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Category:Code Relief or Alternative
MONTHYEARML23048A3042023-03-0808 March 2023 Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047) ML22304A1862022-12-0101 December 2022 Revised Authorization of Alternative Request RV-02 for Pressure Isolation Valve Seat Leakage ML22272A5682022-10-12012 October 2022 Authorization of Alternatives to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Operating and Maintenance Code ML22203A1122022-07-25025 July 2022 Summary of Verbal Authorization of Alternative Request RP-12 for the 1B-B Centrifugal Charging Pump CNL-22-081, Supplement to Sequoyah Nuclear Plant, Unit 1, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-122022-07-21021 July 2022 Supplement to Sequoyah Nuclear Plant, Unit 1, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-12 ML21266A3832021-10-0101 October 2021 Authorization of Alternative Request RP-10 for the 1B-B Motor Driven Auxiliary Feedwater Pump ML19227A1102019-08-26026 August 2019 Alternative Request for the Turbine Driven Auxiliary Feedwater Pumps 10-Year Interval Inservice Testing Program CNL-19-068, Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for2019-07-22022 July 2019 Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for .. ML17059B7912017-03-0202 March 2017 Sequoyah Nuclear Plant, Units 1 and 2 - Relief from the Requirements of the American Society of Mechanical Engineer OM Code (CAC Nos. MF9305 and MF9306) ML16225A6332016-09-0202 September 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Relief Request for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5 (TAC Nos. MF7754-MF7760) ML16123A1312016-05-12012 May 2016 Relief Requests RP-01, RP-02, RP-06, RP-08, and RV-01 Related to the Inservice Testing Program, Fourth 10-Year Interval (CAC Nos. MF7099 and MF7100) ML15329A1862015-12-0404 December 2015 Request for Relief PR-07 for Alternative Inservice Pump Testing at Reference Values ML1109506822011-04-0101 April 2011 American Society of Mechanical Engineers Request for Relief RP-01, Revision 1 ML0924402962009-08-28028 August 2009 American Society of Mechanical Engineers Inservice Inspection Program Relief Request 1-ISI-34 ML0708003612007-06-11011 June 2007 Request for Relief G-RR-1 Regarding Preemptive Weld Overlays on Pressurizer Nozzles ML0617907332006-07-27027 July 2006 Request for Relief from the Requirements of ASME Code ML0601000802006-02-0303 February 2006 Relief Request Response, Authorization to Extend ISI Interval for Reactor Vessel Weld Exams ML0601301942006-01-0909 January 2006 Inservice Test Pressure (Ispt) Program Update and Associated Relief Requests for Third Ten-Year Interval ML0517304872005-08-0202 August 2005 Relief, Inservice Inspection Program Relief Request PDI-4 ML0519502612005-07-0808 July 2005 American Society of Mechanical Engineers Section XI Inservice Inspection Program Relief Request to Extend the Second 10-year ISI Interval for Unit 1 Reactor Vessel Weld Examination - Request No. 1-ISI-27 ML0508104642005-04-0808 April 2005 Second 10-year Interval Inservice Inspection Program Plan Request for Relief No. ISPT-09 ML0502504152005-02-15015 February 2005 Relief, Use of ASME and Pressure Vessel (PV) Code for VT-2 ML0421504382004-10-0606 October 2004 Relief, Relief Request Re. Maximum Allowable Flaw Width When Planar Flaw Evaluation Rules May Be Applied ML0423305572004-08-17017 August 2004 8/17/04, Sequoyah, Units 1 & 2, Relief Request, Two Welds on SQN Unit 1 & 2 Seal Water Injection Filter head-to-shell Welds ML0421904402004-08-0606 August 2004 American Society of Mechanical Engineers (ASME) Section XI Inservice Pressure Test Program Relief Request (ISPT-09) ML0420201942004-07-19019 July 2004 Relief Request, Inservice Inspection of Class 1 & Class 3 Welds ML0332303472003-11-0606 November 2003 Response to NRC Request for Additional Information (RAI) Regarding ASME Section XI Inservice Inspection (ISI) Program Relief Requests 1-ISI-23, 1/2-ISI-24, and 1/2-ISI-25 ML0329302632003-10-15015 October 2003 American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Appendix Viii, Supplement 10 - Qualification Requirements for Dissimilar Metal Piping Welds, Request for Relief PDI-3 ML0329009382003-10-0808 October 2003 Unit 1 - Change to a Commitment Associated with Request for Relief from American Society of Mechanical Engineers (ASME) Code for Replacement of ASME Code Class 3 Piping ML0317505932003-06-14014 June 2003 Request for Relief from American Society of Mechanical Engineers (ASME) Code for Replacement of ASME Code Class 3 Piping ML0314700772003-05-13013 May 2003 American Society of Mechanical Engineers (ASME) Section XI Inservice Inspection (ISI) Program - Relief Requests ML0313203202003-05-0909 May 2003 Request for Relief from American Society of Mechanical Engineers, Section XI Code Requirements for Tests Following Repair, Modification, or Replacement ML0310605452003-04-15015 April 2003 Request for Relief from American Society of Mechanical Engineers (Asme), Section XI Code Requirements - Tests Following Repair, Modification, or Replacement (IWE-5221) ML0219702792002-07-16016 July 2002 Relief Request RR-09 and RR-10 Associated with Inservice Testing Requirements for Vibration Monitoring of the Turbine Driven Auxiliary Feedwater Pumps 2023-03-08
[Table view] Category:Letter
MONTHYEARML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 ML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24018A0142024-01-17017 January 2024 Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913 ML24011A3182024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), October 2023 ML24011A3172024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), September 2023 ML24011A3202024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), December 2023 ML24011A3162024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), August 2023 ML24011A3192024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), November 2023 IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers ML24018A0952024-01-0404 January 2024 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0 ML24004A0332024-01-0303 January 2024 Interim Report of a Deviation or Failure to Comply Crompton Instruments Type 077 Ammeter ML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation CNL-23-068, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) ML23346A1222023-12-12012 December 2023 Annual Non-Radiological Environmental Operating Report - 2023 IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23324A4362023-11-0909 November 2023 Exam Corporate Notification Letter Aka 210-day Letter ML23307A0822023-11-0808 November 2023 Request for Additional Information August 4, 2022, Exemption Request for Deviating from the Conditions of Certificate of Compliance No. 1032, Amendment No. 3, Related to Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation IR 05000327/20230032023-11-0303 November 2023 Integrated Inspection Report 05000327/2023003 and 05000328/2023003 ML23306A1592023-11-0202 November 2023 Enforcement Action EA-22-129 Inspection Readiness Notification ML23292A0792023-10-19019 October 2023 Tennessee Valley Authority - Emergency Plan Implementing Procedure Revision, Includes EPIP-5, Revision 58, General Emergency IR 05000327/20230112023-10-16016 October 2023 Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011 ML23285A0882023-10-12012 October 2023 Submittal of Sequoyah Nuclear Plant, Units 1 and 2, Submittal of Updated Final Safety Analysis Report Amendment 31 ML23284A4252023-10-11011 October 2023 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report; Commitment Summary Report; and Update to the Fire Protection Report ML23283A2792023-10-10010 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0462023-10-0404 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases ML23275A0272023-09-29029 September 2023 Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023 ML23271A1662023-09-28028 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision IR 05000327/20234032023-09-14014 September 2023 Cyber Security Inspection Report 05000327/2023403 and 05000328/2023403 (Cover Letter) ML23257A0062023-09-14014 September 2023 Enforcement Action EA-22-129 Inspection Postponement Request ML23254A2192023-09-11011 September 2023 Emergency Plan Implementing Procedure Revisions ML23254A0652023-09-0707 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000327/20230052023-08-29029 August 2023 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005 ML23233A0122023-08-17017 August 2023 Unit 1 Cycle 25 Refueling Outage - 90-Day Inservice Inspection Summary Report - Supplement ML23233A0142023-08-15015 August 2023 Discharge Monitoring Report (Dmr), July 2023 ML23215A1212023-08-0303 August 2023 301 Exam Administrative Items (2B) Normal Release ML23215A1572023-08-0303 August 2023 Enforcement Action EA-22-129 Inspection Readiness Notification CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information 2024-01-04
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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 August 28, 2009 10 CFR 50.4 10 CFR 50.55a(a)(3)
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Facility Operating License No. DPR-77 NRC Docket No. 50-327
Subject:
American Society of Mechanical Engineers Inservice Inspection Program Relief Request 1-ISI-34
Reference:
Letter from TVA to the NRC, "Unit 1 Cycle 16 90-Day Inservice Inspection Summary Report," dated July 24, 2009 In accordance with 10 CFR 50.55a(a)(3)(i), the Tennessee Valley Authority (TVA) requests the Nuclear Regulatory Commission's (NRC's) approval of an alternative to the requirements of the 2001 Edition through the 2003 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI for the Sequoyah Nuclear Plant Unit 1 third inservice inspection interval.
During preparation of the referenced Unit 1 Cycle 16 90-Day Inservice Inspection Summary Report, it was discovered the scheduled 1st period Examination Category B-B component was inadvertently removed from the examination scope. This issue was documented in TVA's Corrective Action Program. As a result, a relief request as described in the Enclosure is proposed to provide an alternative schedule for the performance of this examination.
TVA requests approval of this alternative by July 31, 2010, to allow sufficient time to revise the affected inservice inspection plan prior to the September, 2010, cycle 17 refueling outage.
printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 August 28, 2009 There are no new regulatory commitments included in this submittal. If you have any questions concerning this information, please contact Kevin Casey at (423) 751-8523.
Respectfully, R. M. Kri Vice President Nuclear Licensing
Enclosure:
Relief Request No. 1-ISI-34 cc (Enclosure):
Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant
ENCLOSURE Tennessee Valley Authority Sequoyah Nuclear Plant, Unit 1 Third 10-Year Interval Relief Request No. 1-ISI-34 COMPONENTS The affected components at the Sequoyah Nuclear Plant, Unit 1 (SQN Ul) are the Steam Generator and Pressurizer Class 1 welds. The Examination Category and Item Numbers are from the American Society of Mechanical Engineers (ASME)Section XI, 2001 Edition through 2003 Addenda (the Code) and are listed below:
Exam Item Cateqory Number Description B-B B2.1 1 Pressurizer Shell to Head Circumferential B-B B2.12 Pressurizer Shell to Head Longitudinal B-B B2.40 Steam Generator Tubesheet to Head Weld II. CODE REQUIREMENTS SQN Ul follows Inspection Program B requirements of IWA-2432 for scheduling of inspection intervals and inspection periods. IWA-2430 requires that inservice examinations and system pressure tests required by IWB, IWC, IWD, IWE and inservice examination and tests of IWF to be completed during each of the inspection intervals for the service lifetime of the plant.
Specific Code requirement for which relief is requested:
IWA-2430(d)(3) allows for the portion of an inspection period to be reduced or extended by as much as one year to enable an inspection to coincide with a plant outage.
II1. PROPOSED ALTERNATIVE Pursuant to 10 CFR 50.55a(a)(3)(i), the Tennessee Valley Authority (TVA) proposes an alternative to the requirement of IWA-2430(d)(3) that the inspection period may only be extended/reduced by a maximum of one year. TVA proposes the first inspection period of the third inspection interval be extended by a total of 16.5 months, the Code allowed one year plus an additional 4.5 months, in order to complete scheduled examinations in Examination Category B-B. In addition, the second period was scheduled for only three years instead of the four years stipulated by Table IWB-2412-1 in order to re-capture the one year extension used in a previous interval. This alternative will result in an additional decrease beyond the one year reduction of an additional 16.5 months. The third inspection period will be un-affected and the third Inspection Interval will end as originally scheduled on May 31, 2015.
This schedule will result in the first inspection period ending and the second inspection period starting in the SQN Ul cycle 17 outage for Examination Category B-B welds.
Weld examinations for Examination Category B-B welds will be completed for both periods in the SQN Ul cycle 17 outage; however, these examinations will be for different components and no examination will be credited for both periods.
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IV. BASIS FOR PROPOSED ALTERNATIVE
Background
SQN Units 1 and 2 are currently in their third inspection interval and are on concurrent intervals. The original third inspection interval and associated inspection period dates for SQN U1 are:
Third Interval: June 1, 2006 to May 31, 2015 1st Period: June 1,2006 to May3l,2009 2nd Period: June 1,2009 to May 31, 2012 3rd Period: June 1,2012 to May 31,2015 The third 10-year inspection interval was reduced by one-year as allowed by IWA-2430(d)(1) in order to maintain the original pattern of intervals.
This request does not alter the third inspection interval start and end dates as described above and in SQN procedure 0-SI-DXI-000-1 14.3, "ASME Section Xl ISI/NDE Progam Unit 1 and Unit 2." The inspection period dates would be revised to the following schedule for SQN U1, Examination Category B-B only:
Third Interval: June 1, 2006 to May 31, 2015 "1stPeriod: June 1, 2006 to October 12, 2010 2nd Period: October 13, 2010 to May 31, 2012 3rd Period: June 1,2012 to May 31, 2015 The sequence/dates for other Examination Categories are included in SQN procedure 0-SI-DXI-000-1 14.3 and will meet the provisions in Table IWB-2412-1 and IWA-2430.
This alternative does not impact other requirements such as third party inspection required by ASME Section XI.
Justification of Alternative Table IWB-2412-1 of the Code currently requires that inspection intervals be divided into three inspection periods of a duration of three years, four years, and three years, respectively, with allowable modifications as specified in IWA-2430. This proposed alternative does not go beyond the five years allowed by the Code for the second inspection period, four year period plus one-year extension. The first inspection period of SQN Ul's third inspection interval for Examination Category B-B will be slightly over four and one-third years in length, well within the five years allowed as compared with an extended second inspection period.
A total of five welds are being examined under Examination Category B-B for the inspection interval under the proposed alternative schedule, these welds will be re-examined at approximately 10-years from their previous examination, as shown in the Table below.
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4 . I Weld ID Exam Cat/Item No. 2nd Interval 3rd Interval Exam Exam Date Schedule Date PZR WP-1 B-B/B2.11 11/04/2001 10/2010 (2nd Period)
PZR WP-5 B-B/B2.1 1 04/01/2003 10/2013 (3rd Period)
PZR WP-6 B-B/B2.12 11/03/2001 10/2010 (2nd Period)
PZR WP-9 B-B/B2.12 04/01/2003 10/2013 (3rd Period)
SG RSGW-A2 B-B/B2.40 09/27/2002 (PSI) 10/2010 (1st period)
The second inspection interval examinations were performed with satisfactory results for each of the welds listed above. Note the Steam Generator (SG) PSI exam was performed due to steam generator replacement. The scheduled 3rd Interval SG exam will be performed on or before October 12, 2010.
Conclusion In summary, the proposed alternative provides an equivalent level of quality and safety and does not deviate from the inspection interval schedule or the approximate 10-year elapsed time between examinations.
V. IMPLEMENTATION SCHEDULE This relief request will be implemented during the third inspection interval for SQN Ul Examination Category B-B.
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