Similar Documents at Surry |
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Category:Letter
MONTHYEARML24283A0702024-10-0707 October 2024 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J IR 05000280/20244032024-10-0303 October 2024 Cyber Security Inspection Report 05000280-2024403 and 05000281-2024403 Cover Letter (Public) IR 05000280/20240102024-10-0202 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000280/2024010 and 05000281/2024010 ML24270A0022024-09-25025 September 2024 Inservice Inspection Owners Activity Report (OAR) ML24248A1712024-09-0303 September 2024 Proposed License Amendment Request - Temporary Service Water Supply to the Component Cooling Heat Exchangers IR 05000280/20240052024-08-26026 August 2024 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2024005 and 05000281-2024005), Rev 1 ML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24207A0402024-08-21021 August 2024 Summary of July 17, 2024, Public Meeting - TS 3.7/3.14 AOT for SW Piping Maintenance IR 05000280/20240112024-08-13013 August 2024 Comprehensive Engineering Team Inspection Report 05000280/2024011 and 05000281/2024011 ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 05000280/LER-2024-001, Troubleshooting Initiated Unknown Turbine Trip Feature in Control System2024-07-30030 July 2024 Troubleshooting Initiated Unknown Turbine Trip Feature in Control System ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24190A4192024-07-0808 July 2024 Inservice Testing (IST) Program for Pumps and Valves Revised Sixth IST Interval Start Date and Updated Technical Specifications References for Alternative Request V-1 ML24179A2932024-07-0101 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24157A0542024-06-13013 June 2024 Audit Summary in Support of License Amendment Request for Proposed Reclassification of Low Head Safety Injection Flow Instrumentation Related to Regulatory Guide 1.97 ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2302024-05-13013 May 2024 Core 1 Cycle 33 Pattern Mdr Revision 0 ML24130A2492024-05-0909 May 2024 Submittal of Information in Support of Surry Power Station Unit 1 Thermal Shield Flexure Replacement Campaign ML24130A2032024-05-0909 May 2024 Proposed License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections Supplemental Information ML24130A1192024-05-0707 May 2024 Inservice Test Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests - Response to Request for Additional Information Regarding Alternative Request V-1 ML24142A3852024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report IR 05000280/20240012024-04-30030 April 2024 Integrated Inspection Report 05000280-2024001 and 05000281-2024001 ML24122C6522024-04-30030 April 2024 Annual Radiological Environmental Operating Report ML24122B3032024-04-29029 April 2024 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change IR 05000280/20244022024-04-29029 April 2024 Security Baseline Inspection Report 05000280/2024402 and 05000281/2024402 ML24115A1952024-04-24024 April 2024 Notification of Surry Power Station Comprehensive Engineering Team Inspection - U.S. NRC Inspection Report 05000280/2024011 and 05000281/2024011 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24108A1812024-04-15015 April 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable Supplemental Information ML24095A2172024-04-12012 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report ML24088A2482024-03-26026 March 2024 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests- Response to Request for Additional Information ML24087A2082024-03-22022 March 2024 Proposed License Amendment Request Addition of Containment Limiting Condition for Operation and Surveillance Requirements ML24078A2642024-03-21021 March 2024 – Regulatory Audit in Support of License Amendment Request to Proposed Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML24087A1522024-03-18018 March 2024 Annual Changes, Tests, and Experiments Report Regulatory Commitment Evaluation Report ML24023A5762024-03-0808 March 2024 Correction to Issuance of Amendment Nos. 315 and 315, Regarding Revised Emergency Plan for Relocation of the Technical Support Center IR 05000280/20230062024-02-28028 February 2024 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - NRC Inspection Reports 05000280/2023006 and 05000281/2023006 ML24032A4712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24051A1782024-02-19019 February 2024 Proposed License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage IR 05000280/20230042024-02-0909 February 2024 Integrated Inspection Report 05000280/2023004 and 05000281/2023004 IR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 IR 05000280/20230102024-01-18018 January 2024 – Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure 2024-09-03
[Table view] Category:Report
MONTHYEARML24270A0022024-09-25025 September 2024 Inservice Inspection Owners Activity Report (OAR) ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML23167B0072023-05-31031 May 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Supplemental Information - LOCA Dose Calculation Summary ML23103A2282023-04-12012 April 2023 Stations Units 1 and 2; Millstone Power Station Units 2 and 3, DOM-NAF-2-P/NP-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML23054A1922023-02-22022 February 2023 ASME OM Code Inservice Testing Program Alternative Request V-01, Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing Supplemental Information ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML22263A3642022-05-23023 May 2022 Alert and Notification System Evaluation Report - ANS Evaluation Redacted Pages 1 - 95 ML22263A3692022-05-0101 May 2022 Alert and Notification System Evaluation Report - ANS Evaluation Redacted Pages 96-190 ML21175A2472021-06-24024 June 2021 2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....- ML20091L9852021-05-0404 May 2021 Record of Decision ML20091L9832021-05-0404 May 2021 SLR License ML21042B3212021-02-11011 February 2021 Stations, Units 1 & 2; Millstone Power Station, Units 2 & 3 - Request for Approval of Fleet Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML20296A6802020-10-22022 October 2020 ASME Section XI Inservice Inspection Program Request for NRC Approval of Proposed Alternative S1-I5-ISL-05 and S2-15-ISL-06 ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20203M1602020-07-20020 July 2020 VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status ML20076A5762020-05-28028 May 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment ML19249B7722019-08-29029 August 2019 Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated) ML19249B7682019-08-29029 August 2019 Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated) ML19249B7742019-08-29029 August 2019 Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated) ML19249B7782019-08-29029 August 2019 Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1 ML19235A0682019-08-19019 August 2019 3M Interam Website ML19235A0742019-08-19019 August 2019 Kbs Sealbags Website ML19235A0702019-08-19019 August 2019 Cera Blanket Website ML19235A0722019-08-19019 August 2019 Duxseal Website ML19235A0802019-08-19019 August 2019 Thermo-Lag Website ML19235A0692019-08-19019 August 2019 Bio K-10 Website ML19235A0782019-08-19019 August 2019 Mineral Wool Website ML19235A0732019-08-19019 August 2019 Gypsum Website ML19235A0712019-08-19019 August 2019 Cerafiber Website ML19235A0752019-08-19019 August 2019 Marinite Slide Plates Products - Piping Tech ML19235A0762019-08-19019 August 2019 Marinite Website ML19235A0772019-08-19019 August 2019 Micarta Website ML19235A0792019-08-19019 August 2019 Pyrocrete Website ML19204A3582019-06-30030 June 2019 WCAP-18258-NP, Revision 1, Flaw Tolerance Evaluation for Susceptible Reactor Coolant Loop Cast Austenitic Stainless Steel Elbow Components for Surry Units 1 and 2. ML19163A1542019-06-0606 June 2019 SLRA - Attachment 4D Letter - Draft to Dominion ML19140A2762019-05-20020 May 2019 Essential Fish Habitat Mapper Results for Surry Power Station ML19095A6022019-04-0202 April 2019 Enclosure 2 - SLRA Mark-Ups Change Notice 2 ML19011A1722019-01-0404 January 2019 Enclosure 3, Attachments 2C-3C - MPS3 EAL Technical Bases Document (Marked-Up) ML19011A1742019-01-0404 January 2019 Enclosure 5 - Surry Power Station, EAL Scheme Revisions-Supporting Documents ML19011A1732019-01-0404 January 2019 Enclosure 4 - North Anna Power Station Units 1 & 2, EAL Scheme Revisions-Supporting Documents ML18218A1712018-07-31031 July 2018 Attachment 5, ANP-3676NP, Revision 0, Surry Fuel-Vendor Independent Small Break LOCA Analysis, Licensing Report ML18108A1232018-04-11011 April 2018 Proposed Alternative Requests S1-15-ISl-04 and S2-15-ISl-04 Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography in Accordance with 10 CFR 50.55a(z)(1) ML17325A7792017-11-22022 November 2017 Review of Steam Generator Tube Report for the Fall 2016 Inspections During Refueling Outage 27 (CAC No. MF9683; EPID L-2017-LRO-0009) ML17339A1752017-09-0707 September 2017 Structural Integrity Associates Report No. 1601007.401, September 2017, Flaw Tolerance Evaluation of the Hot Leg Surge Line Nozzles Using ASME Code Section XI, Appendix L. ML17241A0462017-08-24024 August 2017 Submittal of Cycle 28 Startup Physics Tests Report ML17251A9002017-06-0505 June 2017 Enclosure 2, Attachment E to 17-296, WEKO-SEAL - Recommended Installation Procedures for Water and Waste-Water Piping, Miller Pipeline, Revised 03/05/17 ML16355A1722016-12-20020 December 2016 Storm Surge Technical Evaluation Report Surry Power Station Hazard Reevaluation Review ML15335A0932015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation2.1 of the Near-Term Task Force Review ML15244B2052015-08-24024 August 2015 Virginia Electric and Power Company (Dominion) Surry Power Station Unit 1, Cycle 27 Startup Physics Tests Report ML15097A0782015-04-0707 April 2015 Soarca Surry 2005 Site File 2024-09-25
[Table view] Category:Miscellaneous
MONTHYEARML24270A0022024-09-25025 September 2024 Inservice Inspection Owners Activity Report (OAR) ML23054A1922023-02-22022 February 2023 ASME OM Code Inservice Testing Program Alternative Request V-01, Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing Supplemental Information ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML20091L9832021-05-0404 May 2021 SLR License ML20091L9852021-05-0404 May 2021 Record of Decision ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20076A5762020-05-28028 May 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment ML19163A1542019-06-0606 June 2019 SLRA - Attachment 4D Letter - Draft to Dominion ML19140A2762019-05-20020 May 2019 Essential Fish Habitat Mapper Results for Surry Power Station ML18108A1232018-04-11011 April 2018 Proposed Alternative Requests S1-15-ISl-04 and S2-15-ISl-04 Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography in Accordance with 10 CFR 50.55a(z)(1) ML17325A7792017-11-22022 November 2017 Review of Steam Generator Tube Report for the Fall 2016 Inspections During Refueling Outage 27 (CAC No. MF9683; EPID L-2017-LRO-0009) ML15335A0932015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation2.1 of the Near-Term Task Force Review ML15097A0782015-04-0707 April 2015 Soarca Surry 2005 Site File ML15072A2992015-03-16016 March 2015 Review of the Fall 2013 Steam Generator Tube Inservice Inspection Report Regarding Surry Power Station, Unit 1 Refueling Outage 25 ML15078A2872015-03-12012 March 2015 Engineering Evaluation 14-E15, Dominion Flooding Hazard Reevaluation Report, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Revision 1, Pp. 1 Through 2-114 ML15078A2892015-03-12012 March 2015 Engineering Evaluation 14-E15, Dominion Flooding Hazard Reevaluation Report, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Revision 1, Pp. 2-219 Through the End ML15078A2882015-03-12012 March 2015 Engineering Evaluation 14-E15, Dominion Flooding Hazard Reevaluation Report, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Revision 1, Pp. 2-115 Through 2-218 ML14251A0352014-08-28028 August 2014 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML14086A1942014-04-0909 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14092A4142014-03-31031 March 2014 Response to March 12, 2012 Information Seismic Hazard and Screening Report (CEUS Sites) for Recommendation 2.1 ML13172A0092013-07-0101 July 2013 Nd 2, Closure Evaluation for Report Pursuant to 10 CFR 50.46(a)(3) Concerning Significant Emergency Core Cooling System Evaluation Model Error Related to Nuclear Fuel Thermal Conductivity Degradation ML12293A4512012-10-22022 October 2012 ACRS Assessment of the Quality of Selected NRC Research Projects- Fy 2012 ML12257A0862012-09-20020 September 2012 Review of the 2011 Refueling Outage System Generator Tube Inservice Inspection Report ML12166A1342012-06-27027 June 2012 Closeout of Bulletin 2011-01, Mitigating Strategies. ML12166A5192012-06-14014 June 2012 Transmittal of Final Accident Sequence Precursor (ASP) Analysis ML12073A3852012-03-0808 March 2012 Resources Services, Inc., Notification Letter That Surry Power Station Not Received a Copy of the Waste Shipment Record (Wsr) Signed by the Owner or Operator of the Designated Waste Disposal Site ML12046A8492012-02-27027 February 2012 Review of the Steam Generator Tube Inservice Inspection Report for the Refueling Outage in 2010 ML12024A0782011-12-28028 December 2011 State-of-the-Art Reactor Consequence Analysis (Soarca); Exclusive Summary for the Full NUREG for Peach Bottom and Surry ML1120701442011-07-26026 July 2011 Draft Letter Report, Entitled Risk-Informing EP Oversight: Evaluation of EALs Using Saphia Pilot Study of Peach Bottom and Surry ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML12124A2972010-03-11011 March 2010 Soarca Documents Review/Approval Process ML12124A2962010-02-25025 February 2010 Soarca Peer Review Comments ML0929905702009-10-26026 October 2009 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules ML0921908942009-08-0404 August 2009 Units 1 & 2, Millstone, Units 2 and 3 and Kewaunee - Approved Topical Report DOM-NAF-2, Revision 0.1-A ML0820701992008-07-18018 July 2008 Order EA-03-009 Sixty-Day Report Reactor Pressure Vessel Head Inspection Results ML0705903272007-02-27027 February 2007 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0623300712006-08-16016 August 2006 Fitness-for-Duty Program Semi-Annual Performance Data Report ML0634101622006-02-27027 February 2006 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0523501142005-08-22022 August 2005 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0523504842005-08-22022 August 2005 Owner'S Activity Reports ML0518804802005-07-0707 July 2005 Day Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML0514603252005-05-25025 May 2005 .2 & 3, North Anna Power Station Units 1 & 2, Surry Power Station Units 1 & 2 - Nuclear Liability Insurance Endorsement ML0506001202005-02-28028 February 2005 Owner'S Activity Reports ML0505403042005-02-22022 February 2005 Fitness-for-Duty Program Semi-Annual Performance Data Report Correction of Information ML0505300392005-02-21021 February 2005 Fitness-for-duty Program Semi-Annual Performance Data Report ML0424501642004-08-31031 August 2004 Transmittal of Fitness-for-Duty Program Semi-Annual Performance Data Report for Millstone, North Anna, and Surry Power Stations ML0318903372003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Millstone, Nort ML0234303432002-12-0202 December 2002 Response to Request for Additional Information, Dominion'S Reload Nuclear Design Methodology Topical Report ML19094A2461971-11-0404 November 1971 Transmittal of Final Report Concerning the Operating License Review 2024-09-25
[Table view] |
Text
Serial No.: 24-298 Docket No.: 50-280 Page 2 of 2
cc: U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue NE Suite 1200 Atlanta, Georgia 30303-1257
NRC Senior Resident Inspector Surry Power Station
Mr. J. Klos NRC Project Manager - Surry U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G9A 11555 Rockville Pike Rockville, Maryland 20852-2738
Mr. E. Miller NRC Senior Project Manager - North Anna U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738
Mr. R. Richardson Authorized Nuclear Inspector Surry Power Station Serial No.: 24-298 Docket No.: 50-280
Attachment:
Page 1 of 5
ATTACHMENT
OWNER'S ACTIVITY REPORT (FORM OAR-1 ),
SURRY UNIT 1 REFUELING OUTAGE S1 R32, THIRD PERIOD OF THE FIFTH ISi INTERVAL AND FIRST PERIOD OF THE SIXTH ISi INTERVAL
VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)
CASE
CASES OF ASME BOILER AND PRESSURE VESSEL CODE N-532-5 FORM OAR-1 OW NER'S ACTIVITY REPORT
Report Number 1-5-3-3/1-6-1-1 (Unit 1. 5th Interval. 3rd Period. 3rd Report: Unit 1. 6th Interval. 1st Period, 1st Report)
Plant ____ ~Su=rry-'-'"-'P~o=w=e~r.,,S=ta=ti=on=*~S=S~7~0~H=o..,_g_,,Isl=a=n=d,_,R..,o=a=d'-'. S=u.._rry....,_. """VA......:2=38=8=3.__ _________________ _
Unit No.. __ _ ___ 1=--- --- Commercial service (if applicable) date 12/22/1972 Refueling outage no. __ _,.S"'1R3=2~
Current inspection interval -------------- -....,.,...--=--'S~th"="-=,.,6th.,_,___,.----,-------- ------(lst, 2nd, 3rd, 4th, other)
Current inspection period 3rd 1st (1st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the inspection plans 2004 Edition/ 2019 Edition Date and revision of inspection plans Surry Unit 1 (5th Interval ISi Plan, Rev. 7 11/ 2021; 6th Interval ISi Plan, Rev 0. 12/ 2023)
Edition and Addenda of Section XI applicable to repair /replacement activities, if different than the inspection plans N/ A
Code cases used for inspection and evaluation: See Surry Unit 1. 5th Int and 6th Int.. ISi Plans Section 6 for complete list of code cases (if applicable, including cases modified by Case N-532 and later revisions)
CERTIFICATE OF CONFORMAN CE
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 S1R32 conform to the ~reme~ction XI. O ~ / l Jj "") 02.. u\\ (refueling outage number)
Signed c:l2J"'. ~ I ISI Progam Owner Date - 1 _ _ L-- - I owner or Owner's Designee, Title ---------,.__.'----- ------- ---
CERTIFICATE OF INSERVICE INSPECTIO N
I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by Toe Hartford Steam Boiler Inspection and Insurance Company of 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 a uation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal inj property damage or a loss of any kind arising from or connected with this inspection.
Commissions _ _:_I...:...> _°t___:7 __..:~ __ c_-=...J..>...:...T...L, _,J..,L,_fl.;::__ _______ _
Inspector's Signature (National Board Number and Endorsement)
Date_ G-'--\\ _n _ )_7:_0 _'1.. ____ ~ --
Page 1 of2 CASE
CASES OF ASME BOILER AND PRESSURE VESSEL CODE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT
Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service
Examination Category and Item Description Evaluation Description Item Number
NIA, N/A None Interval 5. ASME XI 2004 Ed.
Page 2 of2 CASE CASES OF ASME BOILER AND PRESSURE VESSEL CODE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT
Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service
Examination Category and Item Description Evaluation Description Item Number
NIA, NIA Pipe flaw in 2" line near valve, 1-SW-885 6. ASME XI 2019 Ed. A thru-wall leak was on a 2* pipe branch line off the Service (42"-WS-13-10), which supplies Service Water to the Component Cooling Heat Exchangers (CCHX). The piping flaw has been valuated in accordance with the 2019 Edition of SME Section XI (Appendix C and nonmandatory Appendix U-S1 and documented in Calculation CEM-0331. The analysis demonstrates the piping will maintain its structural integrity for all design conditions including seismic while in this degraded condition. Based on the corrosion rates, the piping uld be replaced f restored to its design n within two years (expected in 18 Requirements of Nonmandatory ppendix U including augmented examinations.
planned replacement, daily walkdowns, and requent examinations of the flaw are being complied with.
Page 1 of 1 CASE
CASES OF ASME BOILER AND PRESSURE VESSEL CODE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT
Table 2 Abstract of Repair/replacement Activities Required for Continued Service
Code Class Item Description Date Repair/Rep lace m e nt Description o f Wor k Completed Plan Numbe r 1 01-RC-R-1-VESSEL Interval 6. ASME XI 2019 Ed. 5/16/2024 2024-055 h"HERMAL SHIELD FLEXURE REPLACEMENT IAW DC SU 00128.
3 01-CC-E-1A Interval 5. ASME XI 2004 Ed. 2/10/2023 2021-136 Perform weld repairs to end bells.
3 01-CC-E-1B Interval 5. ASME XI 2004 Ed. 1/19/2023 2022-100 Perform weld repairs to end bells.
3 01-CC -E-1C Interval 6. ASME XI 2019 Ed. Perform 1/4/2024 2024-003 weld repairs to end bells.
3 01-CC-E-1C Interval 5. ASME XI 2004 Ed. 1/25/2023 2022-101 Perform weld repairs to end bells.
3 01-CC-E-10 Interval 6. ASME XI 2019 Ed. Perform 1/25/2024 2024-004
~eld repairs to end bells.
3 01 - CC-E-10 Interval 5. ASME XI 2004 Ed. 2/23/2023 2022-102 Perform weld repairs to end bells.
3 01-SW-518 Interval 6. ASME XI 2019 Ed. Pipe 5/22/2024 2024-089 and Flange Replacement on 2" flange upstream of01-SW-518
3 01-SW-PP-3.00-WS-PIPE-Interval 6. ASME XI 2019 Ed. Replace 3/11/2024 2024-057 544-21X pipe.
3 01-SW-PP-30.00-WS-Interval 5. ASME XI 2004 Ed. 2/9/2024 2024-053 PIPE-460-151 Perform weld repairs on 01-SW-PP-30.00-WS-PIPE-460-151.