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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARBYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23159A1302023-06-0808 June 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B1R25) BYRON 2023-0002, Unit 2, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2023-04-0606 April 2023 Unit 2, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements BYRON 2022-0045, Day Inservice Inspection Report for Interval 4, Period 2, (B2R23)2022-07-15015 July 2022 Day Inservice Inspection Report for Interval 4, Period 2, (B2R23) ML21355A4072021-12-21021 December 2021 Day Inservice Inspection Report for Interval 4, Period 2, (81 R24) BYRON 2021-0001, Day Inservice Inspection Report for Interval 4, Period 2, (B2R22)2021-01-13013 January 2021 Day Inservice Inspection Report for Interval 4, Period 2, (B2R22) ML20240A1422020-09-17017 September 2020 Day Inservice Inspection Report for Interval 4, Period 2, (B1R23) BYRON 2020-0053, Steam Generator Tube Inspection Report for Refueling Outage 232020-09-10010 September 2020 Steam Generator Tube Inspection Report for Refueling Outage 23 RS-20-085, Submittal of Relief Request I4R-11 for Braidwood Station, Units 1 and 2, and Relief Request I4R-18 for Byron Station, Units 1 and 2, Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2020-07-24024 July 2020 Submittal of Relief Request I4R-11 for Braidwood Station, Units 1 and 2, and Relief Request I4R-18 for Byron Station, Units 1 and 2, Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 ML19192A0492019-07-11011 July 2019 Day Inservice Inspection Report for Interval 4, Period 1, (B2R21) NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants2019-04-30030 April 2019 Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants BYRON 2018-0130, Transmittal of 90-Day Lnservice Inspection Report for Interval 4, Period 1, (B1R22)2018-12-20020 December 2018 Transmittal of 90-Day Lnservice Inspection Report for Interval 4, Period 1, (B1R22) BYRON 2018-0027, Steam Generator Tube Inspection Report for Refueling Outage 202018-04-0505 April 2018 Steam Generator Tube Inspection Report for Refueling Outage 20 BYRON 2018-0002, Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 3 and Interval 4, Period 1, (B2R20)2018-01-18018 January 2018 Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 3 and Interval 4, Period 1, (B2R20) RS-17-163, Withdrawal of Relief Request RV-2 Associated with the Fourth Inservice Testing Interval2017-11-20020 November 2017 Withdrawal of Relief Request RV-2 Associated with the Fourth Inservice Testing Interval BYRON 2017-0048, Day Inservice Inspection Report for Interval 3, Period 3 and Interval 4, Period 1, (BYR21)2017-06-15015 June 2017 Day Inservice Inspection Report for Interval 3, Period 3 and Interval 4, Period 1, (BYR21) RS-16-224, Relief Request for Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval2016-11-0808 November 2016 Relief Request for Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval ML16300A0362016-10-26026 October 2016 Fourth Ten-Year Interval Inservice Inspection Program BYRON 2016-0076, Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R19)2016-08-11011 August 2016 Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R19) ML16203A1082016-07-21021 July 2016 Fourth Ten-Year Interval Inservice Testing Program BYRON 2016-0011, Steam Generator Tube Inspection Report for Refueling Outage 202016-02-0505 February 2016 Steam Generator Tube Inspection Report for Refueling Outage 20 BYRON 2015-0152, Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 4, (B1R20)2015-12-29029 December 2015 Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 4, (B1R20) ML15216A6092015-08-20020 August 2015 Review of Fall 2014 Steam Generator Tube Inservice Inspection Report RS-15-170, Submittal of Relief Requests Associated with the Fourth Inservice Testing Interval2015-06-22022 June 2015 Submittal of Relief Requests Associated with the Fourth Inservice Testing Interval RS-15-155, Response to Preliminary RAI Regarding Braidwood and Byron Stations Relief Request for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations2015-05-29029 May 2015 Response to Preliminary RAI Regarding Braidwood and Byron Stations Relief Request for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations BYRON 2015-0009, 90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R18)2015-01-21021 January 2015 90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R18) RS-14-251, Revision to the Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations2014-09-0808 September 2014 Revision to the Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations BYRON 2014-0078, Day Inservice Inspection Report for Interval 3, Period 3, (B1R19)2014-06-24024 June 2014 Day Inservice Inspection Report for Interval 3, Period 3, (B1R19) BYRON 2013-0100, Day Inservice Inspection Report for Interval 3, Period 3, (B2R17)2013-07-29029 July 2013 Day Inservice Inspection Report for Interval 3, Period 3, (B2R17) ML13008A0772013-01-0303 January 2013 Inservice Inspection Summary Report, for Inspection Activities from April 24, 2011 to October 8, 2012 ML13008A0932013-01-0303 January 2013 Inservice Inspection Summary Report, Chapter 6.0, Containment ISI Program, Part 7 of 7-08X ML13008A0752013-01-0303 January 2013 Inservice Inspection Summary Report, Form NIS-2 Owner'S Report for Repair/Replacement Activity, as Required by the Provisions of the ASME Code Section XI ML13008A0732013-01-0303 January 2013 Inservice Inspection Summary Report, Form NIS-2 Owner'S Report for Repair/Replacement Activity, as Required by the Provisions of the ASME Code Section XI ML13008A0882013-01-0303 January 2013 Inservice Inspection Summary Report, Form NIS-1 Owner'S Report for Inservice Inspections, Part 4 of 7-05 ML13008A0802013-01-0202 January 2013 Inservice Inspection Summary Report, Weld/Component Outage Summary, Part 2 of 7-03 ML13008A0762013-01-0202 January 2013 Inservice Inspection Summary Report, Common-3rd Interval ASME Section XI Examination Status Report ML1129907832012-02-0101 February 2012 Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations BYRON 2012-0001, Steam Generator Inservice Inspection Summary Report for Refueling Outage 162012-01-0404 January 2012 Steam Generator Inservice Inspection Summary Report for Refueling Outage 16 BYRON 2011-0103, Day Inservice Inspection Report for Interval 3, Period 2, (B1R17)2011-07-21021 July 2011 Day Inservice Inspection Report for Interval 3, Period 2, (B1R17) RS-11-069, Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations2011-04-19019 April 2011 Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations ML1110105352011-04-0808 April 2011 Supplement to Byron Unit 1, Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations RS-11-045, Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations2011-03-24024 March 2011 Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations BYRON 2010-0042, Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 2, (B2R15)2010-08-0303 August 2010 Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 2, (B2R15) BYRON 2010-0041, Steam Generator - Inservice Inspection Summary Report for Refueling Outage 152010-07-23023 July 2010 Steam Generator - Inservice Inspection Summary Report for Refueling Outage 15 ML1000503572010-01-0505 January 2010 90-Day Inservice Inspection Report for Interval 3, Period 1, (B1R16) ML1000503622009-12-17017 December 2009 B1R16 Lsi Outage Report - Form NIS-1 Owner'S Report for Inservice Inspections ML1000503602009-12-17017 December 2009 B1R16 Lsi Outage Report, Bolts, Pumps, and Valves Outage Summary ML0902600752009-01-22022 January 2009 Inservice Inspection Report for Interval 3, Period 1, (B2R14), Cover Through Section 2.0 2023-06-08
[Table view] Category:Letter
MONTHYEARIR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 ML23320A1762023-12-13013 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0027 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23318A5102023-12-0101 December 2023 Relief from the Requirements of the ASME Code IR 05000454/20233012023-11-27027 November 2023 NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301 BYRON 2023-0065, Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline2023-11-17017 November 2023 Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) IR 05000454/20230032023-11-13013 November 2023 Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23313A0852023-11-0909 November 2023 Submittal of 2023-301 Byron Initial License Examination Post-Examination Comments RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23278A0272023-10-0505 October 2023 Operator Licensing Examination Approval - Byron Station, October 2023 RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23251A1622023-09-29029 September 2023 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) ML23242A3282023-09-0101 September 2023 Amendment No. 233 Correction IR 05000454/20235012023-08-31031 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000454/2023501 and 05000455/2023501 IR 05000454/20230052023-08-30030 August 2023 Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005) IR 05000454/20230022023-08-0303 August 2023 Integrated Inspection Report 05000454/2023002 and 05000455/2023002 ML23209A7242023-07-31031 July 2023 Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010 ML23192A0362023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 IR 05000454/20234022023-07-18018 July 2023 Baseline Security Inspection Document; 05000454/2023402; 05000455/2023402 ML23198A0372023-07-17017 July 2023 Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23172A1172023-06-22022 June 2023 Notification of NRC Fire Protection Team Inspection Request for Information RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23159A1302023-06-0808 June 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B1R25) ML23159A1542023-06-0808 June 2023 2022 Regulatory Commitment Change Summary Report RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process ML23157A2832023-06-0606 June 2023 Notification of NRC Baseline Inspection and Request for Information BYRON 2023-0029, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-06-0101 June 2023 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23003A7882023-05-11011 May 2023 Report for December 12-16, 2022, Regulatory Audit Regarding Reinsertion of a High Burnup Accident Tolerant Fuel Lead Test Assembly 2024-02-02
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Byron Generating Station 4450 North German Church Rd Exelon Generation Byron. IL 61010-9794 www.exeloncorp.com September 17, 2020 LTR: BYRON 2020-0056 FILE: 1.10.0101 (1D.101)
United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit 1 Facility Operating License No. NPF-37 NRC Docket No. STN50-454
SUBJECT:
Byron Station Unit 1 90-Day lnservice Inspection Report for Interval 4, Period 2, (B1 R23)
The subject 90-Day lnservice Inspection Report for the Byron Station Unit 1, Refueling Outage Twenty-Three (B 1R23) is being submitted pursuant to the requirements of Article IWA-6000, "Records and Reports" of Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code 2007 Edition I 2008 Addenda.
This letter provides a copy of Form OAR-1 Owner's Activity Report for inservice inspection activities performed during the previous fuel cycle. This report meets the requirements of the ASME Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice Summary Report Preparation and Submission." The report covers the inservice inspections conducted prior to and during the Unit 1 Spring 2020 refueling outage.
If there are any questions regarding this matter, please contact Ms. Zoe Cox, Regulatory Assurance Manager, at (815) 406-2800.
P----
Mark E. Kanavos Site Vice President Byron Generating Station MEK/DA/ZC/rm Attachment
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number B1 R23
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~--~
Plant Byron Generating Station, 4450 N German Church Road, Byron Illinois 61010 Unit No. Commercial Service Date September 16, 1985 Refueling Outage Number B1R23 (if applicable)
Current Inspection Interval Fourth Inspection Interval (ISi), Third Inspection Interval (CISI),
(1 ", 2°*, 3**, 4 1h, other)
Current Inspection Period Second Inspection period (ISi and CISI)
(1", 2°*. 3)
Edition and Addenda of Section XI applicable to the inspection plans ASME Section XI 2007 Edition through 2008 Addenda Date and Revision of inspection plans January 4th, 2017Rev1, August 18th, 2018 Rev 2 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same as above Code Cases used for inspection and evaluation: N-508, N-513-4, N-532-5, N-639, N-706, N-722-1, N-729-4, N-731, N-770-2, N-798, N-800 (if applicable, including cases modified by Case N-532 and later revisions)
CERTIFICATE OF CONFORMANCE I 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) the repair/replacement activities and evaluations supporting the completion of B 1R23 conform to the requir~ Section XI. / . *..__ _ (refueling outage number)
Sigood ~~*~ (Owner :OW:::::::: Date 8/10/2020 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford, Connecticut have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this 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 (I nspector';s]Qnai (National Board Number and Endorsement)
Date Page 1 of 3
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Examination Item Item Description Evaluation Description CateQorv Number Leak in Pipe to nozzle weld IR 04228044 upstream of OSX007 (U-0 CC HX D-8 02.10 N-513-4 evaluation performed under OCC01A SX OUTLET ISOL VLV)
EC 627561 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Date Repair/Replacement Class Description Of Work Completed Plan Number 3 OSX007 Weld Repair on SX through wall leak 05/29/2020 WO 04896208-01 Repairs and machining of OW001 CB 3 OW001CB 1/15/2019 WO 01819747-01 Condenser Chiller SX inlet and outlet pipe flange(s) 3 OSX33A 11/19/2018 WO 04750965-01 face repair/replace 3 OW001CA Perform OW001 CA Condenser Repairs 11/19/2018 WO 04691470-01 Page 2 of 3
ATTACHMENT 2 81 R23 CONTAINMENT ISi (IWE/IWL) RESULTS 81 R23 CONTAINMENT ISi (IWE/IWL) ACTIVITIES During the B1 R23 outage, examinations were completed of the Unit 1 containment liner for the IWE requirements. In addition, during the 23rd fuel cycle, the 35th-year tendon surveillance for Unit 1 and Unit 2 was completed .
ASME IWE/IWL REPORT OF CONTAINMENT DEGRADATION During the B1 R23 outage, examinations were completed of the Unit 1 containment liner to comply with the requirements of IWE-2500.
The following provisions of 10CFR50.55a were reviewed for conditions that require reporting in the B1 R23 ISi Summary Report.
Section XI Concrete containment examinations:
No conditions were found that warranted inclusion in this report as specified by (b)(2)(viii)(E).
Section XI Metal containment examinations:
Conditions were found that warranted inclusion in this report as specified by (b)(2)(ix)(A)(2).
==
Description:==
General Visual examinations of Accessible Surface Areas (Category E-A, Item 1.11) and Moisture Barriers (Category E-A, Item 1.30) of Containment Vessel Pressure Retaining Boundary were performed to meet the periodic inspection requirements of ASME Section XI, Table IWE-2500-1 .
Augmented examinations (Category E-C, Item 4.11 and 4.12) of containment liner were performed at 37 locations below the moisture barrier in accordance with the requirements of ASME Section XI , Table IWE-2500-1, "Category E-C, Containment Surfaces Requiring Augmented Examination". The scope of the examinations included locations that exhibited metal thickness losses greater than 1 /64" in B1 R21.
Inaccessible areas of the liner plate were made accessible by removing approximately 41' of the moisture barrier in B1 R23 under WO #04854505 . The as found condition of the degraded areas behind the moisture barrier is surface corrosion of the carbon steel containment liner. The observed environment is dry with inconsistently scattered areas of small pitting.
Recordable indications were found and documented in IR 04328319 on the following areas:
Area C1 Location 7: Surface rust and pitting 1/16 inches deep.
Area C3 Location 2: Surface rust and pitting 3/64 inches deep.
Area C11 Location 6: Surface rust and pitting 3/64 inches deep.
Evaluation and results:
The containment liner plate material loss due to inactive corrosion exceeded the allowable limit of 10% nominal liner thickness per the ASME code Section XI, Paragraph IWE-3521 (a) at Area C1 Location 7, Area C3 Location 2 and Area C11 Location 6. ASME code Section XI, Subsection IWE states when liner plate metal loss of more than 10% is identified then the condition shall be evaluated for acceptability or repair/replacement. As a supplemental examination, ultrasonic examinations were performed at the three locations exceeding 10%
metal loss. The results are as follows:
Minimum UT reading at Area C1 Location 7: 0.269 inches (UT Report #81R23-UT-030)
Minimum UT reading at Area C3 Location 2: 0.234 inches (UT Report #81 R23-UT-031)
Minimum UT reading at Area C11 Location 6: 0.252 inches (UT Report #81 R23-UT-032)
From the UT reports, it can be seen that Area C1 Location 7 and AREA C11 Location 6 still remain above the nominal thickness of the containment liner plate, which is 0.250". The UT results at AREA C3 Location 2 is acceptable per NDIT No. 8YR-99-226 which provides minimum allowable thickness for the containment liner plate to be 0.125 inches. The three locations exceeding 10% metal loss were previously examined in 81 R21, accepted per EC 618724 and remained essentially unchanged in 81 R23, therefore no longer require successive examination under Table IWE-2500-1, Examination Category E-C. Metal loss at Areas A 1 through A7 did not exceed the 10% nominal liner thickness and met the acceptance standards of IWE-3521 (a), therefore do not require augmented examination in accordance with Table IWE-2500-1, Examination Category E-C.
Corrective Actions:
All excavated areas have been properly cleaned and coated with Level 1 coating and new moisture barrier has been installed. These are corrective measures to further protect the containment liner plate from any future corrosion. The minimum wall thickness for each area has met the owner established acceptance criteria per NDIT No. 8YR-99-226.