ML13008A077
| ML13008A077 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/03/2013 |
| From: | Exelon Generation Co, Exelon Nuclear |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Byron 2013-0005 | |
| Download: ML13008A077 (10) | |
Text
BYRON UNIT 1 B1R18 Fall 2012 Outage INSERVICE INSPECTION
SUMMARY
REPORT For Inspection Activities from April 24, 2011 to October 8, 2012 Commercial Service Date September 16, 1985 Document Completion Date January 3, 2013 Exelon Generation Company (EGC, LLC) 4300 Winfield Rd Warrenville, IL 60555 Byron Nuclear Power Station 4450 North German Church Rd.
Byron, IL 61010
B1R18 INSERVICE INSPECTION
SUMMARY
REPORT SECTION SECTION DESCRIPTION PAGES I i Cover Page I 1 I ii Table of Contents I 1 I 1.0 Report introduction I 6 I 2.1 ISI - Weld / Component Listing 17 2.2 PSI - Weld / Component Listing 3 Examination
- 2. 0 S ummary 2.3 PSI - Bolts, Pumps, and Valves Listing 2 T a bl es 2.4 ISI - Pressure Tests 11 2.5 1SI - Component Supports 8 2.6 ISI - Snubbers 5 3.0 Status of Examination Completion for the Program Plan I 7 I 4.0 Form NIS-1: Preservice and Inservice Examinations 46 1
5.0 Form NIS-2: Repairs / Modifications 79 6.0 Containment ISI Program Condition Reporting 7.0 1131R17 Summary Report Erratum Pages TOTAL PAGES IN REPORT 200
BYRON STATION UNIT 1 REFUELING OUTAGE 18 INSERVICE INSPECTION REPORT 1.
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 April 24, 2011, through October 8, 2012. The majority of these inspections were performed during the eighteenth refueling outage (B1 R18) from September 10 through October 8, 2012.
B1 R18 is the second outage of the Second Period in the Third Inspection Interval.
The examinations were performed in compliance with the rules and regulations of ASME Section XI (applicable edition and addenda), pursuant to the requirements of 10 CFR 50.55a.
See Section 1.7.0 for a listing of referenced documents.
This summary report meets the requirements of ASME Code, IWA-6000 for the inspection of Class 1 and 2 components and piping. Class CC and MC components in the Containment Inservice Inspection (CISI) program are included when examination results require reporting as specified in 10 CFR 50.55a.
The Nondestructive Examination (NDE) Inservice Inspection (ISI) Program Plan for Class 1, 2, 3, CC, and MC components was developed in accordance with the requirements and intent of Section XI Subsections IWA, IWB, 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 and industry initiatives (NEI-03-08) were required. The Byron Station Unit 1 augmented ISI examination requirements include:
a) Class 1 pressure boundary for leakage at nominal operating pressure, in accordance with NRC Generic Letter 88-05; b) Class 1 Alloy 600 weld examinations in accordance with N-722, and N-729-1; c) Class 2 and 3 pressure boundary for leakage at nominal operating pressure, in accordance with NUREG 0737.
d) Class 1 examinations of non-isolable Reactor Coolant System branch lines for Thermal Fatigue in accordance with MRP-146; Note: Specific requests for relief were developed and submitted for NRC review when the code and/or augmented requirement(s) were deemed impractical, results in excessive hardship, or an alternative examination method is determined as more suitable for the particular component.
1.1.1 Identification of Examination Requirements The Section 7.0 of the ISI Program Plan contains the examination program tables. These tables are consistent with the tables found in Subsections IWB, IWC, IWD, IWE, IWF, and IWL-2500 of Section XI of the ASME Code. The examination tables include the corresponding code category, item number, and component/weld selection in conformance with examination requirements of Subsections IWA, IWB, IWC, IWD, IWE, IWF, and IWL.
Section 1.0 Page 1 of 6
BYRON STATION UNIT 1 REFUELING OUTAGE 18 INSERVICE INSPECTION REPORT d
For Class 1, 2, and certain non-class piping components, the requirements of Risk Informe Inservice Inspection (RI-ISI) are followed using EPRI TR1126 57 and Table 1 of ASME Code Case N-578-1.
Augmented examinations as specified by NRC and industry initiatives are included in these tables.
1.1.2 Identification of Exempted Components in ASME Class 1 and Class 2 components, or parts of components, that are not included ation, as specifie d in Section XI the examination tables and are exempt from examin d in Paragraphs IWB and IWC-1200, and Tables IWB-2500-1 and IWC-2500-1 are identifie exempt ing the the ISI Program Plan in conjunction with technical justification(s) for component or system.
Class 1 or 2 piping welds exempted by IWB and IWC-1200 are not included in the RI-ISI and program. Previous selection and examination exemptions identified in Tables IWB not IWC-2500-1 for the piping Examination Categories B-F, B-J, C-F-1, and C-F-2, are d as incorporated into the RI-ISI program. With the adoption of RI-ISI, piping welds classifie Risk Category 6 or 7 are not subject to examina tion.
1.1.3 Implementation of the ISI Program g
Exelon Nuclear, or its designee, visually examined ASME components utilizing the followin The compon ents examine d comply with the ISI test methods: VT-1, VT-2, and VT-3.
Program Schedule, Byron Station Technical Specifications, and/or comply with the ASME Section XI Repair/ Replacement Program.
and VT-Certified personnel performed and evaluated visual examinations (i.e., VT-1, VT-2,
- s. Exelon Nuclear personn el certifica tion
- 3) of Class 1, 2, and 3 components, and support procedures comply with the requirements of ANSI /ASNT CP- 189, 1995 Edition and ASNT SNT-TC -1A, 1984 Edition.
to the Certified personnel performed and evaluated all NDE. Personnel were certified Addition ally, ultrason ic examine rs requirements of the ASNT SNT-TC- 1A, 1984 Edition.
The NDE procedu res were certified in accordance with ANSI /ASNT CP- 189, 1995 Edition.
were developed and certified in conformance with ASME Section V and XI as applicable.
the All ISI NDE, including evaluation of flaw indications, were performed in accordance with nts incorpor ated into the requirements stipulated under Section XI IWA-2200. For compone tion RI-ISI program, the guidance for the examination volume for a given degrada tion mechanism is provided by the EPRI Topical Report while the guidance for the examina method is provided by Code Case N-578- 1. Augmented examinations are performed using the examination method specified in the governing regulatory or industry documents.
1.1.4 Significant Activities During B1 R18 d
The reactor vessel head surface and 100% of the head penetrations were visually examine for evidence of leakage per the require ments specifie d in N -729-1 for Item 84.10 components.
Section 1.0 Page 2 of 6
BYRON STATION UNIT 1 REFUELING OUTAGE 18 INSERVICE INSPECTION REPORT Ultrasonic examination of 100% of the RPV Head penetrations was performed as specified head in N-729-1 for Item B4.20 components. The examination results of the reactor penetrations were acceptable.
Two penetrations that were repaired in B1 R17 by an approved alternate process were d in examined by the liquid penetrant method. These follow up examinations were specifie the approved relief request 13R-19 for the B1 R17 nozzle repairs. Both nozzles revealed ined rejectable rounded indications. The nozzles were repaired by metal removal, re-exam after blending, and accepted for service.
1.1.5 ASME Section XI Code Cases 13R-02 The implementation of the risk- informed program as described in relief request utilized N -578-1.
NIS-2.
For Repair/Replacement activities, code cases are identified on the applicable Form N-460 Alternative Examination Coverage for Class 1 and Class 2 Welds.
N-508-3 Rotation of Serviced Snubbers and Pressure Relief Valves for the Purpose of Testing.
N-513-2 Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping.
N-566-2 Corrective Action for Leakage Identified at Bolted Connections.
N-597-2 Requirements for Analytical Evaluation of Pipe Wall Thinning.
N-639 Alternative Calibration Block Material.
N-665 Alternative Requirements for Beam Angle Measurements Using Refracted Longitudinal Wave Search Units.
N-685 Lighting Requirements for Surface Examination N-686-1 Alternative Requirements for Visual Examinations, VT-1, VT-2, and VT-3 N-700 Alternative Rules for Selection of Classes 1, 2, and 3 Vessel Welded Attachments for Examination.
N-705 Evaluation Criteria for Temporary Acceptance of Degradation in Moderate Energy Class 2 or 3 Vessels and Tanks N-706 Alternative Examination Requirements of Table IWB -2500- 1 and Table IWC-2500-1 for PWR Stainless Steel Residual and Regenerative Heat Exchangers N-753 Vision Tests 1.1.6 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANTI): Jeff Hendricks, Lee Malabanan, and Greg Feigel. These inspectors are associated with Hartford Steam Boiler CT of Harford, Connecticut, Chicago Branch, at 2443 Warrenville Rd., Suite 500, Lisle, Illinois 60532.
Section 1.0 Page 3 of 6
BYRON STATION UNIT 1 REFUELING OUTAGE 18 INSERVICE INSPECTION REPORT 1.2.0 EXAMINATION SUMMARIES g
The following section lists the summaries of examinations performed during the refuelin or for specific tests and cycle. Refer to Section 2.0 for each summary table for information examinations conducted during this term.
- Welds & Components Summaries Inservice Inspection - Weld / Component Listing Preservice Inspection - Weld / Component Listing Preservice Inspection - Bolts, Pumps, and Valves Listing
- System Pressure Test Summaries
- Component Support Examination Summary
- Component Snubber Test Summary 1.3.0 UNIT 1 EXAMINATION COMPLETION STATUS d in A summary table of the examination status of Class 1 and 2 components is containe Section 3.0.
1.4.0 FORM NIS- 1 DATA SHEETS ASME Form NIS-1 were filed during the cycle for Unit 1. See Section 4.0 for the reports.
1.5.0 FORM NIS-2 DATA SHEETS ASME Form NIS-2 were filed during the cycle for Unit 1. See Section 5.0 for the reports.
1.6.0 CONTAINMENT ISI PROGRAM See Reportable conditions were identified for Class MC components during this fuel cycle.
Section 6.0 for a description of the identified condition.
1.7.0 REFERENCED DOCUMENTS 1.7.1 Code of Federal Regulations Title 10 Energy Part 50, Domestic Licensing of Production and Utilization Facilities 50.55a, Codes and Standards 1.7.2 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section V, Nondestructive Examination, 2001 Edition, through 2003 Addenda Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 2001 Edition, through 2003 Addenda Subsection IWA: General Requirements Subsection IWB: Requirements for Class 1 Components Subsection IWC: Requirements for Class 2 Components Section 1.0 Page 4 of 6
BYRON STATION UNIT 1 REFUELING OUTAGE 18 INSERVICE INSPECTION REPORT Subsection IWD: Requirements for Class 3 Components Components Subsection IWE: Requirements for Class MC/Class CC Metallic Liners Supports Subsection IWF: Requirements for Class 1, 2, 3, and MC Component Subsection IWL: Requirements for Class CC Concrete Components a) IWA-2200 Examination Methods b) IWA-6000: Records and Reports c) IWB, and IWC-1 200, Components Exempt from Examination re Test d) IWB, IWC, IWE, IWF, and IWL-2500, Examination and Pressu Requirements Connections.
Code Case N-566-2: Corrective Action for Leakage Identified at Bolted or 3 Piping, Method B.
Code Case N-578-1: Risk-Informed Requirements for Class 1, 2, ing Welds in Class 1 Code Case N-722: Additional Examinations for PWR Pressure Retain Components Fabricated With Alloy 600/821182 Materials.
Code Case N-729-1: Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds Form NIS-1, Owners Report for Inservice Inspections.
Form NIS-2, Owners Report for Repairs or Replacements.
structive Testing 1.7.3 American National Standards Institute/ American Society for Nonde ANSI/ASNT CP-189, 1995 Edition, Standard for Qualification and Certifi cation of Nondestructive Testing Personnel.
1.7.4 American Society for Nondestructive Testing ASNT Recommended Practice No. SNT-TC-1 A, 1984 Edition, Personnel Qualification and Certification in Nondestructive Testing.
1.7.5 Miscellaneous NRC Documents Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressu re Boundary Components in PWR Plants.
NUREG 0737, Clarification of TMI Action Plan Requirements.
1.7.6 Electric Power Research Institute ice Inspection Topical Report TR1 12657 Revision B-A, Revised Risk-Informed Inserv Procedure, December 1999.
lly Stagnant Non-Materials Reliability Program: Management of Thermal Fatigue in Norma June 2011 Isolable Reactor Coolant System Branch Lines (MRP-1 46, Revision 1),
1.7.7 Nuclear Energy Institute NEI 03-08, Guideline for the Management of Materials Issues.
Page 5 of 6 Section 1.0
BYRON STATION UNIT 1 REFUELING OUTAGE 18 INSERVICE INSPECTION REPORT 1.7.8 Byron Station Documents Relief Request 13R-02: Alternate Risk-Informed Selection and Examination Criteria for Category B-F, B-J, C-F-1, and C-F-2 Pressure Retaining Piping Welds.
Relief Request 13R-19: Alternative Requirements for the Repair of a Reactor Vessel Head Penetration In Accordance with 10 CFR 50.55a(a)(3)(i)
Relief Request 13R-20: Request for Relief Alternative Requirements for the Repair of Reactor Vessel Head Penetrations In Accordance with 10 CFR 50.55a(a)(3)(i) 1.8 B1 R17
SUMMARY
REPORT ERRATUM 1.8.1 Report Identifies Incorrect Component The B1R17 90-Day Inservice Inspection Report, Weld/Component Outage Summary which was submitted to the NRC under docket STN50-454 on July 21, 2011 identified that the 1RH-01-PA-RHP E-2 Pump Lug was inspected. However, the supporting documentation was for the E-3 Pump Lug. The initially selected E-2 lug could not be completely inspected due to obstructions. The decision was made to inspect the E-3 lug instead because of these obstructions but the summary report was prepared using the original E-2 designation.
The revised report pages are attached at the end of this report. Reference IR 01398505.
1.8.2 Corrections to Form NIS-2 During the Byron Five-Year ISI Program FASA (AR 01254938), Work Order 1348440 Valve 1S18819D (and adjacent piping) Replacement work package was reviewed and the following issues regarding the repair/replacement requirements were found:
- 1) Since the valve provides the break between Class 1 and Class 2 portions of the system, two different pressure tests are applicable. The Class 2 portion was examined by VT-2 method at 800 psi during the full flow test on 3/31/2011 and the Class 1 portion was examined by VT- 2 method at 2237 psi in conjunction with ascending Mode 3 check valve testing on 4/22/2011. The Form NIS-2 completed for this replacement only acknowledges the Class 2 system leakage test. This was identified as Deficiency 4-1 in the 2011 ISI FASA.
- 2) The replacement check valve was provided with NPV-1 (Certificate Holders Data Report for Nuclear Pumps and Valves) and N -5 (Certificate Holders Data Report for Installation or Shop Assembly of Nuclear Power Plant Components, Supports, and Appurtenances) Forms. Neither of the Forms NPV-1 or N-5 was submitted with the B1 R17 ISI 90 Day Report. This is identified as Deficiency 4-2 in the 2011 ISI FASA.
The revised and the missing report pages are attached at the end of this report. Reference I R 01299748.
An extent of condition review was performed of the B1 R17 Form NIS-2 reports due to the results of the ISI self-assessment. This revealed one report that was missing the reference to an implemented construction code case in WO 01251724. The report was corrected and the work order record was amended with the revised pages.
The revised report pages are attached at the end of this report. Reference IR 01311443.
Section 1.0 Page 6 of 6