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| {{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 August 13, 201510 CFR 50.410 CFR 50.55aATTN: Document Control DeskU. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit IFacility Operating License No. DPR-77NRC Docket No. 50-327 | | {{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 August 13, 2015 10 CFR 50.4 10 CFR 50.55a ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit I Facility Operating License No. DPR-77 NRC Docket No. 50-327 |
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| ==Subject:== | | ==Subject:== |
| | | Unit I Refueling Outage 20 Day Inservice Inspection Summary Report In accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, Article IWA-6230 and Code Case N-532-5, the Tennessee Valley Authority is providing the Sequoyah Nuclear Plant (SQN), Unit 1, Inservice Inspection (ISI) Summary Report within 90 days from completion of the Unit I Refueling Outage 20 (U1R20). The U1R20 refueling outage ended on May 16, 2015.Accordingly, this report is required to be submitted by August 14, 2015.The Enclosure to this letter contains the Owner's Activity Report, a list of items with flaws or relevant conditions that required evaluation for continued service (Table 1), an abstract of repair and replacement activities required for continued service due to a flaw or relevant condition (Table 2), and the evaluation of acceptability of inaccessible areas of the steel containment vessel in accordance with 10 CFR 50.55a(b)(2)(ix)(A). |
| Unit I Refueling Outage 20 Day Inservice Inspection SummaryReportIn accordance with the American Society of Mechanical Engineers (ASME) Boiler andPressure Vessel Code, Section Xl, Article IWA-6230 and Code Case N-532-5, theTennessee Valley Authority is providing the Sequoyah Nuclear Plant (SQN), Unit 1,Inservice Inspection (ISI) Summary Report within 90 days from completion of the Unit IRefueling Outage 20 (U1R20). | |
| The U1R20 refueling outage ended on May 16, 2015.Accordingly, this report is required to be submitted by August 14, 2015.The Enclosure to this letter contains the Owner's Activity Report, a list of items withflaws or relevant conditions that required evaluation for continued service (Table 1), anabstract of repair and replacement activities required for continued service due to a flawor relevant condition (Table 2), and the evaluation of acceptability of inaccessible areasof the steel containment vessel in accordance with 10 CFR 50.55a(b)(2)(ix)(A). | |
| There are no regulatory commitments associated with this submittal. | | There are no regulatory commitments associated with this submittal. |
| Should you haveany questions, please contact Erin Henderson at (423) 843-7170. | | Should you have any questions, please contact Erin Henderson at (423) 843-7170.Sequoyah Nuclear Plant --"/ |
| Sequoyah Nuclear Plant --"/ | | U.S. Nuclear Regulatory Commission Page 2 August 13, 2015 |
| U.S. Nuclear Regulatory Commission Page 2August 13, 2015 | |
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| ==Enclosure:== | | ==Enclosure:== |
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| ASME Section Xl Inservice Inspection Summary Report,Unit 1 Refueling Outage 20cc (Enclosure): | | ASME Section Xl Inservice Inspection Summary Report, Unit 1 Refueling Outage 20 cc (Enclosure): |
| NRC Regional Administrator-Region IINRC Senior Resident Inspector | | NRC Regional Administrator-Region II NRC Senior Resident Inspector |
| -Sequoyah Nuclear PlantNRC Project Manager -Sequoyah Nuclear Plant ENCLOSURE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNIT 1ASME SECTION XIINSERVICE INSPECTION SUMMARY REPORTUNIT I REFUELING OUTAGE 20 FORM OAR-I OWNER'S ACTIVITY REPORTReport. NumberUIC20PlantSEQUOYAH NUCLEAR PLANT. P.O. Box 2000. Soddy-Daisy, TN 37384-2000 Unit No. 1 Commercial service date July 1. 1981 Refueling outage no.(if epp:ic~e)Oe 20Current inspection intervalCurrent inspection periodThird Inspection Interval(1", 2. 2'. 4*, nurwlThird Inspection Period(V. 2> 31Edition and Addenda of Section XI applicable to the inspection plans2001 Edition, 2003 AddendaDate and revision of inspection plansMarch 27, 2015 SI-DXl-000-114.3, Revision 27Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans _____Not Applicable Code Cases used N.-460, N-513-3, N-532-4, N-532-5, N-566-2, N-586-1, N-686-1, N-706-1, N-716-1, N-722-1, N-729-1,for inspection and N-770-1evaluation: | | -Sequoyah Nuclear Plant NRC Project Manager -Sequoyah Nuclear Plant ENCLOSURE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNIT 1 ASME SECTION XI INSERVICE INSPECTION |
| (f urol.ae eL"i1.t u"J.. , | | |
| Sy Case N-532 aow wer. wsru(kisCERTIFICATE OF CONFORMANCE I certify that (al the statements made in this report are correct: | | ==SUMMARY== |
| Ib) the esarninations and tests meet the Inspection Plan as required bythe ASME Code Xl and (c) the repair/replacement activties and evaluations supporting the completion at UIC20conform to the requirements of Section XI. (yO!uoiw otorue w~/. lerDate 5"CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors andand employed by HSB Global Standards of Connecticut have inspected the itemsdescribed in this Owner's Activity Report, and elate that, to the best of my knowledge and belief, the Owner has performed allactivities represented by this report in accordance with the requirements of Section Xl.By signing this cartificate neither the Inspector nor his employer make any warranty, expressed or implied, concerning therepair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall beliable in mann pl} ersonal injury or property damage or a loss of any kind arising from or connected with this inspection. | | REPORT UNIT I REFUELING OUTAGE 20 FORM OAR-I OWNER'S ACTIVITY REPORT Report. Number UIC20 Plant SEQUOYAH NUCLEAR PLANT. P.O. Box 2000. Soddy-Daisy, TN 37384-2000 Unit No. 1 Commercial service date July 1. 1981 Refueling outage no.(if epp:ic~e)Oe 20 Current inspection interval Current inspection period Third Inspection Interval (1", 2. 2'. 4*, nurwl Third Inspection Period (V. 2> 31 Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition, 2003 Addenda Date and revision of inspection plans March 27, 2015 SI-DXl-000-114.3, Revision 27 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans _____Not Applicable Code Cases used N.-460, N-513-3, N-532-4, N-532-5, N-566-2, N-586-1, N-686-1, N-706-1, N-716-1, N-722-1, N-729-1, for inspection and N-770-1 evaluation: (f urol.ae eL"i1.t u"J.. , |
| __________________Commission | | Sy Case N-532 aow wer. wsru(kis CERTIFICATE OF CONFORMANCE I certify that (al the statements made in this report are correct: Ib) the esarninations and tests meet the Inspection Plan as required by the ASME Code Xl and (c) the repair/replacement activties and evaluations supporting the completion at UIC20 conform to the requirements of Section XI. (yO!uoiw otorue w~/. ler Date 5" CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and and employed by HSB Global Standards of Connecticut have inspected the items described in this Owner's Activity Report, and elate 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 Xl.By signing this cartificate neither the Inspector nor his employer make 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 mann pl} ersonal injury or property damage or a loss of any kind arising from or connected with this inspection. |
| ,/, 2t',twoewors OSlaaroaLt N atio.nal soarS Nuawber and Sn'f~~eoownl) | | __________________Commission ,/, 2t', twoewors OSlaaroaLt N atio.nal soarS Nuawber and Sn'f~~eoownl) |
| Date ~ tASME Code Section Xl Exception- | | Date ~ t ASME Code Section Xl Exception- |
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| ASME Category 8-0-1 (RCP hydrastuds) | | ASME Category 8-0-1 (RCP hydrastuds) |
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| Description:== | | Description:== |
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| Using the EPRI guidance, the performance demonstration completed for these exams w.,as not performed as a "btindtest" as required by ASME Section XI, Appendix VIII. Supplement 8, paragraph 2.0. This CR documents the issue and references the NRC issued EGM 14-003 as sufficient technical basis for accepting the examinations. | | Using the EPRI guidance, the performance demonstration completed for these exams w.,as not performed as a "btind test" as required by ASME Section XI, Appendix VIII. Supplement 8, paragraph 2.0. This CR documents the issue and references the NRC issued EGM 14-003 as sufficient technical basis for accepting the examinations. |
| E-1 ASME SECTION XlINSERVICE INSPECTION SUMMARY REPORTSEQUOYAH NUCLEAR PLANT UNIT 1 REFUELING OUTAGE 20TABLE IITEMS WITH FLAWS OR RELEVANT CONDITIONS THATREQUIRED EVALUATION FOR CONTINUED SERVICEExamination Category and Item Description Evaluation Description Item NumberEngineering evaluation, accept as is.The support remains functional. | | E-1 ASME SECTION Xl INSERVICE INSPECTION |
| ThisF-AFI.10D Missing outer hex nut from support 1-RCH- condition was previously identified inF-,F ID 114, Report R0039, NOI 1-SQ-516.
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| change document FCR #7927 andincorporated into calculation 1 RCH01 14, Attachment I.cleaanc beteenpadsandthe Engineering evaluation, accept as is.Improper claac ewe asadte A zero gap is acceptable as long asF-A, FI.40 seismic plates on support 1-CRDH-1, Report the total gap along the array does notR0036, NOI 1-SQ-515 exceed the limits.Boric Acid Evaluation, No additional C-H, C7 .10 Packing leak on 1-FCV-063-174, WO ato sncsay ovsa11670561evidence of corrosion. | | ==SUMMARY== |
| C-,C7 0 Packing leak on 1-FCV-063-0024, WO Boric Acid Evaluation, Cleaned andC-,C.0 116770560 | | REPORT SEQUOYAH NUCLEAR PLANT UNIT 1 REFUELING OUTAGE 20 TABLE I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Description Evaluation Description Item Number Engineering evaluation, accept as is.The support remains functional. |
| : observed, no active leak.E-2 ASME SECTION XIINSERVICE INSPECTION SUMMARY REPORTSEQUOYAH NUCLEAR PLANT UNIT 1 REFUELING OUTAGE 20TABLE 2ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURESREQUIRED FOR CONTINUED SERVICECode Item Description Date Repair/Replacement Class Description of Work Completed Plan NumberNo Applicable Repair/Replacement activities occurred duringq this period.REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A)
| | This F-AFI.10D Missing outer hex nut from support 1-RCH- condition was previously identified in F-,F ID 114, Report R0039, NOI 1-SQ-516. |
| ASME Section Xl, Subsection IWESteel Containment Vessel Inspection Program10 CER 50.55a(b)(2)(ix)(A) requires reporting of the degradation assessment for inaccessible areas when conditions are identified in accessible areas during the performance of the ASMESection Xl, Subsection IWE Steel Containment Vessel (SCV) Inspection Program that couldindicate the presence of or result in degradation to such inaccessible areas.The conditions identified during the SQN Unit 1 Cycle 20 refueling outage on the SCV in anaccessible area were determined to be acceptable and do not affect the degradation assessment for inaccessible areas.E-3}} | | change document FCR #7927 and incorporated into calculation 1 RCH01 14, Attachment I.cleaanc beteenpadsandthe Engineering evaluation, accept as is.Improper claac ewe asadte A zero gap is acceptable as long as F-A, FI.40 seismic plates on support 1-CRDH-1, Report the total gap along the array does not R0036, NOI 1-SQ-515 exceed the limits.Boric Acid Evaluation, No additional C-H, C7 .10 Packing leak on 1-FCV-063-174, WO ato sncsay ovsa 11670561evidence of corrosion. |
| | C-,C7 0 Packing leak on 1-FCV-063-0024, WO Boric Acid Evaluation, Cleaned and C-,C.0 116770560 observed, no active leak.E-2 ASME SECTION XI INSERVICE INSPECTION |
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| | ==SUMMARY== |
| | REPORT SEQUOYAH NUCLEAR PLANT UNIT 1 REFUELING OUTAGE 20 TABLE 2 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Code Item Description Date Repair/Replacement Class Description of Work Completed Plan Number No Applicable Repair/Replacement activities occurred duringq this period.REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A) |
| | ASME Section Xl, Subsection IWE Steel Containment Vessel Inspection Program 10 CER 50.55a(b)(2)(ix)(A) requires reporting of the degradation assessment for inaccessible areas when conditions are identified in accessible areas during the performance of the ASME Section Xl, Subsection IWE Steel Containment Vessel (SCV) Inspection Program that could indicate the presence of or result in degradation to such inaccessible areas.The conditions identified during the SQN Unit 1 Cycle 20 refueling outage on the SCV in an accessible area were determined to be acceptable and do not affect the degradation assessment for inaccessible areas.E-3}} |
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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML24298A1172024-10-24024 October 2024
Cycle 26, 180-Day Steam Generator Tube Inspection Report
ML24211A0412024-07-26026 July 2024
Unit 1 Cycle 26 Refueling Outage - 90-Day Inservice Inspection Summary Report
ML23233A0122023-08-17017 August 2023
Unit 1 Cycle 25 Refueling Outage - 90-Day Inservice Inspection Summary Report - Supplement
ML23192A0972023-07-11011 July 2023
Unit 2 Cycle 25 Refueling Outage - 90-Day Inservice Inspection Summary Report
ML23052A1662023-02-22022 February 2023
Cycle 25 Refueling Outage - 90-Day Inservice Inspection Summary Report
CNL-23-011, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2023-01-18018 January 2023
Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements
ML22038A0942022-02-0404 February 2022
Unit 2 Cycle 24 Refueling Outage - 90-Day Inservice Inspection Summary Report
CNL-21-076, Request for Alternative, 21-ISI-2, Alternative Inspection for Upper Head Injection J-groove Welds2021-09-0303 September 2021
Request for Alternative, 21-ISI-2, Alternative Inspection for Upper Head Injection J-groove Welds
ML21217A2882021-08-0404 August 2021
Cycle 24 Refueling Outage - 90-Day Inservice Inspection Summary Report
ML20056C7032020-02-24024 February 2020
Unit 1 Cycle 23 Refueling Outage -90-Day Inservice Inspection Summary Report
ML19126A2742019-04-25025 April 2019
Unit 2 Cycle 22-180-Day Steam Generator Tube Inspection Report
ML19070A0242019-03-0808 March 2019
Cycle 22 Refueling Outage -90-Day Inservice Inspection Summary Report
CNL-19-012, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection Program, Request for Alternative, 18-ISI-12019-01-30030 January 2019
American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection Program, Request for Alternative, 18-ISI-1
ML18213A0412018-07-31031 July 2018
Unit 1 Refueling Outage 22 - 90-Day Inservice Inspection Summary Report
ML17243A0042017-08-30030 August 2017
Refueling Outage 21 - 90-Day Inservice Inspection Summary Report
CNL-17-057, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Inservice Inspection (ISI) Program, Third Ten Year Interval Request for Relief for 17-ISI-12017-04-28028 April 2017
American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Inservice Inspection (ISI) Program, Third Ten Year Interval Request for Relief for 17-ISI-1
ML17094A2682017-04-0303 April 2017
Refueling Outage 21 - 90-Day Lnservice Inspection Summary Report
ML16076A1872016-03-11011 March 2016
Cycle 20 Refueling Outage - 90 Day Inservice Inspection Summary Report
ML15230A0302015-08-13013 August 2015
Refueling Outage 20 - 90-Day Inservice Inspection Summary Report
ML14342B0042014-12-0101 December 2014
Cycle 19 - 180-Day Steam Generator Tube Inspection Report
ML14259A3342014-09-11011 September 2014
Cycle 19 Refueling Outage - 90-Day Inservice Inspection Summary Report
CNL-14-073, 151-1 and 13-151-2 Relief Request Interval Applicability Clarification2014-05-0909 May 2014
151-1 and 13-151-2 Relief Request Interval Applicability Clarification
ML14055A3982014-02-18018 February 2014
Refueling Outage 19 - 90-Day Inservice Inspection Summary Report
ML13165A0502013-06-11011 June 2013
Cycle 18 - 180-Day Steam Generator Tube Inspection Report
ML13101A1202013-04-0808 April 2013
Refueling Outage 18 - 90-Day Inservice Inspection Summary Report
ML1218500062012-06-29029 June 2012
Refueling Outage 18 - 90-Day Inservice Inspection Summary Report
ML11266A0102011-09-20020 September 2011
Cycle 17 - 90-Day Inservice Inspection Summary Report
ML1104704052011-02-14014 February 2011
Cycle 17 - 90-Day Inservice Inspection Summary Report
ML11350A2402010-10-18018 October 2010
Cycle 17, 180-Day Steam Generator Inspection Report
ML1014504112010-05-19019 May 2010
Cycle 16 - 180-Day Steam Generator Inspection Report
ML1005415802010-02-19019 February 2010
Submittal of Cycle 16 - 90-Day Inservice Inspection Summary Report
ML0920804502009-07-24024 July 2009
Cycle 16 (U1C16) 90-Day Inservice Inspection (ISI) Summary Report
ML0905008482009-02-19019 February 2009
American Society of Mechanical Engineers (ASME) Section XI Inservice Inspection (ISI) Program - Relief Requests
ML0902202762008-11-21021 November 2008
Cycle 15 - 180-Day - Steam Generator Inspection Report
ML0804501542008-02-12012 February 2008
Cycle 15 (U1C15) 90-Day Inservice Inspection (ISI) Summary Report
ML0734505552007-12-0404 December 2007
Unit 2 Cycle 14 (U2C14) - 12-Month Steam Generator (SG) Inspection Report
ML0708603842007-03-21021 March 2007
Cycle 14 (U2C14) 90-Day Inservice Inspection Summary Report
ML0622800522006-08-0404 August 2006
Unit 1 Cycle 14 (U1C14) 90-Day Inservice Inspection (ISI) Summary Report
ML0612101052006-04-21021 April 2006
Risk-Informed Inservice Inspection (RI-ISI) Program and Updated Inservice Inspection Program for Third 10-Year Interval
ML0601302812006-01-10010 January 2006
Inservice Test (IST) Program Update and Associated Relief Requests for Third Ten-Year Interval
ML0601301942006-01-0909 January 2006
Inservice Test Pressure (Ispt) Program Update and Associated Relief Requests for Third Ten-Year Interval
ML0532002652005-11-10010 November 2005
ASME Boiler and Pressure Vessel Code, TVA Request to Use ASME Section XI, 2001 Edition, Through the 2003 Addenda Generically for Nondestructive Examination Procedures-GISI-4
ML0523506752005-08-10010 August 2005
Unit Cycle 13 90-Day Inservice Inspection Summary Report
ML0505504132005-02-15015 February 2005
Unit 1 Cycle 13, 90-day Inservice Inspection Summary Report
ML0432806252004-11-22022 November 2004
Steam Generating (SG) Tube Plugging Report - SG Tube Inspections During, Unit 1 Cycle 13 Refueling Outage
ML0407003862004-02-26026 February 2004
Cycle 12 (U2C12) 90-Day Inservice Inspection (ISI) Summary Report
ML0335107022003-12-12012 December 2003
Unit 2 Steam Generator (SG) Tube Plugging Report - SG Tube Inspections During Unit 2 Cycle 12 Refueling Outage
ML0326608852003-09-11011 September 2003
Cycle 12 (U1C12) 90-Day Inservice Inspection (ISI) Summary Report
ML0230106832002-10-25025 October 2002
Cycle 11 12-Month Steam Generator Inspection Report
ML0223305952002-08-0505 August 2002
Unit 2 Cycle 11 (U2C11) 90-Day Inservice Inspection (ISI) Summary Report
2024-07-26
[Table view]
Category:Letter
MONTHYEARCNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)2024-11-12012 November 2024
Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)
ML24312A1552024-11-0606 November 2024
Cycle 27 Core Operating Limits Report, Revision 1
IR 05000327/20240032024-11-0606 November 2024
Integrated Inspection Report 05000327/2024003 and 05000328/2024003
CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)2024-11-0404 November 2024
License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)
ML24304A8492024-10-31031 October 2024
December 2024 Requalification Inspection Notification Letter
IR 05000327/20250102024-10-29029 October 2024
Notification of Sequoyah, Units 1 and 2 - Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2025010 and 05000328/2025010
ML24298A1172024-10-24024 October 2024
Cycle 26, 180-Day Steam Generator Tube Inspection Report
CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
05000327/LER-2024-001, Reactor Trip Due to a Turbine Trip2024-10-17017 October 2024
Reactor Trip Due to a Turbine Trip
ML24282B0412024-10-15015 October 2024
Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2
ML24260A1682024-10-0404 October 2024
Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5
ML24284A1072024-09-26026 September 2024
Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2
05000328/LER-2024-001, Reactor Trip Due to an Electrical Trouble Turbine Trip2024-09-25025 September 2024
Reactor Trip Due to an Electrical Trouble Turbine Trip
CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024
Decommitment of Flood Mode Mitigation Improvement Systems
CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024
Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description
ML24262A0602024-09-23023 September 2024
Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan
ML24267A0402024-09-19019 September 2024
Cycle 27 Core Operating Limits Report Revision 0
CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024
Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML24185A1742024-09-18018 September 2024
Cover Letter - Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation
ML24253A0152024-09-0808 September 2024
Emergency Plan Implementing Procedure Revisions
ML24247A2212024-08-29029 August 2024
Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-21-160, NEI 03-08 Needed Guidance: PWR Lower Radial Support Clevis Insert X-750 Bolt Inspection Requirements, September 1, 2021
ML24247A1802024-08-28028 August 2024
Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea
IR 05000327/20240052024-08-26026 August 2024
Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005
ML24239A3972024-08-23023 August 2024
Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243
CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024
Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),
IR 05000327/20240022024-07-31031 July 2024
Integrated Inspection Report 05000327/2024002 and 05000328/2024002
ML24211A0572024-07-29029 July 2024
Submittal of Emergency Plan Implementing Procedure Revision
ML24211A0542024-07-29029 July 2024
Operator License Examination Report
ML24211A0412024-07-26026 July 2024
Unit 1 Cycle 26 Refueling Outage - 90-Day Inservice Inspection Summary Report
ML24199A0012024-07-22022 July 2024
Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2)
ML24172A1342024-07-15015 July 2024
Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter
ML24191A4652024-07-0909 July 2024
Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
ML24177A0282024-06-25025 June 2024
Emergency Plan Implementing Procedure Revisions
ML24176A0222024-06-24024 June 2024
Retraction of Interim Report of a Deviation or Failure to Comply – Transducer Model 8005N
ML24089A1152024-06-21021 June 2024
Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2)
ML24145A0852024-05-30030 May 2024
1B-B Diesel Generator Failure - Final Significance Determination Letter
ML24145A1052024-05-29029 May 2024
301 Exam Approval Letter
ML24134A1762024-05-13013 May 2024
Submittal of 2023 Annual Radiological Environmental Operating Report
CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML24128A0352024-05-0707 May 2024
Providing Supplemental Information to Apparent Violation
ML24120A0582024-04-26026 April 2024
10 CFR 50.46 Annual Report for Sequoyah Nuclear Plant Units 1 and 2
ML24116A2612024-04-25025 April 2024
Interim Report of a Deviation or Failure to Comply - Transducer Model 8005N
ML24114A0482024-04-23023 April 2024
Annual Radioactive Effluent Release Report for 2023 Monitoring Period
CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024
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Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 August 13, 2015 10 CFR 50.4 10 CFR 50.55a ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit I Facility Operating License No. DPR-77 NRC Docket No. 50-327
Subject:
Unit I Refueling Outage 20 Day Inservice Inspection Summary Report In accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, Article IWA-6230 and Code Case N-532-5, the Tennessee Valley Authority is providing the Sequoyah Nuclear Plant (SQN), Unit 1, Inservice Inspection (ISI) Summary Report within 90 days from completion of the Unit I Refueling Outage 20 (U1R20). The U1R20 refueling outage ended on May 16, 2015.Accordingly, this report is required to be submitted by August 14, 2015.The Enclosure to this letter contains the Owner's Activity Report, a list of items with flaws or relevant conditions that required evaluation for continued service (Table 1), an abstract of repair and replacement activities required for continued service due to a flaw or relevant condition (Table 2), and the evaluation of acceptability of inaccessible areas of the steel containment vessel in accordance with 10 CFR 50.55a(b)(2)(ix)(A).
There are no regulatory commitments associated with this submittal.
Should you have any questions, please contact Erin Henderson at (423) 843-7170.Sequoyah Nuclear Plant --"/
U.S. Nuclear Regulatory Commission Page 2 August 13, 2015
Enclosure:
ASME Section Xl Inservice Inspection Summary Report, Unit 1 Refueling Outage 20 cc (Enclosure):
NRC Regional Administrator-Region II NRC Senior Resident Inspector
-Sequoyah Nuclear Plant NRC Project Manager -Sequoyah Nuclear Plant ENCLOSURE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNIT 1 ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT UNIT I REFUELING OUTAGE 20 FORM OAR-I OWNER'S ACTIVITY REPORT Report. Number UIC20 Plant SEQUOYAH NUCLEAR PLANT. P.O. Box 2000. Soddy-Daisy, TN 37384-2000 Unit No. 1 Commercial service date July 1. 1981 Refueling outage no.(if epp:ic~e)Oe 20 Current inspection interval Current inspection period Third Inspection Interval (1", 2. 2'. 4*, nurwl Third Inspection Period (V. 2> 31 Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition, 2003 Addenda Date and revision of inspection plans March 27, 2015 SI-DXl-000-114.3, Revision 27 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans _____Not Applicable Code Cases used N.-460, N-513-3, N-532-4, N-532-5, N-566-2, N-586-1, N-686-1, N-706-1, N-716-1, N-722-1, N-729-1, for inspection and N-770-1 evaluation: (f urol.ae eL"i1.t u"J.. ,
Sy Case N-532 aow wer. wsru(kis CERTIFICATE OF CONFORMANCE I certify that (al the statements made in this report are correct: Ib) the esarninations and tests meet the Inspection Plan as required by the ASME Code Xl and (c) the repair/replacement activties and evaluations supporting the completion at UIC20 conform to the requirements of Section XI. (yO!uoiw otorue w~/. ler Date 5" CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and and employed by HSB Global Standards of Connecticut have inspected the items described in this Owner's Activity Report, and elate 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 Xl.By signing this cartificate neither the Inspector nor his employer make 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 mann pl} ersonal injury or property damage or a loss of any kind arising from or connected with this inspection.
__________________Commission ,/, 2t', twoewors OSlaaroaLt N atio.nal soarS Nuawber and Sn'f~~eoownl)
Date ~ t ASME Code Section Xl Exception-
Reference:
T/A Condition Report 1024964.
Subject:
ASME Category 8-0-1 (RCP hydrastuds)
==
Description:==
Using the EPRI guidance, the performance demonstration completed for these exams w.,as not performed as a "btind test" as required by ASME Section XI, Appendix VIII. Supplement 8, paragraph 2.0. This CR documents the issue and references the NRC issued EGM 14-003 as sufficient technical basis for accepting the examinations.
E-1 ASME SECTION Xl INSERVICE INSPECTION
SUMMARY
REPORT SEQUOYAH NUCLEAR PLANT UNIT 1 REFUELING OUTAGE 20 TABLE I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Description Evaluation Description Item Number Engineering evaluation, accept as is.The support remains functional.
This F-AFI.10D Missing outer hex nut from support 1-RCH- condition was previously identified in F-,F ID 114, Report R0039, NOI 1-SQ-516.
change document FCR #7927 and incorporated into calculation 1 RCH01 14, Attachment I.cleaanc beteenpadsandthe Engineering evaluation, accept as is.Improper claac ewe asadte A zero gap is acceptable as long as F-A, FI.40 seismic plates on support 1-CRDH-1, Report the total gap along the array does not R0036, NOI 1-SQ-515 exceed the limits.Boric Acid Evaluation, No additional C-H, C7 .10 Packing leak on 1-FCV-063-174, WO ato sncsay ovsa 11670561evidence of corrosion.
C-,C7 0 Packing leak on 1-FCV-063-0024, WO Boric Acid Evaluation, Cleaned and C-,C.0 116770560 observed, no active leak.E-2 ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT SEQUOYAH NUCLEAR PLANT UNIT 1 REFUELING OUTAGE 20 TABLE 2 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Code Item Description Date Repair/Replacement Class Description of Work Completed Plan Number No Applicable Repair/Replacement activities occurred duringq this period.REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A)
ASME Section Xl, Subsection IWE Steel Containment Vessel Inspection Program 10 CER 50.55a(b)(2)(ix)(A) requires reporting of the degradation assessment for inaccessible areas when conditions are identified in accessible areas during the performance of the ASME Section Xl, Subsection IWE Steel Containment Vessel (SCV) Inspection Program that could indicate the presence of or result in degradation to such inaccessible areas.The conditions identified during the SQN Unit 1 Cycle 20 refueling outage on the SCV in an accessible area were determined to be acceptable and do not affect the degradation assessment for inaccessible areas.E-3
