT-3 SNUBBER SR FT PASS Failed 2FW06002S Expansion Sample F-A Fl.lO 2RC16AD-2/2CV14004S SNUBBER SR FT PASS F-A Fib 2RC22AA-1.5/2RC16013S 2RC22AA-1-1/2 VT-3 SNUBBER SR FT PASS Failed 2FW06002S Expansion Sample F-A Fl.b0 2RC22AB-l.5/2RC17002S 2RC22AB-1-l/2 VT-3 SNUBBER SR FT PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 6
7/10/2007
- ExeI~n_
Byron Station Unit 2 Byron Station Outage B2R13 Snubber Outage Summary (Page 7 of 11)
SYSTEM:
Section Xi component ID
Line Number
1Relief Technical
~ActuaI Results Cat emj~Descrip~on
~Requests~Notes Exam
~
Comments F-A Fib 2RC22AB-l.5/2RC17018S 2RC22AB-i-l/2 VT-3 SNUBBEA SR FT PASS Replaced with a Lisega F-A Fl. 10 2RC24AA-4/2AYO6O17S 2AC24AA-4 VT-3 NAP SNUBBER SR Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 7
7/10/2007 Exeln_
Byron Station Unit 2 Byron Station Outage B2R13 Snubber Outage Summary (Page 8 of 11)
SYSTEM:
Residual Heat Removal System (RH)
Section XI Component ID TLine Number Relief Technical Actual Results
~
11111111 Requests Notesixarn I
Comments F-A Fl.20 2RHO2AA-8/2RHO7O11S 2RHO2AA-8 SNUBBER SR F-A F1.20 2AHO2AA-8/2RH07012S 2AHO2AA-8 SNUBBER SR F-A Fl.20 2RHO2AA-8/2RH07013S 2RHO2AA-8 SNUBBER SR FT PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 8
7/10/2007 Exekrn..
Byron Station Unit 2 Byron Station Outage B2R13 Snubber Outage Summary (Page 9 of 11)
SYSTEM:
Section Xl
~ComponentID Line Number Relief
- Technical Actual Results
~scpt~r~~
~
Requests Notes Exam Comments F-A Fib 2RYO1AA-412RY06018S 2RYO1AA-4 VT-3 NAP SNUBBER SR F-A Fib 2RYO2B-3/2AYO9001S 2AYO2B-3 VT-3 SNUBBER SR FT PASS F-A Fl.10 2RYO2B-3/2RY09077S 2RYO2B-3 VT-3 NAP SNUBBER SR F-A Fb.b0 2AYO2B-3/2AYO9100S 2AYO2B-3 VT-3 NAP SNUBBER F-A Fib 2RY11A-14/2RYO5O1OS SNUBBER SR 2RY11A-14 VT-3 NAt SR Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 9
7/10/2007
~xeI~n~
Byron Station Unit 2 Byron Station Outage B2R13 Snubber Outage Summary (Page lOof 11)
SYSTEM:
Steam Generator Blowdown System (SD)
Component ID LIne Number
~ReIief
~Technic&- Actual Results cat.
- ltOestion~
II
Requests Notes Exam Comments NA NA 2SDO1CB-212SD01003S 2SDO1CB-2 VT-3 SNUBBER SR FT PASS NA NA 2SDO1CC-2/2SD03002S 2SDO1CC-2 SNUBBER SR FT PASS NA NA 2SDO1CE-2/25D22019S 2SDO1CE-2 VT-3 NAP SNUBBER SR FT PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-l 220 and IWF-2500 tables 10
7/1 0/2007 E~xeJ~n_
Byron Station Unit 2 Byron Station Outage B2R13 Snubber Outage Summary (Page 11 of 11)
SYSTEM:
Safety Injection System (SI)
Section XI Component ID
Line Number Relief Techn~eI-TActuat Results Cat Item Dcript
~
Requests Notes Exam Comments F-A Fi.20 2SPO2BA-6/2SP18A049S 2SIO2BA-6 SNUBBER SR NA NA 2SIO3BB-4/2SP i3026S 2SIO3BB-4 VT-3 NAP SNUBBER SR FT PASS Failed 2FW06002S Expansion Sample NA NA 2SIO3CB-2/2S113027S 2SIO3CB-2 SNUBBER SR FT PASS F-A SNUB 2SIO5DC-6/2SP09014-S1 2SIO5DC-6 DBL VT-3 NAt SNUBBER SR F-A SNUB 2SIO5DC-6/2S109014-S2 2SIO5DC-6 DBL VT-3 NAP SNUBBER SR F-A Fib 2S1O8JC-1.512SP20001S 2SIO8JC-l-l/2 VT-3 SNUBBER SR F-A F1.10 2SIO8JC-1.5/2S12000SS 2SIO8JC-1-l/2 SNUBBER SR NA NA 2SI18ED-2I2S116037S 2SI18ED-2 VT-3 SNUBBER SR FT PASS Note: Section Xl Category numbersN/A-ed are exempt from IWF-1220 and IWF-2500 tables 11
7/10/2007
- - Exelt~n.
Byron Station Unit 2 B2R13 ISP Outage Report Detailed Inservice Inspection Snubber Listing SYSTEM:
Chemical & Volume Control System (CV)
Section XI Component ID Line Number Relief Technical Exam Results Cat.
,t~
Description Requests Notes Comments NA NA 2CV1 4EB-2/2CV360065 SNUBBER 2CV1 SR FT PASS F-A Fl.10 2CVA7AA-2i2CV25012S SNUBBER 2CVA7AA-2 SR FT NAt Page 1-1 7/10/2007
7/10/2007 ExeI~
n_
Byron Station UnIt 2 B2R13 ISI Outage Report Detailed Inservice Inspection Snubber Listing SYSTEM:
Section XI Component ID Line Number Relief Tethna~f~xam
~
i~m Description Requests Notes Comments F-A F1.20 SNUBBER SR FT PASS Page 1-2 7/10/2007
7/10/2007 ExeI~n.
Byron Station Unit 2 B2R13 PSI Outage Report Detailed Inservice Inspection Snubber Listing SYSTEM:
Section XI Component ID Line Number Relief Technical Exam Results Cat.
Item -- Description Requests Notes Comments NA NA 2RCO8AC-3/4/2AC1 8003S SNUBBER 2RCO8AC-3/4 SR FT PASS F-A Fl.10 2RC22AB-b.5/2RC1 70l8S SNUBBER 2RC22AB-l -1/2 SR FT PASS Page 1-3 7/10/2007
7/10/2007 ExelIn Byron Station Unit 2 B2R13 ISI Outage Report Detailed Inservice Inspection Snubber Listing SYSTEM:
Safety Injection System (SI)
Section XI
~omponent ID rLineNumb~
Relief Techrilc~
Exam Results
~
~L~___
~
J____
Comments NA NA SNUBBER SR FT PASS Page 1-4 7/10/2007
I I
(
(This report is used to verify that the periodic I
requirements of Tables IWx-24b2-1 will be met by the interval schedule.)
BYRON STATION UNIT 2 - 3RD INTERVAL I
~
(The percentage requirements of Tables IWx-2412-i apply to the Category and were applied to each Item only when practical.)
I
~
ASME SECTION XI EXAMINATION STATUS REPORT CATEGORY B-A NON-DEFERRED EXAMS CATEGORY B-A DEFERRED EXAMS CATEGORY B-B NON-DEFERRED EXAMS
% Selected 100.00%
100.00%
0 25.00%
o 62.50%
% Exams Completed Period 1 Period 2 0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
Period 3 0.00%
0.00%
0.00%
0.00%
- 1. (B2.40) Per Examination Category B-B, Note 1, examinations may be limited to one vessel among a group of vessels performing a similarfunction.
CATEGORY B-D NON-DEFERRED EXAMS
- of Comp 6
6 8
Total Selected 6
- Exams Completed mm Per 2 max 2
0 3
3 0
4 4
0 6
9 0
14 Per 3
% Selected 0
100.00%
0 100.00%
0 100.00%
0 100.00%
% Exams Completed Period 1 Period 2 i6.67%
16.67%
0.00%
0.00%
0.00%
0.00%
5.00%
5.00%
Period 3 16.67%
0.00%
0.00%
5.00%
Cat.
B-A B-A item No.
Bl.21 Bb.40
- of Total
- Exams Completed Camp Selected mm Per 1 max mm Per 2 max 1
1 0
1 1
1 0
1 1
1 0
0 1
1 0
1 Totals:
2 2
0 0
1 1
0 1
- of Total
- Exams Completed Cat. Item No. Camp Selected mm Per 1 max mm Per 2 max B-A B1.li 3
3 N/A 3
N/A N/A 0
N/A B-A Bi.21 1
1 N/A 1
N/A N/A 0
N/A B-A Bb.30 1
1 N/A 1
N/A N/A 0
N/A Totals:
5 5
WA 5
N/A N/A 0
N/A Cat. Item No.
- of Camp Total Selected mm Per 1 max
- Exams Completed mm Per 2 max B-B B2.lb 2
2 0
0 1
1 0
1 B-B B2.b2 2
2 0
0 1
1 0
1 B-B B2.40 4
1 0
0 1
1 0
1 Totals:
8 5
1 0
2 3
0 3
% Selected
% Exams Completed PerIod 1 Period 2 PerIod 3 100.00%
0.00%
0.00%
0.00%
100.00%
0.00%
0.00%
0.00%
100.00%
000%
000%
0.00%
% Exams Completed Period 1 Period 2 PerIod 3 100.00%
100.00%
100.00%
100.00%
100.00%
100.00%
100.00%
100.00%
100.00%
100.00%
100.00%
100.00%
100.00%
100.00%
100.00%
100.00%
Per 3 0
0 0
Per 3 0
0 0
0 Per 3 0
0 Cat.
B-D B-D B-D Item No.
B3.li0 B3. 120 63.140 Totals:
mm Per 1 max 1
1 3
6 1
0 3
8 2
0 4
20 20 4
1 10
- 1. (B3.120 & B3.l40) Per 10 CFR 50.55a(b)(2)(xxi)(A), Table IWB-2500-b examination requirements, the provisions of Table IWB-2500-b, Examination Category 6-0, Item Numbers 83.120 and 83.140 in the 1998 Edition must be applied when using the 1999 Addenda through the latest edition and addenda, and requires that a visual examination with enhanced magnification may be performed on the inside radius section in place of an ultrasonic examination.
Section 3.0 Page 1 of 8