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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
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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, 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