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| | number = ML12114A060 | | | number = ML12114A060 |
| | issue date = 04/05/2012 | | | issue date = 04/05/2012 |
| | title = Cover Letter - Revision to the Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling Technical Report, SQN2-SGR-TR1, Submitted in Tva'S Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP (TAC No. ME7225 | | | title = Cover Letter - Revision to the Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling Technical Report, SQN2-SGR-TR1, Submitted in Tva'S Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP |
| | author name = Carlin J T | | | author name = Carlin J |
| | author affiliation = Tennessee Valley Authority | | | author affiliation = Tennessee Valley Authority |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000April 5, 201210 CFR 50.410 CFR 50.90ATTN: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, D.C. 20555-0001Sequoyah Nuclear Plant, Unit 1Facility Operating License No. DPR-77Docket No. 50-327Subject:Reference:Revision to the Sequoyah Unit 2 Steam Generator ReplacementRigging and Heavy Load Handling Technical Report,SQN2-SGR-TRI, Submitted in TVA's Heavy Load Lifts and UHSOne Time Change in Support of Unit 2 SGRP (TAC NO. ME7225)1. Letter from TVA to NRC, "Application to Revise Sequoyah NuclearPlant, Unit 1, Operating License and Technical Specification 3.7.5,"Ultimate Heat Sink," to Support Sequoyah Nuclear Plant, Unit 2,Steam Generator Replacement Project (TS-SQN-2011-05)," datedSeptember 29, 20112. Electronic Mail from NRC to TVA, "Sequoyah, Unit 1 LAR -HeavyLoad Lifts and UHS One Time Change in Support of Unit 2 SGRP(TAC NO. ME7225)," dated January 13, 20123. Letter from TVA to NRC, "Response to NRC Request forAdditional Information Regarding the Heavy Load Lifts and UHSOne Time Change in Support of Unit 2 SGRP (TAC NO.ME7225)," dated February 10, 20124. Electronic Mail from NRC to TVA, "Sequoyah, Unit 1 LAR -HeavyLoad Lifts and UHS One Time Change in Support of Unit 2 SGRP(TAC NO. ME7225)," dated February 2, 20125. Letter from TVA to NRC, "Response to Second NRC Request forAdditional Information Regarding the Heavy Load Lifts and UHSOne Time Change in Support of Unit 2 SGRP (TAC NO.ME7225)," dated March 5, 2012 U.S. Nuclear Regulatory CommissionPage 2April 5, 2012The purpose of this letter is to submit Revision 3 of the Sequoyah Unit 2 SteamGenerator Replacement Rigging and Heavy Load Handling Technical Report,SQN2-SGR-TR1.By letter dated September 29, 2011 (Reference 1), the Tennessee Valley Authority(TVA) submitted a one-time request for amendment to the Operating License (OL)for Sequoyah Nuclear Plant (SQN), Unit 1. The amendment request proposed toadd a one-time license condition to the SQN, Unit 1, OL for the conduct of heavyload lifts associated with the SQN, Unit 2, Steam Generator Replacement Project(SGRP). The one-time license condition establishes special provisions andrequirements for the safe operation of SQN, Unit 1, while large heavy load lifts areperformed on SQN, Unit 2. In addition, a one-time change to SQN, Unit 1, TechnicalSpecification (TS) 3.7.5, "Ultimate Heat Sink," is also proposed to implementadditional restrictions with respect to maximum average Essential Raw CoolingWater System supply header water temperature during large heavy load liftsperformed to support the SQN, Unit 2, SGRP.By electronic mail dated January 13, 2012, (Reference 2), the NRC forwarded arequest for additional information (RAI) regarding the proposed changes establishingthe special provisions and requirements for large heavy load lifts on SQN, Unit 2.TVA responded to this first RAI by letter dated February 10, 2012 (Reference 3).Subsequently, by electronic mail dated February 2, 2012, the NRC forwarded asecond RAI. TVA responded to the second RAI by letter dated March 5, 2012(Reference 5).Since submittal of the Reference 5 response to the second RAI, an alternateinterfacing lift point for removal of the old steam generators (OSGs) has beenidentified. In Enclosure 2 to Reference 1, TVA provided the Sequoyah Unit 2 SteamGenerator Replacement Rigging and Heavy Load Handling Technical Report,SQN2-SGR-TR1, Revision 2. This Technical Report documents the provisions madeto ensure that heavy load handling activities associated with the Unit 2 SGRPOutage can be accomplished without impacting the safe operation of Unit 1. Section5.1, "Description of Cranes and Heavy Loads, Outside Lift System," of Revision 2 ofthe Technical Report describes using a lifting lug welded to the Main Steam nozzleas the interfacing lift point for removal of the OSGs. The alternate OSG interfacinglift point revises the interfacing lift point from the lifting lug to the secondary sidemanways, which will be fitted with keeper plates to enable slings to be utilized to rigout the OSGs. The secondary side manway lift point is described in Section 5.1 ofRevision 3 of the Technical Report provided in Enclosure 1 to this letter. | | {{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 April 5, 2012 10 CFR 50.4 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Facility Operating License No. DPR-77 Docket No. 50-327 |
| U.S. Nuclear Regulatory CommissionPage 3April 5, 2012Utilizing the secondary side manways as the OSG interfacing lift point eliminates theignition sources in the Containment Building associated with welding the lifting lug tothe Main Steam nozzle, including the post-weld heat treatment processes.Eliminating the ignition sources improves the safety of personnel working in theContainment Building during the welding processes. In addition, using thesecondary side manways is considered a more efficient method for removal of theOSGs which reduces the likelihood of human error by reducing complexity.Furthermore, since the OSG removal task activity duration will be reduced, there willbe a corresponding reduction in personnel radiation exposure.Revision 3 of the Technical Report in Enclosure 1 to this letter supersedes in itsentirety, Revision 2 of the Technical Report previously submitted in Enclosure 2 ofReference 1. In addition to the interfacing lift point revision described above, thefollowing changes are also included in Revision 3 to the Technical Report:* Added valve numbers to Figures 6-1 and 8-2 as addressed in the response toRAI Question 2 of the enclosure to Reference 5;* Corrected the test weight;* Changed Figure 5-3 to illustrate raising the Outside Lift System foundation by6 inches;* Changed the reference to "Liebherr 1400/1" crane to be "Liebherr 1400/1 orLiebherr 1400/2" to permit use of either crane; and,* Made changes to reflect the updated Replacement Steam Generator riggingweight.The changes are identified by revision bars in the Technical Report provided inEnclosure 1 to this letter. Enclosure 2 to this letter provides an affected page listingof each of the changes included in Revision 3 of the Technical Report.TVA has evaluated the revision to the OSG interfacing lift point and the otherchanges made in Revision 3 of the Technical Report and determined that there is noimpact on the no significant hazards considerations associated with the OL and TSamendment request submitted in Reference 1. TVA has further determined that theproposed amendment still qualifies for a categorical exclusion from environmentalreview pursuant to the provision of 10 CFR 510.22(c)(9). In addition, TVA hasconcluded that there is no change to the Probabilistic Risk Assessment (PRA)Insights as documented in Section 9.0 of the Technical Report. In accordance with10 CFR 50.91 (b)(1), TVA is sending a copy of this letter and enclosures to theTennessee State Department of Environment and Conservation. | | |
| U.S. Nuclear Regulatory CommissionPage 4April 5, 2012There are no regulatory commitments included in this submittal. If you have anyquestions, please contact Clyde Mackaman at (423) 751-2834.I declare under penalty of perjury that the foregoing is true and correct. Executed onthe 9" day of April 2012.Resp~vc~tfully,Vice PresidentSequoyah Nuclear PlantEnclosures:1. Sequoyah Unit 2 Steam Generator Replacement Rigging and HeavyLoad Handling Technical Report, SQN2-SGR-TR1, Revision 32. SQN2-SGR-TR1 Revision 3 Affected Page Listcc: (Enclosures):NRC Regional Administrator -Region IINRC Senior Resident Inspector -Sequoyah Nuclear PlantDirector, Division of Radiological Health, Tennessee State Department ofEnvironment and Conservation | | ==Subject:== |
| }} | | Revision to the Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling Technical Report, SQN2-SGR-TRI, Submitted in TVA's Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP (TAC NO. ME7225) |
| | |
| | ==Reference:== |
| | : 1. Letter from TVA to NRC, "Application to Revise Sequoyah Nuclear Plant, Unit 1, Operating License and Technical Specification 3.7.5, "Ultimate Heat Sink," to Support Sequoyah Nuclear Plant, Unit 2, Steam Generator Replacement Project (TS-SQN-2011-05)," dated September 29, 2011 |
| | : 2. Electronic Mail from NRC to TVA, "Sequoyah, Unit 1 LAR - Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP (TAC NO. ME7225)," dated January 13, 2012 |
| | : 3. Letter from TVA to NRC, "Response to NRC Request for Additional Information Regarding the Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP (TAC NO. |
| | ME7225)," dated February 10, 2012 |
| | : 4. Electronic Mail from NRC to TVA, "Sequoyah, Unit 1 LAR - Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP (TAC NO. ME7225)," dated February 2, 2012 |
| | : 5. Letter from TVA to NRC, "Response to Second NRC Request for Additional Information Regarding the Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP (TAC NO. |
| | ME7225)," dated March 5, 2012 |
| | |
| | U.S. Nuclear Regulatory Commission Page 2 April 5, 2012 The purpose of this letter is to submit Revision 3 of the Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling Technical Report, SQN2-SGR-TR1. |
| | By letter dated September 29, 2011 (Reference 1), the Tennessee Valley Authority (TVA) submitted a one-time request for amendment to the Operating License (OL) for Sequoyah Nuclear Plant (SQN), Unit 1. The amendment request proposed to add a one-time license condition to the SQN, Unit 1, OL for the conduct of heavy load lifts associated with the SQN, Unit 2, Steam Generator Replacement Project (SGRP). The one-time license condition establishes special provisions and requirements for the safe operation of SQN, Unit 1, while large heavy load lifts are performed on SQN, Unit 2. In addition, a one-time change to SQN, Unit 1, Technical Specification (TS) 3.7.5, "Ultimate Heat Sink," is also proposed to implement additional restrictions with respect to maximum average Essential Raw Cooling Water System supply header water temperature during large heavy load lifts performed to support the SQN, Unit 2, SGRP. |
| | By electronic mail dated January 13, 2012, (Reference 2), the NRC forwarded a request for additional information (RAI) regarding the proposed changes establishing the special provisions and requirements for large heavy load lifts on SQN, Unit 2. |
| | TVA responded to this first RAI by letter dated February 10, 2012 (Reference 3). |
| | Subsequently, by electronic mail dated February 2, 2012, the NRC forwarded a second RAI. TVA responded to the second RAI by letter dated March 5, 2012 (Reference 5). |
| | Since submittal of the Reference 5 response to the second RAI, an alternate interfacing lift point for removal of the old steam generators (OSGs) has been identified. In Enclosure 2 to Reference 1, TVA provided the Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling Technical Report, SQN2-SGR-TR1, Revision 2. This Technical Report documents the provisions made to ensure that heavy load handling activities associated with the Unit 2 SGRP Outage can be accomplished without impacting the safe operation of Unit 1. Section 5.1, "Description of Cranes and Heavy Loads, Outside Lift System," of Revision 2 of the Technical Report describes using a lifting lug welded to the Main Steam nozzle as the interfacing lift point for removal of the OSGs. The alternate OSG interfacing lift point revises the interfacing lift point from the lifting lug to the secondary side manways, which will be fitted with keeper plates to enable slings to be utilized to rig out the OSGs. The secondary side manway lift point is described in Section 5.1 of Revision 3 of the Technical Report provided in Enclosure 1 to this letter. |
| | |
| | U.S. Nuclear Regulatory Commission Page 3 April 5, 2012 Utilizing the secondary side manways as the OSG interfacing lift point eliminates the ignition sources in the Containment Building associated with welding the lifting lug to the Main Steam nozzle, including the post-weld heat treatment processes. |
| | Eliminating the ignition sources improves the safety of personnel working in the Containment Building during the welding processes. In addition, using the secondary side manways is considered a more efficient method for removal of the OSGs which reduces the likelihood of human error by reducing complexity. |
| | Furthermore, since the OSG removal task activity duration will be reduced, there will be a corresponding reduction in personnel radiation exposure. |
| | Revision 3 of the Technical Report in Enclosure 1 to this letter supersedes in its entirety, Revision 2 of the Technical Report previously submitted in Enclosure 2 of Reference 1. In addition to the interfacing lift point revision described above, the following changes are also included in Revision 3 to the Technical Report: |
| | * Added valve numbers to Figures 6-1 and 8-2 as addressed in the response to RAI Question 2 of the enclosure to Reference 5; |
| | * Corrected the test weight; |
| | * Changed Figure 5-3 to illustrate raising the Outside Lift System foundation by 6 inches; |
| | * Changed the reference to "Liebherr 1400/1" crane to be "Liebherr 1400/1 or Liebherr 1400/2" to permit use of either crane; and, |
| | * Made changes to reflect the updated Replacement Steam Generator rigging weight. |
| | The changes are identified by revision bars in the Technical Report provided in to this letter. Enclosure 2 to this letter provides an affected page listing of each of the changes included in Revision 3 of the Technical Report. |
| | TVA has evaluated the revision to the OSG interfacing lift point and the other changes made in Revision 3 of the Technical Report and determined that there is no impact on the no significant hazards considerations associated with the OL and TS amendment request submitted in Reference 1. TVA has further determined that the proposed amendment still qualifies for a categorical exclusion from environmental review pursuant to the provision of 10 CFR 510.22(c)(9). In addition, TVA has concluded that there is no change to the Probabilistic Risk Assessment (PRA) |
| | Insights as documented in Section 9.0 of the Technical Report. In accordance with 10 CFR 50.91 (b)(1), TVA is sending a copy of this letter and enclosures to the Tennessee State Department of Environment and Conservation. |
| | |
| | U.S. Nuclear Regulatory Commission Page 4 April 5, 2012 There are no regulatory commitments included in this submittal. If you have any questions, please contact Clyde Mackaman at (423) 751-2834. |
| | I declare under penalty of perjury that the foregoing is true and correct. Executed on the 9" day of April 2012. |
| | Resp~vc~tfully, Vice President Sequoyah Nuclear Plant |
| | |
| | ==Enclosures:== |
| | : 1. Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling Technical Report, SQN2-SGR-TR1, Revision 3 |
| | : 2. SQN2-SGR-TR1 Revision 3 Affected Page List cc: (Enclosures): |
| | NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant Director, Division of Radiological Health, Tennessee State Department of Environment and Conservation}} |
Letter Sequence Other |
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MONTHYEARML11307A3692011-10-31031 October 2011
NRR E-mail Capture - Sequoyah, Unit 1 - Acceptance Review of LAR Requesting to Add a One-Time License Condition to Conduct Heavy Load Lifts for Unit 2 SGRP
Project stage: Acceptance Review
ML12019A2642012-01-13013 January 2012
NRR E-mail Capture - Sequoyah, Unit 1 LAR - Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP
Project stage: Other
ML12034A2272012-02-0202 February 2012
NRR E-mail Capture - Sequoyah, Unit 1 LAR - Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP
Project stage: Other
ML12046A6462012-02-10010 February 2012
Response to NRC Request for Additional Information Regarding the Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP
Project stage: Response to RAI
ML12089A4912012-03-0505 March 2012
Response to NRC Second Request for Additional Information Regarding the Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP
Project stage: Request
ML12114A0612012-04-0505 April 2012
Technical Report, SQN2-SGR-TRI, Revision 3, Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling.
Project stage: Other
ML12114A0602012-04-0505 April 2012
Cover Letter - Revision to the Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling Technical Report, SQN2-SGR-TR1, Submitted in Tva'S Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP
Project stage: Other
ML12121A2332012-05-0202 May 2012
Meeting Notice - Notice of Forthcoming Meeting Via Conference Call with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Unit 1, Heavy Loads Amendment Request (TAC No. ME7225.)
Project stage: Meeting
ML12144A2972012-05-22022 May 2012
Response to Nuclear Regulatory Commission (NRC) Third Request for Additional Information Regarding the Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP
Project stage: Request
ML12136A5222012-07-0505 July 2012
Summary of Public Telephone Call with Tennessee Valley Authority Regarding Heavy Load Lifts License Amendment Request Risk Informed Request for Additional Information
Project stage: RAI
ML12213A0352012-07-30030 July 2012
NRR E-mail Capture - Sequoyah 1 - Heavy Loads LAR
Project stage: Other
ML12234A3812012-09-0606 September 2012
Issuance of Amendment Regarding the Proposed Operating License and Technical Specification Changes for Unit 2 Replacement Steam Generator Project to Conduct Heavy Load Lifts
Project stage: Approval
ML12263A1632012-09-20020 September 2012
Safety Evaluation Corrections for Amendment No. 330 Associated with Unit 2 Replacement Steam Generator Project to Conduct Heavy Load Lifts (TAC No. ME7225) (TS-SQN-2011-05)
Project stage: Approval
2012-04-05
[Table View] |
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Category:Letter
MONTHYEARML24304A8492024-10-31031 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-24-060, 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
CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024
Decommitment of Flood Mode Mitigation Improvement Systems
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
Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42
ML24144A2362024-04-20020 April 2024
Discharge Monitoring Report (Dmr), March 2024
ML24144A2322024-04-20020 April 2024
Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9
ML24089A0882024-04-18018 April 2024
– Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting
ML24102A1212024-04-18018 April 2024
Summary of Conference Call with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Unit 1 Spring 2024 Steam Generator Tube Inspections
CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024
Hydrologic Engineering Center River Analysis System Project Milestone Status Update
CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
IR 05000327/20240012024-04-17017 April 2024
Integrated Inspection Report 05000327/2024001 and 05000328/2024001
ML24109A0272024-04-16016 April 2024
Cycle 27 Core Operating Limits Report Revision 0
CNL-23-006, Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)2024-04-15015 April 2024
Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)
ML24106A0502024-04-12012 April 2024
Discharge Monitoring Report (Dmr), February 2024
2024-09-08
[Table view] |
Text
Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 April 5, 2012 10 CFR 50.4 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Facility Operating License No. DPR-77 Docket No. 50-327
Subject:
Revision to the Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling Technical Report, SQN2-SGR-TRI, Submitted in TVA's Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP (TAC NO. ME7225)
Reference:
- 1. Letter from TVA to NRC, "Application to Revise Sequoyah Nuclear Plant, Unit 1, Operating License and Technical Specification 3.7.5, "Ultimate Heat Sink," to Support Sequoyah Nuclear Plant, Unit 2, Steam Generator Replacement Project (TS-SQN-2011-05)," dated September 29, 2011
- 2. Electronic Mail from NRC to TVA, "Sequoyah, Unit 1 LAR - Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP (TAC NO. ME7225)," dated January 13, 2012
- 3. Letter from TVA to NRC, "Response to NRC Request for Additional Information Regarding the Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP (TAC NO.
ME7225)," dated February 10, 2012
- 4. Electronic Mail from NRC to TVA, "Sequoyah, Unit 1 LAR - Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP (TAC NO. ME7225)," dated February 2, 2012
- 5. Letter from TVA to NRC, "Response to Second NRC Request for Additional Information Regarding the Heavy Load Lifts and UHS One Time Change in Support of Unit 2 SGRP (TAC NO.
ME7225)," dated March 5, 2012
U.S. Nuclear Regulatory Commission Page 2 April 5, 2012 The purpose of this letter is to submit Revision 3 of the Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling Technical Report, SQN2-SGR-TR1.
By letter dated September 29, 2011 (Reference 1), the Tennessee Valley Authority (TVA) submitted a one-time request for amendment to the Operating License (OL) for Sequoyah Nuclear Plant (SQN), Unit 1. The amendment request proposed to add a one-time license condition to the SQN, Unit 1, OL for the conduct of heavy load lifts associated with the SQN, Unit 2, Steam Generator Replacement Project (SGRP). The one-time license condition establishes special provisions and requirements for the safe operation of SQN, Unit 1, while large heavy load lifts are performed on SQN, Unit 2. In addition, a one-time change to SQN, Unit 1, Technical Specification (TS) 3.7.5, "Ultimate Heat Sink," is also proposed to implement additional restrictions with respect to maximum average Essential Raw Cooling Water System supply header water temperature during large heavy load lifts performed to support the SQN, Unit 2, SGRP.
By electronic mail dated January 13, 2012, (Reference 2), the NRC forwarded a request for additional information (RAI) regarding the proposed changes establishing the special provisions and requirements for large heavy load lifts on SQN, Unit 2.
TVA responded to this first RAI by letter dated February 10, 2012 (Reference 3).
Subsequently, by electronic mail dated February 2, 2012, the NRC forwarded a second RAI. TVA responded to the second RAI by letter dated March 5, 2012 (Reference 5).
Since submittal of the Reference 5 response to the second RAI, an alternate interfacing lift point for removal of the old steam generators (OSGs) has been identified. In Enclosure 2 to Reference 1, TVA provided the Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling Technical Report, SQN2-SGR-TR1, Revision 2. This Technical Report documents the provisions made to ensure that heavy load handling activities associated with the Unit 2 SGRP Outage can be accomplished without impacting the safe operation of Unit 1. Section 5.1, "Description of Cranes and Heavy Loads, Outside Lift System," of Revision 2 of the Technical Report describes using a lifting lug welded to the Main Steam nozzle as the interfacing lift point for removal of the OSGs. The alternate OSG interfacing lift point revises the interfacing lift point from the lifting lug to the secondary side manways, which will be fitted with keeper plates to enable slings to be utilized to rig out the OSGs. The secondary side manway lift point is described in Section 5.1 of Revision 3 of the Technical Report provided in Enclosure 1 to this letter.
U.S. Nuclear Regulatory Commission Page 3 April 5, 2012 Utilizing the secondary side manways as the OSG interfacing lift point eliminates the ignition sources in the Containment Building associated with welding the lifting lug to the Main Steam nozzle, including the post-weld heat treatment processes.
Eliminating the ignition sources improves the safety of personnel working in the Containment Building during the welding processes. In addition, using the secondary side manways is considered a more efficient method for removal of the OSGs which reduces the likelihood of human error by reducing complexity.
Furthermore, since the OSG removal task activity duration will be reduced, there will be a corresponding reduction in personnel radiation exposure.
Revision 3 of the Technical Report in Enclosure 1 to this letter supersedes in its entirety, Revision 2 of the Technical Report previously submitted in Enclosure 2 of Reference 1. In addition to the interfacing lift point revision described above, the following changes are also included in Revision 3 to the Technical Report:
- Added valve numbers to Figures 6-1 and 8-2 as addressed in the response to RAI Question 2 of the enclosure to Reference 5;
- Corrected the test weight;
- Changed Figure 5-3 to illustrate raising the Outside Lift System foundation by 6 inches;
- Changed the reference to "Liebherr 1400/1" crane to be "Liebherr 1400/1 or Liebherr 1400/2" to permit use of either crane; and,
- Made changes to reflect the updated Replacement Steam Generator rigging weight.
The changes are identified by revision bars in the Technical Report provided in to this letter. Enclosure 2 to this letter provides an affected page listing of each of the changes included in Revision 3 of the Technical Report.
TVA has evaluated the revision to the OSG interfacing lift point and the other changes made in Revision 3 of the Technical Report and determined that there is no impact on the no significant hazards considerations associated with the OL and TS amendment request submitted in Reference 1. TVA has further determined that the proposed amendment still qualifies for a categorical exclusion from environmental review pursuant to the provision of 10 CFR 510.22(c)(9). In addition, TVA has concluded that there is no change to the Probabilistic Risk Assessment (PRA)
Insights as documented in Section 9.0 of the Technical Report. In accordance with 10 CFR 50.91 (b)(1), TVA is sending a copy of this letter and enclosures to the Tennessee State Department of Environment and Conservation.
U.S. Nuclear Regulatory Commission Page 4 April 5, 2012 There are no regulatory commitments included in this submittal. If you have any questions, please contact Clyde Mackaman at (423) 751-2834.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 9" day of April 2012.
Resp~vc~tfully, Vice President Sequoyah Nuclear Plant
Enclosures:
- 1. Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling Technical Report, SQN2-SGR-TR1, Revision 3
- 2. SQN2-SGR-TR1 Revision 3 Affected Page List cc: (Enclosures):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant Director, Division of Radiological Health, Tennessee State Department of Environment and Conservation
