ML070180609
| ML070180609 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/05/2007 |
| From: | Exelon Nuclear |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML070180609 (138) | |
Text
BYRON Exekm.
UNIT 1 Nuciear B1R14 FaIl2006 Outage INSERVICE INSPECTION
SUMMARY
REPORT For Inspection Activities from March 26, 2005 to October 16, 2006 Commercial Service Date September 16, 1985 Document Completion Date January 5, 2007 Exelon Generation Company (EGC, LLC) 4300 Winfield Rd Warrenvifle, IL 60555 Byron Nuclear Power Station 4450 North German Church Rd.
Byron, IL 61010
BYRON UNIT 1 Exek,n~
B1R14 Nuclear INSERVICE INSPECTION
SUMMARY
REPORT ISECTION SECTION DESCRIPTION PAGESI I
I
~CoverPage I
1 I
I U
ITable of Contents I
1
-I I
1.0 I Report Introduction I
5 I
20 3.0 Examination Summary Tables Status ISI - Weld / Component Listing ISI - Bolts, Pumps, and Valves Listing PSI - Weld / Component Listing PSI - Bolts, Pumps, and Valves Listing ISI
- Pressure Tests 2nd Inspection Interval ISI
- Pressure Tests 3rd Inspection Interval ISI
- Component Supports ISI - Snubbers I
I I_________________________________________________
4.0 Form NIS-1 Welds, Bolts, Pumps, Valves, Supports, and Snubbers Pressure Tests 2nd Inspection Interval Pressure Tests 3rd Inspection Interval Examination Completion 21 2
2 1
1 2
8 9
8 46 2
5 I
I 1
5.0 I Form NIS-2 I
Repairs/ Modificationsl 90 1
I 6.0 JContainment Inservice Inspection Report I
5 1
TOTALPAGESINREPORTj 209 1 I
Section 1.0 Report Introduction
BYRON STATION UNIT 1 REFUELING OUTAGE 14 INSERVICE INSPECTION REPORT
1.0 INTRODUCTION
Inservice inspections of American Society of Mechanical Engineers (ASME) Class 1, 2, 3, CC, and MC components were conducted at Byron Station Unit 1 from March 26, 2005 through October 16, 2006. The majority of these activities were performed during the fourteenth refueling outage (B1R14)from September 11 through October 16, 2006.
The examinations were performed in compliance with the rules and regulations of ASME Section Xf, Division 1, Rules for Inseriice Inspection ofNuclear Power Plant Components, (app)icab~eedition 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 CJass 1 and 2 components and piping. This report also includes inspection results of components for Class 3 and Augmented Programs.
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 ((SI) Program Plan for Class 1, 2, and 3 components was developed in accordance with the requfrements and intent of Section XI Subsections IWA, )WB, IWC, IWD, IWE, IWF and IWL, 2001 Edition, through the 2003 Addenda.
In addition to the ASME Section XI requirements of examination, certain Nuclear Regulatory Commission (NRC) augmented ISI inspections were required. The Byron Station Unit 1 augmented examination requirements snelude:
a) Class 1 pressure boundary for leakage at nominal operating pressure, ~naccordance with NRC Generic Letter 88-05; b) Class 2 and 3 pressure boundary for leakage at nominal operating pressure, in accordance with NUREG 0737; c) Class 2 IWC-1220 exempted piping per Information Notice No. 79-19 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 ~WB,IWC, IWD, IWE, IWF, and $WL-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 IWA, IWB, IWC, IWD, IWE, IWF, and IWL of Section XI of the ASME Code.
For Class 1, 2, and certain non-class piping components, the requirements of Risk Informed Inservice Inspection (RI-ISI) are followed using EPRI TR1 12657 and Table 1 of ASME Code Case N-578-1.
1.2 Identification of Exempted comøonents 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 SectIon 1.0 Page 1 of 5
BYRON STATION UNIT 1 REFUELING OUTAGE 14 INSERVICE INSPECTION REPORT Table IWD-2500-1, 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-ISI program. With the adoption of RI-ISI, welds evaluated as Risk Category 6 or 7 are not required to be subject to examination.
1.3 Implementation of the ISI ProQram 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 ISI 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 afl 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-189, 1995 Revision. The NDE procedures were developed and certified in conformance with ASME Section V and XI, 2001 Edition through the 2003 Addenda, and the 1995 Edition with the 1996 Addenda as applicable.
AU ISI NDE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section XI, 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.
1.4 Second and Third 10-Year Insr~ectionIntervals The 14th fuel cycle for Unit 1 encompasses a time span of March 26, 2005 to October 16, 2006. Activities that occurred prior to January 16, 2006 were performed during the Second Inspection Interval. Activities that occurred on or after January 16, 2006 were performed during the Third Inspection Interval.
1.5 Sicjnificant Activities During Bi R14 During the refueling outage, the AHoy 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.
Section 1.0 Page 2 of 5
BYRON STATION UNIT 1 REFUELING OUTAGE 14 INSERVICE INSPECTION REPORT 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 14th 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 case is used for the implementation of the risk-informed program as described in relief request l3R-02.
N-578-1 Risk-Informed Requirements for Class 1, 2, or 3 Piping, MethodB.
Portions of the following cases were utilized as described in relief request 13R-08 for the full structural weld overlays applied to the pressurizer safe-end welds:
N-504-2 Alternative Rules for Repairof Classes 1, 2, and 3Austenitic Stainless Steel Piping.
N-638-1 Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW 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. Use of the following case was applicable during this time:
N-41 6-2 Alternative Pressure Test Requirement for Welded Repairs or Installation of Replacement Items by Welding, Class 1, 2, and 3 1.7 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANtI): J. Snyder, G. Feigel, J. Hendricks, and L. 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 foflowing 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 Section 1.0 Page 3 of 5
BYRON STATION UNIT 1 REFUELING OUTAGE 14 INSERVICE INSPECTiON REPORT System Pressure Test Summary Tests performed during the 2nd Inspection Interval Tests performed during the 3rd Inspection tnterval Component Support Examination Summary Component Snubber Test Summary 3.0 UNIT 1 EXAMINATION COMPLETION STATUS A summary table of the examination status of Class 1, 2, and 3 components is contained in Section 3.0.
4.0 FORM NIS-1 DATA SHEETS Welds, Bolts, Pumps, Valves, Supports, and Snubbers Pressure Tests 2nd Inspection Interval Pressure Tests 3rd Inspection Interval 5.0 FORM NIS-2 DATA SHEETS ASME Form NIS-2, Owners Report for Repairs or Replacements, were filed during the cycle for Unit 1. See Section 5.0 for the reports.
6.0 CONTAINMENT PSI PROGRAM Reportable conditions were identified for Class CC components during this fuel cycle.
The reporting requirements in 1 OCFR5O.55a (b)(2)(viii)(E) are applicable for this summary report. See Section 6.0 for the report on these conditions.
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, 1989 Edition.
Section V, Nondestructive Examination, 1995 Edition, with the 1996 Addenda.
Section V, Nondestructive Examination, 2001 Edition, through 2003 Addenda.
Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (for 2~Inspection Interval pressure tests and repair/replacement activies).
Section 1.0 Page 4 of 5
BYRON STATION UNIT 1 REFUELING OUTAGE 14 INSERVICE INSPECTION REPORT Section Xl, Rules for Inservice Inspection of Nuclear Power Plant Components, 1995 Edition, 1996 Addenda (for Appendix VIII requirements).
Section Xl, Rules for InseMce Inspection ofNuclear PowerPlant Components, 2001 Edition, through 2003 Addenda (for 3id Inspection Interval).
7.3 American Nat~onaIStandards Institute I American Society for Nondestructive TestinQ 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 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.
Information Notice No. 79-19, Pipe Cracks in Stagnant Borated Water Systems at PWR Plants.
7.6 Electric Power Research Institute Material Reliability Program Primary System Piping Butt Weld Inspection and Evaluation Guideline (MAP-i 39) July 14, 2005.
Topical Report TR1 12657 Revision B-A, Revised Risk-Informed Inservice Inspection Procedure.
Section 1.0 Page 5 of 5
Section 2.0 Examination Summary Tables
1/5/2007 Exeión Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld / Component Listing SYSTEM:
Containment Spray System (CS)
Section XI
~omponent ID Line Number Relief Technical ~ode R~uI~~tuaI Results Description Requests Notes Coverage Exam Exam Comments R-A R1.20 1CSO2AA-1O/CO1 1CSO2AA-1O 13R-02 C5.11 100 VOL-E UT NRI Reducer - ElbOW 13T-O1 13T-02 OBS14-117 A-A R1.20 1CSO2AA-1O/C65 EJbow - Pipe OBS14-170 1CSO2AA-1O 13R-02 C5.11 13T-O1 131-02 100 VOL-E UT Nfl R-A R1.20 1CSO2AA-1O/C88 Elbow - Reducer OBS14-118 Root Geometry 3~o Intermfttent 1CSO2AA-10 13R-02 C5.11 13T-O1 13T-02 100 VOL-E UT GEOM A-A R1.20 1CSO6AA-6/C07 Pipe - Elbow OBS 14119 1CSO6AA-6 13R-02 C5.11 13T-O1 131-02 100 VOL-E UT NR1 A-A R120 1CSO6AA-6/C08 ElbOW - Pipe OBS14-120 1CSO6AA-6 13R-02 C5.11 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 1CSO6AB-6/C05 Elbow - Pipe OBS14-122 1CSO6AB-6 13R-02 C5.11 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 1CSO6AB-6/C06 Pipe - Pipe OBS14-123 1CSO6AB-6 13R-02 C5.11 13T-O1 13T-02 100
~
VOL-E UT NRI R-A R1.20 1CS1OAA-6/C06 Pipe - Elbow OBS14-168 1CS1OAA-6 13R-02 C511 (31-01 13T-02 100 VQL-E UT NRI A-A R1.20 1CS1OAA-6/C20 Elbow - Pipe OBS 14~169 1CS1OAA-6 13R-02 C5.11 13T-O1 13T-02 100 VOL-E UT NRI 1
1/5/2007 SYSTEM:
Exekn..
Byron Station UnIt 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing Chemical & Volume Control System (CV)
A-A R120 1CVO5B-8/C24 1CVO5B-8 13R-02 C5.11 100 VOL-E UT NRI Elbow - Pipe 13T-O1 13T-02 OBS 14171 A-A R1.20 1CVO5B-8/C25 Pipe-Tee OBS14-172 1CVO5B-8 13R-02 C5.11 13T-O1 131-02 100 VOL-E UT NRI A-A R120 1CVO5B-8/C26 Tee - Pipe OBS14-173 1CVO5B-8 13R-02 C5.11 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 1CVO8AA-41C03 Elbow - Pipe OBS14-124 1CVO8AA-4 13R-02 C5.21 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 1CVO8AA-41C17 Pipe - Tee OBS14-175 1CVO8AA-4 13R-02 C5.21 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 1CVO8BA-4/C09 Pipe - Elbow OBS14-178 1CVO8BA-4 13R-02 C5.21 13T-O1 13T-02 100 VOL-E UT NRI R-A R1.20 1CVO8BA-4/C21 Pipe-Tee OBS14-180 Root Geometry 3600 Intenii~llent.
1CVO8BA-4 13R-02 C5.21 13T-O1 i3T-02 100 VOL-E UT GEOM R-A R1.20 1CVO9A-41C02 Reducer - Tee OBS14-176 1CVO9A-4 13R-02 C5.21 131-01 13T-02 100 VOL-E UT NRI R-A R1.20 1CVO9A-41C03 Tee-Pipe OBS14-177 1CVO9A-4 13R-02 C5.21 13T-O1 13T-02 100 VOL-E UT NAI A-A R1.20 1CVO9A-41C07 Pipe - Elbow OBS 14181 Root Geometry36O~Intermittent.
1CVO9A-4 13R-02 C5.21 13T-O1 131-02 100 VOL-E UT GEOM 2
1/5/2007 Exekrn..
Byron Station Unft 1 B1R14 ISP Outage Report Detailed Inservice Inspection Weld / Component Listing SYSTEM:
Chemical & Volume Control System (CV)
Section XI Component~D Line Number Relief Technicifi Code Required Actual Results Cat Description Requests Notes Coverage Exam Exam Comments R*A R1.20 1CVA1A-6/C02 1CVA1A-6 13R-02 C5.11 100 VOL-E UT NRI Elbow-Pipe 131-01 13T-02 OBS14-174 A-A R1.11 OBS14-001 1CVA3AA-2/W-06 Pipe - Elbow 1CVA3AA-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NAI A-A R1.11 OBS14-002 1CVA3AA-2/W-07 Elbow - Pipe 1CVA3AA-2 13R-02 B940 131-01 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-003 1CVA3B-2PW-74 Pipe - Elbow 1CVA3B-2 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 Nfl A-A R1.11 OBS14-004 1CVA3B-2/W-75 Elbow - Pipe 1CVA3B-2 13R-02 B9.40 131-01 131-02 VT-2 VT-2 NRI A-A R1.11 OBS14-005 1CVA3B-2/W-76 Pipe - ElbOW 1CVA3B-2 13R-02 B9.40 l3T-O1 13T-02 VT-2 VT-2 NRI A-A Rill OBS14-006 1CVA3B-2/W-77 Elbow - Pipe 1CVA3B-2
~
13R-02 B9.40 131-01 13T-02 VT-2 VT-2
~
NRI R-A R1.11 OBS14-007 1CVA3B-2/W-84 Pipe - Elbow 1CVA3B-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-008 1CVA3B-ZW-85 Elbow - Pipe 1CVA3B-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 Nfl R-A R1.11 OBS14-009 1CVA5AA-2/W-04 Pipe-ElbOW 1CVA5AA-2 13R-02 B9.40 131-01 131-02 VT-2 VT-2 NRI A-A R1.11 OBS14-010 1CVA5AA-2/W-05 Elbow - Pipe 1CVA5AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI 3
1/5/2007 Exeión~
Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld / Component Listing SYSTEM: Chemical & Volume Control System (CV)
R-A R1.11 1CVA6AA-2/W-04 1CVA6AA-2 13R-02 B9.40 VT-2 VT-2 NRI Pipe - Elbow 13T-O1 13T-02 CBS14-011 R-A R1.11 OBS14-012 1CVA6AA-2/W-05 Elbow - Pipe 1CVA6AA-2 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 NRI A-A R1.11 OBS14-013 1CVA7AA-2/W-08 Pipe - Elbow 1CVA7AA-2 13R-02 B940 13T-O1 131-02 VT-2 VT-2 NRI fl-A R1.11 OBS14-014 1CVA7AA-2/W-09 Elbow - Pipe 1CVA7AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NAP 4
Exekn.
Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM:
A-A Al.11 1FWO3DA-16/CO1 1FWO3DA-16 13R-02 C5.51 97 VOL-E UT GEOM R1.18 Valve-Pipe 13T-O1 13T-02 OBS14-125 Root Geometry3600 Intermittent. Exam obstructed by adjacent branch connection.
A-A R1.11 1FWO3DA-16/C02 Ri.18 Pipe - Penetration OBS14-126 Root Geometry360~Intermittent 1FWO3DA-16 13R-02 C5.51 13T-O1 13T-02 100 VOL-E UT GEOM A-A R1.11 1FWO3DD-16/C14 R1.18 Pipe - Elbow OBS14-213 1FWO3DD-16 13R-02 C5.51 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.11 1FWO3DD-1&C15 R1.18 Elbow-Pipe OBS14-214 1FWO3DD-16 13R-02 C5.51 131-01 13T-02 100 VOL-E UT NRI
~
A-A R1.11 1FWO3DD-16/C16 R1.18 Pipe-Elbow OBS14-215 1FWO3DD-16 13R-02 C5.51 13T-O1 131-02 100 VOL-E UT NRI A-A R1.1l 1FWO3DD-1&C17 R1.18 Elbow-Pipe OBS14-216 1FWO3DD-16 13R-02 C5.51 131-01 13T-02 100 VOL-E UT NAP A-A R1.11 lFW03DD-16~C19.O1 R1.18 Pipe-Elbow OBS14-217 1FWO3DD-16 I3R-02 C5.51 131-01 I3T-02 100 VOL-E UT NRI A-A R1.11 1FWO3DD-16/C20.O1 R1.18 Elbow-Pipe OBS14-218 1FWO3DD-16 i3R-02 C5.51 13T-O1 131-02 100 VOL-E UT NRI A-A R1.11 1FW87CA-6/CO7A R1.18 Elbow-Pipe OBS14-127 1FW87CA-6 13R-02 C5.51 13T-01 131-02 100 VOL-E UT NAt R-A R1.11 1FW87CA-6/CO8A R1.18 Pipe-SOL OBS14-128 Spot mid-wall indication seen outside exam 1FW87CA-6 voume. One-sidede 13R-02 xam due to pipe C5.51 131-01 131-02 to sweep-o-le 92 VOL-E t configuration.
UT IND 1/5/2007 5
1/5/2007 Exelon Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM:
Main Steam System (MS)
Section XI component ID Line Number
Relief
- Technlc& code
!R~r~ Actual Results.
Description Requests Notes Coverage Exam Exam A-A R1.20 1MSO1AB-32.75/CO1.O1 1MSO1AB-32.75 13R-02 C5.51 100 VOL-E UT NAI Safe End - Elbow 13T-O1 131-02 OBS14-130 A-A R1.20 1MSO1AB-32.75/CO1A Nozzle - Safe End OBS14-131 1MSO1AB-32.75 13R-02 C5.51 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 1MSO1CD-30.251C01 Pipe - Valve OBS14-129 Root Geometry 3600 IntermIttent 1MSO1CD-30.25 13R-02 13T-O1 13T-02 100 VOL-E UT GEOM fl-A R1.20 1MSO7AB-28/C08 Pipe
- Elbow OBS14-183 1MSO7AB-28 13R-02 C5.51 13T-O1 13T-02 100 VOL-E UT NAt R-A Rl.20 1MSO7BB-28/CO1 Elbow - Pipe 088 14-182 1MSO7BB-28 13R-02 C5.51 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 1MSO7BB-281C12 Pipe - Cap OBS14-184 1MSO7BB-28 13R-02 C5.51 13T-O1 131-02 100 VOL-E UT NRI R-A R1.20 1MS13AA-81C08 Pipe - Valve OBS14-132 1MS13AA-8 13R-02 C5.51 13T-O1 13T-02 100 VOL-E UT NRI R-A R1.20 1MS13AA-81C09 Valve - Elbow OBS 14133 Root Geometry3~°Intermittent IMS13AA-8 13R-02
~
C5.51 13T-O1 13T-02 100 VOL-E UT GEOM fl-A R1.20 1MS13AA-81C10 Elbow - Pipe OBS14-134 1MS13AA-8 13R-02 C5.51 13T-O1 13T-02 100 VOL-E UT NAt R-A R1.20 1MS13AA-8/C11 Pipe - Reducer OBS 14135 1MS13AA-8 13R-02 C5.51 131-01 131-02 100 VOL-E UT NRI R-A R1.20 1MS13AA-8/C12 Reducer - Valve OBS14-136 1MS13AA-8 13R-02 C5.51 131-01 131-02 100 VOL-E UT NRI 6
1/512007 Exekn..
Byron Station UnIt 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM:
Pressurizer (PZR)
Section XI ComponentID Line Number Relief Technical Code Required Actual Results Cat Description
Requests Notes Coverage Exam Exam
-~
Comments B-D B3.11O 1RY-O1-S/PN-O1 1RY-O1-S Surge Nozzle OBS14-197 Exam limited by nozzle configuration and heater penetrations.
B-D 83.120 1 RY-Ol -S/PN-O1-NIA 1 RY-Ol -S Surge Nozzle Inner Radius 13R-03 40 VOL UT NRI 13R-03 VOL UT NRI OBS14-198 B-D B3.11O 1RV-O1-SIPN-02 1RY-O1-S 13R-12 77 VOL UT NR~
Spray Nozzle OBS14-199 Scanning limited by nozzle configuration B-D B3.120 1RY-O1-S/PN-02-NIR 1RY-O1-S VOL UT NRI Spray Nozzle Inner Radius OBS14-200 B-D B3.11O 1RY-O1-S/PN-03 1RY-O1-S 13R-12 77 VOL UT NAI Safety Nozzle OBS14-201 Scanning limited by nozzle configuration B-D B3.120 1RY-.O1-S/PN-03-NIR 1RY-O1-S VOL UT NRI Safety Nozzle Inner Radius OBS14-202 B-D B3.11O 1RY-O1-S/PN-05 1RY-O1-S 13R-12 68 VOL UT NAI Relief Nozzle OBS14-203 Scanning limited by nozzle configuration B-D B3.120 1RY-O1-S/PN-05-NJR 1RY-O1-S VOL UT Nfl Relief Nozzle Inner Radius OBS14-204 B-D B3.11O 1RY-O1-S/PN-06 1RY-O1-S 13R-12 77 VOL LiT NRI Relief Nozzle OBS14-205 Scanning Iimfted by nozzle configuration B-D B3.120 1RY-O1-S/PN-06-NIR 1RY-01-S VOL UT NAI Relief Nozzle Inner Radius OBS14-206 7
1/5/2007 Exek!in_,
Byron Station Unit 1 B1R14 ~SIOutage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM:
A-A R1.20 1RC13AA-2/W-O1 1RC13AA-2 13R-02 B9.40 VT-2 VT-2 NRI SOL - Pipe 131-0 1 13T-02 OBS14-015 R-A A1.20 OBS14-016 1RC13AA-2/W-02.O1 Pipe-Tee 1RC13AA-2 13R-02 89.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.20 OBS 14017 1RC13AA-2/W-03 Tee - Reducer 1RC13AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NR~
A-A R1.20 OBS14-018 1RC13AA-21W-04 Tee-Pipe 1RC13AA-2 13R-02 B9.40 131-01 13T-02 11-2 VT-2 Nfl A-A fl1.20 CBS14-019 1RC13AA-2/W-05 Pipe-Valve 1RC13AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A Ri.20 OBS14-020 1RC13AB-2/W-O1 SOL - Pipe 1RC13AB-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.20 OBS14-021 1RC13AB-2/W-09 Pipe - Valve 1RC13AB-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI A-A R1,20 OBS14-022 1RC13AC-2/W-O1 SOL-Pipe 1RC13AC-2 13R-02
~
B9.40 131-01 13T-02 VT-2 VT-2 NAI A-A R1.20 OBS14-023 1RC13AD-2,W-O1 SOL - Pipe
~
1RC13AD-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-024 1RC14AA-2!W-02 Pipe - Elbow 1RC14AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NAt R-A R1.11 OBS14-025 1RC14AA-2/W-03 Elbow - Pipe 1RC14AA-2 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 Nfl 8
1/5/2007 Exek,n..
Byron Stallon Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld / Component Listing SYSTEM: Reactor Coolant System (RC)
Section XI ComponentID Line Number
-Reflef Technical Code Requfred Actual Results DescripUon Requests Notes Coverage Exam Exam Comments R-A R1.11 1RC14AA-2/W-03A 1RC14AA-2 13R-02 B9.40 VT-2 VT-2 NRI Pipe - Tee 13T-O1 13T-02 OBS14-026 A-A Rill OBS14-027 1RC14AA-2/W-03B Tee - Reducer 1RC14AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.11 OBS14-028 1RC14AA-2/W-03C Tee - Pipe 1RC14AA-2 13fl-02 89.40 13T-O1 13T-02 VT-2 VT-2 NRI fl-A R1.11 OBS14-029 1RC14AA-2/W-04 Pipe - Elbow 1RC14AA-2 13R-02 B940 13T-O1 13T02 VT-2 VT-2 NRI A-A R1.11 OBS14-030 1RC14AA-2/W-05 Elbow - Pipe 1RC14AA-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NAI A-A R1.11 OBS14-031 1RC14AA-21W-06 Pipe - Valve 1RC14AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.11 OBS14-032 1RC14AA-2PW-07 Valve - Pipe 1RC14AA-2 13R-02 B9AO 13T-O1 131-02 VT-2 VT-2 NAt R-A Rill OBS14-033 1RC14AA-2/W-08 Pipe - Tee 1RC14AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NAt R-A R1.11 OBS14-034 1RC14AA-2/W-09 Tee - Reducer 1RC14AA-2 13R-02 B9.40 13T-01 13T-02 VT-2 VT-2 NRI R-A R1.11 OBS14-035 1RC14AA-2iW-1O Reducer - Pipe 1RC14AA-2 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 NRI A-A flu OBS14-036 1RC14AA-2/W-11 Pipe
- Valve 1RC14AA-2 13R-02 B9.40 13T-01 13T-02 VT-2 VT-2 NRI 9
1/5/2007 Exeln Byron Station UnIt 1 B1R14 IS! Outage Report Detailed Inservice Inspection W&d I Component Listing SYSTEM:
Section XI Component ID Line Number Relief Technical Code RequiTed Actual Results Descrlpflon Requests Notes Coverage Exam Exam Comments A-A flu 1RC14AA-2/W-12 1RC14AA-2 13R-02 B9.40 VT-2 VT-2 NAI Pipe - Coupling 13T-O1 13T-02 OBS14-037 R-A R1.11 OBS14-038 1RCt4AA-2,W-13 Coupling - Pipe 1RC14AA-2 13R-02 B9.40 13T-Ol 131-02 VT-2 VT-2 NRI R-A R1.11 OBS14-039 1RC14AB-2/W-07 Coupling - Pipe 1RC14AB-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NAt A-A Rl.11 OBS14-040 1RC14AB-2/W-08 Pipe - Valve 1RC14AB-2 13R-02 B940 13T-O1 13T-02 VT-2 VT-2 NR~
A-A R1.11 OBS14-041 1RC14AB-2JW-09 Valve - Pipe 1RC14AB-2 13R-02 B940 13T01 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-042 1RC14AB-2/W-1O Pipe - Tee 1RC14AB-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-043 1RC14AB-2/W-11 Tee - Reducer 1RC14AB-2 13R-02 B940 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-044 1RC14AC-2/W-08 Pipe - Valve 1RC14AC-2 13R-02
~
B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-045 1RC14AD-2/W-08 Pipe - Valve 1RC14AD-2 13R-02 89.40 13T-O1 131-02 VT-2 VT-2 NRI R-A Ri.11 OBS 14.046 1RC14AD-2PW-09 Valve-Pipe 1RC14AD-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-047 1RC14AD-2~W-1O Pipe - Tee 1RC14AD-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI 10
1/5/2007 Exekrn..
Byron Station UnIt 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM: Reactor Coolant System (RC)
A-A R1.11 1RC14AD-2/W-11 1RC14AD-2 13R-02 B9.40 VT-2 VT-2 NRI Tee - Reducer 13T-O1 13T-02 OBS14-048 R-A R1.11 OBS14-049 1RC14AD-21W-12 Tee - Pipe 1RC14AD-2 13R-02 B940 13T-O1 13T-02 VT-2 VT-2 NRI A-A Rill OBS14-050 1RC14AD-21W-13 Pipe-Valve 1RC14AD2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI R-A R1.11 OBS14-051 1RC16AA-21W-02 Pipe - Valve 1RC16AA-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-052 1RC16AA-21W-03 Valve - Pipe 1RC16AA-2 13R-02 B9.40 13T-01 13T-02 VF-2 VT-2 NRI A-A R1.11 OBS14-053 1RC16AA-2/W-04 Pipe - ElbOW 1RC16AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.11 OBS14-054 1RC16AA-2/W-05 ElbOW - Pipe 1RC16AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2
~
NRI A-A R1.tl OBS 14055 1RC16AA-2/W-06 Pipe - Elbow 1RC16AA-2 13R-02 B9A4) 13T-01 131-02 VT-2 VT-2 NRI A-A R1.20 OBS14-056 1RC16AA-2/W-07 Elbow - Pipe 1RC16AA-2 13R-02 B9.40 13T-Ol 131-02 VT-2 VT-2 NRI R-A R1.20 OBS14-057 1RC16AA-2/W-08 Pipe - SOL 1RC16AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.11 CBS 14058 1IRC16AB-2/W-02 Pipe - Elbow 1RC16AB-2 13R-02 B9.40 13T-01 J3T-02 VT-2 VT-2 Nfl
- 11
1/5/2007 Exekin Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld / Component Listing SYSTEM:
R-A R1.11 1RC21AA-8/J07 1RC21AA-8 13R-02 B9.1l 100 VOL-E UT NRI Pipe - Elbow 13T-O1 13T-02 OBS14-137 A-A R1.11 OBS14-138 1RC21AA-81J08 Elbow - Pipe 1RC21AA-8 13R-02 B9.11 13T-01 13T-02 100 VOL-E UT NAP A-A R1.11 OBS14-139 1RC21AA-81J09 Pipe - Elbow 1RC21AA-8 13R-02 89.11 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.11 OBS14-140 1RC21AA-8/J1O Elbow - Pipe 1RC21AA-8 13R-02 B9.11 13T-O1 131-02 100 VOL-E UT NAI A-A R1.20 OBS14-141 1RC21AA-8/J11 Pipe - Pipe 1RC21AA-8 13R-02 B9.11 13T-O1 131-02 100 VOL-E UT NRI R-A R1.20 OBS14-059 1RC22AA-1.5/W-O1 Reducer - Coupling 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.20 OBS14-060 1RC22AA-1.51W-02 Coupling - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 NRI A-A R1.20 OBS14-061 1RC22AA-1.51W-03 Pipe - Elbow 1RC22AA-1.5 13R-02 B9.40 131-01 131-02 VT-2 VT-2 NRI A-A R1.20 OBS14-062 1RC22AA-1.&W-04 Elbow - Pipe 1RC22AA-t5 13R-02 89.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.20 OBS14-063 1RC22AA-1.5iW-05 Pipe - Elbow 1RC22AA-1.5 13R-02 B9.40 13T-O1 131-02 VT-2
~
VT-2 NRI R-A R1.20 OBS14-064 1RC22AA-1.SW-06 Elbow - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 NRI 12
1/5/2007 Exel~n_
Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM:
Section XI Component ID Line Number Relief Technical Code Required Actual Results
Description Requests Notes Coverage Exam Exam Comments R-A R1.20 1RC22AA-1.51W-07 1RC22AA-1.5 13R-02 B9.40 VT-2 VT-2 NAI Pipe - Elbow 13T-01 13T-02 OBS14-065 A-A R1.20 OBS14-066 1RC22AA-1.51W-08 Elbow - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.20 OBS14-067 1RC22AA-1.5/W-09 Pipe - ElbOW 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NAt A-A R1.20 OBS14-068 1RC22AA-1.5,W-1O ElbOW - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 Nfl A-A R1.20 O~14-069 1RC22AA-1.5/W-11 Pipe - Elbow 1RC22AA-1.5 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NAP R-A R1.20 OBS14-070 1RC22AA-1.51W-12 Elbow-Pipe 1RC22AA-1.5 13R-02 89.40 13T-01 13T-02 VT-2 VT-2 NRI A-A R1.20 OBS14-071 1RC22AA-1.51W-13.O1 Pipe-Valve 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2
~
NAt R-A R1.20 OBS 14072 1RC22AA-1.5/W-14.O1 Vatve - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.20 OBS14-073 1RC22AA-1.51W-15.O1 Pipe - Elbow 1RC22AA-1.5 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 NRI R-A R1.20 OBS14-074 1RC22AA-1.5,W-16.O1 Elbow - Pipe 1RC22AA-1.5 13R-02 B9.40 137-01 13T-02 VT-2 VT-2 NAI R-A R1.20 OBS14-075 1RC22AA-1.5/W-17 Pipe - Coupling 1RC22AA-1.5 13R-02
~
B9.40 131-01 13T-02 VT-2 VT-2 NRI 13
1/5/2007 Exekn.
Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection W&d I Component Listing SYSTEM:
Section XI ComponentID Line Number Relief Technical Code Required Actual Results eat.
- Descrlption Requests Notes Coverage Exam Exam Comments A-A R1.20 1RC22AA-1.5/W-18 1RC22AA-1.5 13R-02 B9.40 VT-2 VT-2 NRI Coupling - Pipe 13T-O1 13T-02 OBS14-076 R-A R1.20 OBS14-077 1RC22AA-1.&W-19 Pipe - Flange 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.20 OBS14-078 1RC22AA-1.51W-20 Flange - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NAP A-A R1.20 OBS14-079 1RC22AA-1.5/W-21 Pipe - Tee 1RC22AA-1.5 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI A-A R1.20 OBS14-080 1RC22AA-1.5/W-22 Tee - Reducer 1RC22AA-1.5 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 NRI R-A R1.20 OBS14-081 1RC22AA-1.5/W-23 Tee - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.20 OBS14-082 1RC22AA-1.5/W-24 Pipe - Tee 1RC22AA-1.5 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt R-A R1.20 OBS14-083 1RC22AA-15/W-25 Tee - Reducer 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.20 OBS14-084 1RC22AA-1.5dW-26 Tee - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.20 1RC22AA-1.5/W-27 1RC22AA-15 13A-02 B9.40 VT-2 VT-2 NRI Pipe - Valve 13T-O1 13T-02 OBS14-085 A-A R1.20 1RC22AA-1.5/W-28 1RC22AA-1.5 Valve - Pipe 13R-02 B9.40 VT-2 VT-2 Nfl 13T-O1 13T-02 OBS14-086 14
1/5/2007 Exeh~n Byron Station Unit 1 Bi R14 ISI Outage Report Detailed Inservice Inspection Weld / Component Listing SYSTEM:
Section XI Component ID
- Line Number Relief Technical Code Required Actual Results Description Requests Notes Coverage Exam Exam Comments R-A R1.20 1RC22AA-1.5/W-29 1RC22AA-1.5 13R-02 B9.40 VT-2 VT-2 NRI Pipe - Elbow 13T-O1 13T-02 OBS14-087 A-A R1.20 OBS14-088 1RC22AA-1.5/W-30 Elbow - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 Nfl R-A R1.20 OBS14-089 1RC22AA-1.5/W-31 Pipe* Elbow 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NAP R-A Ri.20 OBS14-090 1 RC22AA-1.5/W-32 Elbow - Pipe 1 RC22AA-1.5 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 Nfl R-A R1.20 OBS14-091 1RC22AA-1.5/W-33 Pipe-WOL 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.20 OBS 14144 1RC24AA-41J06 Pipe - Elbow 1RC24AA-4 13R-02 B9.11 131-01 13T-02 100 VOL-E UT NRI R-A R1.20 OBS14-145 1RC24AA-4/J07 Elbow - Pipe 1RC24AA-4 13R-02 B9.11 131-01 13T-02 100 VOL-E UT NRI R-A R1.20 OBS14-146 1RC24AA-41J09 Pipe - Elbow 1RC24AA-4 13R-02 B9.11 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 OBS14-147 1RC24AA-4/J1O Elbow - Pipe 1RC24AA-4 13R-02 B9.11 13T-O1 13T-02 100 VOL-E UT NRI 15
BYRON Exekm.
UNIT 1 Nuciear B1R14 FaIl2006 Outage INSERVICE INSPECTION
SUMMARY
REPORT For Inspection Activities from March 26, 2005 to October 16, 2006 Commercial Service Date September 16, 1985 Document Completion Date January 5, 2007 Exelon Generation Company (EGC, LLC) 4300 Winfield Rd Warrenvifle, IL 60555 Byron Nuclear Power Station 4450 North German Church Rd.
Byron, IL 61010
BYRON UNIT 1 Exek,n~
B1R14 Nuclear INSERVICE INSPECTION
SUMMARY
REPORT ISECTION SECTION DESCRIPTION PAGESI I
I
~CoverPage I
1 I
I U
ITable of Contents I
1
-I I
1.0 I Report Introduction I
5 I
20 3.0 Examination Summary Tables Status ISI - Weld / Component Listing ISI - Bolts, Pumps, and Valves Listing PSI - Weld / Component Listing PSI - Bolts, Pumps, and Valves Listing ISI
- Pressure Tests 2nd Inspection Interval ISI
- Pressure Tests 3rd Inspection Interval ISI
- Component Supports ISI - Snubbers I
I I_________________________________________________
4.0 Form NIS-1 Welds, Bolts, Pumps, Valves, Supports, and Snubbers Pressure Tests 2nd Inspection Interval Pressure Tests 3rd Inspection Interval Examination Completion 21 2
2 1
1 2
8 9
8 46 2
5 I
I 1
5.0 I Form NIS-2 I
Repairs/ Modificationsl 90 1
I 6.0 JContainment Inservice Inspection Report I
5 1
TOTALPAGESINREPORTj 209 1 I
Section 1.0 Report Introduction
BYRON STATION UNIT 1 REFUELING OUTAGE 14 INSERVICE INSPECTION REPORT
1.0 INTRODUCTION
Inservice inspections of American Society of Mechanical Engineers (ASME) Class 1, 2, 3, CC, and MC components were conducted at Byron Station Unit 1 from March 26, 2005 through October 16, 2006. The majority of these activities were performed during the fourteenth refueling outage (B1R14)from September 11 through October 16, 2006.
The examinations were performed in compliance with the rules and regulations of ASME Section Xf, Division 1, Rules for Inseriice Inspection ofNuclear Power Plant Components, (app)icab~eedition 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 CJass 1 and 2 components and piping. This report also includes inspection results of components for Class 3 and Augmented Programs.
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 ((SI) Program Plan for Class 1, 2, and 3 components was developed in accordance with the requfrements and intent of Section XI Subsections IWA, )WB, IWC, IWD, IWE, IWF and IWL, 2001 Edition, through the 2003 Addenda.
In addition to the ASME Section XI requirements of examination, certain Nuclear Regulatory Commission (NRC) augmented ISI inspections were required. The Byron Station Unit 1 augmented examination requirements snelude:
a) Class 1 pressure boundary for leakage at nominal operating pressure, ~naccordance with NRC Generic Letter 88-05; b) Class 2 and 3 pressure boundary for leakage at nominal operating pressure, in accordance with NUREG 0737; c) Class 2 IWC-1220 exempted piping per Information Notice No. 79-19 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 ~WB,IWC, IWD, IWE, IWF, and $WL-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 IWA, IWB, IWC, IWD, IWE, IWF, and IWL of Section XI of the ASME Code.
For Class 1, 2, and certain non-class piping components, the requirements of Risk Informed Inservice Inspection (RI-ISI) are followed using EPRI TR1 12657 and Table 1 of ASME Code Case N-578-1.
1.2 Identification of Exempted comøonents 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 SectIon 1.0 Page 1 of 5
BYRON STATION UNIT 1 REFUELING OUTAGE 14 INSERVICE INSPECTION REPORT Table IWD-2500-1, 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-ISI program. With the adoption of RI-ISI, welds evaluated as Risk Category 6 or 7 are not required to be subject to examination.
1.3 Implementation of the ISI ProQram 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 ISI 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 afl 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-189, 1995 Revision. The NDE procedures were developed and certified in conformance with ASME Section V and XI, 2001 Edition through the 2003 Addenda, and the 1995 Edition with the 1996 Addenda as applicable.
AU ISI NDE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section XI, 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.
1.4 Second and Third 10-Year Insr~ectionIntervals The 14th fuel cycle for Unit 1 encompasses a time span of March 26, 2005 to October 16, 2006. Activities that occurred prior to January 16, 2006 were performed during the Second Inspection Interval. Activities that occurred on or after January 16, 2006 were performed during the Third Inspection Interval.
1.5 Sicjnificant Activities During Bi R14 During the refueling outage, the AHoy 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.
Section 1.0 Page 2 of 5
BYRON STATION UNIT 1 REFUELING OUTAGE 14 INSERVICE INSPECTION REPORT 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 14th 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 case is used for the implementation of the risk-informed program as described in relief request l3R-02.
N-578-1 Risk-Informed Requirements for Class 1, 2, or 3 Piping, MethodB.
Portions of the following cases were utilized as described in relief request 13R-08 for the full structural weld overlays applied to the pressurizer safe-end welds:
N-504-2 Alternative Rules for Repairof Classes 1, 2, and 3Austenitic Stainless Steel Piping.
N-638-1 Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW 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. Use of the following case was applicable during this time:
N-41 6-2 Alternative Pressure Test Requirement for Welded Repairs or Installation of Replacement Items by Welding, Class 1, 2, and 3 1.7 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANtI): J. Snyder, G. Feigel, J. Hendricks, and L. 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 foflowing 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 Section 1.0 Page 3 of 5
BYRON STATION UNIT 1 REFUELING OUTAGE 14 INSERVICE INSPECTiON REPORT System Pressure Test Summary Tests performed during the 2nd Inspection Interval Tests performed during the 3rd Inspection tnterval Component Support Examination Summary Component Snubber Test Summary 3.0 UNIT 1 EXAMINATION COMPLETION STATUS A summary table of the examination status of Class 1, 2, and 3 components is contained in Section 3.0.
4.0 FORM NIS-1 DATA SHEETS Welds, Bolts, Pumps, Valves, Supports, and Snubbers Pressure Tests 2nd Inspection Interval Pressure Tests 3rd Inspection Interval 5.0 FORM NIS-2 DATA SHEETS ASME Form NIS-2, Owners Report for Repairs or Replacements, were filed during the cycle for Unit 1. See Section 5.0 for the reports.
6.0 CONTAINMENT PSI PROGRAM Reportable conditions were identified for Class CC components during this fuel cycle.
The reporting requirements in 1 OCFR5O.55a (b)(2)(viii)(E) are applicable for this summary report. See Section 6.0 for the report on these conditions.
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, 1989 Edition.
Section V, Nondestructive Examination, 1995 Edition, with the 1996 Addenda.
Section V, Nondestructive Examination, 2001 Edition, through 2003 Addenda.
Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition (for 2~Inspection Interval pressure tests and repair/replacement activies).
Section 1.0 Page 4 of 5
BYRON STATION UNIT 1 REFUELING OUTAGE 14 INSERVICE INSPECTION REPORT Section Xl, Rules for Inservice Inspection of Nuclear Power Plant Components, 1995 Edition, 1996 Addenda (for Appendix VIII requirements).
Section Xl, Rules for InseMce Inspection ofNuclear PowerPlant Components, 2001 Edition, through 2003 Addenda (for 3id Inspection Interval).
7.3 American Nat~onaIStandards Institute I American Society for Nondestructive TestinQ 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 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.
Information Notice No. 79-19, Pipe Cracks in Stagnant Borated Water Systems at PWR Plants.
7.6 Electric Power Research Institute Material Reliability Program Primary System Piping Butt Weld Inspection and Evaluation Guideline (MAP-i 39) July 14, 2005.
Topical Report TR1 12657 Revision B-A, Revised Risk-Informed Inservice Inspection Procedure.
Section 1.0 Page 5 of 5
Section 2.0 Examination Summary Tables
1/5/2007 Exeión Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld / Component Listing SYSTEM:
Containment Spray System (CS)
Section XI
~omponent ID Line Number Relief Technical ~ode R~uI~~tuaI Results Description Requests Notes Coverage Exam Exam Comments R-A R1.20 1CSO2AA-1O/CO1 1CSO2AA-1O 13R-02 C5.11 100 VOL-E UT NRI Reducer - ElbOW 13T-O1 13T-02 OBS14-117 A-A R1.20 1CSO2AA-1O/C65 EJbow - Pipe OBS14-170 1CSO2AA-1O 13R-02 C5.11 13T-O1 131-02 100 VOL-E UT Nfl R-A R1.20 1CSO2AA-1O/C88 Elbow - Reducer OBS14-118 Root Geometry 3~o Intermfttent 1CSO2AA-10 13R-02 C5.11 13T-O1 13T-02 100 VOL-E UT GEOM A-A R1.20 1CSO6AA-6/C07 Pipe - Elbow OBS 14119 1CSO6AA-6 13R-02 C5.11 13T-O1 131-02 100 VOL-E UT NR1 A-A R120 1CSO6AA-6/C08 ElbOW - Pipe OBS14-120 1CSO6AA-6 13R-02 C5.11 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 1CSO6AB-6/C05 Elbow - Pipe OBS14-122 1CSO6AB-6 13R-02 C5.11 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 1CSO6AB-6/C06 Pipe - Pipe OBS14-123 1CSO6AB-6 13R-02 C5.11 13T-O1 13T-02 100
~
VOL-E UT NRI R-A R1.20 1CS1OAA-6/C06 Pipe - Elbow OBS14-168 1CS1OAA-6 13R-02 C511 (31-01 13T-02 100 VQL-E UT NRI A-A R1.20 1CS1OAA-6/C20 Elbow - Pipe OBS 14~169 1CS1OAA-6 13R-02 C5.11 13T-O1 13T-02 100 VOL-E UT NRI 1
1/5/2007 SYSTEM:
Exekn..
Byron Station UnIt 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing Chemical & Volume Control System (CV)
A-A R120 1CVO5B-8/C24 1CVO5B-8 13R-02 C5.11 100 VOL-E UT NRI Elbow - Pipe 13T-O1 13T-02 OBS 14171 A-A R1.20 1CVO5B-8/C25 Pipe-Tee OBS14-172 1CVO5B-8 13R-02 C5.11 13T-O1 131-02 100 VOL-E UT NRI A-A R120 1CVO5B-8/C26 Tee - Pipe OBS14-173 1CVO5B-8 13R-02 C5.11 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 1CVO8AA-41C03 Elbow - Pipe OBS14-124 1CVO8AA-4 13R-02 C5.21 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 1CVO8AA-41C17 Pipe - Tee OBS14-175 1CVO8AA-4 13R-02 C5.21 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 1CVO8BA-4/C09 Pipe - Elbow OBS14-178 1CVO8BA-4 13R-02 C5.21 13T-O1 13T-02 100 VOL-E UT NRI R-A R1.20 1CVO8BA-4/C21 Pipe-Tee OBS14-180 Root Geometry 3600 Intenii~llent.
1CVO8BA-4 13R-02 C5.21 13T-O1 i3T-02 100 VOL-E UT GEOM R-A R1.20 1CVO9A-41C02 Reducer - Tee OBS14-176 1CVO9A-4 13R-02 C5.21 131-01 13T-02 100 VOL-E UT NRI R-A R1.20 1CVO9A-41C03 Tee-Pipe OBS14-177 1CVO9A-4 13R-02 C5.21 13T-O1 13T-02 100 VOL-E UT NAI A-A R1.20 1CVO9A-41C07 Pipe - Elbow OBS 14181 Root Geometry36O~Intermittent.
1CVO9A-4 13R-02 C5.21 13T-O1 131-02 100 VOL-E UT GEOM 2
1/5/2007 Exekrn..
Byron Station Unft 1 B1R14 ISP Outage Report Detailed Inservice Inspection Weld / Component Listing SYSTEM:
Chemical & Volume Control System (CV)
Section XI Component~D Line Number Relief Technicifi Code Required Actual Results Cat Description Requests Notes Coverage Exam Exam Comments R*A R1.20 1CVA1A-6/C02 1CVA1A-6 13R-02 C5.11 100 VOL-E UT NRI Elbow-Pipe 131-01 13T-02 OBS14-174 A-A R1.11 OBS14-001 1CVA3AA-2/W-06 Pipe - Elbow 1CVA3AA-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NAI A-A R1.11 OBS14-002 1CVA3AA-2/W-07 Elbow - Pipe 1CVA3AA-2 13R-02 B940 131-01 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-003 1CVA3B-2PW-74 Pipe - Elbow 1CVA3B-2 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 Nfl A-A R1.11 OBS14-004 1CVA3B-2/W-75 Elbow - Pipe 1CVA3B-2 13R-02 B9.40 131-01 131-02 VT-2 VT-2 NRI A-A R1.11 OBS14-005 1CVA3B-2/W-76 Pipe - ElbOW 1CVA3B-2 13R-02 B9.40 l3T-O1 13T-02 VT-2 VT-2 NRI A-A Rill OBS14-006 1CVA3B-2/W-77 Elbow - Pipe 1CVA3B-2
~
13R-02 B9.40 131-01 13T-02 VT-2 VT-2
~
NRI R-A R1.11 OBS14-007 1CVA3B-2/W-84 Pipe - Elbow 1CVA3B-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-008 1CVA3B-ZW-85 Elbow - Pipe 1CVA3B-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 Nfl R-A R1.11 OBS14-009 1CVA5AA-2/W-04 Pipe-ElbOW 1CVA5AA-2 13R-02 B9.40 131-01 131-02 VT-2 VT-2 NRI A-A R1.11 OBS14-010 1CVA5AA-2/W-05 Elbow - Pipe 1CVA5AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI 3
1/5/2007 Exeión~
Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld / Component Listing SYSTEM: Chemical & Volume Control System (CV)
R-A R1.11 1CVA6AA-2/W-04 1CVA6AA-2 13R-02 B9.40 VT-2 VT-2 NRI Pipe - Elbow 13T-O1 13T-02 CBS14-011 R-A R1.11 OBS14-012 1CVA6AA-2/W-05 Elbow - Pipe 1CVA6AA-2 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 NRI A-A R1.11 OBS14-013 1CVA7AA-2/W-08 Pipe - Elbow 1CVA7AA-2 13R-02 B940 13T-O1 131-02 VT-2 VT-2 NRI fl-A R1.11 OBS14-014 1CVA7AA-2/W-09 Elbow - Pipe 1CVA7AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NAP 4
Exekn.
Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM:
A-A Al.11 1FWO3DA-16/CO1 1FWO3DA-16 13R-02 C5.51 97 VOL-E UT GEOM R1.18 Valve-Pipe 13T-O1 13T-02 OBS14-125 Root Geometry3600 Intermittent. Exam obstructed by adjacent branch connection.
A-A R1.11 1FWO3DA-16/C02 Ri.18 Pipe - Penetration OBS14-126 Root Geometry360~Intermittent 1FWO3DA-16 13R-02 C5.51 13T-O1 13T-02 100 VOL-E UT GEOM A-A R1.11 1FWO3DD-16/C14 R1.18 Pipe - Elbow OBS14-213 1FWO3DD-16 13R-02 C5.51 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.11 1FWO3DD-1&C15 R1.18 Elbow-Pipe OBS14-214 1FWO3DD-16 13R-02 C5.51 131-01 13T-02 100 VOL-E UT NRI
~
A-A R1.11 1FWO3DD-16/C16 R1.18 Pipe-Elbow OBS14-215 1FWO3DD-16 13R-02 C5.51 13T-O1 131-02 100 VOL-E UT NRI A-A R1.1l 1FWO3DD-1&C17 R1.18 Elbow-Pipe OBS14-216 1FWO3DD-16 13R-02 C5.51 131-01 13T-02 100 VOL-E UT NAP A-A R1.11 lFW03DD-16~C19.O1 R1.18 Pipe-Elbow OBS14-217 1FWO3DD-16 I3R-02 C5.51 131-01 I3T-02 100 VOL-E UT NRI A-A R1.11 1FWO3DD-16/C20.O1 R1.18 Elbow-Pipe OBS14-218 1FWO3DD-16 i3R-02 C5.51 13T-O1 131-02 100 VOL-E UT NRI A-A R1.11 1FW87CA-6/CO7A R1.18 Elbow-Pipe OBS14-127 1FW87CA-6 13R-02 C5.51 13T-01 131-02 100 VOL-E UT NAt R-A R1.11 1FW87CA-6/CO8A R1.18 Pipe-SOL OBS14-128 Spot mid-wall indication seen outside exam 1FW87CA-6 voume. One-sidede 13R-02 xam due to pipe C5.51 131-01 131-02 to sweep-o-le 92 VOL-E t configuration.
UT IND 1/5/2007 5
1/5/2007 Exelon Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM:
Main Steam System (MS)
Section XI component ID Line Number
Relief
- Technlc& code
!R~r~ Actual Results.
Description Requests Notes Coverage Exam Exam A-A R1.20 1MSO1AB-32.75/CO1.O1 1MSO1AB-32.75 13R-02 C5.51 100 VOL-E UT NAI Safe End - Elbow 13T-O1 131-02 OBS14-130 A-A R1.20 1MSO1AB-32.75/CO1A Nozzle - Safe End OBS14-131 1MSO1AB-32.75 13R-02 C5.51 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 1MSO1CD-30.251C01 Pipe - Valve OBS14-129 Root Geometry 3600 IntermIttent 1MSO1CD-30.25 13R-02 13T-O1 13T-02 100 VOL-E UT GEOM fl-A R1.20 1MSO7AB-28/C08 Pipe
- Elbow OBS14-183 1MSO7AB-28 13R-02 C5.51 13T-O1 13T-02 100 VOL-E UT NAt R-A Rl.20 1MSO7BB-28/CO1 Elbow - Pipe 088 14-182 1MSO7BB-28 13R-02 C5.51 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 1MSO7BB-281C12 Pipe - Cap OBS14-184 1MSO7BB-28 13R-02 C5.51 13T-O1 131-02 100 VOL-E UT NRI R-A R1.20 1MS13AA-81C08 Pipe - Valve OBS14-132 1MS13AA-8 13R-02 C5.51 13T-O1 13T-02 100 VOL-E UT NRI R-A R1.20 1MS13AA-81C09 Valve - Elbow OBS 14133 Root Geometry3~°Intermittent IMS13AA-8 13R-02
~
C5.51 13T-O1 13T-02 100 VOL-E UT GEOM fl-A R1.20 1MS13AA-81C10 Elbow - Pipe OBS14-134 1MS13AA-8 13R-02 C5.51 13T-O1 13T-02 100 VOL-E UT NAt R-A R1.20 1MS13AA-8/C11 Pipe - Reducer OBS 14135 1MS13AA-8 13R-02 C5.51 131-01 131-02 100 VOL-E UT NRI R-A R1.20 1MS13AA-8/C12 Reducer - Valve OBS14-136 1MS13AA-8 13R-02 C5.51 131-01 131-02 100 VOL-E UT NRI 6
1/512007 Exekn..
Byron Station UnIt 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM:
Pressurizer (PZR)
Section XI ComponentID Line Number Relief Technical Code Required Actual Results Cat Description
Requests Notes Coverage Exam Exam
-~
Comments B-D B3.11O 1RY-O1-S/PN-O1 1RY-O1-S Surge Nozzle OBS14-197 Exam limited by nozzle configuration and heater penetrations.
B-D 83.120 1 RY-Ol -S/PN-O1-NIA 1 RY-Ol -S Surge Nozzle Inner Radius 13R-03 40 VOL UT NRI 13R-03 VOL UT NRI OBS14-198 B-D B3.11O 1RV-O1-SIPN-02 1RY-O1-S 13R-12 77 VOL UT NR~
Spray Nozzle OBS14-199 Scanning limited by nozzle configuration B-D B3.120 1RY-O1-S/PN-02-NIR 1RY-O1-S VOL UT NRI Spray Nozzle Inner Radius OBS14-200 B-D B3.11O 1RY-O1-S/PN-03 1RY-O1-S 13R-12 77 VOL UT NAI Safety Nozzle OBS14-201 Scanning limited by nozzle configuration B-D B3.120 1RY-.O1-S/PN-03-NIR 1RY-O1-S VOL UT NRI Safety Nozzle Inner Radius OBS14-202 B-D B3.11O 1RY-O1-S/PN-05 1RY-O1-S 13R-12 68 VOL UT NAI Relief Nozzle OBS14-203 Scanning limited by nozzle configuration B-D B3.120 1RY-O1-S/PN-05-NJR 1RY-O1-S VOL UT Nfl Relief Nozzle Inner Radius OBS14-204 B-D B3.11O 1RY-O1-S/PN-06 1RY-O1-S 13R-12 77 VOL LiT NRI Relief Nozzle OBS14-205 Scanning Iimfted by nozzle configuration B-D B3.120 1RY-O1-S/PN-06-NIR 1RY-01-S VOL UT NAI Relief Nozzle Inner Radius OBS14-206 7
1/5/2007 Exek!in_,
Byron Station Unit 1 B1R14 ~SIOutage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM:
A-A R1.20 1RC13AA-2/W-O1 1RC13AA-2 13R-02 B9.40 VT-2 VT-2 NRI SOL - Pipe 131-0 1 13T-02 OBS14-015 R-A A1.20 OBS14-016 1RC13AA-2/W-02.O1 Pipe-Tee 1RC13AA-2 13R-02 89.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.20 OBS 14017 1RC13AA-2/W-03 Tee - Reducer 1RC13AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NR~
A-A R1.20 OBS14-018 1RC13AA-21W-04 Tee-Pipe 1RC13AA-2 13R-02 B9.40 131-01 13T-02 11-2 VT-2 Nfl A-A fl1.20 CBS14-019 1RC13AA-2/W-05 Pipe-Valve 1RC13AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A Ri.20 OBS14-020 1RC13AB-2/W-O1 SOL - Pipe 1RC13AB-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.20 OBS14-021 1RC13AB-2/W-09 Pipe - Valve 1RC13AB-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI A-A R1,20 OBS14-022 1RC13AC-2/W-O1 SOL-Pipe 1RC13AC-2 13R-02
~
B9.40 131-01 13T-02 VT-2 VT-2 NAI A-A R1.20 OBS14-023 1RC13AD-2,W-O1 SOL - Pipe
~
1RC13AD-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-024 1RC14AA-2!W-02 Pipe - Elbow 1RC14AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NAt R-A R1.11 OBS14-025 1RC14AA-2/W-03 Elbow - Pipe 1RC14AA-2 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 Nfl 8
1/5/2007 Exek,n..
Byron Stallon Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld / Component Listing SYSTEM: Reactor Coolant System (RC)
Section XI ComponentID Line Number
-Reflef Technical Code Requfred Actual Results DescripUon Requests Notes Coverage Exam Exam Comments R-A R1.11 1RC14AA-2/W-03A 1RC14AA-2 13R-02 B9.40 VT-2 VT-2 NRI Pipe - Tee 13T-O1 13T-02 OBS14-026 A-A Rill OBS14-027 1RC14AA-2/W-03B Tee - Reducer 1RC14AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.11 OBS14-028 1RC14AA-2/W-03C Tee - Pipe 1RC14AA-2 13fl-02 89.40 13T-O1 13T-02 VT-2 VT-2 NRI fl-A R1.11 OBS14-029 1RC14AA-2/W-04 Pipe - Elbow 1RC14AA-2 13R-02 B940 13T-O1 13T02 VT-2 VT-2 NRI A-A R1.11 OBS14-030 1RC14AA-2/W-05 Elbow - Pipe 1RC14AA-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NAI A-A R1.11 OBS14-031 1RC14AA-21W-06 Pipe - Valve 1RC14AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.11 OBS14-032 1RC14AA-2PW-07 Valve - Pipe 1RC14AA-2 13R-02 B9AO 13T-O1 131-02 VT-2 VT-2 NAt R-A Rill OBS14-033 1RC14AA-2/W-08 Pipe - Tee 1RC14AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NAt R-A R1.11 OBS14-034 1RC14AA-2/W-09 Tee - Reducer 1RC14AA-2 13R-02 B9.40 13T-01 13T-02 VT-2 VT-2 NRI R-A R1.11 OBS14-035 1RC14AA-2iW-1O Reducer - Pipe 1RC14AA-2 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 NRI A-A flu OBS14-036 1RC14AA-2/W-11 Pipe
- Valve 1RC14AA-2 13R-02 B9.40 13T-01 13T-02 VT-2 VT-2 NRI 9
1/5/2007 Exeln Byron Station UnIt 1 B1R14 IS! Outage Report Detailed Inservice Inspection W&d I Component Listing SYSTEM:
Section XI Component ID Line Number Relief Technical Code RequiTed Actual Results Descrlpflon Requests Notes Coverage Exam Exam Comments A-A flu 1RC14AA-2/W-12 1RC14AA-2 13R-02 B9.40 VT-2 VT-2 NAI Pipe - Coupling 13T-O1 13T-02 OBS14-037 R-A R1.11 OBS14-038 1RCt4AA-2,W-13 Coupling - Pipe 1RC14AA-2 13R-02 B9.40 13T-Ol 131-02 VT-2 VT-2 NRI R-A R1.11 OBS14-039 1RC14AB-2/W-07 Coupling - Pipe 1RC14AB-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NAt A-A Rl.11 OBS14-040 1RC14AB-2/W-08 Pipe - Valve 1RC14AB-2 13R-02 B940 13T-O1 13T-02 VT-2 VT-2 NR~
A-A R1.11 OBS14-041 1RC14AB-2JW-09 Valve - Pipe 1RC14AB-2 13R-02 B940 13T01 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-042 1RC14AB-2/W-1O Pipe - Tee 1RC14AB-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-043 1RC14AB-2/W-11 Tee - Reducer 1RC14AB-2 13R-02 B940 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-044 1RC14AC-2/W-08 Pipe - Valve 1RC14AC-2 13R-02
~
B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-045 1RC14AD-2/W-08 Pipe - Valve 1RC14AD-2 13R-02 89.40 13T-O1 131-02 VT-2 VT-2 NRI R-A Ri.11 OBS 14.046 1RC14AD-2PW-09 Valve-Pipe 1RC14AD-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-047 1RC14AD-2~W-1O Pipe - Tee 1RC14AD-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI 10
1/5/2007 Exekrn..
Byron Station UnIt 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM: Reactor Coolant System (RC)
A-A R1.11 1RC14AD-2/W-11 1RC14AD-2 13R-02 B9.40 VT-2 VT-2 NRI Tee - Reducer 13T-O1 13T-02 OBS14-048 R-A R1.11 OBS14-049 1RC14AD-21W-12 Tee - Pipe 1RC14AD-2 13R-02 B940 13T-O1 13T-02 VT-2 VT-2 NRI A-A Rill OBS14-050 1RC14AD-21W-13 Pipe-Valve 1RC14AD2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI R-A R1.11 OBS14-051 1RC16AA-21W-02 Pipe - Valve 1RC16AA-2 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS14-052 1RC16AA-21W-03 Valve - Pipe 1RC16AA-2 13R-02 B9.40 13T-01 13T-02 VF-2 VT-2 NRI A-A R1.11 OBS14-053 1RC16AA-2/W-04 Pipe - ElbOW 1RC16AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.11 OBS14-054 1RC16AA-2/W-05 ElbOW - Pipe 1RC16AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2
~
NRI A-A R1.tl OBS 14055 1RC16AA-2/W-06 Pipe - Elbow 1RC16AA-2 13R-02 B9A4) 13T-01 131-02 VT-2 VT-2 NRI A-A R1.20 OBS14-056 1RC16AA-2/W-07 Elbow - Pipe 1RC16AA-2 13R-02 B9.40 13T-Ol 131-02 VT-2 VT-2 NRI R-A R1.20 OBS14-057 1RC16AA-2/W-08 Pipe - SOL 1RC16AA-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.11 CBS 14058 1IRC16AB-2/W-02 Pipe - Elbow 1RC16AB-2 13R-02 B9.40 13T-01 J3T-02 VT-2 VT-2 Nfl
- 11
1/5/2007 Exekin Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld / Component Listing SYSTEM:
R-A R1.11 1RC21AA-8/J07 1RC21AA-8 13R-02 B9.1l 100 VOL-E UT NRI Pipe - Elbow 13T-O1 13T-02 OBS14-137 A-A R1.11 OBS14-138 1RC21AA-81J08 Elbow - Pipe 1RC21AA-8 13R-02 B9.11 13T-01 13T-02 100 VOL-E UT NAP A-A R1.11 OBS14-139 1RC21AA-81J09 Pipe - Elbow 1RC21AA-8 13R-02 89.11 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.11 OBS14-140 1RC21AA-8/J1O Elbow - Pipe 1RC21AA-8 13R-02 B9.11 13T-O1 131-02 100 VOL-E UT NAI A-A R1.20 OBS14-141 1RC21AA-8/J11 Pipe - Pipe 1RC21AA-8 13R-02 B9.11 13T-O1 131-02 100 VOL-E UT NRI R-A R1.20 OBS14-059 1RC22AA-1.5/W-O1 Reducer - Coupling 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.20 OBS14-060 1RC22AA-1.51W-02 Coupling - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 NRI A-A R1.20 OBS14-061 1RC22AA-1.51W-03 Pipe - Elbow 1RC22AA-1.5 13R-02 B9.40 131-01 131-02 VT-2 VT-2 NRI A-A R1.20 OBS14-062 1RC22AA-1.&W-04 Elbow - Pipe 1RC22AA-t5 13R-02 89.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.20 OBS14-063 1RC22AA-1.5iW-05 Pipe - Elbow 1RC22AA-1.5 13R-02 B9.40 13T-O1 131-02 VT-2
~
VT-2 NRI R-A R1.20 OBS14-064 1RC22AA-1.SW-06 Elbow - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 NRI 12
1/5/2007 Exel~n_
Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM:
Section XI Component ID Line Number Relief Technical Code Required Actual Results
Description Requests Notes Coverage Exam Exam Comments R-A R1.20 1RC22AA-1.51W-07 1RC22AA-1.5 13R-02 B9.40 VT-2 VT-2 NAI Pipe - Elbow 13T-01 13T-02 OBS14-065 A-A R1.20 OBS14-066 1RC22AA-1.51W-08 Elbow - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.20 OBS14-067 1RC22AA-1.5/W-09 Pipe - ElbOW 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NAt A-A R1.20 OBS14-068 1RC22AA-1.5,W-1O ElbOW - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 Nfl A-A R1.20 O~14-069 1RC22AA-1.5/W-11 Pipe - Elbow 1RC22AA-1.5 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NAP R-A R1.20 OBS14-070 1RC22AA-1.51W-12 Elbow-Pipe 1RC22AA-1.5 13R-02 89.40 13T-01 13T-02 VT-2 VT-2 NRI A-A R1.20 OBS14-071 1RC22AA-1.51W-13.O1 Pipe-Valve 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2
~
NAt R-A R1.20 OBS 14072 1RC22AA-1.5/W-14.O1 Vatve - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.20 OBS14-073 1RC22AA-1.51W-15.O1 Pipe - Elbow 1RC22AA-1.5 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 NRI R-A R1.20 OBS14-074 1RC22AA-1.5,W-16.O1 Elbow - Pipe 1RC22AA-1.5 13R-02 B9.40 137-01 13T-02 VT-2 VT-2 NAI R-A R1.20 OBS14-075 1RC22AA-1.5/W-17 Pipe - Coupling 1RC22AA-1.5 13R-02
~
B9.40 131-01 13T-02 VT-2 VT-2 NRI 13
1/5/2007 Exekn.
Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection W&d I Component Listing SYSTEM:
Section XI ComponentID Line Number Relief Technical Code Required Actual Results eat.
- Descrlption Requests Notes Coverage Exam Exam Comments A-A R1.20 1RC22AA-1.5/W-18 1RC22AA-1.5 13R-02 B9.40 VT-2 VT-2 NRI Coupling - Pipe 13T-O1 13T-02 OBS14-076 R-A R1.20 OBS14-077 1RC22AA-1.&W-19 Pipe - Flange 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.20 OBS14-078 1RC22AA-1.51W-20 Flange - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NAP A-A R1.20 OBS14-079 1RC22AA-1.5/W-21 Pipe - Tee 1RC22AA-1.5 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NRI A-A R1.20 OBS14-080 1RC22AA-1.5/W-22 Tee - Reducer 1RC22AA-1.5 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 NRI R-A R1.20 OBS14-081 1RC22AA-1.5/W-23 Tee - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.20 OBS14-082 1RC22AA-1.5/W-24 Pipe - Tee 1RC22AA-1.5 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt R-A R1.20 OBS14-083 1RC22AA-15/W-25 Tee - Reducer 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.20 OBS14-084 1RC22AA-1.5dW-26 Tee - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.20 1RC22AA-1.5/W-27 1RC22AA-15 13A-02 B9.40 VT-2 VT-2 NRI Pipe - Valve 13T-O1 13T-02 OBS14-085 A-A R1.20 1RC22AA-1.5/W-28 1RC22AA-1.5 Valve - Pipe 13R-02 B9.40 VT-2 VT-2 Nfl 13T-O1 13T-02 OBS14-086 14
1/5/2007 Exeh~n Byron Station Unit 1 Bi R14 ISI Outage Report Detailed Inservice Inspection Weld / Component Listing SYSTEM:
Section XI Component ID
- Line Number Relief Technical Code Required Actual Results Description Requests Notes Coverage Exam Exam Comments R-A R1.20 1RC22AA-1.5/W-29 1RC22AA-1.5 13R-02 B9.40 VT-2 VT-2 NRI Pipe - Elbow 13T-O1 13T-02 OBS14-087 A-A R1.20 OBS14-088 1RC22AA-1.5/W-30 Elbow - Pipe 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 Nfl R-A R1.20 OBS14-089 1RC22AA-1.5/W-31 Pipe* Elbow 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NAP R-A Ri.20 OBS14-090 1 RC22AA-1.5/W-32 Elbow - Pipe 1 RC22AA-1.5 13R-02 B9.40 131-01 13T-02 VT-2 VT-2 Nfl R-A R1.20 OBS14-091 1RC22AA-1.5/W-33 Pipe-WOL 1RC22AA-1.5 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.20 OBS 14144 1RC24AA-41J06 Pipe - Elbow 1RC24AA-4 13R-02 B9.11 131-01 13T-02 100 VOL-E UT NRI R-A R1.20 OBS14-145 1RC24AA-4/J07 Elbow - Pipe 1RC24AA-4 13R-02 B9.11 131-01 13T-02 100 VOL-E UT NRI R-A R1.20 OBS14-146 1RC24AA-41J09 Pipe - Elbow 1RC24AA-4 13R-02 B9.11 13T-O1 13T-02 100 VOL-E UT NRI A-A R1.20 OBS14-147 1RC24AA-4/J1O Elbow - Pipe 1RC24AA-4 13R-02 B9.11 13T-O1 13T-02 100 VOL-E UT NRI 15
1/5/2007 Exekrn..
Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM:
Residual Heat Removal System (RH)
Section XI Component ID
-Line Number Relief Technical Code Required Actual Results Deactiption Requests Notes Coverage Exam Exam Comments A-A R1.20 1RHO1BA-12/C18 1RHO1BA-12 131R-02 C5.11 100 VOL-E UT NAI Pipe - Elbow 13T-O1 13T-02 OBS14-148 A-A R1.20 1RHO1BA-12/C21 1RHO1BA-12 Elbow - Pipe OBS14-149 13R-02 C5.11 100 VOL-E UT NRI 13T-O1 13T-02 R-A R1.20 1RHO2AA-8/C02 1RHO2AA-8 Elbow - Elbow OBS14-150 13R-02 C5.11 100 VOL-E UT NAt 131-01 13T-02 A-A R1.20 1RHO2AA-8/C06 1RHO2AA-8 Elbow - Pipe OBS14-151 13R-02 C5.11 100 VOL-E UT NRI 13T-O1 13T02 A-A R1.20 1RHO2AA-81C07 1RHO2AA-8 Pipe - Elbow OBS14-152 13R-02 C5.11 100 VOL-E UT NRI 13T-O1 13T-02 A-A R1.20 1RHO2AA-8/C09 1RHO2AA-8 Pipe - Elbow OBS14-154 13R-02 C5.11 100 VOL-E UT NAI 13T-O1 13T-02 A-A R1.20 1RHO2AA-8/C1O 1RHO2AA-8 Elbow - Pipe OBS14-153 13R-02 C5.11 100 VOL-E UT NRI 13T-O1 13T-02 C-A C1.1O 1RH-02-AB/RHEC-01 1RH-02-AB Shell - Flange OBS14-155 ID geometryseen 3600 intermittent. Dividerpate welds seen.
no change in size. IRef: RIR B1R14-UT-O1O.
13R-13 50 VOL UT GEOM 50 VOL UT IND Acceptable planar indications previously reported in Bi R08 recorded and C-A C1.20 1RH-02-AB/RHEC-02 1RH-02-AB SheU - Head OBS14-156 ID geometry seen36O~intermittent. Divider plate welds seen.
100 VOL UT GEOM 100 UT IND Porosity indications previouslyreported seen and recorded. Ret: AIR R-A R1.20 1RH12A-8/CO1 1RH12A-8 Tee-Pipe OBS14-188 Tee to pipe configuration prevented 100% access to weld on u 13R-02 C5.11 91 VOL-E UT NRJ 13T-O1 13T-02 pstream side.
16
1/5/2007 Exekrn Byron Station UnIt 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM:
SecUon XI Component ID Line Number Reief Technical Code Required Actual Results cai.
Description Requests Notes Coverage Exam Exam comments R-A R1.11 1RY18A-21W-05A 1RY18A-2 13R-02 B9.40 VT-2 VT-2 NRI Valve - Pipe 131-01 13T-02 OBS14-092 A-A R1.11 OBS14-093 1RY18A-21W-06 Pipe - Elbow 1RY18A-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 Nfl A-A R1.11 CBS14-094 1RY18A-2/W-07 Elbow - Pipe 1RY18A-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI R-A R1.11 OBS14-095 1RV18A-2iW-08 Pipe - EJbow 1RY18A-2 13R-02 B940 13T-01 13T-02 VT-2 VT-2 NRI A-A R1.11 OSS14-096 1RY18A-21W-09 Elbow - Pipe 1RY18A-2 13R-02 B9.40 13T-O1 13T-02 VT-2 VT-2 NRI A-A R1.11 OBS 14097 1RY18A-21W-1O Pipe - WOL 1RY18A-2 13R-02 B9.40 13T-O1 131-02 VT-2 VT-2 NRI 17
1/5/2007 ExeI~n Byron Station UnIt 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM:
Section XI Component ID Line Number Relief Technical Code Required Actual Results Description Requests Notes Coverage Exam Exam Comments B-B B2.40 1RC-01-BB/SGW-01 1RC-01-BB 100 VOL UT NRI Tubesheet - Primary Head OBS14-190 18
1/5/2007 Exekrn..
Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection WeJd I Component Listing SYSTEM: Safety Injection System (SI)
Section Xl Component ID
~LineNumber Relief Technical Code Required Actual Results Cat DescrIption
Requests Notes coverage Exam
Exam Comments A-A R1.20 1SIO1B-24/C03 1SIO1B-24 13R-02 C5.11 100 VOL-E UT NAt Elbow - Pipe 13T-01 13T-02 OBS14-194 A-A R1.20 CBS14-195 1SIO1B-24/C04 Pipe - Pipe lSlOlB-24 l3R-02 C5.11 13T-01 13T-02 100 VOL-E UT NAI A-A A1.20 OBS14-196 1SIO1B-241C05 Pipe - Elbow 1SIO1B-24 13R-02 C5.11 13T-01 l3T-02 100 VOL-E UT NAP A-A A1.11 CBS14-098 1SIO8GC-1.5/W-01 Reducer - Coupling 1SIO8GC-1.5 13A-02 B940 l3T-01 13T-02 VT-2 VT-2 NAI A-A R1.11 OBS14-099 1SIO8GC-1.5/W-02 Coupling - Pipe 1SIO8GC-1.5 13R-02 B9.40 l3T-01 l3T-02 VT-2 VT-2 NAt R-A A1.11 OBS14-100 1SIO8GC-1.5/W-03 Pipe - Elbow 1SIO8GC-1.5 13R-02 B9.40 13T-01 13T-02 VT-2 VT-2 NAP A-A R1.11 CBS14-101 1SIO8GC-1.51W-04 Elbow - Pipe 1SIO8GC-1.5 13A-02 B9.40 13T-01 13T-02 VT-2 VT-2 NAP A-A RL11 CBS14-102 1SIO8GC-1.51W-05 Pipe - Reducer 1SIO8GC-1.5 13A-02 B9.40 13T-01 I3T-02 VT-2 VT-2 NRI A-A A1.11 OBS14-103 1SIO8HA-2/W-01 Reducer - Pipe 1SIO8HA-2 l3R-02 B9.40 13T-01 131-02 VT-2 VT-2 NAt A-A R1.11 OBS14-104 15108i-IA-2/W-02 Pipe - Flange 1SIO8HA-2 13A-02 B9.40 l3T-01 13T-02 VT-2 VT-2 NAI A-A A1.11 OBS14-105 1S1081-IA-2/W-03 Flange - Pipe 1SIO8HA-2 l3R-02 B9.40 13T-01 13T-02 VT-2 VT-2 NAP 19
1/5/2007 Exekrn..
Byron Station Unft 1 B1R14 1St Outage Report Detailed Inservice Inspection Weld I Component Listing 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 A1.11 1SPO8HA-2iW-04 1SPO8HA-2 13A-02 89.40 VT-2 VT-2 NAP Pipe - Reducer 13T-01 13T-02 OBS14-106 A-A A1.11 CBS14-107 1SIO8JA-1.5/W-06 Pipe - Valve 1SIO8JA-1.5 l3A-02 89.40 131-01 131-02 VT-2 VT-2 NAP A-A R1.11 CBS14-108 1SIO8JA-151W-07 Valve - Pipe 1SIO8JA-1.5 13A-02 89.40 131-01 13T-02 VT-2 VT-2 NAI A-A A1.11 OBS 14109 lSlQ8.jA-1.5/W-08 Pipe - Coupling 1SIO8JA-1.5 13A-02 B9.40 131-01 l3T-02 VT-2 VT-2 NAI A-A A1.11 OBS14-110 1SIO8JA-1.51W-09 Coupling - Pipe 1SIO8JA-1.5 13A-02 B9.40 l3T-01 l3T-02 VT-2 VT-2 NAP A-A R1.11 08514-111 1SIO8JA-1.51W-10 Pipe - Flange 1SIO8JA-1.5 13A-02 B9.40 13T-01 (31-02 VT-2
~
VT-2 NAt A-A A1.11 CBS14-112 1SIO8JA-1.5,W-11 Flange - Pipe 1SIO8JA-1.5 13A-02 89.40 131-01 131-02 VT-2 VT-2 NAI A-A A1.11 OBS 14113 1SIO8JA-1.51W-12 Pipe - Elbow 1SIO8JA-1.5 13A-02 B9.40 (31-01 13T-02 VT-2 VT-2 NAP A-A A1.11 CBS14-114 1S108.JA-1.5/W-13 Elbow - Pipe
~
1SIO8JA-1.5 13A-02 B9.40 131-01 131-02 VT-2 VT-2 NAI A-A A1.11 CBS 14115 1SIO8JA-1.5/W-14 Pipe - Elbow 1SIOSJA-1.5 13A-02 B9.40 131-01 13T-02 VT-2 VT-2 NAt A-A A1.11 CBS14-116 1SIO8JA-1.5/W-15 Elbow - Pipe 1SIO8JA-1.5 t3A-02 B9.40 131-01 131-02 VT-2 VT-2 NAI 20
1/512007 Exekn Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing SYSTEM: Safety Injection System (SI)
Section XI Component ID LIne Number Relief Technical Code Required Actual Results
~~Description n
Requests Notes Coverage Exam Exam Comments NA ECCS 1SIO9BA-10/J13 1SIO9BA-10 100 VOL UT NAt Pipe - Elbow CBS14-191 NA ECCS 1SIO9BA-10/J14 1SIO9BA-10 100 VOL UT NRI Elbow - Pipe CBS14-192 21
1/512007 Byron Station Unft 1 B1R14 ISI Outage Report Detailed Inservice Inspection Bolts, Pumps, and Valves Listing SYSTEM:
NA PFB-AY VT-i NAI B-G-2 B7.50 1 AYO3BB-6/FLG 1-12 Piping Flange Bolting CBS 14207 Examination of replaced valve due to maintenance disassembly B-M-2 B1250 1AY8O1OB/INT SUAF Valve Body Interior VT-3 NAI CBS14-208 Examination of replaced valve due to maintenance disassembly 1
1/5/2007 Byron Station Unit 1 B1R14 1St Outage Report Detailed lnservice Inspection Bolts, Pumps, and Valves Listing SYSTEM:
Safety Injection System (SI)
B-G-2 B7.70 1S18818B/BLT 1-16 NA VT-i NAI Valve Studs, Nuts, Bushings, and Washers CBS14-209 Examination due to maintenance dissassembly B-M-2 812.50 1S18818B/INT SURF VT-3 NAI Valve Body Interior CBS14-210 Examination due maintenance disassembly 2
1/5/2007 Exekin Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing (PSI)
SYSTEM:
N/A N/A 1RYO1C-4/JOiS 1AYO1C-4 13A-08 100 VOL UT NAt Reducer - Safe End Overlay Baseline exam for full structural weld overlay.
N/A N/A 1AY-01-S/PN-01-F1S 1RY-Oi-S 13A-08 VOL UT (ND Surge Nozzle - Safe End Overlay Baseline exam of full structural weld overlay. Laminar Indications, accepted per 81 Ri 4PN-01 -SW1-EVAL-Ol. 98.57% coverage in clrc direction and 97.35% In axial direction.
N/A N/A 1AY-Oi-S/PN-02-F2S iRY-01-S 13A-08 100 VOL UT NAt Spray Nozzle Safe-End Overlay Baseline exam of full structural weld overlay.
N/A N/A 1AY-Oi-S/PN-03-F3S 1RY-Oi-S t3R-08 VOL UT (ND Relief Nozzle Safe-End Overlay VOL UT (ND Baseline exam for full structural weld overlay. 3 Laminar indications, accept. 3 Planar indications in and out of weld area 2 rejected per Bi Al4-PN-03-SW3-EVAL-01. Repairexam.
1 Acceptable planar and 3 laminar indications remain outside of repair area. 99.64%
coverage in circ direction and 98.29% in axial direction.
N/A N/A 1RV-01-S/PN-04-F4S 1RY-01-S I3R-08 VOL UT IND Relief Nozzle Safe-End Overlay VOL UT IND Baseline exam for full structural weld overlay. 2 Planar Indications in and out of weld area 1 rejected per 81 R14-PN-04-SW4-EVAL-01.
Repair exam.
1 Laminar and 1 Planar indications in and out of weld area Acceptable per B1A14-PN-04-SW4-EVAL-01-Rl. 100%
coverage in circ direction and 98.16% in axial direction.
N/A N/A 1AY-01-S/PN-05-F5S 1RY-01-S 13A-08 100 VOL UT NRI Relief Nozzle Safe-End Overlay Baseline exam for full structural weld overlay.
N/A N/A 1RY-0l-S/PN-06-F6S 1AV-01-S 13A-08 VOL UT IND Relief Nozzle Sate-End Overlay VOL UT NRI Baseline exam for full structural weld overlay. Baseline exam for Nozzle to Safe-End weld. 9 laminar Indications, accept. 7 Planar indications rejected per Bi R14-PN-06-SW6-EVAL-01. Repair exam. No recordable indications.
97.27% coverage In ci~tdirection and 92.04% in axial direction.
N/A N/A 1RYO2A-6/JO1S 1AVO2A-6 13R-08 100 VOL UT NAI Safe End - Elbow Overlay Baseline exam for full structural weld overlay.
N/A N/A 1AYO3AA-6/JO1S 1RYO3AA-6 13R-08 100 VOL UT NRI Safe End - Elbow Overlay Baseline exam for full structural weld overlay.
N/A N/A 1RYO3AB-6/JO1S 1RYO3AB-6 l3R-08 100 VOL UT NAI Safe End - Elbow Overlay Baseline exam for full structural weld overlay.
N/A N/A 1AYO3AC-&JO1S 1RYO3AC-6 13A-08 VOL UT IND Safe End - Elbow Overlay VOL UT NAP Baseline exam for full structural weld overlay.
1 assumed planar rejected per 81 A14-PN-06-SW6-EVAL-Oi.
Repair exam. Norecordable Indications.
99.80% coverage In circ directionand 98.83% in axial direction.
N/A N/A 1AY11A-14/JO1AS 1AY11A-14 l3R-08 VOL UT (ND Safe End - Pipe Overlay Baseline exam of full structural weld overlay. Laminar Indications, accepted per Bi R14-PN-01-SW1-EVAL-01. 99.29% coverage in circ direction and 98.59% In axial direction.
Page 1-1 1/5/2007
1/5/2007 Exekin..
Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Weld I Component Listing (PSI)
SYSTEM: Safety Injection System (SI)
NA NA 1SI18FB-2/W-01.01 1SI18FB-2 l3A-02 B9.40 100 SURF PT NRI Valve-Pipe l3T-01 13T-02 Baseline exam for 1S18819B valve replacement. WO 00908949-14 FW-956.
NA NA 1SI18FB-2/W-02.01 1SI18FB-2 l3A-02 Pipe - Elbow Baseline exam for iSl88i 9B valve replacement. WO 00908949-01 FW-i.
B9.40 13T-01 131-02 100 SURF PT NAI NA NA 1SI18FC-2/W-01.03 lSli8FC-2 13R-02 Valve - Pipe Baseline exam for 1S18819C valve replacement. WO 00908951-09 FW-3.
89.40 13T-01 13T-02 100 SURF PT NAt NA NA 1SI18FC-2/W-02.03 1SI18FC-2 13A-02 Pipe - Elbow Baseline exam for iSl88i9C valve replacement. WC 00908951-01 FW-i. l/i6~
89.40 131-01 131-02 Al, acceptable.
100 SURF PT RI Page 1-2 1/5/2007
115(2007 Exek)n.
Byron Station UnIt 1 B1R14 ISI Outage Report Detailed Inservice Inspection Bolts, Pumps, and Valves Listing (PSI)
SYSTEM: Reactor Coolant System (RY)
B-G-2 B7.50 1RYO3BB-6/FLG 1-12 NA PFB-RY VT-i NRI Piping Flange Bolting Baseline exam for 1 RYBO1 OB replacement Page 1-1 1/5/2007
Exelon Components I Examinations OUTAGE INSPECTION
SUMMARY
Byron Unit 1 B1R14 C7.50 C7.70 Pumps, Pressure Retaining Boundary Chemical & Volume Control:
1CVOl PA 1CVOl PB CV-2-1 CV-2-2 Valves, Pressure Retaining Boundary Chemical and Volume Control:
CV-2-1 CV-2-2 x
x x
x SYSTEM:
Pressure Tests, All Systems
~
111 ~
,NTERVAL:
PERIOD:
Second Third
~
~
~
~
~*t~*~
~
CLASS 2 COMPONENTS C7.30 Piping, Pressure Retaining Boundary Chemical & Volume Control:
CV-2-1 X
CV-2-2 X
Process Sampling:
PS-2-1 X
2 P5-2-2 X
2 Steam Generator Blowdown sb~
x 1
Refer to the System Pressure Test Summary for Subsystem Descriptions.
2 Pneumatic test is conducted normal operating pressure, and is not a hydro test.
Process Sampling:
P5-2-i PS-2-2 Steam Generator Blowdown SD-2-1 x
x x
2 2
Page 1 of 1
Exelon Byron Unit 1 Components I Examinations OUTAGE INSPECTION
SUMMARY
B1R14
~Y~ItM:
II~I~I1vRL:
rtrlluu:
Pressure Tests, All S stems Third First CLASS 1 COMPONENTS B15.1O Reactor Vessel Pressure Retaining Boundry X
1 CLASS 2 COMPONENTS C2.33 Nozzle-to-Shell (or Head) When Inside of Vessel is Inaccessible 1RHO2AA RH-2-l X
1RHO2AB RH-2-2 X
C7.lO Pressure Retaining Components:
Auxiliary Feedwater:
AF-2-l X
AF-2-2 X
Containment Spray:
CS-2-l X
CS-2-2 X
Chemical & Volume Control:
CV-2-3 X
3 CV-2-4 X
CV-2-5 X
CV-2-6 X
CV-2-7 X
CV-2-8 X
CV-2-9 X
CV-2-lO X
4 Fuel Pool Cooling:
FC-2-l X
Fire Protection:
FP-2-l X
Feedwater:
FW-2-l X
FW-2-2 X
Main Steam:
MS-2-l X
MS-2-2 X
Off Gas:
OG-2-l X
Primary Containment:
PC-2-1 X
Page 1 of 2
Exelon Byron Unit 1 Components I Examinations B 1 R14 OUTAGE INSPECTION
SUMMARY
SYSTEM:
INTERVAL:
PERIOD:
Pressure Tests, All S stems Third First EXAMINA C7.lO Process Sampling:
(contd, PS-2-3 PS-2-4 X
PS-2-5 X
PS-2-6 X
Reactor Coolant:
RC-2-i X
Residual Heat Removal:
RH-2-l X
RH-2-2 X
RH-2-3 X
RH-2-4 X
RH-2-5 X
RH-2--6 X
Safety Injection:
51-2-1 x
51-2-2 X
S(-2-3 x
S1-2-5 X
Sl-2-6 x
SI-2-7 x
Sl-2-8 x
Service Water:
SX-2-1 X
SX-2-2 X
1 The ASME Class 1 Pressure Boundary Leakage Test (VT-2) was performed on 10/15/06.
2 Refer to the System Pressure Test Summary for Subsystem Descriptions.
3 The Inservice Inspection (VT-2) of CV-2-3 was performed with the exception of the Chemical Volume Control Positive Displacement Pump (1CVO2P) and its associated piping and valves between the suction and discharge manual isolation valves.
This Class 2 pump has been indefinitely taken out of service per Byron On-Site reviews92-088 and 93-006.
4 Pneumatic test is conducted normal operating pressure, and is not a hydro test.
x Page 2 of 2
1/5/2007 Byron Station Unit 1 B1R14 lSI Outage Report Detailed Inservice Inspection Support Listing SYSTEM: Auxiliary Feedwater System (AF)
F-A P1.30 1AFO2AA-6/1AFO1O3OR 1AFO2AA-6 VT-3 NAI RIGID F-A F1.30 1AFO2AA-6/1AFO1O32X 1AFO2AA-6 VT-3 NRI SEISMIC F-A F1.30 1AFO2AA-6/1AFO1O38R 1AFO2AA-6 VT-3 NRI AIGID 1
Exebn.
Byron Station Unit 1 B1R14 151 Outage Report Detailed Inservice Inspection Support Listing SYSTEM: Component Cooling System (CC)
SectIon XI 1St Identifier Line Number Relief Technical Actual Results c~t. Item Requests Notes Exam Comments F-A F1.30 1CCO1AA-12/1CCO1O36V 1CCO1AA-12 VT-3 NRI VARIABLE F-A F1.30 1CCO1AA-12/1CCO1O53X 1CCO1AA-12 VT-3 NAI SEISMIC F-A Fi.30 1CCO1B-16/1CCO1008X 1CCO1B-16 VT-3 NAI SEISMIC F-A F1.30 1CCO1C-i6/1CCO1002X 1CCO1C-16 VT-3 NAI SEISMIC F-A F1.30 1CCO1C-16/1CCO1003R 1CCO1C-16 VT-3 NAI RIGID F-A F1.30 1CCO1C-16/1CCO1004X 1CCO1C-16 VT-3 NAt SEISMIC F-A F1.30 1CCO2CA-12/1CCO2O18X 1CCO2CA-12 VT-3 NRI SEISMIC F-A Fl.30 1CCO2CB-12/ICCO2O14R 1CCO2CB-12 VT-3 NRI RIGID F-A Fl.30 1CCO2CB-12/1CCO2O15X 1CCO2CB-12 VT-3 NAI SEISMIC F-A F1.30 1CCO2CB-12/1CCO2O16A 1CCO2CB-12 VT-3 NAI RIGID 2
1/5/2007 Exel~n.
Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Support Listing SYSTEM:
Chemical & Volume Control System (CV)
F-A Fl.20 1CVO5B-8/1CV08029A 1CVO5B-8 VT-3 NAI RIGID F-A Fl.10 1CV45B-2/1CV22004X 1CV45B-2 VT-3 NAI SEISMIC F-A Fib 1CV45B-2/1CV22008X 1CV45B-2 VT-3 NAI SEISMIC F-A F1.10 1CVA3B-2/1CVO9004A 1CVA3B-2 VT-3 NAI RIGID F-A Fib 1CVA3B-2/1CVO9O16X 1CVA3B-2 VT-3 NAI SEISMIC F-A F1.l0 1CVA3B-2/1CV11O21X 1CVA3B-2 VT-3 NAI SEISMIC F-A Fl.lO 1CVA3B-211CV25019X 1CVA3B-2 VT-3 NAI SEISMIC F-A F1.10 iCVA3B-2/1CV25025X 1CVA3B-2 VT-3 NAI SEISMIC F-A Fi.1O 1CVA3B-2/1CV25049A 1CVA3B-2 VT-3 NRI ANCHOR 3
1/5/2007 Exeln..
Byron Station Unit 1 B1R14 1St Outage Report Detailed Inservice Inspection Support Listing SYSTEM:
Diesel Generator System (DG)
FA Fi.40 1DGO1KA-X/S 1DGO1KA-X VT-3 NRI DG JWCOOLER A SUPPORT 4
1/5/2007 Exekn..
Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Support Listing SYSTEM:
F-A Fl.10 1AC14AB-211CV15050V 1RC14AB-2 VT-3 NAt VARIABLE F-A F1.iO 1RC16AA-2J1CV12004V 1AC16AA-2 VT-3 NAI VARIABLE F-A F1.10 1AC21BA-8/1RCO1005V 1RC21BA-8 VT-3 NAt VAAtABLE F-A Fb.lO 1AC24AA-4/1RYO6115X 1AC24AA-4 VT-3 NAI SEISMIC 5
1/5/2007 Eceh! n Byron Station Unit 1 B1R14 151 Outage Report Detailed Inservice Inspection Support Listing SYSTEM:
Residual Heat Removal System (RH)
Section XI iSI Identifier Line Number Relief Technical Actual Re~uIts
_~_
Requests Notes Exam Comments 1AHO1AA-l2 VT-3 NRI F-A Fb.10 1AHO1AA-12/1RHO2O76X SEISMIC Fi.20 1RHO1BA-12/1SI06072X SEISMIC 1RHO1BA-l2 VT-3 NAt F-A 6
1/5/2007 Exelcn Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Support Listing SYSTEM:
Safety Injection System (SI)
Section XI ISI Identifier LIne Number Relief
.Tethnlcat Actual Reeul%s Item Description Requests Notes Exam Comments F-A Fb.20 1SIO2BA-6!1S118O43X 1SIO2BA-6 VT-3 NAt SEISMIC F-A Fl.l0 bSIO3DA-2/lSIbbOO9X 1SIO3DA-2 VT-3 NRI SEISMIC F-A Fl.iO 1SIO3DA-2/lSlliOb6X 1SIO3DA-2 VT-3 NRI SEISMIC F-A Fl.20 1SIO5CA-8/1SIO1O26X 1SIO5CA-8 VT-3 NAt SEISMIC F-A F1.20 1SIO5CA-8/lStO200bX 1SIO5CA-8 VT-3 NAt SEISMIC F-A F1.bO 1SIO5DA-6/bSIOiOi7X 1SIO5DA-6 VT-3 NAI SEISMIC F-A Fb.l0 1SIO5DA-6/1SIO1O24V 1SIO5DA-6 VT-3 NAt VARIABLE F-A Fi.l0 bSIO5DA-6I1S101072X 1SIO5DA-6 VT-3 NRI SEISMIC F-A Fb.lO 1SIO5DA-6/1SIO1O73X 1SIO5DA-6 VT-3 NRI SEISMIC F-A Fb.20 1SIO6BB-24/1S106042V 1SIO6BB-24 V1-3 NAI VARIABLE F-A Fl.iO 1SIO8GB-1-b/2J1SI25005X 1SIOSGB-l-b/2 VT-3 NAt SEISMIC F-A Fl.iO 1SIO8GB-i-i/2/1SI25006X 1SIO8GB-b-i/2 VT-3 NAt SEISMIC F-A Fb.i0 1SIO8HA-211SI25015X 1SIOSHA-2 VT-3 NAt SEISMIC F-A Fb.1O 1SIO8JA-b-b/2/1S124003X 1SIO8JA-b-1/2 VT-3 NAt SEISMIC F-A Fib 1SIO8JA-i-i/2/1S124005X 1SIO8JA-b-i/2 VT-3 NAI SEISMIC F-A Fi.iO 1SIO8JA-b-i/2/iSt24Oi4X 1SIO8JA-i-i/2 17-3 NAI SEISMIC 7
1/5/2007 Exek,n..
Byron Station Unit 1 B1R14 ISI Outage Report Detailed Inservice Inspection Support Listing SYSTEM:
Essential Service Water System (SX)
F-A Fl.30 1SXO3A-30/1SXO2O39A 1SXO3A-30 VT-3 NRI RIGID F-A F1.20 1SXO6CA-14/1SXO6003X 1SXO6CA-i4 VT-3 NAI SEISMIC F-A Fi.20 1SXO6CA-b4/bSXO6004X 1SXO6CA-l4 VT-3 NRI SEISMIC F-A Fl.20 1SXO6EA-iO/1SXO6O14X 1SXO6EA-lO VT-3 NAI SEISMIC F-A F1.20 bSXO6EC-bO/1SXO6O23A 1SXO6EC-10 VT-3 NAI ANCHOR F-A Fi.20 1SXO7FA-i6/1SXO8001R 1SXO7FA-16 VT-3 NAP AIGID F-A Fi.30 1SXO7GA-i6/1SXO5003A 1SXO7GA-i6 11-3 NAI RIGID F-A Fl.20 1SXO8AD-bO/i SX07024V 1SXO8AD-iO VT-3 NAI VARIABLE 8
1/5/2007 Exeln Byron Station UnIt 1 Byron Station Outage B1R14 Snubber Outage Summary (Page 1 of 9)
SYSTEM:
Boric Acid Processing System (AB)
NA NA OABE2AA-4/iABi8Oi iS OABE2AA-4 VT-3 NRI SNUBBER SR NA NA 1ABJ3AB-4I1AB18O4OS 1ABJ3AB-4 VT-3 NAt SNUBBER SR Note: SeCtIOn XI Category numbers N/A-ed are exempt from IWF-b220 and IWF-2500 tables 1
1/5/2007 Byron Station Unit 1 Byron Station Outage B1R14 Snubber Outage Summary (Page 2 of 9)
SYSTEM: Component Cooling System (CC)
NA NA 1CC38FB-3/1CC36028S 1CC38FB-3 17-3 NAI SNUBBER SR NA NA 1CC3BFB-3/1CC36030S 1CC38FB-3 VT-3 NRI SNUBBER SR FT PASS NA NA lCc3sFo-3/1CCSSOOSS ICC38FD-3 VT-3 NRI SNUBBER SR NA NA 1CC38FD-3/bC~38009S 1CC38FD-3 VT-3 NRI SNUBBER SA NA NA bCc3gCB-2/iCC3eOiiS 1CC39CB-2 VT-3 NAt SNUBBER SR NA NA 1CC39CD-2/ICC3SOO2S ICC39CD-2 11-3 NRI SNUBBER SR NA NA 1CC39CD-2/1CC38O11S 1CC39CD-2 VT-3 NRI SNUBBER SR FT PASS NA NA ICC4OAC-3/4J1CC37O14S 1CC4OAC-3/4 VT-3 NRI SNUBBER SR FT PASS NA NA ICC4OAD-3/411CC38005S ICC4OAD-3/4 VT-3 NRI SNUBBER SR NA NA 1CC4OAD-3/4,fiCc3soO6s bCC4OAD-3/4 VT-3 NAt SNUBBER SR NA NA 1CC5OAC-3/1CC31O21S 1CC5OAC-3 VT-3 NRI SNUBBER SR NA NA 1CC5OB-3/1CC24OI3S 1CC5OB-3 11-3 NRI SNUBBER SR FT PASS NA NA 1CC54AC-2/1CC32001S 1CC54AC-2 VT-3 NRI SNUBBER SR NA NA 1CC54AC-2/1CC32002S 1CC54AC-2 VT-3 NRI SNUBBER SR FT PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-b220 and IWF-2500 tables 2
1/5/2007 Exek,n Byron Station Unit 1 Byron Station Outage B1R14 Snubber Outage Summary (Page 3 of 9)
SYSTEM: Chemical & Volume Control System (CVI F-A P1.20 1CVO5CB-6/1CVO8006S 1CVO5CB-6 VT.3 NRI SNUBBER SR FT PASS F-A Fi.20 1CVOSCB-6/1CVOSO1OS 1CVO5CB-6 VT-3 NAt SNUBBER SR FT PASS NA NA ICVI5AB-3/4/1CV2BOO2S ICV15AB-3/4 11-3 NRI SNUBBER SR F-A Fi.1O 1CV45B-2/1RYO6124S 1CV45B-2 VT-3 NRI SNUBBER SR FT PASS F-A F1.iO 1CVA5AA-2/1CV15O54S 1CVA5AA-2 VT-3 NAP SNUBBER SR F-A F1.bO 1CVA6AA-2/1CVO9O63S ICVA6AA-2 11-3 NRI SNUBBER SR F-A Fb.iO 1CVA7AA-2/1CV25O11S 1CVA7AA-2 VT-3 NAt SNUBBER SR F-A Fib 1CVA7AA-2/1CV25O14S 1CVA7AA-2 VT-3 NAt SNUBBER SR F-A Fl.bO 1CVA7AA-211CV25016S 1CVA7AA-2 11-3 NRI SNUBBER SR NA SNUB 1RC14AB-2/iCVb5O39-Si 1RC14AB-2 11-3 NAt SNUBBER SR NA SNUB 1RC14AB-2/iCVi5O39-S2 1AC14AB-2 11-3 NRI SNUBBER SR NA SNUB 1RCI4AC-2I1CV09061-S1 IRC14AC-2 11-3 NRI SNUBBER SR NA SNUB 1RC14AC-2/1CVO9O61-S2 1RC14AC-2 VT-3 NAt SNUBBER SR Note: Section XI Category numbers N/A-ed are exempt from IWF-i220 and IWF-2500 tables 3
1/5/2007 Exekrn..
Byron Station Unit 1 Byron Station Outage B1R14 Snubber Outage Summary (Page 4 of 9)
SYSTEM:
Main Steam System (MS)
NA SNUB 1MSO1AD-30.25/1MS08007-Si 1MSO1AD-30.25 VT-3 NAt SNUBBER SR FT PASS NA SNUB 1 MSO1AD-30.25/b MS08007-S2 1 MSOb AD-30.25 VT-3 NRI SNUBBER SR FT PASS NA SNUB 1MSO7AB-28/iMSOiO92-Si 1MSO7AB-28 VT-3 NRI SNUBBER SR FT PASS NA SNUB 1 MSO7AB-28/1 MSO1092-S2 1 MSO7AB-28 VT-3 NRI SNUBBER SR FT PASS NA SNUB 1 MSO7BA-28/i MSO1 074-51 1 MSO7BA-28 VT-3 NAI SNUBBER SR FT PASS NA SNUB 1 MSO7BA-28/i MSO1 074-S2 1 MSO7BA-28 VT-3 NRI SNUBBER SR FT PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-i 220 and IWF-2500 tables 4
1/5/2007 Exek~
Byron Station Unit 1 Byron Station Outage BIR14 Snubber Outage Summary (Page 5 of 9)
SYSTEM:
F-A F1.40 1ACO1BA-iA/1RCO6S 1RCO1BA-lA VT-3 NRI SNUBBER SR VT-3 NRI F-A Fi.40 1RCO1BA-1A/1ACO7S 1RCO1BA-iA VT-3 NRI SNUBBER SR FT PASS F-A F1.40 1RCO1BB-iB/1RCO8S 1RCO1BB-iB VT-3 NRI SNUBBER SR VT-3 NRI F-A F1.40 1RCO1BB-iB/1ACOSS 1RCO1BB-1B VT-3 NRI SNUBBER SR VT-3 NRI F-A Fl.40 1RCO1BC-1C/1RC1OS IRCO1OC-1C 11-3 NA!
SNUBBER SR VT-3 NA!
F-A F1.40 1RCO1BC-1C/1AC1iS IRCO1BC-iC VT-3 NRI SNUBBER SR VT-3 NRI F-A Fl.40 1RCO1BD-1D/1RC12S 1RCO1BD-1D VT-3 NRI SNUBBER SR VT-3 NRI F-A Fi.40 1RCO1BD-1D/1AC13S 1ACO1BD-bD 17-3 NRI SNUBBER SR VT-3 NA!
NA NA 1 RCO8AB-3/4/iRC1 7025S 1 RCO8AB-3/4 VT-3 NRI SNUBBER SR F-A Fb.b0 1RCI4AB-2/1CV15O14S 1RC14AB-2 11-3 NA!
SNUBBER SR F-A F1.l0 1RC14AB-2/1CV15O4OS 1AC14AB-2 VT-3 NRI SNUBBER SA NA SNUB 1RC14AB-2/bCVb5O4l-S1 1RCI4AB-2 VT-3 NRI SNUBBER SR FT PASS NA SNUB 1RC14AB-2/iCVi5O4l-S2 1RC14AB-2 VT-3 NRI SNUBBER SR FT PASS F-A F1.iO 1AC14AB-2/1CV15O53S 1AC14AB-2 VT-3 NAP SNUBBER SR F-A F1.bO 1RC14AC-2/1CVO9O66S 1RC14AC-2 11-3 NA!
SNUBBER SR F-A F1.bO 1AC14AC-2/1CV09067S 1AC14AC-2 VT-3 NRI SNUBBER SR Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 5
1/5/2007 Exekn..
Byron Station Unit 1 Byron Station Outage B1R14 Snubber Outage Summary (Page 6 of 9)
SYSTEM:
F-A Fib 1AC14AC-2/1CV09068S 1RC14AC-2 VT-3 NAt SNUBBER SR F-A F1.10 1RC14AC-211CV09069S 1AC14AC-2 VT-3 NRI SNUBBER SR NA NA 1RC2OAB-314/1RC17O12S bAC2OAB-3/4 VT-3 NRI SNUBBER SR F-A Fi.iO 1RC22AB-i.5/1RC17003S 1RC22AB-b.5 VT-3 NAt SNUBBER SR F-A Fl.bO 1RC22AB-1.5/1RC17Ob5S 1RC22AB-15 11-3 NAt SNUBBER SR F-A F1.iO 1RC22AB-b.5/1RC17028S 1RC22AB-b.5 VT-3 NRI SNUBBER SR F-A F1.b0 1RC22AD-b.&1RC19007S 1RC22AD-l.5 VT-3 NRI SNUBBER SR Note: Section XI Category numbers N/A-ed are exempt from IWF-1 220 and IWF-2500 tables 6
1/5/2007 E~eIorL.
Byron Station UnIt 1 Byron Station Outage Bi R14 Snubber Outage Summary (Page 7 of 9)
SYSTEM:
Residual Heat Removal System (RH)
SectIon XI
~~Iiern Comments ISI IdentIfIer LIne Number Relief Requests Technical Notes Actual Exam Results
~
F-A Fb.bO 1AHO1AA-b2/1AH02054S SNUBBER 1AHO1AA-12 SR VT-3 NAI F-A Fb.20 1RHO2AB-8/1AHO8O15S SNUBBER 1RHO2AB-8 SR VT-3 NAt NA NA 1RH26AA-3/4/1RHO2b12S SNUBBER 1RH26AA-3/4 SR 11-3 FT NRI PASS NA NA 1RH26AB-3/4/1AHO21O2S SNUBBER 1RH26AB-3/4 SR VT-3 FT NRI PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-i220 and IWF-2500 tables 7
1/5/2007 Exek~n_
Byron Station Unit 1 Byron Station Outage B1R14 Snubber Outage Summary (Page 8 of 9)
SYSTEM:
F-A Fl.l0 1RYO1AA-4/1RY06066S 1RYO1AA-4 VT-3 NAt SNUBBER SR F-A Fi.iO 1RYO1B-6/1AYO6O22S 1AYO1B-6 VT-3 NAP SNUBBER SR F-A F1.10 1RYO1B-6/1RY06025S 1RVO1B.-6 VT-3 NRI SNUBBER SR F-A F1.iO 1RYO1B-6/1RY06026S 1AYO1B-6 VT-3 NAt SNUBBER SR F-A Fi.10 1AYO1B-611AY06027S 1RYO1B-6 11-3 NAP SNUBBER SR F-A F1.10 1RYO1B-611RY06030S 1RYO1B-6 VT-3 NRI SNUBBER SR F-A Fb.iO 1RYO1B-6/1AYO6O31S 1RYO1B-6 VT-3 NAt SNUBBER SR FT PASS F-A F1.iO 1AYO2B-3/1AYO9O77S 1RYO2B-3 VT-3 NRI SNUBBER SR NA SNUB 1RYO6B-3/1RY09078-Si 1AYO6B-3 VT-3 NRI SNUBBER SR NA SNUB 1 RYO6B-3/i RV09078-S2 1 RYO6B-3 VT-3 NAt SNUBBER SR F-A F1.iO 1RY18A-2J1RV06O97S 1RY18A-2 VT-3 NAP SNUBBER SR Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 8
Snubber Outage Summary (Page 9 of 9)
Exek,n.
Byron Station Unit 1 Byron Station Outage B1R14 SYSTEM:
Safety Iniection System (SI)
F1.20 Fb.20 Fi.20 Fb.20 Fi.20 Fi.20 1 SIO5CA-8/1 SlOb0255 SNUBBER 1 SIO5CA-8/bS102003S SNUBBER 1SIO5CA-8/1S103003S SNUBBER 1SIO5CB-8/b SI04024S SNUBBER 1 SPO5CB-8/iSIO9006S SNUBBER 1 SIO5CB-8/1SI09043S SNUBBER Note: Section Xl Category numbers N/A-ed are exempt from IWF-b220 and IWF-2500 tables 9
1/5/2007 F-A F-A F-A F-A F-A F-A 1 SIO5CA-8 1 SIO5CA-8 1SIO5CA-8 1SIO5CB-8 1 SIO5CB-8 1 SIO5CB-8 SR SR SR SR SR SR VT-3 VT-3 11-3 VT-3 11-3 NAt NRI NRI NAI NAt
Section 30 Status
(This report is used to verify that the periodic requirements ofTables IWx-24i2-i will be met by the interval schedule.)
BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables IWx-2412-1 apply to ASME SECTION Xi EXAMINATION STATUS REPORT the Category and were applied to each Item only when CATEGORY B-A NON-DEFERRED EXAMS Cat B-A B-A CATEGORY B-A DEFERRED EXAMS Per 3
% Selected 0
b0O.OO%
O 100.00%
o 100.00%
% Exams Completed Period 1 PerIod 2 0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
Period 3 0.00%
0.00%
0.00%
Cat.
B-A B-A
- ot Total Comp Selected 3
3 mm N/A 2
2 N/A 5
5 N/A CATEGORY B-B NON-DEFERRED EXAMS
- Exams Completed mm Per2 max N/A 0
N/A N/A 0
N/A N/A 0
N/A
- 1. (B2.40) Per Examination Category B-B. Note 1, examInations may be limited to one vessel among a group of vessels performing a similar function.
CATEGORY B-D NON-DEFERRED EXAMS
% Exams Completed Period 1 PerIod 2 0.00%
0.00%
0.00%
0.00%
0.00%
- ~f Total Item No. Comp Selected mm Per 1 max Bt30 1
1 0
0 1
B1.40 1
1 0
0 1
Totals:
2 2
0 0
1
- Exams Completed mm Per2 max 1
0 1
1 0
1 1
0 1
Item No.
Bi.11 Bb.21 Totals:
Per 1 0
0 0
max N/A N/A N/A max 2
- 01 Total Cat.
Item No. Comp Selected mm B-B 82.11 2
2 0
B-B 8212 2
2 0
B-B B2.40 Totals:
4 8
1 5
0 1
Per 1 0
0 1
Per 3 0
0 0
Per 3 0
0 0
0
- Exams Completed mm Per2 max 1
0 1
1 0
1 1
0 1
2 0
2 100.00%
100.00%
100.00%
% Selected b0O.000/o 100.00%
25.00%
62.50%
Cat.
B-D B-D B-D Item No.
B3.lbO 83.120 83.140 Totals:
- 01 Total Comp Selected mm Per 1 6
6 6
6 1
1 5
5 3
max 3
8 8
2 0
4 20 20 4
10 10 Period 3 0.00%
0.00%
0.00%
Period 3 0.00%
0.00%
100.00%
20.00%
Period 3 83.33%
83.33%
0.00%
50.00%
- Exams Completed mm Per2 max
-2 0
-1
-2 0
-1 4
0 6
0 0
5
% Exams Completed PerIod 1 PerIod 2 0.00%
0.00%
0.00%
0.00%
100.00%
100.00%
20.00%
20.00%
% Exams Completed PerIod 1 PerIod 2 83.33%
83.33%
83.33%
83.33%
0.O0%
0.00%
50.00%
50.00%
Per3
% Selected O
100.00%
O 100.00%
O 100.00%
0 100.00%
- 1. (83.120 & B3.b40) Per 10 CFR 50.55a(b)(2)(xxl)(A), Table IWB-2500-b examination requirements, the provisions of Table IWB-2500-1, Examination Category B-D, Item Numbers B3. 120 and B3.140 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
(This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables tWx-24i2-1 apply to requirements of Tables tWx-24i2-1 will be ASME SECTION XI EXAMINATION STATUS REPORT the Category and were applied to each Item only when CATEGORY B-D DEFERRED EXAMS
- of Total
- Exams Completed
% Exams Completed Cat. Item No. Comp Selected mm Per 1 max mm Per 2 max Per 3
% Selected Period I Period 2 Period 3 B-D B3.90 8
5 N/A 0
N/A N/A 0
N/A 0
100.00%
0.00%
0.00%
0.00%
B-D 83.100 8
8 N/A 0
N/A N/A 0
N/A 0
100.00%
0.00%
0.00%
0.00%
Totals:
16 16 N/A 0
N/A N/A 0
N/A 0
100.00%
0.00%
0.00%
0.00%
- 1. (B3.b 00) This Item Number requires a visual examination with enhanced magnification in lieu of volumetric examination, as allowed by Code Case N-648-i.
- 2. (83.90 & 83.100) Per Examination Category B-D, Note 5, for PWAs In the second and successive Inspection intervals, these examinations may be deferred to the end of the interval provided no repair/replacement activities have been performed on the examination Item, and no flaws or relevant conditions requiring successive Inspections in accordance with IWB-2420(b) are contained in the examination item.
CATEGORY B-G-1 DEFERRED EXAMS
- of Total
- Exams Completed
% Exams Completed Cat. Item No. Comp Selected mln Per 1 max mln Per 2 max Per 3
% Selected Period 1 PerIod 2 Period 3 B-G-1 B6.bO 3
3 N/A 0
N/A N/A 0
N/A 0
100.00%
0.00%
0.00%
0.00%
B-G-1 B6.2()
3 3
N/A 0
N/A N/A 0
N/A 0
100.00%
0.00%
0.00%
0.00%
B-G-1 B6.40 1
1 N/A 0
N/A WA 0
N/A 0
100.00%
0.00%
0.00%
0.00%
B-G-i B6.50 3
3 N/A 0
N/A N/A 0
N/A 0
100.00%
0.00%
0.00%
0.00%
B-G-1 B6.90 8
8 N/A 0
N/A N/A 0
N/A 0
100.00%
0.00%
0.00%
0.00%
B-G-i B6.iOO 8
8 N/A 0
N/A N/A 0
N/A 0
100.00%
0.00%
0.00%
0.00%
B-G-i B6.ibO 8
8 N/A 0
N/A N/A 0
N/A 0
100.00%
0.00%
0.00%
0.00%
B-G-1 B6.170 I
I N/A 0
N/A N/A 0
N/A 0
100.00%
0.00%
0.00%
0.00%
B-G-1 B6.180 4
1 N/A 0
N/A N/A 0
N/A 0
25.00%
0.00%
0.00%
0.00%
B-G-1 B6.i90 4
0 N/A 0
N/A N/A 0
N/A 0
O.00%
0.00%
0.00%
0.00%
B-G-1 B6.200 4
0 N/A 0
N/A N/A 0
N/A 0
O.000/o 0.00%
0.00%
0.00%
B-G.1 B6.210 8
2 N/A 0
N/A N/A 0
N/A 0
25.00%
0.00%
0.00%
0.00%
BG.b B6.220 8
0 N/A 0
N/A N/A 0
N/A 0
0.000/o 0.00%
0.00%
0.00%
B-G-1 B6.230 8
0 N/A 0
N/A N/A 0
N/A 0
0.00%
0.00%
0.00%
0.00%
Totals:
71 38 N/A 0
N/A N/A 0
N/A 0
53.52%
0.00%
0.00%
0.00%
- 1. (B8.10 & B6.20 & B6.50) Single components representing one third of the 54 Reactor Vessel Closure Head Nuts, Closure Studs, and Closure Washers, Bushings.
- 2. (B6.40) A single component scheduled the first inspection period, representing all of the 54 Reactor VesselThreads In Flange to be examined.
- 3. (B6.90 & B6.100 & B6.1 10) EIght components are tracked In the database, each representing all of the Bolts and associated Nuts, Bushings, and Washers and Flange Surfaces on one of the eight Steam Generator Manways. Each of the eight entries represents 20 bolts and associated parts for an Individual manway.
SectIon 3.0 Page 2 of 8
(This report Is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables lWx-2412-1 appty to met by the Interval schedule.)
will be ASME SECTION XI EXAMINATION STATUS REPORT the Category and were applied to each Item only when
- 4. (86.170) A single component represents the five sets of CETC column nuts.
- 5. (B6.180) Four components are tracked in the database, each representing one of the 24 Bolts on one of the four Reactor Coolant Pumps (96 total) as reported in the ISI Program Plan. The volumetric examination of these components Is limited to only one of the pumps per Examination Category B-G-1, Note 3 and Examination Category B-L-2, Note 1. ExamInation is required only once per inspection interval.
- 6. (B6.190 & 86.200) Four components are tracked In the database, each representing all 24 assocIated Flange Surfaces and Nuts, Bushings, and Washers for one of the four Reactor Coolant Pumps (96 total) as reported In the ISI Program Plan. The visual examination of these components is limited to only one of the pumps per ExaminatIon Category B-G-1, Note 3 and Examination Category B-L-2, Note 1. Also, per ExamInatIon Category B-G-i, Note 4 and ExamInation Category B-L-2, Note 2, examinatIon Is required only when a pump Is disassembled for maintenance, repair, or volumetric examination or bolting Is removed. Examination Is required only once per inspection Interval.
- 7. (B6.210) Eight components are tracked In the database, each representing all of the Botts and associated Nuts, Bushings, and Washers and Flange Surfaces on one of the eight Reactor Coolant Valves as reported In the ISI Program Plan. The volumetric examination of these components Is limited to only one of the valves per Examination Category 8-0-1, Note 3 and Examination Category B-M-2, Note 3. ExaminatIon Is required only once per Inspection Interval.
- 8. (86.220 & 86.230) EIght components are tracked In the database, each representing all of the Bolts and associated Nuts, Bushings, and Washers and Flange Surfaces on one of the eight Reactor Coolant Valves as reported in the ISI Program Plan. The visual examination ofthese components is limited to only one of the valves per Examination Category B-G-1, Note 3 and Examination Category B-M-2, Note 3. Aiso, per Examination Category B-G-l, Note 4 and Examination Category B-M-2, Note 2, examinatIon is required only when a valve Is disassembled for maintenance, repair, or volumetric examination or bolting is removed. Examination Is required only once per inspection interval.
CATEGORY B-G-2 DEFERRED EXAMS
- of Total
- Exams Completed
% Exams Completed Cat.
Item No. Comp Selected mm Per 1 max mm Per 2 max Per 3
% Selected PerIod 1 Period 2 PerIod 3 B-G-2 87.10 2
0 N/A 0
N/A N/A 0
N/A 0
0.00%
0.00%
0.00%
0.00%
B-G-2 B7.20 1
0 N/A 0
N/A N/A 0
N/A 0
0.00%
0.00%
0.00%
0.00%
B-G-2 B7.50 20 I
N/A I
N/A N/A 0
N/A 0
5.00%
100.00%
100.00%
100.00%
B-G-2 B7.60 4
0 N/A 0
N/A N/A 0
N/A 0
0.00%
0.00%
0.00%
0.00%
B-G-2 B7.70 26 1
N/A 1
N/A N/A 0
N/A 0
3.85%
100.00%
100.00%
100.00%
Totals:
53 2
N/A 2
N/A N/A 0
N/A 0
3.77%
100.00%
100.00%
100.00%
- 1. (87.10) Two components representing the CETC and RVUS Clamp Bolts and associated Nuts as reported In the ISI Program Plan.
- 2. (87.20) A single component is scheduled In the first Inspection period, representing all 16 Pressurizer Manway Bolts and associated Nuts as reported In the lSl Program Plan.
- 3. (B7.50) Per Examination Category 8-0-2, Note 3, examInation Is required only when a bolted connection Is disassembled or bolting is removed. Also, per ExamInation Category B-G-2, Note 3, examinations are limited to at least one bOlted connection within each group of bOlted connections that are similar In design, size, function, and service. Examination Is required only once per inspection interval within each bolted connection group.
- 4. (B7.60) Four components are tracked in the database, each representing all 36 Bolts and associated Nuts for one of the four Reactor Coolant Pumps (144 total) as reported in the PSI Program Plan.
Per Examination Category 8-0-2, Note2 and Examination Category B-L-2, Note 2, examinatIon Is required only when a pump Is disassembled for maintenance, repair, or volumetric examination or bolting is removed. Also, per Examination Category B-G-2, Note 2 and Examination Category B-L-2, Note 1, examinatIons are limited to at least one pump within each group of pump that are of the same size, design, manufacturing method, and function. Examination is required only once per Inspection interval within each valve group.
- 5. (87.70) Per Examination Category B-G-2, Note 2 and Examination Category B-M-2, Note 2, examInation Is required only when a valve is disassembled for maintenance, repair, or volumetric examination or bolting is removed. Also, per Examination Category B-G-2, Note 2 and Examination Category B-M-2, Note 3, examinatIons are limited to at least one valve within each group of valves that are of the same size, design, manufacturing method, and function. Examination is required only once per inspection interval within each valve group.
SectIon 3.0 Page 3 of 8
(This report Is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables IWx-241 2-1 apply to requirernentsefTableslWx-2412-l will be ASME SECTION XI EXAMINATION STATUS REPORT the Category and were applied to each Item only when CATEGORY B-K NON-DEFERRED EXAMS
- of Total
- Exams Completed
% Exams Completed Cat. Item No. Comp Selected mm Per 1 max mln Per 2 max Per3
% Selected PerIod 1 PerIod 2 PerIod 3 B-K B10.10 2
2 0
0 1
1 0
1 0
100.00%
0.00%
0.00%
0.00%
B-K B10.20 7
3 1
0 1
2 0
2 0
42.86%
0.00%
0.00%
0.00%
Totals:
9 5
1 0
2 3
0 3
0 55.56%
0.00%
0.00%
0.00%
- 1. (B10.l0) Per ExamInation Category B-K, Note 4, formultiple vessels of similardesign, function and service, only one welded attachment of only one of the multiple vessels shall be selected for examination. Conservatively, a welded attachment of each type of welded attachment of one of multiple vessels will be examined.
- 2. (B10.20 & B10.30) Per Examination Category B-K, Note 5, for piping, pumps, and valves, a sample of 10% of the welded attachments associated with the component supports selected for examination under IWF-2510 shall be examined. This requirement is conservatively interpreted to mean that tO% of the total ClassI welded attachments shall be examined. The interpretation Is consistent with the previous NRC condition on the use of CodeCase N-509.
CATEGORY B-L-2 DEFERRED EXAMS
- of Total
- Exams Completed
% Exams Completed Cat. Item No. Comp Selected mm Per 1 max mm Per 2 max Per 3
% Selected Period 1 Period 2 PerIod 3 B-L-2 B12.20 4
0 N/A 0
N/A N/A 0
N/A 0
0.00%
0.00%
0.00%
0.00%
Totals:
4 0
N/A 0
N/A N/A 0
N/A 0
0.00%
0.00%
0.00%
0.00%
- 1. (BI2.20) The examination of pump casings is limited to only one of the pumps performingsimilarfunctions in the system per Examination Category B-L-2, Note I. Also, per Examination Category B-L-2, Note 2, examInation is required only when a pump Is dIsassembled for maintenance, repair, or volumetric examination. Examination is required only once per inspection Interval.
CATEGORY B-M-2 DEFERRED EXAMS
- of Total
- Exams Completed
% Exams Completed Cat. Item No. Comp Selected mm Per 1 max mln Per 2 max Per 3
% Selected Period 1 PerIod 2 PerIod 3 B-M-2 812.50 37 2
N/A 2
N/A N/A 0
N/A 0
5.41%
100.00%
100.00%
100.00%
Totals:
37 2
N/A 2
N/A N/A 0
N/A 0
5.41%
100.00%
100.00%
100.00%
- 1. (BI2.50) Per Examination Category B-M-2, Note 2, examination is required only when a valve is disassembled for maintenance, repair, or volumetric examination. Also, per Examination Category B-M-2, Note 3, examInatIons are limited to at least one valve within each group of valves that are of the same size, design, manufacturing method, and function. ExaminatIon is required only once per Inspection Interval within each valve group.
SectIon 3.0 Page 4 of 8
(This report is used to verify that the periodIc requirements of Tables IWx-2412-1 will be met by the interval schedule.)
BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables lWx-2412-1 apply to ASME SECTION XI EXAMINATION STATUS REPORT the Category and were applied to each Item only when practical.)
CATEGORY B-N-I NON-DEFERRED EXAMS
- of Total Comp Selected mm Per 1 2
1 0
0 2
1 0
0
- Exams Completed mln Per2 1
0 1
0
% Exams Completed PerIod 1 Period 2 0.00%
0.00%
0.00%
0.00%
Cat. item No.
BN2 p1350 B-~4-2 p13.60 Totals:
CATEGORY B-N-2 DEFERRED EXAMS
- of Total (O~) Se~eç~edm~ per 1 1
1 N/A 0
1 1
N/A 0
2 2
/A 9
CATEGORY B-N-3 DEFERRED EXAMS
- of Total Comp Selected mm 1
1 N/A Totals:
1 1
N/A CATEGORY B-O DEFERRED EXAMS Cat. Item No.
8-0 814.10 Totals:
- Exams Completed
~pir~per~max N/A 0~
N/A N/A 0
N/A PJdA p
N/A
- Exams Completed mm Per2 max N/A 0
N/A N/A 0
N/A
- Exams Completed mm Per 2 max N/A 0
N/A N/A 0
N/A Per 3
% Selected 0
100.00%
0 100.00%
Per 3
% Selected 0
100.00%
0 100.00%
% Exams Completed Period 1 Period 2 0.00%
0.00%
0.00%
0.00%
0.00%
0.00%
% Exams Completed Period 1 Period 2 0.00%
0.00%
0.00%
0.00%
% Exams Completed Period 1 Period 2 0.00%
0.00%
0.00%
0.00%
Cat. Item No.
B-N-i B13.10 Totals:
max 1
max 1
Per 3 0
0
% Selected 50.00%
50.00%
- 1. (B13.l0) ~%Selected~exceeds 100% sInce the vessel interior Is selected for examination twice each period (sixtimes during the interval). The two ASME Section Xi exams per period consist of a vessel cavity exam and vessel head exam.
Period 3 0.00%
0.00%
Cat. Item No.
B-N-3 B13.70 Per 3 0
0 0
% Selected 100.00%
100.00%
00.00%
max N/A N/~
max N/A N/A max N/A N/A Per 1 0
0 Per 1 0
0
- of Comp 5
5 Total Selected 5
5 mm N/A N/A Period 3 0.00%
0.00%
0.00%
Period 3 0.00%
000%
Period 3 0.00%
0.00%
- 1. (B14.l0) 10% of the 45 CAD Housings (as reported in the PSI Program Plan) are required to be examined each Interval per this Item Number. These 5 components represent that 10% population.
Section 3.0 Page 5 of 8
(This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables lWx-2412-1 apply to requirements of Tables lWx-2412-1 will be ASME SECTION XI EXAMINATiON STATUS REPORT the Category and were applied to each Item only when CATEGORY B-P NON-DEFERRED EXAMS
- of Total
- Exams Completed
% Exams Completed Cat. item No. Comp Selected mm Per 1 max mm Per 2 max Per 3
% Selected PerIod 1 PerIod 2 Period 3 B-P 815.10 5
5 N/A 0
N/A N/A Ci N/A 0
100.00%
0.00%
0.00%
0.00%
Totals:
5 5
N/A 0
N/A N/A 0
N/A 0
100.00%
0.00%
0.00%
0.00%
- 1. (815.10) ~%selected~exceeds 100% sInce Class 1 pressure tests are performed each refueling outage.
- 2. (B15.10) Five components representing the five systems In Class 1 as reported in the ISI Program Plan.
CATEGORY C-A NON-DEFERRED EXAMS
- of Total
- Exams Completed
% Exams Completed Cat. Item No. Comp Selected mm Per 1 max mm Per 2 max Per 3
% Selected PerIod 1 Period 2 Period 3 C-A C1.10 6
2 0
1 1
1 0
1 0
33.33%
50.00%
50.00%
50.00%
C-A C1.20 6
2 0
1 1
1 0
1 0
33.33%
50.00%
50.00%
50.00%
C-A C1.30 4
1 0
0 1
1 0
1 0
25.00%
0.00%
0.00%
0.00%
Totals:
16 5
1 2
2 1
0 1
0 31.25%
40.00%
40.00%
40.00%
- 1. (Cl.10 & Cl.20) Per Examination Category C-A, Note 3, in the case of multiple vessels of similardesign, size, and service, the required examinations may be limitedto one vessel or distributed among the vessels.
CATEGORY C-B NON-DEFERRED EXAMS
- of Total
- Exams Completed
% Exams Completed Cat. Item No. Comp Selected mln Per 1 max mm Per 2 max Per 3
% Selected PerIod 1 PerIod 2 Period 3 C-B C2.21 12 5
1 0
2 3
3 0
41.67%
0.00%
0.00%
0.00%
C-B C2.22 8
1 0
0 1
1 0
1 0
12.50%
0.00%
0.00%
0.00%
Totals:
20 6
1 0
3 3
0 4
0 30.00%
0.00%
0.00%
0.00%
- 1. (C2.21 & C2.22) Per Examination Category C-B, Note 4, in the case of multiple vesseis of similardesign, size, and service, the required examinations may be limited to one vessel or distributed among the vessels.
- 2. (C2.22) Due to the unique configuration of the heatexchanger nozzle reinforcing pads being on the internal surface, the nozzle inner radius section is inaccessible for examination. (See Relief Request l3R-04).
SectIon 3.0 Page 6 of 8
(This report is used to verifythat the periodIc requirements of Tables lWx-2412-l will be met by the Interval schedule.)
BYRON STATION UNIT I AND UNIT COMMON - 3RD INTERVAL ASME SECTION XI EXAMINATION STATUS REPORT (The percentage requirements of Tables IWx-241 2-1 apply to the Category and were applied to each Item only when practical.)
CATEGORY C-C NON-DEFERRED EXAMS
- of Comp 2
61 20 83 Total Selected 7
- Exams Completed mm Per 2 max 1
0 4
0 5
1 0
1 5
0 7
- 1. (C7.10) % selected exceeds l00% since Class 2 pressuretests are performed each inspection period.
Per 3
% Selected 0
50.00%
0 11.48%
0 10.00%
0 12.05%
- 2. (C7.l0) Twenty-nine components representIng the twenty-nine systems In Class 2 as reported In the PSI Program Plan.
CATEGORY F-A NON-DEFERRED EXAMS
- 1. (Fl.30 & Fl.40) Unit 0 (Common) components are scheduled with and included in the Unit I counts.
% 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%
- 2. (Fl.40) Per Examination Category F-A, Note 3, for multiple components other than piping within a system ofsimilar design, function, and service, the supports ofonly one of the multiple components are required to be examined.
Cat.
C-C C-C C-C Item No.
C3.iO C3.20 C3.30 Totals:
mm 0
2 Per 1 max 0
1 0
3 2
0 0
1 10 2
0 5
- 1. (C3.l0) Per Examination Category C-C, Note 4, for multiple vessels of similardesign, function, and service, only one welded attachment of only one of the multiple vessels shall be selected for examInation. Conservatively, a welded attachment of each type of welded attachment of one of multiple vessels will be examined.
- 2. (C3.20 & C3.30) Per Examination Category C-C, Note 5, for piping, pumps, and valves, a sample of 10% ofthe welded attachments associated with the component supports selected for examination under IWF-25l0 shall be examined. This requirement is conservatively interpreted to mean that 10% of the total Class 2 welded attachments shall be examined. The interpretation Is consistent with the previous NRC condition on theuse of Code Case N-509.
CATEGORY C-H NON-DEFERRED EXAMS
- of Total
- Exams Completed
% Exams Completed Cat. Item No. Comp Selected mln Per 1 max mm Per 2 max Per 3
% Selected PerIod 1 PerIod 2 PerIod 3 C-H C7.10 29 29 N/A 0
N/A N/A 0
N/A 0
100.00%
0.00%
0.00%
0.00%
Totals:
29 29 N/A 0
N/A N/A 0
N/A 0
100.00%
0.00%
0.00%
0.00%
Cat. Item No.
- of Comp Total Selected mm Per 1 max
- Exams Completed mm Per 2 max Per 3
% Selected
% Exams Completed Period 1 PerIod 2 PerIod 3 F-A F1.10 467 122 20 26 61 35 0
65 0
26.12%
21.31%
21.31%
21.31%
F-A Fl.20 598 99 16 13 49 37 0
61 0
16.56%
13.13%
13.13%
13.13%
F-A F1.30 1005 103 17 15 51 37 0
62 0
10.25%
14.56%
14.56%
14.56%
F-A Fl.40 74 38 7
1 19 18 0
27 0
51.35%
2.63%
2.63%
2.63%
Totals:
2144 362 58 55 181 126 0
216 0
16.88%
15.19%
15.19%
15.19%
Section 3.0 Page 7 of 8
(This report Is used to verifythat the periodic BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables lWx-241 2-I apply to requirements of Tables Wx-2412-l will be ASME SECTION Xl EXAMINATION STATUS REPORT and were applied to each Item only when CATEGORY R-A NON-SOCKETWELDS
- of Total
- Exams Completed
% Exams Completed Cat. Item No. Comp Selected mln Per 1 max mm Per 2 max Per 3
% Selected Period 1 Period 2 Period 3 A-A 1
127 32 6
10 16 6
0 14 0
25.20%
31.25%
31.25%
31.25%
R-A 2
134 36 6
4 18 14 0
23 0
26.87%
11.11%
11.11%
11.11%
R-A 4
1400 143 23 47 71 25 0
60 0
10.21%
32.87%
32.87%
32.87%
R-A 5
65 10 2
0 5
5 0
7 0
15.38%
0.00%
0.00%
0.00%
Totals:
1726 221 36 61 110 50 0
104 0
12.80%
27.60%
27.60%
27.60%
- 1. (BER Welds)The # of Comp and 4* Selected include all BER welds which have been integrated into the RISI Program and are selected In accordance with the Risk Informed BER methodology.
CATEGORY R-A SOCKET WELDS
- of Total
- Exams Completed
% Exams Completed Cat. Item No. Comp Selected mm Per 1 max mlii Per 2 max Per 3
% Selected PerIod 1 PerIod 2 PerIod 3 A-A 2
93 38 N/A 38 N/A N/A 0
N/A 0
40.88%
100.00%
100.00%
100.00%
A-A 4
188 44 N/A 44 N/A N/A 0
N/A 0
23.40%
100.00%
100.00%
100.00%
A-A 5
345 34 N/A 34 N/A N/A 0
N/A 0
9.86%
100.00%
100.00%
100.00%
Totals:
626 116 N/A 116 N/A lIlA 0
N/A 0
18.53%
100.00%
100.00%
100.00%
- 1. (Socket Welds) Socket welds forExaminatIon Category A-Apiping structural elements are listed separatelyfrom butt welds due tothe fact that socket welds are selected for examination in ~each~
refuellng outage. Including socket welds In the # of Comp, Total Selected, and # Selected fields with the butt welds would misrepresentthe % Selecteddistributions for the remainder of the Examination Category. However, socket welds are listed with the butt welds for Examination Category A-A exam selections in the ~TenYear Interval Schedule and Examination Status report that follows.
- 2. (SocketWelds) For A-Asocket welds, % Selected~exceeds 1 00% sInce they are examined each outage.
- 3. (Socket Welds)Byron UnIt 1 has 626 socket welds that fall within the scope of the RISI Program and 116 were selected to be examined. Socket welds that were selected for examination under the RlSl program will be inspected with a VT-2 exam each refueling outage per ASME CodeCase N-578-1, Table 1, footnote 12.
Section 3.0 Page 8 of 8
Section 4.0 Form NIS
- 1
1/5/2007 Exekin..
Byron Station Unit 1 B1R14 iSi Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Cede Rules (Page 1 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfieid Road, Warrenvilie, Illinois 60555 (Name andAddress ot Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Nameand Address of Plant)
- 3. Plant UnIt:
1
- 4. Owner Certificate Of AuthorIzation (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-198
- 7. Components Inspected: Containment Spray System (CS)
Component or Appurtenance Manufacturer or Installer Manufacturer or Installer SerIal No.
State or Province No.
National Board No.
1CSO2AA-10/C01 Hunter Corp.
1-CS-2-N5 NA NA 1CSO2AA-10/C65 Hunter Corp.
1-CS-2-N5 NA NA 1 CSO2AA-10/C88 Hunter Corp.
1 -CS-2-N5 NA NA 1 CSO6AA-6/C07 Hunter Corp.
1 -CS-2-N5 NA NA 1CSO6AA-6/C08 Hunter Corp.
1-CS-2-N5 NA NA 1CSO6AB-61C05 Hunter Corp.
1-CS-2-N5 NA NA 1 CSO6AB-6/C06 Hunter Corp.
1 -CS-2-N5 NA NA 1CS1OAA-6/C06 Hunter Corp.
1-CS-2-N5 NA NA 1CS1OAA-6/C20 Hunter Corp.
1-CS-2-N5 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) sIze is 8 1/2 In. x 11 in., (2) informatIon in items 1 through 6 of this report Is included on each sheet, and (3) each sheet is numbered and the number of sheets is reconled at the top of this form.
Ccm Gwnera~dFoam
115/2007 Exek!n.
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME CodeRules (Page 2 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenviiie, illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, liiinois 61010 (Name andAddress ofPlant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (If required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-198
- 7. Components Inspected: Chemical & Volume Control System (CV)
Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
1RC14AB-2/iCV1 5039-Si Pacific Scientific 23835 NA NA 1 RC14AB-2/iCvi 5039-S2 Pacific Scientific 7345 NA NA 1 RC1 4AC-2/1CV09061-Si Pacific Scientific 13545 NA NA 1RC14AC-2/1CV09061-S2 Pacific Scientific 13599 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) Information in items 1 through 6 of this report is included on each sheet, and (3) each sheet Is numbered and the number of sheets is recorded at thetop of this form.
Com Ge~ed Foam
1/512007 Exekin..
Byron Station Unit I B1R14 lSI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 3 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Addressof Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name andAddress of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-198
- 7. Components inspected:
Chemical & Volume Control System (CV)
Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No.
State or ProvInce No.
National Board No.
CLASS 1 CV PIPING -
LEAKAGE Hunter Corp.
NA NA NA Note: Supplemental sheets In form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2in. x 11 in., (2) InformatIon In items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and thenumber of sheets is recorded at the topof this form.
Com Gwne~edFoam
1/5/2007
~
Exekn..
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 4 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address ofOwner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, illinois 61010 (Name and Addressof Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. CommercIal Service Date:
09/16/85
- 6. National Board Number for Unit:
N-i98
- 7. Components Inspected:
Chemical & Volume Control System (CV)
Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
1CVO5B-8/1CV08029R Hunter Corp.
N/A N/A N/A 1CV45B-2/1CV22004X Hunter Corp.
N/A N/A N/A ICV45B-2/1CV22008X Hunter Corp.
N/A N/A N/A 1CVA3B-2/1CVO9004R Hunter Corp.
N/A N/A N/A 1 CVA3B-2/1CVO9O16X Hunter Corp.
N/A N/A N/A 1CVA3B-2/1CV11O21X Hunter Corp.
N/A N/A N/A 1CVA3B-2/1CV25O19X Hunter Corp.
N/A N/A N/A 1 CVA3B-2/1 CV25025X Hunter Corp.
N/A N/A N/A 1 CVA3B-2/1CV25049A Hunter Corp.
N/A N/A N/A Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) Information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets Is recorded at the top of this form.
Cam& G~d Foam
1/5/2007 Exek,n Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the ProvIsions of the ASME Code Rules (Page 5 of 46)
- 1. Owner:
Exeion Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuciear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name andAddress of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. NatIonal Board Number for Unit:
N-i98
- 7. Components Inspected:
Chemical & Volume Control System (CV)
Component or Appurtenance Manufacturer or installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
1CVO5B-8/C24 Hunter Corp.
NA NA NA 1 CVO5B-8/C25 Hunter Corp.
NA NA NA 1CVO5B-8/C26 Hunter Corp.
NA NA NA 1CVO8AA-4/C03 Hunter Corp.
NA NA NA 1CVO8AA-4/C17 Hunter Corp.
NA NA NA 1CVO8BA-4/C09 Hunter Corp.
NA NA NA 1CVO8BA-4/C21 Hunter Corp.
NA NA NA 1 CVO9A-4/C02 Hunter Corp.
NA NA NA 1 CVO9A-4/C03 Hunter Corp.
NA NA NA 1 CVO9A-4/C07 Hunter Corp.
NA NA NA 1CVA1A-6/C02 Hunter Corp.
NA NA NA 1 CVA3AA-21W-06 Hunter Corp.
1-CV-i -N5 NA NA 1CVA3AA-2/W-07 Hunter Corp.
i-CV-i-N5 NA NA Note: Supplemental sheets In form of lists, sketches, or drawings may be used, provided (1) sIze is 8 1/2 in. x 11 in., (2) information in Items 1 through 6 of this report is Included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the topof this form.
Comput& Gen.rat.d Form
1/5/2007 Exek,n.
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 6 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name andAddress of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of AuthorizatIon (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-i98
- 7. Components Inspected: Chemical & Volume Control System (CV)
Component or Appurtenance Manufacturer or Installer Manufacturer r Installe Serial No.
State or Province No.
National Board No.
1CVA3B-21W-74 Hunter Corp.
1 -CV-1 -N5 NA NA 1CVA3B-2/W-75 Hunter Corp.
i-CV-1-N5 NA NA 1 CVA3B-2/W-76 Hunter Corp.
1 -CV-i -N5 NA NA 1CVA3B-2/W-77 Hunter Corp.
1-CV-i-N5 NA NA 1 CVA3B-2/W-84 Hunter Corp.
1 -CV-i -N5 NA NA 1 CVA3B-2iW-85 Hunter Corp.
1 -CV-1-N5 NA NA 1 CVA5AA-2,W-04 Hunter Corp.
1-CV-i -N5 NA NA 1 CVA5AA-2,W-05 Hunter Corp.
1 -CV-i -N5 NA NA 1CVA6AA-2tW-04 Hunter Corp.
1-CV-1-N5 NA NA 1CVA6AA-21W-05 Hunter Corp.
i-CV-1-N5 NA NA 1CVA7AA-2/W-08 Hunter Corp.
1-CV-i-N5 NA NA 1 CVA7AA-2,W-09 Hunter Corp.
1 -CV-1 -N5 NA NA Note: Supplemental sheets in form of lists, sketches, ordrawings may be used, provIded (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the topof this form.
Computer Generated Form
1/5/2007 Exekn.
Byron Station Unit 1 B1R14 ISi Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 7 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Nameand Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. NatIonal Board Number for Unit:
N-198
- 7. Components Inspected:
Chemical & Volume Control System (CV)
Component or Appurtenance Manufacturer or installer Manufacturer or In t lie Seri:lNo.
State or Province No.
National Board No.
1 CVO5CB-6/1 CVO8006S Pacific Scientific 17048 NA NA 1CVO5CB-6/1 CVO8O1 OS Pacific Scientific 2129 NA NA 1CVO5CB-6/1 CVO8O1 OS Pacific Scientific 2129 NA NA 1CV1 5AB-3/4/1CV28002S Pacific Scientific 33927 NA NA 1CV45B-2/1RY06124S Pacific Scientific 8030 NA NA 1CVA5AA-2/1Cvi 5054S Pacific Scientific 22192 NA NA 1CVA5AA-2/1CV15O54S Pacific Scientific 22192 NA NA 1 CVA6AA-2/1 CV09063S Pacific Scientific 8078 NA NA 1 CVA6AA-2/iCV09063S Pacific Scientific 8078 NA NA 1CVA7AA-2/1CV25O11S Pacific Scientific 8846 NA NA 1CVA7AA-2/1CV25O14S Pacific Scientific 8813 NA NA 1CVA7AA-2/1CV2501 6S Pacific Scientific 8810 NA NA 1CVA7AA-2/iCV2501 6S Pacific Scientific 8810 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 In. x 11 in., (2) information In items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
ComputerGenerated Form
1/5/2007 Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 8 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenviiie, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, illinois 61010 (Nameand Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i6/85
- 6. National Board Number for Unit:
N-198
- 7. Components Inspected:
Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
1 FWO3DA-1 6/COl Hunter Corp.
1 -FW-1-N5 NA NA 1FWO3DA-16/C02 Hunter Corp.
i-FW-i-N5 NA NA 1FWO3DD-16/C14 Hunter Corp.
1-FW-1-N5 NA NA 1FWO3DD-i6/C15 Hunter Corp.
i-FW-i-N5 NA NA 1FWO3DD-16/C16 Hunter Corp.
i-FW-1-N5 NA NA 1 FWO3DD-1 6/Ci7 Hunter Corp.
1 -FW-1-N5 NA NA 1FWO3DD-i6/C19.Oi Bechtel Power Corp.
1-FW-i-N5 NA NA i FWO3DD-i 6/C20.O1 Bechtel Power Corp.
1 -FW-i -N5 NA NA 1FW87CA-6/CO7A W. A. Pope Corp.
i-FW-i-N5 NA NA 1FW87CA-6/CO8A W. A. Pope Corp.
1-FW-1-N5 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size Is 8 1/2 in. x 11 in., (2) Information in Items 1 through 6 of this report is included on each sheet, and (3)each sheet is numbered and the number of sheets is recorded at the top of this form.
Computer Generated Form
1/5/2007 Exekn..
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 9 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Nameand Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-i 98
- 7. Components Inspected:
Main Steam System (MS)
Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
1 MSO7AB-28/iMSO1 092-Si Pacific Scientific 10027 NA NA 1MSO7AB-28/1MSO1 092-S2 Pacific Scientific 7010 NA NA 1MSO7BA-28/i MSO1 074-Si Pacific Scientific 8051 NA NA 1 MSO7BA-28/iMSOi074-S2 Pacific Scientific 6413 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 In. x 11 In., (2) Information in items 1 through 6 of this report is included on each sheet, and (3) each sheet Is numbered and thenumber of sheets is recorded at the topof this form.
ComputerGenerated Form
1/5/2007 Exe Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 10 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron NuclearPower Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-i98
- 7. Components Inspected: Main Steam System (MS)
Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
1 MS01AD-30.25/1 MS080075 Pacific Scientific N/A N/A N/A Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provIded (1) size Is 8 1/2 in. x 11 in., (2) information in items 1 through 6 ofthis report is included on each sheet, and (3)each sheet is numbered and the numberof sheets is recorded at the top of this form.
ComputerGenerated Form
1/5/2007 EeIcn~
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME CodeRules (Page ii of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address ofOwner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 6iOiO (Name andAddress of Plant)
- 3. Plant UnIt:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-i98
- 7. Components Inspected:
Main Steam System (MS)
Component or Appurtenance Manufacturer or Installer Manufacturer or installer Serial No.
State or Province No.
National Board No.
1MSO1AB-32.75/COi.01 Bechtel Power Corp.
i-MS-i-N5 NA NA 1MSO1AB-32.75/CO1A Bechtel Power Corp.
1-MS-1-N5 NA NA 1 MSO1 CD-3O.25/COi Hunter Corp.
1-MS-i -N5 NA NA 1 MSO7AB-28/C08 Hunter Corp.
1-MS-i -N5 NA NA 1 MSO7BB-28/COi Hunter Corp.
i-MS-i -N5 NA NA 1 MSO7BB-28/Ci2 Hunter Corp.
i-MS-i-N5 NA NA 1MSi 3AA-8/C08 Hunter Corp.
1-MS-i-N5 NA NA 1 MS1 3AA-8/C09 Hunter Corp.
i-MS-i-N5 NA NA 1MSi3AA-8/C10 Hunter Corp.
i-MS-i-N5 NA NA 1 MSi 3AA-8/Ci 1 Hunter Corp.
i-MS-i-N5 NA NA 1MS13AA-8/Ci2 Hunter Corp.
i-MS-1-N5 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3)each sheet is numbered and the number of sheets is recorded at the top of this form.
Computer Generated Form
1/5/2007 Exek,n..
Byron Station Unit 1 B1R14 ISi Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 12 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Addressof Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
i
- 4. Owner Certificate Of Authorization (If required):
N/A
- 5. Commercial Service Date:
09/i 6/85
- 6. National Board Number for Unit:
N-i 98
- 7. Components Inspected:
Main Steam System (MS)
Component or Appurtenance Manufacturer or Installer Manufacturer or installer Serial No.
State or Province No.
National Board No.
1 MSO1 AD-30.25/1MS08007-Si Pacific Scientific 10507 NA NA iMSO1AD-30.25/1 MSO8007-S2 Pacific Scientific i049i NA NA Note: Supplemental sheets In form of lists, sketches, or drawings may be used, provided (1) size Is 8 1/2 in. x 11 In., (2) information in items 1 through 6 of this report Is included on each sheet, and (3) each sheet is numbered and thenumber of sheets is recorded at the top of this form.
ComputerGeneratid Form
1/5/2007 Exel~,n Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME CodeRules (Page i3 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address ofPlant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-i 98
- 7. Components inspected: Pressurizer (PZR)
Component or Appurtenance Manufacturer or Installer Manufacturer installer Serial No.
State or Province No.
National Board No.
i RY-Oi-S/PN-Oi Westinghouse Corp.
1721 U-20i 291 Wi3580 1 RY-Oi-S/PN-Oi -NIR Westinghouse Corp.
i 72i U-201291 Wi3580 iRY-01-S/PN-02 Westinghouse Corp.
i72i U-20129i Wi3580 1RY-Oi-S/PN-02-N1R Westinghouse Corp.
i72i U-20i29i W13580 1RY-Oi-S/PN-03 Westinghouse Corp.
1721 U-20i29i Wi3580 1 RY-Oi-S/PN-03-N1R Westinghouse Corp.
1721 U-20i 291 W13580 1RY-Oi-S/PN-05 Westinghouse Corp.
1721 U-20i29i Wi3580 iRY-0i-S/PN-05-NIR Westinghouse Corp.
i72i U-20i29i Wi3580 1RY-Oi-S/PN-06 Westinghouse Corp.
i72i U-201291 W13580 1RY-Oi-S/PN-06-NIR Westinghouse Corp.
1721 U-20i29i Wi3580 Note: Supplemental sheets In form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information In items 1 through6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at thetop of this form.
Computer Generated Form
1/5/2007 Exekn..
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page i4 of 46)
- 1. Owner:
Exeion Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name andAddress of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 6i010 (Nameand Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i6/85
- 6. National Board Number for Unit:
N-i 98
- 7. Components Inspected:
Component or Appurtenance Manufacturer or Installer Manufacturer or installer Serial No.
State or Province No.
National Board No.
CLASS 1 RC PIPING - LEAKAGE Hunter Corp.
NA NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size Is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
Computer Generated Form
1/5/2007 Exekn~
Byron Station Unit 1 B1R14 lSl Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 15 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfieid Road, Warrenville, Illinois 60555 (Name andAddress of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 6iOiO (Name and Address ofPlant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i6/85
- 6. National Board Number for Unit:
N-i98
- 7. Components inspected:
Component or Appurtenance Manufacturer or Installer Manufacturer or installer Serial No.
State or Province No.
National Board No.
1 RC1 4AB-2/1CV15O39S Pacific Scientific N/A N/A N/A 1RC14AB-2/iCVi 5050V Hunter Corp.
N/A N/A N/A 1RCi4AC-2/iCVO9O6i S Pacific Scientific N/A N/A N/A 1 RCi 6AA-2/1 CVi2004V Hunter Corp.
N/A N/A N/A 1 RC21 BA-8/1 RCO1005V Hunter Corp.
N/A N/A N/A 1 RC24AA-4/1RYO61 15X Hunter Corp.
N/A N/A N/A Note: Supplemental sheets in form of lists, sketches, ordrawings may be used, provided (1) size is 8 1/2 In. x 11 in., (2) Information in items 1 through 6 of this report is Included on each sheet, and (3) each sheet is numbered and thenumber of sheets is recorded at the top of this form.
ComputerGenerated Fans
1/5/2007
~Exekn~
Byron Station Unit 1 B1R14 iSi Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the ProvisIons of the ASME Code Rules (Page l6of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address ofOwner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 6i010 (Nameand Address of Plant)
- 3. Plant Unit:
i
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i6/85
- 6. National Board Number for Unit:
N-i 98
- 7. Components Inspected:
Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
i RC1 3AA-2/W-01 Hunter Corp.
1-AC-i -N5 NA NA 1RCi3AA-21W-02.Oi W. A. Pope Corp.
i-RC-i-N5 NA NA 1 RC1 3AA-2/W-03 Hunter Corp.
1-AC-i -N5 NA NA iRC13AA-21W-04 Hunter Corp.
i-RC-i-N5 NA NA 1RC13AA-2iW-05 Hunter Corp.
i-RC-i-N5 NA NA 1RCi3AB-21W-Oi Hunter Corp.
i-RC-1-N5 NA NA 1RC13AB-2iW-09 Hunter Corp.
i-AC-1-N5 NA NA 1RC13AC-2tW-01 Hunter Corp.
i-AC-1-N5 NA NA 1RC13AD-2iW-Oi Hunter Corp.
i-RC-1-N5 NA NA 1AC14AA-21W-02 Hunter Corp.
1-RC-i-N5 NA NA 1RC14AA-2/W-03 Hunter Corp.
1-RC-1-N5 NA NA iRCi4AA-2/W-03A Hunter Corp.
i-RC-i-N5 NA NA 1AC14AA-2,W-03B Hunter Corp.
i-RC-i-N5 NA NA Note: Supplemental sheets in form of lists, sketches, ordrawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information In Items 1 through 6 ofthis report is included on each sheet, and (3) each sheet is numbered and the numberof sheets Is recorded at the top of this form.
Computer Generated Form
1/5/2007 Exekn Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the ProvIsIons of the ASME Code Rules (Page i 7 of 46)
- 1. Owner:
Exeion Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenvilie, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i 6/85
- 6. National Board Number for Unit:
N-198
- 7. Components inspected:
Component or Appurtenance Manufacturer or installer Manufacturer or i stailer Sal No.
State or Province No.
National Board No.
1RC14M-2/W-03C Hunter Corp.
1-RC-1-N5 NA NA iRCi4AA-2/W-04 Hunter Corp.
1-AC-i-N5 NA NA 1ACi4AA-2/W-05 Hunter Corp.
i-RC-1-N5 NA NA 1RC14AA-2/W-06 Hunter Corp.
i-RC-1-N5 NA NA 1RC14AA-2iW-07 Hunter Corp.
i-RC-i-N5 NA NA 1RC14AA-2/W-08 Hunter Corp.
i-RC-1-N5 NA NA 1RC14AA-2/W-09 Hunter Corp.
1-RC-i-N5 NA NA 1RC14AA-21W-10 Hunter Corp.
1-RC-i-N5 NA NA 1AC14AA-2tW-il HunterCorp.
1-RC-i-N5 NA NA 1RC14AA-2/W-i2 Hunter Corp.
i-RC-i-N5 NA NA 1RCi4AA-2/W-i3 Hunter Corp.
1-RC-1-N5 NA NA 1RC14AB-2/W-07 Hunter Corp.
i-RC-i-N5 NA NA 1RC14AB-2/W-08 Hunter Corp.
1-AC-i-N5 NA NA Note: Supplemental sheets In form of lists, sketches, or drawings may be used, provIded (1) size is 8 1/2 In. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets Is recorded at the topof this form.
Computer Generated Form
1/5/2007 Exekn..
Byron Station Unit 1 B1R14 lSl Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page i8 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
i
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-i 98
- 7. Components Inspected: Reactor Coolant System (RC)
Component or Appurtenance Manufacturer or Installer Manufacturer or installer Serial No.
State or Province No.
National Board No.
1RC14AB-2iW-09 Hunter Corp.
1-RC-1-N5 NA NA 1RC14AB-2iW-iO Hunter Corp.
i-RC-i-N5 NA NA 1 RC1 4AB-2/W-i 1 Hunter Corp.
1-AC-i -N5 NA NA 1AC14AC-2/W-08 Hunter Corp.
1-RC-1-N5 NA NA 1RC14AD-2/W-08 Hunter Corp.
i-RC-i-N5 NA NA 1RCi4AD-2iW-09 Hunter Corp.
i-RC-1-N5 NA NA 1RCi4AD-2/W-iO Hunter Corp.
1-RC-i-N5 NA NA 1RC14AD-2/W-ii Hunter Corp.
1-AC-i-N5 NA NA iRC14AD-2/W-i2 Hunter Corp.
1-RC-i-N5 NA NA 1AC14AD-2iW-i3 Hunter Corp.
1-RC-i-N5 NA NA 1 RC1 6AA-2/W-02 Hunter Corp.
i-AC-i -N5 NA NA 1 RC1 6AA-2/W-03 Hunter Corp.
1-AC-i -N5 NA NA 1 AC16AA-2iW-04 Hunter Corp.
i-AC-i -N5 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through6 of this report is Included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top ofthis form.
Co~GeneratedFonn
1/5/2007 Exelcrn Byron Station Unit 1 B1R14 151 Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page igof 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address ofOwner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Addressof Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Numberfor Unit:
N-i98
- 7. Components Inspected: Reactor Coolant System (RC)
Component or Appurtenance Manufacturer or installer Manufacturer r In tall r Seri:l NC).
State or Province No.
National Board No.
1AC16M-2iW-05 Hunter Corp.
i-RC-1-N5 NA NA 1RCi6AA-2/W-06 Hunter Corp.
i-AC-1-N5 NA NA 1RCi6AA-2/W-07 Hunter Corp.
i-RC-i-N5 NA NA 1RCi6AA-2/W-08 Hunter Corp.
i-RC-i-N5 NA NA 1 RC1 6AB-21W-02 Hunter Corp.
i-AC-i -N5 NA NA 1AC21AA-8/J07 Hunter Corp.
1-RC-i-N5 NA NA 1RC21AA-8/J08 Hunter Corp.
1-RC-1-N5 NA NA 1 RC21 AA-8/J09 Hunter Corp.
1-AC-i -N5 NA NA 1AC21AA-8/JiO Hunter Corp.
1-RC-i-N5 NA NA 1RC21AA-8/J1i Hunter Corp.
i-AC-1-N5 NA NA 1RC22AA-i.5/W-01 Hunter Corp.
i-AC-i -N5 NA NA 1 AC22AA-i.51W-02 Hunter Corp.
1-AC-i -N5 NA NA 1RC22AA-1.5,W-03 Hunter Corp.
i-AC-i-N5 NA NA Note: Suppiementai sheets In form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 In. x 11 In., (2) information In items 1 through 6 of this report Is included on each sheet, and (3) each sheet is numbered and thenumber of sheets is recorded at the top of this form.
Computer Generated Form
1/5/2007 Byron Station Unit 1 B1R14 ISi Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 20 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfieid Road, Warrenville, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, illinois 610i0 (Name and Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i6/85
- 6. National Board Number for Unit:
N-i98
- 7. Components inspected:
Component or Appurtenance Manufacturer or installer Manufacturer r installer Serial No.
State or Province No.
National Board No.
1 RC22AA-1.5/W-04 Hunter Corp.
i-AC-i -N5 NA NA 1 AC22AA-1.5/W-05 Hunter Corp.
i-AC-i-N5 NA NA iRC22AA-i.5/W-06 Hunter Corp.
i-AC-i-N5 NA NA 1AC22AA-1.5/W-07 Hunter Corp.
i-RC-1-N5 NA NA 1AC22AA-i.5/W-08 Hunter Corp.
i-AC-i -N5 NA NA 1RC22AA-i.5/W-09 Hunter Corp.
i-RC-1-N5 NA NA 1RC22AA-1.5/W-iO Hunter Corp.
1-AC-i-N5 NA NA 1 RC22AA-i.5/W-i i Hunter Corp.
i-AC-i -N5 NA NA 1AC22AA-1.51W-i2 Hunter Corp.
1-RC-1-N5 NA NA 1AC22AA-i.5/W-i3.01 NPSW Venture Corp.
i-RC-i-N5 NA NA iAC22AA-i.5/W-14.01 NPSW Venture Corp.
1-AC-1-N5 NA NA 1RC22AA-i.51W-i5.Oi NPSW Venture Corp.
1-RC-i-N5 NA NA iRC22AA-1.5/W-i6.Oi NPSW Venture Corp.
i-AC-i-N5 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) Information In items 1 through 6 of this report is Included on each sheet, and (3) each sheet is numbered and the numberof sheets Is recorded at the topof this form.
ComputerGenerated Form
1/5/2007
- E~eI~n_
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As RequIred by the Provisions of the ASME Code Rules (Page 21 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenvilie, Illinois 60555 (Name and Address ofOwner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name andAddress of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (If required):
N/A
- 5. Commercial Service Date:
09/i 6/85
- 6. National Board Number for Unit:
N-i98
- 7. Components Inspected: Reactor Coolant System (AC)
Component or Appurtenance Manufacturer or Installer Manufacturer o Installer S~rialNo.
State or Province No.
NatIonal Board No.
1 AC22AA-1.5,W-i7 Hunter Corp.
i-AC-i -N5 NA NA 1RC22AA-i.5/W-i8 Hunter Corp.
1-RC-i-N5 NA NA 1RC22AA-i.5/W-i9 Hunter Corp.
i-RC-i-N5 NA NA i RC22AA-1.5/W-20 Hunter Corp.
i-AC-i-N5 NA NA 1 AC22AA-1.5iW-2i Hunter Corp.
i-AC-i-N5 NA NA i RC22AA-1.51W-22 Hunter Corp.
1 -RC-i-N5 NA NA i RC22AA-1.5/W-23 Hunter Corp.
i-AC-i -N5 NA NA 1 AC22AA-i.5/W-24 Hunter Corp.
1-AC-i -N5 NA NA 1 RC22AA-i.5/W-25 Hunter Corp.
i-AC-i -N5 NA NA 1 RC22AA-i.5/W-26 Hunter Corp.
1-AC-i -N5 NA NA 1AC22AA-1.5/W-27 Hunter Corp.
1-RC-i-N5 NA NA 1 RC22AA-1.5/W-28 Hunter Corp.
1-AC-i -N5 NA NA iRC22AA-i.51W-29 Hunter Corp.
1-RC-i-N5 NA NA Note: Supplemental sheets In form of lists, sketches, or drawings may be used, provided (1) size Is 8 1/2 in. x 11 in., (2) informatIon in items 1 through 6 of this report is included on each sheet, and (3)each sheet is numbered and the number of sheets Is recorded at the top of this form.
Computer Generated Form
1/5/2007
- Ecek,n.
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-.1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 22 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenvilie, Illinois 60555 (Name and Address ofOwner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 610i0 (Name and Address of Plant)
- 3. Plant Unit:
i
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-i98
- 7. Components Inspected: Reactor Coolant System (AC)
Component or Appurtenance Manufacturer or installer Manufacturer
~
State or Province No.
National Board No.
i AC22AA-1.5/W-30 Hunter Corp.
i-RC-1-N5 NA NA 1 AC22AA-i.5/W-31 Hunter Corp.
1-AC-i -N5 NA NA i AC22AA-1.5/W-32 Hunter Corp.
1-AC-i -N5 NA NA iRC22AA-1.5/W-33 Hunter Corp.
i-AC-1-N5 NA NA I AC24AA-4/J06 Hunter Corp.
i-AC-i-N5 NA NA 1AC24AA-4/J07 Hunter Corp.
1-RC-i-N5 NA NA 1 RC24M-4/J09 Hunter Corp.
i-AC-i-N5 NA NA iAC24AA-4/JiO Hunter Corp.
1-RC-1-N5 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 ofthis report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
Computer Generated Form
1/5/2007
- Exekfrn~.
Byron Station Unit 1 B1R14 iSl Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 23 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfieid Road, Warrenviile, illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 6i Oi 0 (Name and Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i 6/85
- 6. NatIonal Board Number for UnIt:
N-i98
- 7. Components Inspected:
Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
iRCOi BA-iA/iACO6S Paul Munroe PD-i423-333 NA NA iRCOi BA-iAi RCO7S Paul Munroe PD-1423-322 NA NA 1ACO1BB-iB/iACO8S Paul Munroe PD-1423-329 NA NA iRCOiBB-iB/1RCO9S Paul Munroe PD-1423-327 NA NA 1RCO1BC-iC/1RC1OS Paul Munroe PD-i423-334 NA NA 1ACO1BC-iC/lRCii5 Paul Munroe PD-1423-331 NA NA 1ACO1BD-1D/iACi25 Paul Munroe PD-i423-32i NA NA 1RCO1BD-1D/iRC13S Paul Munroe PD-i423-3i8 NA NA iACO8AB-3/4/i AC1 7025S Pacific Scientific 2619 NA NA 1RCi4AB-2/1CVi5O14S Pacific Scientific 5842 NA NA 1AC14AB-2/iCVi5Ol4S Pacific Scientific 5842~
NA NA 1RCi4AB-2/i CV1 5040S Pacific Scientific i309i NA NA 1AC14AB-2/i Cvi5041-51 Lisega 7058 NA NA Note: Supplemental sheets In form of lists, sketches, or drawings may be used, provided (1) sIze is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.
Computer Generated Form
1/5/2007 Exekn.
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 24 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
1
- 4. OwnerCertificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i 6/85
- 6. National Board Number for Unit:
N-198
- 7. Components Inspected:
Component or Appurtenance Manufacturer or installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
1AC14AB-2/i CV1 504i-S2 Lisega 2800 NA NA 1RC14AB-2/iCVi5053S Pacific Scientific 2193 NA NA 1AC14AB-2/i CV1 5053S Pacific Scientific 2193 NA NA 1AC14AC-2/i CV090665 Pacific Scientific 12037 NA NA 1AC14AC-2/iCV09067S Pacific Scientific 22295 NA NA 1AC14AC-2/1 CV09067S Pacific Scientific 22295 NA
~
NA 1RC14AC-2/1CV09068S Pacific Scientific i0170 NA NA
~
1AC14AC-2/1 CV09069S Pacific Scientific 12821 NA NA iRCi4AC-2/1 CV09069S Pacific Scientific 12821 NA NA iRC2OAB-3/4/1 AC1 7012S Pacific Scientific 14743 NA NA 1 RC22AB-1.5/i AC1 7003S Pacific Scientific 7692 NA NA i RC22AB-i.5/1RC17O15S Pacific Scientific 20437 NA NA 1 AC22AB-1.5/1 AC17028S Pacific Scientific 5666 NA NA Note: Supplemental sheets In form of lists, sketches, or drawings may be used, provided (1) size Is 8 1/2 In. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3)each sheet is numbered and the numberof sheets is recorded at the top of thIs form.
ComputerGenerat.d Form
1/5/2007 Exekrn.
Byron Station Unit 1 B1R14 iSi Outage Report FORM NJS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 25 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
i
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Numberfor Unit:
N-i98
- 7. Components inspected:
Component or Appurtenance Manufacturer or installer Manufacturer cnstaller State or Province No.
National Board No.
i RC22AD-i.5/1 RC1 9007S Pacific Scientific 9658 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size Is 8 1/2 in. x 11 in., (2) information in Items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form Computer Generated Form
1/5/2007 Exekm..
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As RequIred by the ProvisIons of the ASME Code Rules (Page 26 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfieid Road, Warrenville, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, illinois 61010 (Name andAddress of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-i98
- 7. Components Inspected:
Residual Heat Removal System (RH)
Component or Appurtenance Manufacturer or Installer Manufacturer
~
State or Province No.
National Board No.
P CLASS i RH IPING
- LEAKAGE Hunter Corp.
NA NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) sIze is 8 1/2 in. x 11 in., (2) Information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
Computer Generated Form
1/5/2007
-- E~ekni Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME CodeRules (Page 27 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 6i 010 (Name and Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i 6/85
- 6. National Board Number for Unit:
N-i98
- 7. Components Inspected:
Residual Heat Removal System (RH)
Component or Appurtenance Manufacturer or installer Manufacturer
~
State or Province No.
National Board No.
1RHO1AA-12/1 RH02076X Hunter Corp.
N/A N/A N/A iRHOiBA-12/1 S106072X Hunter Corp.
N/A N/A N/A Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information In items 1 through 6 of this report is included on each sheet, and (3)each sheet is numbered and the numberof sheets Is recorded at the top of this form.
Computer Generated Form
1/5/2007
~E,cek!n~
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As RequIred by the Provisions of the ASME Code Rules (Page 28 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfieid Road, Warrenviile, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Addressof Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i 6/85
- 6. National Board Numberfor Unit:
N-i98
- 7. Components Inspected:
Residual Heat Removal System (RH)
Component or Appurtenance Manufacturer or installer Manufacturer Seri:l No.
State or Province No.
National Board No.
1AHO1BA-12/C18 Hunter Corp.
1-RH-2-N5 NA NA 1RHO1BA-i2/C21 Hunter Corp.
i-AH-2-N5 NA NA 1 RHO2AA-8/C02 Hunter Corp.
i -RH-2-N5 NA NA i RHO2AA-8/C06 Hunter Corp.
i -RH-2-N5 NA NA i RHO2AA-8/C07 Hunter Corp.
1 -AH-2-N5 NA NA 1 RHO2AA-8/C09 Hunter Corp.
i -RH-2-N5 NA NA 1AHO2AA-8/C10 Hunter Corp.
1-RH-2-N5 NA NA 1RH-02-AB/AHEC-01 Joseph OatCorp.
2267-lB U122327 837 1AH-02-AB/RHEC-02 Joseph Oat Corp.
2267-lB Ui22327 837 1 RH1 2A-8/C01 Hunter Corp.
1 -RH-2-N5 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in Items 1 through 6 of this report is Included on each sheet, and (3) each sheet Is numbered and thenumber of sheets is recorded at the top of this form.
ComputerGenerated Form
1/5/2007
- Exekni~
Byron Station Unit 1 B1R14 iSl Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the ProvIsions of the ASME Code Rules (Page 29 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
i
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-198
- 7. Components Inspected:
Residual Heat Removal System (RH)
Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
1RHOiAA-i2/i RH02054S Pacific Scientific 9629 NA NA i RHO2AB-8/1 RHO8O1 5S Pacific Scientific 9892 NA NA 1AH26AA-3/4/1 RHO21 l2S Lisega i4850 NA NA 1 RH26AB-3/4/1 AHO21 02S Pacific Scientific 7482 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provIded (1) size is 8 1/2 in. x 11 in., (2) Information in Items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at thetopofthisform.
Computer Generated Form
1/5/2007 Exekrn..
Byron Station Unit 1 B1R14 ISi Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the ProvisIons of the ASME Code Rules (Page 30 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Nameend Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 6i010 (Name and Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-i98
- 7. Components Inspected:
Component or Appurtenance Manufacturer or installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
i RYO6B-3/i RY09078-Si Pacific Scientific 8555 NA NA 1 RYO6B-3/i RY09078-S2 Pacific Scientific 9665 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) sIze is 8 1/2 In. x 11 In., (2) information in items 1 through 6 ofthis report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
Computer Generated Form
1/5/2007 Exekn..
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page3i of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name andAddress of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i6/85
- 6. National Board Number for Unit:
N-i 98
- 7. Components Inspected: Reactor Coolant System (RY)
Componentor Appurtenance Manufacturer or Installer Manufacturer or installer Serial No.
State or Province No.
National Board No.
iRYO3BB-6/FLG 1-12 Hunter Corp.
i-RY-i-N5 NA NA 1RYO3BB-6/FLG 1-12 Hunter Corp.
1-RY-1-N5 NA NA 1RY8O1OB/INT SURF Hunter Corp.
i-RY-1-N5 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provIded (1) size is 8 1/2 in. x 11 in., (2) Information in items 1 through 6 ofthis report is included on each sheet, and (3) each sheet Is numbered and the number of sheets is recorded at the top of this form.
1/5/2007 Byron Station Unit 1 B1R14 lSl Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the ProvisIons of the ASME Code Rules (Page 32 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 6iOiO (Name and Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i 6/85
- 6. National Board Number for Unit:
N-i 98
- 7. Components Inspected: Reactor Coolant System (RY)
Component or Appurtenance Manufacturer or Installer Manufacturer
~
State or Province No.
National Board No.
CLASS i RY PIPING -
LEAKAGE Hunter Corp.
NA NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 In., (2) information in Items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
ComputerGenerated Form
1/5/2007
- Exekn Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 33 of 46)
- 1. Owner:
Exeion Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenviile, illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Addressof Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-i 98
- 7. Components Inspected:
Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
1 RYO1 C-4/JOi S Westinghouse Corp.
1-RY-i -N5 NA NA i RY-Oi-S/PN-Oi -FiS Westinghouse Corp.
1 -RY-1-N5 NA NA i RY-Oi -S/PN-02-F2S Westinghouse Corp.
1 -RY-i -N5 NA NA 1 RY-Ol -S/PN-03-F3S Westinghouse Corp.
1 -RY-i -N5 NA NA 1RY-Oi-S/PN-04-F4S Westinghouse Corp.
1-RY-1-N5 NA NA 1 RY-Ol-S/PN-05-F5S Westinghouse Corp.
1 -RY-1 -N5 NA NA 1 RY-Ol-S/PN-06-F6S Westinghouse Corp.
i -RY-1 -N5 NA NA 1 RYO2A-6/JOiS Westinghouse Corp.
i -RY-1 -N5 NA NA 1 RYO3A.A-6/JOi S Westinghouse Corp.
1 -RY-i -N5 NA NA 1 RYO3AB-6/JOiS Westinghouse Corp.
1 -RY-i -N5 NA NA 1 RYO3AC-6/J01S Westinghouse Corp.
1 -RY-1 -N5 NA NA 1 RYi iA-i 4/JOiAS Westinghouse Corp.
i -RY-i -N5 NA NA 1RY18A-21W-05A Hunter Corp.
1-RC-1-N5 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings maybe used, provIded (1) size is 8 1/2 In. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet Is numbered and the numberof sheets is recorded at the top of this form.
Computer Generated Form
1/5/2007 Exekn..
Byron Station Unit 1 B1R14 1St Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 34 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenvilie, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Addressof Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i 6/85
- 6. National Board Number for Unit:
N-i98
- 7. Components Inspected:
Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
1 RY1 8A-2,W-06 Hunter Corp.
1-RC-1 -N5 NA NA 1 RY1 8A-2/W-07 Hunter Corp.
1 -RC-i-N5 NA NA 1RYi8A-2,W-08 HunterCorp.
i-RC-1-N5 NA NA 1RY18A-2/W-09 Hunter Corp.
1-RC-1-N5 NA NA iRY18A-2/W-iO Hunter Corp.
i-RC-i-N5 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) sIze Is 8 1/2 in. x 11 in., (2) information In Items 1 through 6 of this report Is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
ComputerGeneratedForm
1/5/2007 e
Byron Station Unit 1 B1R14 ISi Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the ProvisIons of the ASME Code Rules (Page 35 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address ofOwner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 610i0 (Name and Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i 6/85
- 6. National Board Number for Unit:
N-i 98
- 7. Components Inspected:
Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
i RYO1 AA-4/1 RY06066S Pacific Scientific 20685 NA NA 1 RYO1 B-6/i RY06022S Pacific Scientific 10163 NA NA 1 RYO1B-6/i RY06025S Pacific Scientific 9660 NA NA i RYO1 B-6/1 RY06026S Pacific Scientific 8478 NA NA 1 RYO1B-6/iRY06027S Pacific Scientific 9687 NA NA i RYOi B-6/iRYO6O3OS Pacific Scientific 10146 NA NA 1 RYO1 B-6/1 RYO6O3iS Pacific Scientific 6027 NA NA 1 RYO2B-3/1 RY09077S Pacific Scientific 14793 NA NA 1RY18A-2/1RY06097S Pacific Scientific 15029 NA NA Note: Supplemental sheets Inform of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. xli in., (2) information in Items 1 through 6 of this report is included on each sheet, and (3) each sheet Is numbered and the number of sheets is recorded at the top of this form.
Computer Generated Form
1/512007 E~cek~~n_
Byron Station Unit 1 B1R14 iSi Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the ProvIsIons of the ASME Code Rules (Page 36 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenvilie, Illinois 60555 (Name and Address ofOwner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
i
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i 6/85
- 6. National Board Number for Unit:
N-i 98
- 7. Components Inspected:
Component or Appurtenance Manufacturer or installer Manufacturer or installer Serial No.
State or Province No.
National Board No.
1 RC-01-BB/5GW-01 Babcock & Wilcox Industries 7722-03 1LU-242903 166 Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size Is 8 1/2 In. x ii in., (2) information in items 1 through 6 of this report is Included on each sheet, and (3) each sheet is numbered and the number ofsheets is recorded at the topof this form.
Computer Generated Form
1/5/2007
~Exek n..
Byron Station Unit 1 B1R14 iSI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 37 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name andAddress of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name andAddress of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-198
- 7. Components inspected:
Safety Injection System (SI)
Component or Appurtenance Manufacturer or Installer Manufacturer
~
State or Province No.
National Board No.
1SI8818B/BLT 1-16 Hunter Corp.
1-SI-i-N5 NA NA 1S18818B/INT SURF Hunter Corp.
1-Si-i-N5 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 In., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet Is numbered and the number of sheets is recorded at the topof this form.
Computer Generated Form
1/5/2007 ExeP~n~
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the ProvIsIons of the ASME Code Rules (Page 38 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-198
- 7. Components Inspected: Safety Injection System (SI)
Component or Appurtenance Manufacturer or Installer Manufacturer
~I~II N
State or Province No.
National Board No.
CLASS 1 SI PIPING -
LEAKAGE Hunter Corp.
NA NA NA Note: Supplemental sheets in form of lists, sketches, ordrawings may be used, provIded (1) size is 8 1/2 in. x ii in., (2) informatIon in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
ComputerGenerated Form
1/5/2007 Exekrn..
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 39 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Addressof Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-i98
- 7. Components inspected:
Safety Injection System (Si)
Component or Appurtenance Manufacturer or installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
1SIO2BA-6/1Si18043X Hunter Corp.
N/A N/A N/A i SIO3DA-2/i SIi 1 009X Hunter Corp.
N/A N/A N/A 1S1O3DA-2/lSli 1016X Hunter Corp.
N/A N/A N/A 1SIO5CA-8/iSIO1 026X Hunter Corp.
N/A N/A N/A 1S1O5CA-8/1 Sl02001X Hunter Corp.
N/A N/A N/A 1 SIO5DA-6/iSiOi 01 7X Hunter Corp.
N/A N/A N/A 1SIO5DA-6/1 SiOl 024V Hunter Corp.
N/A N/A N/A 1SIO5DA-6/1 SlOl 072X Hunter Corp.
N/A N/A N/A 1SIO5DA-6/iSIO1O73X Hunter Corp.
N/A N/A N/A 1SIO6BB-24/i S106042V Hunter Corp.
N/A N/A N/A 1SIO8GB-i-1/2/1 S125005X Hunter Corp.
N/A
~
N/A N/A 1SIO8GB-i-1/2/iS125006X Hunter Corp.
N/A N/A N/A 1S1O8HA-2/iSi25Ol5X Hunter Corp.
N/A N/A N/A Note: Supplemental sheets In form of lists, sketches, or drawings may be used, provIded (1) size is 8 1/2 in. x 11 In., (2) information in items 1 through 6 of this report Is included on each sheet, and (3) each sheet Is numbered and the numberof sheets is recorded at the top of this form.
ComputerGenerated Form
1/5/2007
- Exel~n Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of theASME Code Rules (Page 40 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name andAddress of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Nameand Address of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i 6/85
- 6. National Board Number for Unit:
N-198
- 7. Components inspected:
Safety injection System (SI)
Component or Appurtenance Manufacturer or installer Manufacturer or Installer Seriai No.
State or Province No.
National Board No.
iSIO8JA 1/2/iS124003X Hunter Corp.
N/A N/A N/A iS1O8JA i/2/1S124005X Hunter Corp.
N/A N/A N/A 1SIO8JA 1/2/1 S12401 4X Hunter Corp.
N/A N/A N/A Note: Supplemental sheets informof lists, sketches, or drawings may be used, provided (1) size is 81/2 In. xli in., (2) information In Items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
Computer Generated Form
1/5/2007 Exekin..
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the ProvisIons of the ASME Code Rules (Page 41 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name andAddress of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
i
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i 6/85
- 6. National Board Number for Unit:
N-i 98
- 7. Components Inspected:
Safety Injection System (SI)
Component or Appurtenance Manufacturer or installer Manufacturer
~
State or Province No.
National Board No.
1SIO1 B-24/C03 Hunter Corp.
NA NA NA lSlOiB-24/C04 Hunter Corp.
NA NA NA 1SIO1 B-24/C05 Hunter Corp.
NA NA NA 1SIO8GC-1.5iW-01 Hunter Corp.
1-Sl-1-N5 NA NA 1SIO8GC-1.5/W-02 Hunter Corp.
1-Sl-1-N5 NA NA 1SIO8GC-1.5iW-03 Hunter Corp.
i-SI-1-N5 NA NA iSIO8GC-i.5/W-04 Hunter Corp.
i-SI-1-N5 NA NA 1 SIO8GC-i.5/W-05 Hunter Corp.
1-SI-i -N5 NA NA 1SIO8HA-21W-01 Hunter Corp.
1-Sl-1-N5 NA NA 1 SIO8HA-21W-02 Hunter Corp.
1-SI-i -N5 NA NA 1SIO8HA-2,W-03 Hunter Corp.
1-Sl-1-N5 NA NA 1SIO8HA-ZW-04 Hunter Corp.
i-SI-1-N5 NA NA iSIO8JA-1.51W-06 Hunter Corp.
1-Sl-1-N5 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) sIze is 8 1/2 in. x 11 In., (2) Information In items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
Computer Generated Form
1/5/2007 Exek,n..
Byron Station UnIt 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 42 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, illinois 61010 (Name and Address04 Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Numberfor Unit:
N-i98
- 7. Components Inspected: Safety Injection System (SI)
Component or Appurtenance Manufacturer or installer Manufacturer
~
State or Province No.
National Board No.
iSIO8JA-1.5Mf-07 Hunter Corp.
i-Sl-1-N5 NA NA iSIO8JA-1.51W-08 Hunter Corp.
i-Si-1-N5 NA NA iS1O8JA-i.5/W-09 Hunter Corp.
1-Sl-i-N5 NA NA 1SIOSJA-i.5/W-10 Hunter Corp.
i-Sl-i-N5 NA NA 1 SiO8JA-1.5iW-i 1 Hunter Corp.
1-Si-i-N5 NA NA 1SIOSJA-1.5/W-12 Hunter Corp.
i-Sl-1-N5 NA NA 1SIO8JA-i.5,W-i3 Hunter Corp.
1-Sl-i-N5 NA NA 1SIO8JA-1.51W-i4 Hunter Corp.
1-Sl-i-N5 NA NA 1SIO8JA-i.51W-15 Hunter Corp.
1-Si-i-N5 NA NA 1SIO9BA-10/J13 Hunter Corp.
1-Sl-1-N5 NA NA iSIO9BA-iO/Ji4 Hunter Corp.
1-Sl-1-N5 NA NA 1SI18FB-2iW-01.01 NPSW Venture Corp.
1-SI-i-N5 NA NA 1S118FB-2/W-02.01 NPSW Venture Corp.
1-Sl-i-N5 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size Is8 1/2 in. xii in., (2) information in items 1 through 6 ofthis report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
Computer Generated Form
1/5/2007 Exekin..
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 43 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenviile, Illinois 60555 (Name and Address ofOwner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name andAddress of Plant)
- 3. Plant Unit:
1
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/i 6/85
- 6. NatIonal Board Number for Unit:
N-198
- 7. Components inspected: Safety Injection System (SI)
Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
1SI18FC-21W-0i.03 NPSW Venture Corp.
i-Sl-1-N5 NA NA 1SI18FC-2/W-02.03 NPSW Venture Corp.
1-Sl-i-N5 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x ii In., (2) information in Items 1 through 6 ofthis report Is Included on each sheet, and (3)each sheet is numbered and the number of sheets Is recorded at the top of this form.
Computer Generated Form
1/5/2007
-~
-~ Exekin..
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the ProvIsIons of the ASME Code Rules (Page 44 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenvilie, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Piant Unit:
1
- 4. Owner Certificate Of Authorization (it required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-i98
- 7. Components Inspected: Safety Injection System (SI)
Component or Appurtenance Manufacturer or installer Manufacturer
~
State or Province No.
National Board No.
1 SIO5CA-8/iSlOl025S Pacific Scientific 20071 NA NA 1 S1O5CA-8/i SIO2003S Pacific Scientific 6923 NA NA 1 SIO5CA-8/i S103003S Pacific Scientific 16673 NA NA 1S1O5CB-8/iS104024S Pacific Scientific 12170 NA NA 1SIO5CB-8/1SIO9006S Pacific Scientific 2058 NA NA 1 SIO5CB-8/i S109O43S Pacific Scientific 3195 NA NA i SIO5CB-8/iSl09043S Pacific Scientific 3195 NA NA Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 In., (2) informatIon in items 1 through 6 of this report is Included on each sheet, and (3) each sheet Is numbered and the number of sheets Is recorded at the topof this form.
Computer Generat.d Form
1/5/2007 Exekin..
Byron Station Unit 1 B1R14 lSI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 45 of 46)
- 1. Owner:
Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
- 2. Plant:
Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 6i010 (Name and Address of Plant)
- 3. Plant Unit:
i
- 4. Owner Certificate Of Authorization (if required):
N/A
- 5. Commercial Service Date:
09/16/85
- 6. National Board Number for Unit:
N-i98
- 7. Components Inspected: Essential Service Water System (SX)
Component or Appurtenance Manufacturer or Installer Manufacturer
~
State or Province No.
National Board No.
iSXO6CA-14/i SXO6003X Hunter Corp.
N/A N/A N/A 1SXO6CA-14/1 SXO6004X Hunter Corp.
N/A N/A N/A 1SXO6EA-i 0/1 SXO6O14X Hunter Corp.
N/A N/A N/A 1SXO6EC-i 0/1 SX06023A Hunter Corp.
N/A N/A N/A iSXO7FA-16/1SXO800iR Hunter Corp.
N/A N/A
~
N/A 1SXO8AD-10/iSX07024V Hunter Corp.
N/A N/A N/A Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 In. x 11 in., (2) infomiatlon in items 1 through 6 ofthis report is Included on each sheet, and (3) each sheet is numbered and the number of sheets Is recorded at the top of this form.
ComputerGenerated Form
1/5/2007
- ExeI~n..
Byron Station Unit 1 B1R14 ISI Outage Report FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 46 of 46)
(BACK)
- 8. ExamInation Dates:
3/26/05 to 10/16/06
- 9. InspectIon Period Identification:
First Insoection Period
- 10. inspection Interval IdentificatIon:
Third Inspection Interval
- 11. Applicable Edition of SectIon Xl:
2001 Addenda 2003
- 12. Date / Revision of Inspection Plan:
8/1/06
/
i
- 13. Abstract of Examinations and Test. Include a list of examinations and tests and a statement concerning status of workrequired for the Inspection Plan.
Refer to the Outage Summary Report and lSl Program Plan
- 14. Abstract of Results of Examinations and Tests.
Refer to the Outage Summary Report
- 15. Abstractof Corrective Measures.
Refer to the Outage Summary Report We certify that a) the statements made in this report are correct, b) the examinations and tests meetthe Inspection Plan as required bythe ASME Code, Section Xl, and c) corrective measures taken conform to the rules of the ASME Code, Section Xl.
Certificate of Authorization No. (if applIcable):
N/A Expiration Date:
N/A Date: i/ ~S/b~7 Signed for:Exelon Generation Company By:
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commision issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford CT.
have inspected the components described in this Owners Report during the period 3/26/05 to 10/16/06
, and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, and corrective measures described in this Owners Report. Futhermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
~7 I
~J L.1J Inspectors Signature Commissions:
ILL1254 Date: ______________________, 20 P F National Board, State, Province, and Endorsements Computer Generated Form
B1R14 FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules
- 1. Owner: Exelon Generation Company (EGG, LLC) 4300 Winfield Road Warrenville, IL 60555 (Name and Address of Owner)
- 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
One (i)
- 4. Owner Certificate of Authorization:
N/A
- 5. Comercial Service Date:
09/i 6/85
- 6. National Board Number of Unit:
N-198
- 7. Components Inspected: Class 2 System Pressure Tests Component or Appurtenance Manufactureror Installer Manufacturer or State or Province Installer Serial No.
Number National Board Number C7.30 CV-2-1 Hunter Corporation N/A N/A N/A C7.30 CV-2-2 Hunter Corporation N/A N/A N/A C7.30 P5-2-i Hunter Corporation N/A N/A N/A C7.30 PS-2-2 Hunter Corporation N/A N/A N/A C7.30 SD-2-1 Hunter Corporation N/A N/A N/A C7.50 1CV-01-PA CV.2-1 Pacific Pump 149770 N/A 198 C7.50 i CV-01 ~PB CV-2-2 Pacific Pump 49771 N/A 201 C7.70 GV-2-1 Hunter Corporation N/A N/A N/A C7.70 CV-2-2 Hunter Corporation N/A N/A N/A C7.70 P5-2-i Hunter Corporation N/A N/A N/A C7.70 PS-2-2 Hunter Corporation N/A N/A N/A C7.70 SD-2-1 Hunter Corporation N/A N/A N/A ComputerGenerated Form Page 1 of 2
B1R14 FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules
- 8. Examination Dates:
March 26, 2005 to October 16, 2006
- 9. InspectionPeriod identification:
Third Period
- 10. inspection Interval Identification:
Second Interval
- 11. Applicable Edition of Section XI 1989 Edition with No Addenda
- 12. Date/Revision of Inspection PLan:
July 15, 2006 / Revision 8
- 13. Abstractof Examinations and Test. Include a list of examinations and tests and a statement concerning statusof work required for the Inspection Plan.
Referto the Outage Summary Report and ISI Program Plan. All examinations and tests are within the completion requirements specified in the applicable Section XI subsections.
- 14. Abstract of Results of Examinations and Tests.
Refer to the Outage Summary Report.
- 15. Abstract of CorrectiveMeasures.
Refer to the Outage Summary Report.
We certify that a) the statements made in this report are correct, b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xl, and C) corrective measures taken conform to the rules of the ASME Code, Section Xl.
Certificate of Authorization No. (If applicable):
N/A Expiration Date:
N/A Date:
17 Signed For:
Exelon Generation Company By:
/h1Cj~d~
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by Hartford Steam Boiler of CT of Hartford. CT have inspected the components described this Owners Report during the period 3/26/2005 to 10/16/2006 and state that to the best of myknowledge and belief, the owner has performed examinations and tests and taken corrective measures described in this Owners Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, and corrective measuresdescribed in the Owners Report. Futhermore, neither the Inspector nor his employer shall be liable in any manner forany personal injuly or propertydamage or a loss of any kind arising from orconnected with this inspection.
-~
~
Commissions:
ILL-i254 Inspectors Signature National Board, State, Province, and Endorsements Date: _________________, 20 ~
Computer Generated Form Page 2 of 2
B1R14 FORM NIS-i OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules
- 1. Owner: Exelon Generation Company (EGC, LLC) 4300 Winfield Road Warrenville, IL 60555 (Name and Address of Owner)
- 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
One (1)
- 4. Owner Certificate of Authorization:
N/A
- 5. Comercial Service Date:
09/16/85
- 6. National Board Number of Unit:
N-198
- 7. Components Inspected: Class 1 System Pressure Tests or I
Manufacturer or Appurtenance J
Installer I
Manufacturer or j_Installer Serial No.
State or Province Number National Board I
Number Westinghouse 1 AC-Ol-R Corporation 640-0004-51 B-09061 N-198 Westinghouse 1 RC-01-R Corporation 640-0004-52 B-09061 N-198 Westinghouse 1 RY-Ol -S Corporation 1721 U-201291 W13580 Babcock & Wilcox RC-01-BA Incorporated 7720-02 ILU-242904 165 Babcock & Wilcox RC-01-BB Incorporated 7720-03 ILU-242903 166 Babcock & Wilcox RC-01-BC Incorporated 7720-01 ILU-242902 164 Babcock & Wilcox AC-Ol-BD Incorporated 7720-04 ILU-242901 167 Hunter Corporation 1 Piping N/A N/A N/A Westinghouse AC-Ol-PA Corporation 1-115E121-G01 N/A W25819 Westinghouse RC-01-PB Corporation 2-1 15E121-G01 N/A W25820 Westinghouse AC-Ol-PC Corporation 3-115E121-G01 N/A W25821 Westinghouse RC-01-PD Corporation 4-115E121-G01 N/A W25822 Hunter Corporation 1 Valves N/A N/A N/A ComputerGenerated Form Page 1 of 5
B1R14 FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules
- 1. Owner: Exelon Generation Company (EGC, LLC) 4300 Winfield Road Warrenville, IL 60555 (Name and Address of Owner)
- 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
One (1)
- 4. Owner Certificate of Authorization:
N/A
- 5. Comercial Service Date:
09/16/85
- 6. National Board Number of Unit:
N-1 98
- 7. Components Inspected: Class 2 System Pressure Tests Component or Appurtenance I
Manufacturer or Installer Manufacturer or Installer Serial No.
State or ProvInce Number National Board Number C2.33 1 RH-02-AA Joseph Oat Corporation 2267-lA U122326 836 C2.33 1 RH-02-AB Joseph Oat Corporation 2267-lB U122327 837 C7.10 AF-2-1 Hunter Corporation N/A N/A N/A C7. 10 AF..2-2 Hunter Corporation N/A N/A N/A C7.10 CS-2-1 Hunter Corporation N/A N/A N/A C7.10 CS-2-2 Hunter Corporation N/A N/A N/A C7.10 CV-2-3 Hunter Corporation N/A N/A N/A C7.10 CV-2-4 Hunter Corporation N/A N/A N/A C7.10 CV-2-E Hunter Corporation N/A N/A N/A C7.10 CV-2-6 Hunter Corporation N/A N/A N/A C7.10 CV-2-7 Hunter Corporation N/A N/A N/A C7. 10 CV-2-l Hunter Corporation N/A N/A N/A C7.10 CV-2-~ Hunter Corporation N/A N/A N/A C7.10 CV-2-1 0 Hunter Corporation N/A N/A N/A C7.10 FC-2-1 Hunter Corporation N/A N/A N/A C7.10 FP-2-1 Hunter Corporation N/A N/A N/A C7.10 FW-2-1 Hunter Corporation N/A N/A N/A ComputerGenerated Form Page 2 of 5
B1R14 FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules
- 1. Owner: Exelon Generation Company (EGG, LLC) 4300 Winfield Road Warrenville, IL 60555 (Name and Addressof Owner)
- 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
One (1)
- 4. Owner Certificate of Authorization:
N/A
- 5. Comercial Service Date:
09/16/85
- 6. National Board Number of Unit:
N-i 98
- 7. Components Inspected: Class 2 System Pressure Tests (contd)
Component or Appurtenance 1
Manufactureror J
Installer 1
Manufacturer or J_Installer Serial No.
T State or Province Number 1
National Board J
Number G7.10 f~~22Hunter Corporation N/A N/A N/A C7.l0 MS-2-1 Hunter Corporation N/A N/A N/A C7.10 MS-2-2 Hunter Corporation N/A N/A N/A C7. 10 OG-2-1 Hunter Corporation N/A N/A N/A C7.l0 PC-2-l Hunter Corporation N/A N/A N/A C7.10 PS-2-3 Hunter Corporation N/A N/A N/A C7.l0 PS-2-~ Hunter Corporation N/A N/A N/A C7.l0 PS-2-5 Hunter Corporation N/A N/A N/A C7. 10 PS-2-6 Hunter Corporation N/A N/A N/A C7.10 RC-2-1 Hunter Corporation N/A N/A N/A C7.iO RH-2-i Hunter Corporation N/A N/A N/A C7.i0 RH-2-2 Hunter Corporation N/A
~
N/A N/A C7.10 RH-2-3 Hunter Corporation N/A N/A N/A C7.10 RH-2-4 Hunter Corporation N/A N/A N/A C7.10 RH-2-5 Hunter Corporation N/A N/A N/A C7.l0 RH-2-6 Hunter Corporation N/A N/A N/A C7.10 S1-2-1 Hunter Corporation N/A N/A N/A Computer Generated Form Page 3 of 5
B1R14 FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules
- 1. Owner: Exelon Generation Company (EGG, LLC) 4300 Winfield Road Warrenville, IL 60555 (Name and Address of Owner)
- 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
- 3. Plant Unit:
One (1)
- 4. Owner Certificate of Authorization:
N/A
- 5. Comercial Service Date:
09/16/85
- 6. National Board Number of Unit:
N-i 98
- 7. Components Inspected: Glass 2 System Pressure Tests (contd) or Computer Generated Form Page 4 of 5
B1R14 FORM NIS-i OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules
- 8. Examination Dates:
March 26, 2005 to October 16, 2006
- 9. Inspection Period Identification:
First Period
- 10. Inspection Interval Identification:
Third Interval
- 11. Applicable Edition of Section XI 2001 Edition through 2003 Addenda
- 12. Date/Revision of Inspection Plan:
August 1. 2006 / Revision i
- 13. Abstract ofExaminations and Test. Include a list of examinations and tests and a statement concerningstatus ofwork required for the inspection Plan.
Refer to the Outage Summary Report and ISI Program Plan. All examinations and tests are within the completion requirements specified in the applicable Section Xl subsections.
- 14. Abstract of Results ofExaminations and Tests.
Refer to the Outage Summary Report.
- 15. Abstract ofCorrective Measures.
Refer to the Outage Summary Report.
We certify that a) the statements made in this report are correct, b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI, and c) corrective measures taken conform to the rules of the ASME Code, Section Xl.
Certificate of Authorization No. (If applicable):
N/A Expiration Date:
N/A Date:
Signed For:
Exelon Generation Company By: ~
~
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by Hartford Steam Boiler of CT of Hartford. CT have inspected the components described this Owners Report duringthe period 3/26/2005 to 10/16/2006 and state that to the best of myknowledge and belief, the owner has performed examinationsand tests and taken corrective measuresdescribed in this Owners Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, and corrective measures described in the Owners Report. Futhermore, neither the Inspector nor his employer shall be liable in any manner for any personal injuryor property damage or a loss of any kind arising from orconnected with this inspection.
Commissions:
ILL-i 254 Inspectors Signature National Board, State, Province, and Endorsements Date:
20
~9~P Computer Generated Form Page 5 of 5
Section 5.0 Form NIS 2
BYRON STATION UNIT 1 REFUELING OUTAGE i4 INSERVICE INSPECTION REPORT 5.0 FORM NIS-2 DATA SHEETS A total of 80 ASME Form NIS-2, Owners Report for Repairs or Replacements, were filed during Byron Station Unit 1 Cycle 14. The following is a system summary of NlS-2s generated:
SYSTEM TOTAL NIS-2 REPORTS NUMBER OF PAGES AB
- Boric Acid 1
1 AF
1 CC
- Component Cooling 2
2 CV
- Chemical & Volume Control 6
6 DG
- Diesel Generator 4
4 DO
- Diesel Fuel Oil 2
2 FP
- Fire Protection 7
7 MS
- Main Steam 4
7 AC
- Reactor Coolant 2
4 RH
4 RY
- Reactor Coolant Pressurizer 13 13 SA
- Station Air 1
1 SD
- Steam Generator Blowdown 5
5 SI
- Safety Injection 8
10 SX
- Essential Service Water 15 15 VA
- Auxiliary Building Ventilation i
1 WO - Chilled Water 2
2 XX
- Spare Components 2
4 TOTAL 80 89 Section 5.0 Page 1 of 1
DOCUMENT NO.:
933885-08 REV. NO.:
0 FORM NIS-2 OWNERS REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl 1.
Owner Exelon Nuclear Date 8/24/06 Name 4300 WInfleld Road, WarrenvIlle, IL Sheet 1
of 1
Address 2.
Plant Byron Nuclear Power Station Unit 00 Name 4450 N. German Church Road, Byron, IL Work Order No. 00933885-08 Address Repair Organization, P.O. No., Job No., etc.
3.
Work Performed by Byron MechanIcal Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No.
Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4.
Identification of System AB BORIC ACID PROCESSING 5.
(a) Applicable Construction Code ASME Section III 1974 Edition, S75 Addenda, NONE Code Case (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity:
2001 Edltion/2003 Addenda (c)Section XI Code Case(s)
NONE 6.
Identification of Components Name of Component Name of Manufacturer Manufacturer Setial No.
National Board No.
Other Identification Year Built Corrected, Removed, or Installed ASME Code stamped (Yesor No)
DEMIN RESIN FILL PIPE STUB WELD WESTiNGHOUSE N-2301.40 73550 OABO3D 1976 INSTALLED YES 7.
Description of Work MAINTENANCE TO THE DEMIN RESIN SCREEN 8.
Test Conducted:
Hydrostatic 0 Other 0 Pressure Pneumatic 0 125 psi Nominal Operating Pressure ~
Exempt0 Test Temp.
Ambient
°F Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
CUT DEMIN RESIN FILL PIPE STUB AND REWELD TO ACCESS TO FACILITATE
FORM NIS-2 (Back) 9, Remarks Work Order No. 00933885-08 Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE I certifythat the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.
Type Code Symbol Stamp Not Applicable Certificate of Auth~rizationN Not ApplIcable Signed
(~ç~
~
C4rtI Date
.1
,20 06 Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of IllinoIs and employed by HSB CT of Hartford, CT have in pected the components described in this Owners Report during the period to
, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.
By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report.
Furthermore, neither the Inspectornor his employer shall be liable in any manner for any personal injury or roperty damageo a loss of any kind arising from or connected with this inspection.
Commissions
/zI.- /J5.f Inspectors Signature National Board, State Province, and Endorsements Date:
~i~<
,20
~
I DOCUMENT NO.:
11 REV. NO.:
0 FORM NIS-2 OWNERS REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions ofthe ASME Code Section XI 1.
Owner Exelon Nuclear Date 9/17/06 Name 4300 Winfield Road, Warrenvllle, IL Sheet 1
of 1
Address 2.
Plant Byron Nuclear Power Station Unit 01 Name 4450 N. German Church Road, Byron, IL Work Order No. 00811568-02 Address Repair Organization, P.O. No., Job No., etc.
3.
Work Performed by Byron Mechanical Type CodeSymbol Stamp Not Applicable Maintenance Name Authorization No.
Not ApplIcable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4.
Identification of System AF AUX FEEDWATER 5.
(a) Applicable Construction Code ASME Section III 19 74 Edition, S74 Addenda, N-249-1 Code Case thru -5 (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity: 2001 EdltionI2003 Addenda (c)
Section Xl Code Case(s)
NONE 6.
Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)
Component Manufacturer SerIal No.
No.
Identification Built U-BOLT W/ NUTS ITT GRINNELL NJA N/A 1AF15005G 1982 REMOVED NO U-BOLT W/
NUTS Bergen-Power Pipe Support Heat Code:
JB1214 and 805430-1 N/A CAT ID #42969 1AF15005G 1999 INSTALLED NO 3/4HEAVY HEX Nova Machine Trace Code:
N/A CAT ID #37031 2003 INSTALLED NO NUT J718 AF15005G U-BOLT W/ NUTS ITT GRINNELL N/A N/A 1AF15O12G 1982 REMOVED N
U-BOLT W/ NUTS Bergen-Power Pipe Support UTC Number:
0002744085 N/A CAT ID #35816 1AF15O12G 2006 INSTALLED NO 7.
Description of Work REPLACE U-BOLTS PER EC #355518 8.
Test Conducted:
Hydrostatic 0 VT-3 Other ~
Pressure Pneumatic 0 N/A psi Nominal Operating Pressure 0 Exempt 0 Test Temp.
N/A Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
FORM NIS-2 (Back) 9.
Remarks Work Order No. 00811568-02 Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp Not Applicable Certificate of uthorization No.
Not Applicable Signed S~
1~.
~
Date Il/i
,20 DL Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued bythe National Board of Boiler and Pressure Vessel inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have inspected the components described in this Owners Report during the period to
, and state that to the best of my knowledge and belief, the O~nerhas performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report.
Furthermore, neither the Inspectornor his employer shall be liable in any manner for any personal injury orproperty damage or a loss of any kind arising from or connected with this inspection.
Commissions
~it-jic~
Inspectors Signature National Board, State Province, and Endorsements Date:
1V~.a~/
,20 p~
I DOCUMENT NO.:
3A REV. NO.:
1 FORM NIS-2 OWNERS REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1.
Owner Exelon Nuclear Name Date 6/21/06 2.
3.
Unit 01 1
Work Order No. 00662470-01 Repair Organization, P.O. No., Job No., etc.
Type Code Symbol Stamp Not Applicable Authorization No.
Not Applicable Expiration Date Not Applicable 4.
Identification of System CC COMPONENT COOLING ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)
Component Manufacturer Serial No.
No.
Identification Built RELIEF VALVE CROSBY N56891-00-0001 N/A 1CC9422A 1974 REMOVED YES RELIEF VALVE CROSBY N56891-00-0021 N/A 1CC9422A 1977 INSTALLED YES NOZZLE CROSBY N90104-38-0023 N/A INSTALLED VLV;
~
1977 REMOVED YES NOZZLE CROSBY N90104-50-0039 INSTALLED VLV; N/A S/N:N56891-00-0021 1984 INSTALLED NO DISC CROSBY N90105-38-0023 N/A INSTALLED VLV; S/N:N56891-00-0021 1977 REMOVED YES DISC CROSBY N90105-50-0047 N/A INSTALLED VLV; S/N:N56891-00-0021 2003 INSTALLED NO 7.
Description of Work REPLACE RELIEF VALVE. REPLACE VALVE NOZZLE, DISC IN REPLACEMENT VALVE 8.
Test Conducted:
Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure ~
Exempt 0 Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
Sheet 4300 Winfleld Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Work Performed by Byron Mechanical Maintenance Name 4450 N. German Church Road, Byron, IL Address of 1
5.
(a) Applicable Construction Code ASME Section III 1971 Edition, W/72 Addenda, None Code Case (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity:
2001 Edltlon/2003 Addenda (c) Section Xl Code Case(s)
NONE 6.
Identification of Components Other 0 Pressure 130 psi TestTemp.
89
FORM NIS-2 (Back) 9.
Remarks Work Order 00662470-01 Applicable Manufacturers uata ~eportsto t~eauacnea CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.
Type Code Symbol Stamp Not Applicable of Au~ori~atio~t~
~
Not ApplIcable Date
,20 VL~
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have in,pecjed the components described in this Owners Report during the period to
~9/,~4%4c, and state that to the best of my knowledge and belief, the O~nerhas pertorme6 ex~iinationsand taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the inspector nor his employermakes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report.
Furthermore, neither the Inspector nor his employer shall be liable in any mannerfor any personal injury or property dama e or a loss of any kind arising from or connected with this inspection.
~li~s1~
Commissions
,2c7 Inspectors Signature National Board, State Province, and Endorsements Date:
~4
,20
~
(Final)
DOCUMENT NO.:
3.0 REV. NO.:
0 FORM NIS-2 OWNERS REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xi 1.
Owner Exelon Nuclear Date 09/15/06 Name 4300 Winfleld Road, Warrenville, IL Sheet 1
of 1
Address 2.
Plant Byron Nuclear Power Station Unit 01 Name 4450_N. German Church Road, Byron, IL Work Order No. 792386-01 Address Repair Orgaruzation, P.O. No., Job No., etc.
3.
Work Performed by N P S & W VENTURE Type Code Symbol Stamp Not Applicable Name Authorization No.
Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4.
Identification of System Component Cooling 5.
(a) Applicable Construction Code ASME Section III 1974
- Edition, S74 Addenda, 1644 Rev. 7, 1651, 1682, 1683, 1685, 1686, 1728, 1729, 1734, N-108, N-180 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c)Section XI Code Case(s)
NONE 6.
Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes orNo)
Component Manufacturer Serial No.
No.
Identification BUilt Snubber, PSA (PSA-1 /4~
Pacific Scientific 3348 N/A 1CC37014S 1977 Removed Yes Snubber, Lisega Lisega 30400002-05 N/A 1CC37014S 2004 Installed No 7.
Description of Work REPLACED SNUBBER 8.
Test Conducted:
Hydrostatic 9 VT-3 Other ~
Pressure Pneumatic D Nominal Operating Pressure 0 psi Test Temp.
Exempt 0
¶ Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size Is 81/2in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
FORM NIS-2 (Back) 9.
Remarks WO 792386-01 Applicable Manufacturers Data deports to ~eattached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp Not Applicable Certificate of Authorization No.
Not Applicable Signed Date
/°/-~(
,20 06 Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have i!),spe1pted the components described in this Owners Report during the period to
, and state that to the best of my knowledge and belief, th~O~nerhas performe~eIaminations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report.
Furthermore, neitherthe Inspector nor his employer shall be liable in any manner for any personal injury orproperty damage or a loss of any kind arising from or connected with this inspection.
Commissions Inspecto?s Signature National Board, State Province, and Endorsements Date:
,44~JA
,20 06 (Final)
I DOCUMENT NO.:
3.0 REV. NO.:
0 1
FORM NIS-2 OWNERS REPORT FOR REPNRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1.
Owner Exelon Nuclear Date 09/15/06 Name 4300Winfleld Road, Warrenvllle, IL Sheet 1
of 1
Address 2.
Plant Byron Nuclear Power Station Unit 01 Name 4450 N. German Church Road, Byron, IL Work Order No. 594993-01 Address Repak Organization. P.O. No., Job No., etc.
3.
Work Performed by N P S & W VENTURE Type Code Symbol Stamp Not Applicable Name Authorization No.
Not Appflcable 36400 S. Essex Road, WIlmington, IL 60481 ExpIration Date Not Applicable Address 4.
Identification of System Chemical Volume 5.
(a) Applicable Construction Code ASME Section III 1974 EditIon, S74 Addenda.
1644 Rev. 7, 1651, 1682, 1683, 1685, 1686, 1728. 1729, 1734, N-108, N-iSO Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement ActiVity 2001 EdItion / 2003 Addenda (C)
Section Xl Code Case(s)
NONE 6.
IdentificatIon of Components ASME Corrected, Code National Removed, or Stamped Name of Nameol Manufacturer Board Other Year Installed (Yes or No)
Lomponent Manufacturer Serial No.
No.
Identification B&llft Snubber, PSA-PaCific 7058 N/A 1CV15041-S1 1977 Removed Yes Snubber, Lisega Lisega 30400002-03 N/A 1CV15041-S1 2004 Installed No 7.
Description of Work REPLACED SNUBBER 8.
Test Conducted:
Hydrostatic 0 PneumatIc 0 Nominal Operating Pressure 0 Exempt0 VT-3 Other ~
Pressure psi Test Temp.
Note: Supplemental sheets In form of lists, sketches, or drawings may be used, provided (1) sIze is 81/2 in. x 11 in., (2)
Information In items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
FORM NIS-2 (Back) 9.
Remarks WO 594993-01
~ppiicaoie~anuiacturersusia ~eportsio De anacnea CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp Not Applicable Certificate of Signed No.
Not Owners Designee, Title Date /6/O
,20 06 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of IllInois and employed by HSB CT of Hartford, CT have inspected the components described in this Owners Report during the period g/,j /~
to
~/ij /~L
, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report In accordance with the requirements of the ASME Code, SectIon Xi.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report.
Furthermore, neither the Inspector nor his employer shall be liable In any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Commissions XL~
Inspectors Signature National Board, State Province, and Endorsements Date:
___________,2006 (Final)
DOCUMENT NO.:
3.0 REV. NO.:
0 FORM NIS-2 OWNERS REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI Owner Exelon Nuclear Date 09/15~6 Name 4300 WinfleId Road, Warrenvllle, IL Sheet 1
of 1
Address Plant Byron Nuclear Power Station Unit 01 Name 4450 N. German Church Road, Byron, IL Work Order No. 594995-01 Address Repair Organization, P.O. No., Job No., etc.
WorK Performed by N P S & W VENTURE Type Code Symbol Stamp Not Applicable Name Authorization No.
Not Applicable 36400 S. Essex Road, WIlmington, IL 60481 ExpiratIon Date Not Applicable Address Identification of System Chemical Volume Applicable Construction Code ASME Section III 1974 EditIon, S74 Addenda, 1644 Rev. 7, 1651, 1682, 1683, 1685, 1686, 1728, 1729, 1734, N-108, N-180 Code Case Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda Section XI Code Case(s)
NONE identificatIon of Components ASME Corrected, Code National Removed, or Stamped of Nameof Manufacturer Board Other Year Installed (Yes orNo)
Component Manufacturer Serial No.
No.
Identification Bullt PSA 2800 N/A 1CV15O41-S2 1977 Removed Yes Lisega Lisega 30400002-04 N/A 1CV15041-S2 2004 Installed No 7.
Description of Work REPLACED SNUBBER 8.
Test Conducted:
HydrostatIc 0 VT-3 Other ~
Pressure Pneumatic 0 Nominal Operating Pressure 0
_________psi TestTemp.
Note: Supplemental sheets in form of lists, sketches, or drawings maybe used, provided (1) sIze is 83~In. x ii in., (2)
Information in items 1 through 6on (his report is Included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe lop of this form.
Exempt0
FORM N1S-2 (Back) 9.
Remarks WO 594995-01 Applicable Manufacturers Data ~eponsio oe anacnea CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct arid this conforms to the requirements of the ASME Code, Section Xl.
Type Code Symbol Stamp Not Applicable Certificate of Authoriz tlon o.
Not Applicable Signed Date
/010
.20 06 Owner Owners Designee, Title CERTIFICATE OF iNSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have inspected the components described in this Owners Report during the period
?/iI 4~c~to 9I4~/e~,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neitherthe Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or roperty damage or a loss of any kind arising from or connected with this inspection.
Commissions
.Z1~/JY~
Inspectors Signature National Board, State Province, and Endorsements Date:
.20 06 (Final)
DOCUMENT NO.:
3-1 REV. NO.:
0 FORM NIS-2 OWNERS REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions ofthe ASME Code Section XI Owner Exelon Nuclear Date 09/17/06 Name 4300Wlntield Road, Warrenville, IL Sheet 1
of 1
Address Plant Byron Nuclear Power Station Unit 1
Name 4450 N. German Church Road, Byron, IL WorkOrder No.00793219-01 Address Repair Organization, P.O. No., Job No., etc.
Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplIcable Maintenance Name Authorization No.
Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address IdentIfication of System CV (Chemical Volume and Control)
Applicable ConstructIon Code ASME Section III 1971 Edition, W172 Addenda, None Code Case Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 EdItion~2003Addenda Section Xl Code Case(s)
None.
Identification of Components ASME Corrected, Code National Removed, or Stamped of Nameof Component Manufac~er Manufacturer Serial No.
Board No.
Other Identification Year Buift Installed (Yes or No)
Cover Kerotest
~
Body P-9911-1-(1)Z Cover P.991 1-2-(1)Z 9608 1CV8368C sIN NOl-18 1976 Removed Yes Cover Kerotest we~c~
Body P-9911-1-(1)Z Cover P-9911-2-(1)Z 9608 1CV8368C S/N: N01-18 1976 Installed Yes 8.
Test Conducted:
Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Other 0 Pressure Exempt~
psi Test Temp.
Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.
S I
7.
Description of Work Remove Existing Seal Weld and Re-install Seal Weld
FORM NIS-2 (Back) 9.
Remarks WO 00793219-01 5
Applicable Manufacturers uata deports to oe attacnea CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp Not Applicable Certificate of uthorization No.
Not ApplIcable Signed
~ at46{
4~Aw~.,
~
Cap/~fl,,ti41DyZ.
Date
/~2/.t~4.20 O~
Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued bythe National Board of Boiler and Pressure Vessei inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have i9sppcted the components described in this Owners Report during the period 5
_____________ to
, and state that to the best of my knowledge and belief, th~O~ner has perfoniid~1e~aminationsand taken corrective measures described inthis Owners Report in accordance with the requirements of the ASME Code, Section Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report.
Furthermore, nefther the Inspector nor his employer shall be liable in any mannerfor any personal injury or property damá~or a loss of any kind arising from or connected with this inspection.
Commissions ____________________
Inspectors Signature National Board, State Province, and Endorsements Date:
,V~/. 2/
,20 ti~
r DOCUMENT NO.:
Doc 3-1 REV. NO.:
0 FORM NIS-2 OWNERS REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1.
Owner Exelon Nuclear Date 9/18/06 Name 4300 Winfleld Road, WarrenvIlle, IL Sheet 1
of 1
Address 2.
Plant Byron Nuclear Power Station Unit 1
Name 4450 N. German Church Road, Byron, IL Work Order No. 00810976-01 Address Repair Organization, P.O. No., Job No., etc.
3.
Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplIcable Maintenance Name Authorization No.
Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4.
5.
6.
Identification of System CV Chemical and Volume Control.
(a) Applicable Construction Code ASME Section III 1971 Edition, Sf72 Addenda, 1649 Code Case (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity:
2001 Edition/2003 Addenda (C)
Section Xl Code Case(s)
None Identification of Components Nameof Name of Manufacturer National Board Other Year Corrected, Removed, or Installed ASME Code Stamped (Yes or No)
Component Manufacturer Serial No.
No.
Identification BuIft Crosby N56900-OO-0075 N/A 1CV8123 1998 Removed Yes Crosby N56900-OO-0017 N/A 1CV8123 1975 Installed Yes 7.
Description of Work Replace flanged relief valve.
8.
Test Conducted:
Hydrostatic 0 Other 0 Pressure Pneumatic 0 30 psi Nominal Operating Pressure ~
Exempt 0 Test Temp.
105 Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
FORM NIS-2 (Back) 9.
Remarks Work Order No. 00810976-01 Applicable Manufacturersl)ata Reports to bttchd CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.
Type Code Symbol Stamp Not ApplIcable Certificate of ~thorizationNo.
Not Applicable Signed
~
S Date LI/vt.
,20 t9(~~
Owne r Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued bythe National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have in,pected the components described in this Owners Report during the period to
, and state that to the best of my knowledge and belief, th6 OW?ter has performedex~riinationsand taken corrective measures described in thisOwners Report in accordancewith the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report.
Furthermore, neitherthe Inspector nor his employershall be liable in any manner for any personal injury or property d ageor a loss of any kind arising from or corjnected with this inspection.
Commissions
/11-1154 Inspectors Signature National Board, State Province, and Endorsements Date:
jV~*~/7
,20 z~~
(Final)
I FORM NIS-2 OWNERS REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl 1.
Owner Exelon Nuclear Date 01/20/06 Name 4300 Winfleld Road, Warrenville, IL Sheet I
of I
Address 2.
Plant Byron Nuclear Power Station Unit 0
Name 4450 N. German Church Road, Byron1 IL Work OrderNo. 00811071-01 Mdress Repair Organization, P.O. No., Job No., etc.
3.
Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No.
Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4.
Identification of System CV-CHEMICAL & VOLUME CONTROL - SPARE VALVE 5.
(a) Applicable Construction Code ASME Section Ill 1971 Edition, W/72 Addenda, None Code Case (b)
Applicable Edition of Section Xl Used for Repair/Replacement Activity: 2001 Edition!2003 Mdenda (C)
Section Xl Code Case(s)
None 6.
Identification of Components t
Nameof Component Nameof Manufacturer Manufacturer Serial No.
National Board No.
Other Identification Year Built Corrected, Removed, or installed Code ASME Stamped (Yes orNo)
NOZZLE CROSBY N90137-49.0162 N/A CAT ID: 27689 S/N:N56903-0O-0027 1979 REMOVED NO NOZZLE CROSBY
~
N90137-08-0346 N/A CAT ID: 27689 S/N:N56903-O0-0027 1998 INSTALLED NO DISC INSERT CROSBY N90448-39-0137 N/A CAT ID: 27689 S/N:N56903-00-0027 1979 REMOVED NO DISC INSERT CROSBY N90448-97-0359 N/A CAT ID: 27689 SIN:N56903-O0-0027 2004 INSTALLED NO 7.
Description of Work REPLACE NOZZLE AND DISCINSERT IN SPARE VALVE RETURN VALVE TO STORES UNDER CAT. ID.:27689.
8.
Test Conducted:
Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Exempt ~
Spare Valve Other 0 Pressure n/a psi Test Temp.
n/a
°F Note: Supplemental sheets In form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 In., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets Is recorded at the top of this form.
FORM N1S-2 (Back) 9.
Remarks Work Order No. 00811071-01 Applicable Manufacturers Data Keports to be attacneci RELIEF VALVE S/N: N56903-00-0027 REMOVED FROM ICVI 17 UNDER W/O 00617355.
CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.
Type Code Symbol Stamp Not Applicable Certificate of Au orization No.
Not Applicable Signed
~
Date 20
~(~-
(~or O%~nersDesignee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Provinceof Illinois and employed by HSB CT of Hartford, CT have inspected the components described in this Owners Reportduring the period to
, and state that to the best of my knowledge and belief, tf~eowner has performed ~aminaflonsand taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.
By signing this certificate neither the Inspector nor his employermakes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report.
Furthermore, neitherthe Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Commissions lii- /~V Inspectors Signature National Board, State Province, and Endorsements Date:
20 Ob (FINAL)