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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 ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule 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 IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter ML24011A3162024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), August 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 ML24011A3192024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), November 2023 ML24011A3182024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), October 2023 ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) 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 ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public CNL-23-069, 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-23-068, 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) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23346A1222023-12-12012 December 2023 Annual Non-Radiological Environmental Operating Report - 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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-23-061, 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 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 2024-01-09
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Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing April 1, 2010 10 CFR 50.4 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390
Subject:
Insights from Questions and Responses From March 25, 2010 Discussion Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors On March 25, 2010, a telephone discussion was held between Tennessee Valley Authority (TVA) and contractor personnel and the Nuclear Regulatory Commission (NRC) staff concerning the proposed testing of emergency recirculation sump strainers for the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Unit 1.During this discussion several questions and comments were raised by TVA personnel that were answered or responded to by the NRC staff. At the end of this telephone call, the NRC staff requested that the questions asked and the answers given be documented by TVA and submitted for NRC staff concurrence.
The enclosure to this letter provides discussion of the insights from those questions and the respective responses for NRC review and concurrence.
App'printed on recycled paper k 2 U.S. Nuclear Regulatory Commission Page 2 April 1, 2010 There are no regulatory commitments in this letter. Should there be any questions regarding this letter, please contact Rod Cook at (423) 751-2834.Respectfully, R. M. Krich Enclosure Insights from Questions and Responses from March 25, 2010 Discussion Regarding GL 2004-02 Strainer Testing cc: (Enclosure)
NRC Regional Administrator
-Region II NRC Senior Resident Inspector
-Sequoyah Nuclear Plant NRC Senior Resident Inspector-Watts Bar Nuclear Plant ENCLOSURE Insights from Questions and Responses from March 25, 2010 Discussion Regarding GL 2004-02 Strainer Testing 1. Test Strainer's Configuration
-The staff agrees we can / should confine the test strainer on 3 sides; leaving one face on the upstream side of flow to the strainer fully exposed. The distance between the walls and test strainer shall be one half the gap distance between strainers in an array. See test configuration concept below.6 ft I 75% Strainer Flow 6 ft 5 ft Test Apparatus Layout 2. Mixing Energy -The intent is to prevent settling in the upstream high energy area and to use as much mixing energy as is possible to prevent settling in the lower level mixing area. Energy in the lower level mixing area is limited so as not to disturb the test strainer's debris bed during formation and testing.A successful thin bed / low fiber test is judged as one where all but residual debris has transported to and on the test strainer.A successful high fiber test is judged as one where the test strainer cavity strainer is full of debris and other debris is pushed up against the upstream face of the test strainer cavity. It is therefore acceptable in this situation for debris to also be located E-1 in the low level mixing area as it cannot reach the screen because it is impeded by other debris.3. Latent fiber can be included with other fiber "fines" in design basis testing. Only fiber"fines" are used in thin bed tests.4. The staff recommended batches of mixed fibers and particulates not be mixed together prior to introduction for a design basis test. The Sure-Flow Strainer (SFS)Team proposes to mix fibers and particulates separately and to introduce them to the trash pump transfer tank at the same time prior to the introduction of this debris to the test tank. Same goal will be accomplished, i.e. fiber and particulate will be well mixed at introduction.
Debris is introduced in several locations to disperse the debris throughout the upstream high energy area of the tank.Performance Contracting Incorporated (PCI) proposes to dilute fibers 5 to 1 (on a volume basis); which approximately equates to 8 grams of fiber to 1 liter of water.Staff indicated that they thought an acceptable dilution ratio was up to 15 to 25 grams of fiber to 1 liter of water., 5. The staff recommended the debris transfer tank / pipe and pump be flushed after all debris is introduced.
The SFS Team agrees and will also take the pump apart to confirm all debris has been transferred to the tank.6. The SFS Team proposed for thin bed tests to introduce fibers in incremental batches of one eighth inch thick; up to one half inch. At one half inch of fibers on the screen, the SFS gaps would be closed. The SFS Team believes any thicker bed cannot be considered to be a thin bed for SFS.The staff questioned if something less than a one eighth inch thick batch is appropriate to test if something less than a one eighth inch thick bed might be a worst case for the thin bed regime. Given the SFS's uniform flow control to all disks, the SFS Team believes the one eighth inch increment is appropriate.
The staff cautioned that one eighth inch increments are too large as the max thin bed head-loss condition is approached.
For a uniform flow strainer the staff anticipates that the thin bed regime may be achieved at less than a one eighth inch. Staff will comment later on a more detailed approach for thin bed testing and how to judge if the thin bed regime has been achieved, based on incremental head loss changes between fiber additions.
- 7. When to terminate the non-chemical debris introductions during a thin bed test was discussed.
Following comments from the staff, the Tennessee Valley Authority (TVA) asked for clarification regarding the use of subjective terms to describe when a change in head loss should, or should not be accepted as the point at which to stop adding fibers. What the SFS Team heard is the following:
If after introducing any batch of fibers following the first batch the head loss increase is 10% or less of the previously established head loss, then the introduction of fiber batches should stop. Allow the head loss to stabilize and then introduce chemicals.
E-2 If the head loss increases by more than 10% compared to the prior head loss reading, another batch of fibers should be added. This step is repeated until the condition above is reached or until the equivalent of one half inch of fibers has been introduced.
Paul Klein then suggested that adding chemicals to thicker fiber beds might not yield the highest overall head loss.The SFS Team needs additional clarification from the staff on how to reconcile this comment. In the past history of GSI-191, at whatever debris bed thickness a plant specific design basis reaches its peak thin bed head loss, it is that debris bed to which chemical precipitates should be added. To require otherwise would seem to impose on TVA multiple thin bed tests not required of other licensees and testing vendors "to date." The staff agreed to provide additional guidance to TVA and the SFS Team on the thin bed test criteria later.8. TVA will call the staff with milestone schedule dates for the next steps on April 2, 2010 at 10:00 am eastern.9. The licensee will submit a Test Plan for comment to the staff.E-3