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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 December 19, 2017 Mr. Joseph W. Shea Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 December 19, 2017 Mr. Joseph W. Shea Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| WATIS BAR NUCLEAR PLANT, UNIT 2- | | WATIS BAR NUCLEAR PLANT, UNIT 2- |
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| ==SUMMARY== | | ==SUMMARY== |
| OF OCTOBER 27, 2017, CONFERENCE CALL WITH TENNESSEE VALLEY AUTHORITY RE: FALL 2017 STEAM GENERATOR INSPECTIONS (EPID L-2017-LR0-0050) | | OF OCTOBER 27, 2017, CONFERENCE CALL WITH TENNESSEE VALLEY AUTHORITY RE: FALL 2017 STEAM GENERATOR INSPECTIONS (EPID L-2017-LR0-0050) |
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| ==Dear Mr. Shea:== | | ==Dear Mr. Shea:== |
| On November 13, 2017, the U.S Nuclear Regulatory Commission staff participated in a conference call with representatives of the Tennessee Valley Authority (the licensee) regarding the ongoing steam generator inspection activities at the Watts Bar Nuclear Plant, Unit 2. A list of participants is provided as Enclosure | | |
| : 1. A summary of the conference call is provided as Enclosure 2, which includes a list of questions and the licensee's draft responses discussed during the call. If you have any questions regarding this matter, I may be reached at (301) 415-6020 or Robert.Schaaf@nrc.gov.
| | On November 13, 2017, the U.S Nuclear Regulatory Commission staff participated in a conference call with representatives of the Tennessee Valley Authority (the licensee) regarding the ongoing steam generator inspection activities at the Watts Bar Nuclear Plant, Unit 2. A list of participants is provided as Enclosure 1. A summary of the conference call is provided as , which includes a list of questions and the licensee's draft responses discussed during the call. |
| Docket No. 50-391 | | If you have any questions regarding this matter, I may be reached at (301) 415-6020 or Robert.Schaaf@nrc.gov. |
| | Sincerely, |
| | ~Rgj_! |
| | Robert G. Schaaf, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. List of Participants | | : 1. List of Participants |
| : 2. Conference Call Summary cc: Distribution via Listserv Sincerely, ~Rgj_! Robert G. Schaaf, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LIST OF PARTICIPANTS NOVEMBER 13, 2017, CONFERENCE CALL WITH TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 2 FALL 2017 STEAM GENERATOR INSPECTIONS U.S. Nuclear Regulatory Commission Farideh Saba Alan Huynh Paul Klein Andrew Johnson Alexander Butcavage Tennessee Valley Authority Kim Hulvey Russell Wells Jeremy Mayo Dan Folsom Jesse Baron Enclosure 1 | | : 2. Conference Call Summary cc: Distribution via Listserv |
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| | LIST OF PARTICIPANTS NOVEMBER 13, 2017, CONFERENCE CALL WITH TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 2 FALL 2017 STEAM GENERATOR INSPECTIONS U.S. Nuclear Regulatory Commission Farideh Saba Alan Huynh Paul Klein Andrew Johnson Alexander Butcavage Tennessee Valley Authority Kim Hulvey Russell Wells Jeremy Mayo Dan Folsom Jesse Baron Enclosure 1 |
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| ==SUMMARY== | | ==SUMMARY== |
| OF NOVEMBER 13, 2017, CONFERENCE CALL WITH TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 2 FALL 2017 STEAM GENERATOR TUBE INSPECTIONS DOCKET NO. 50-391 On November 13, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with Tennessee Valley Authority (the licensee), regarding the ongoing steam generator (SG) tube inspection activities at Watts Bar Nuclear Plant (Watts Bar), Unit 2. Several topics regarding the ongoing inspections were discussed during the conference call. A summary of the discussion follows. | | OF NOVEMBER 13, 2017, CONFERENCE CALL WITH TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 2 FALL 2017 STEAM GENERATOR TUBE INSPECTIONS DOCKET NO. 50-391 On November 13, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with Tennessee Valley Authority (the licensee), regarding the ongoing steam generator (SG) tube inspection activities at Watts Bar Nuclear Plant (Watts Bar), Unit 2. |
| | Several topics regarding the ongoing inspections were discussed during the conference call. A summary of the discussion follows. |
| * This was the first refueling outage for the Watts Bar, Unit 2, SGs following the recently completed operating cycle of 0.74 effective full power years. At the time of the call, the licensee was almost finished with eddy current exams but still had some additional SG inspections (e.g., SG 4 foreign object search and retrieval) to complete. | | * This was the first refueling outage for the Watts Bar, Unit 2, SGs following the recently completed operating cycle of 0.74 effective full power years. At the time of the call, the licensee was almost finished with eddy current exams but still had some additional SG inspections (e.g., SG 4 foreign object search and retrieval) to complete. |
| * The licensee provided an overview of the design of its SGs during the call. The Watts Bar, Unit 2, Westinghouse Model D3 SGs were fabricated in the early 1970s. Each SG has 4,674 mill-annealed Alloy 600 tubes that have a nominal outer diameter of 0.75 inches and nominal wall thickness of 0.043 inches. The tubes are supported by drilled carbon steel tube support plates (TSPs) and were hard roll expanded for the full depth of the tubesheet. | | * The licensee provided an overview of the design of its SGs during the call. The Watts Bar, Unit 2, Westinghouse Model D3 SGs were fabricated in the early 1970s. Each SG has 4,674 mill-annealed Alloy 600 tubes that have a nominal outer diameter of 0.75 inches and nominal wall thickness of 0.043 inches. The tubes are supported by drilled carbon steel tube support plates (TSPs) and were hard roll expanded for the full depth of the tubesheet. The licensee stated that some tubes were pulled prior to operation to aid loose parts retrieval efforts. |
| The licensee stated that some tubes were pulled prior to operation to aid loose parts retrieval efforts. | |
| * The licensee stated that there was no primary-to-secondary leakage observed during the recently completed operating cycle, no secondary side pressure tests were performed, and no in-situ pressure tests or tube pulls were planned. | | * The licensee stated that there was no primary-to-secondary leakage observed during the recently completed operating cycle, no secondary side pressure tests were performed, and no in-situ pressure tests or tube pulls were planned. |
| * The licensee stated that there were two deviations taken to the industry guidelines. | | * The licensee stated that there were two deviations taken to the industry guidelines. One was related to the Water Chemistry guidelines for high ionic impurities at startup, due to the long shutdown during the operating cycle. This deviation was closed at the time of the call. The other deviation was due to the performance of preservice inspections prior to hydrostatic tests instead of after the hydrostatic tests. This deviation was to be closed after the outage. |
| One was related to the Water Chemistry guidelines for high ionic impurities at startup, due to the long shutdown during the operating cycle. This deviation was closed at the time of the call. The other deviation was due to the performance of preservice inspections prior to hydrostatic tests instead of after the hydrostatic tests. This deviation was to be closed after the outage. | |
| * The licensee provided the scope of its inspections, which included: | | * The licensee provided the scope of its inspections, which included: |
| o 100 percent full-length bobbin o +PointŽ inspections of U-bends in rows 1-4 o Special interest inspections for non-resolved bobbin indications o 100 percent hot leg (HL) top of tubesheet o 50 percent X-probe up to the sixth TSP Gust above the preheater inlet) on cold leg (CL) sid~ for loose parts o +PointŽ or X-probe of dents/dings 5 volts (HL to top CL TSP) Enclosure 2 o 20 percent +PointŽ or X-probe of dents/dings 2 volts o Channel head inspections o Foreign object search and retrieval (FOSAR) o Sludge lancing o Steam drum inspections | | o 100 percent full-length bobbin o +Point' inspections of U-bends in rows 1-4 o Special interest inspections for non-resolved bobbin indications o 100 percent hot leg (HL) top of tubesheet o 50 percent X-probe up to the sixth TSP Gust above the preheater inlet) on cold leg (CL) sid~ for loose parts o +Point' or X-probe of dents/dings ~ 5 volts (HL to top CL TSP) |
| * The licensee stated that tube wear from anti-vibration bars was the only form of degradation detected. | | Enclosure 2 |
| The maximum depth was 15 percent through-wall for all indications. | | |
| | o 20 percent +Point' or X-probe of dents/dings ~ 2 volts o Channel head inspections o Foreign object search and retrieval (FOSAR) o Sludge lancing o Steam drum inspections |
| | * The licensee stated that tube wear from anti-vibration bars was the only form of degradation detected. The maximum depth was 15 percent through-wall for all indications. |
| * The licensee stated that in-situ pressure tests and tube pulls were not performed. | | * The licensee stated that in-situ pressure tests and tube pulls were not performed. |
| * Regarding loose parts, the licensee stated that X-probe inspections, FOSAR, and sludge lancing were performed. | | * Regarding loose parts, the licensee stated that X-probe inspections, FOSAR, and sludge lancing were performed. The licensee stated that one loose part was not removed from the SGs and tubes surrounding it would be plugged. There were no wear indications associated with loose parts. The licensee also stated that while sludge lancing is typically performed prior to FOSAR, it performed some FOSAR prior to sludge lancing. |
| The licensee stated that one loose part was not removed from the SGs and tubes surrounding it would be plugged. There were no wear indications associated with loose parts. The licensee also stated that while sludge lancing is typically performed prior to FOSAR, it performed some FOSAR prior to sludge lancing. The licensee removed 24.5, 22.5, 27.5, and 35 pounds of sludge from SGs 1, 2, 3, and 4, respectively. | | The licensee removed 24.5, 22.5, 27.5, and 35 pounds of sludge from SGs 1, 2, 3, and 4, respectively. |
| The NRC staff did not identify any issues that required followup action at this time; however, the NRC staff asked to be notified in the event that any unusual conditions were detected during the remainder of the outage. | | The NRC staff did not identify any issues that required followup action at this time; however, the NRC staff asked to be notified in the event that any unusual conditions were detected during the remainder of the outage. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| WADS BAR NUCLEAR PLANT, UNIT 2 - | | WADS BAR NUCLEAR PLANT, UNIT 2 - |
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| ==SUMMARY== | | ==SUMMARY== |
| OF OCTOBER 27, 2017, CONFERENCE CALL WITH TENNESSEE VALLEY AUTHORITY RE: FALL 2017 STEAM GENERATOR INSPECTIONS (EPID L-2017-LR0-0050) | | OF OCTOBER 27, 2017, CONFERENCE CALL WITH TENNESSEE VALLEY AUTHORITY RE: FALL 2017 STEAM GENERATOR INSPECTIONS (EPID L-2017-LR0-0050) |
| DATED DECEMBER 19, 2017 DISTRIBUTION: | | DATED DECEMBER 19, 2017 DISTRIBUTION: |
| PUBLIC RidsACRS_MailCTR Resource RidsNrrDorlLpl2-2 Resource RidsNrrDmlrMccb Resource AHuynh, NRR AJohnson, NRR AButcavage, R-11 ADAMS A ccess1on N ML17339A090 o.: OFFICE D0RULPL2-2/PM D0RULPL2-2/LA NAME RSchaaf BClayton (LRonewicz for) DATE 12/11/2017 12/08/2017 RidsRgn2Mai1Center Resource RidsNrrDssStsb Resource RidsNrrLABClayton Resource RidsNrrPMWattsBar Resource PKlein, NRR SWalkery, R-11 JNadel, R-11 *b d >Y memoran um DMLR/MCCB/BC* | | PUBLIC RidsRgn2Mai1Center Resource RidsACRS_MailCTR Resource RidsNrrDssStsb Resource RidsNrrDorlLpl2-2 Resource RidsNrrLABClayton Resource RidsNrrDmlrMccb Resource RidsNrrPMWattsBar Resource AHuynh, NRR PKlein, NRR AJohnson, NRR SWalkery, R-11 AButcavage, R-11 JNadel, R-11 ADAMS A ccess1on N o.: ML17339A090 *b>Y memoran d um OFFICE D0RULPL2-2/PM D0RULPL2-2/LA DMLR/MCCB/BC* D0RULPL2-2/BC D0RULPL2-2/PM BClayton NAME RSchaaf SBloom UShoop RSchaaf (LRonewicz for) |
| D0RULPL2-2/BC D0RULPL2-2/PM SBloom UShoop RSchaaf 11/27/2017 12/19/2017 12/19/2017 OFFICIAL RECORD COPY}} | | DATE 12/11/2017 12/08/2017 11/27/2017 12/19/2017 12/19/2017 OFFICIAL RECORD COPY}} |
Letter Sequence Other |
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MONTHYEARML17339A0902017-12-19019 December 2017
Summary of October 27, 2017, Conference Call with Tennessee Valley Authority Fall 2017 Steam Generator Inspections
Project stage: Other
2017-12-19
[Table View] |
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Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024
Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI)
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
IR 05000390/20243012024-10-17017 October 2024
Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301
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
ML24261C0062024-10-0404 October 2024
Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96
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
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
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
05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024
Automatic Reactor Trip Due to Main Generator Protection Relay Actuation
IR 05000390/20240052024-08-28028 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005
ML24218A1442024-08-27027 August 2024
Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate
IR 05000390/20244022024-08-20020 August 2024
– Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public
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),
ML24219A0262024-08-12012 August 2024
Request for Withholding Information from Public Disclosure
IR 05000390/20240022024-08-0707 August 2024
Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev
ML24204A2652024-07-25025 July 2024
Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate
ML24199A0012024-07-22022 July 2024
Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2)
ML24170A8002024-07-15015 July 2024
Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts
ML24172A1342024-07-15015 July 2024
Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter
IR 05000390/20244402024-07-12012 July 2024
95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter
05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024
Inoperability of Both Trains of Unit 2 Low Head Safety Injection
ML24131A0012024-07-0202 July 2024
Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2
CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024
Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)
CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024
License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS
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)
ML24141A0482024-05-17017 May 2024
EN 56958_1 Ametek Solidstate Controls, Inc
ML24100A7642024-05-16016 May 2024
Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062)
IR 05000390/20240012024-05-14014 May 2024
Integrated Inspection Report 05000390/2024001 and 05000391/2024001
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
05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024
Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO
IR 05000391/20240072024-04-30030 April 2024
Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007
ML24120A1182024-04-29029 April 2024
– Notification of NRC Supplemental Inspection (95001) and Request for Information
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
ML24087A1912024-04-18018 April 2024
Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting
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-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024
License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)
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
ML24072A0052024-04-15015 April 2024
Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report
CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024
Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)
IR 05000390/20244012024-04-0202 April 2024
– Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public)
CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024
Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements
05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024
Automatic Reactor Trip Due to Main Generator Protection Relay Actuation
CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024
Annual Insurance Status Report
CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024
Guarantee of Payment of Deferred Premiums - 2023 Annual Report
CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024
Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule
ML24081A0262024-03-21021 March 2024
Emergency Plan Implementing Procedure Revisions
ML24079A0312024-03-19019 March 2024
Wb 2024-301, Corporate Notification Letter (210-day Ltr)
2024-09-05
[Table view]
Category:Meeting Summary
MONTHYEARML24292A1832024-10-30030 October 2024
Summary of Meeting with Tennessee Valley Authority, October 16, 2024, to Discuss Proposed License Amendment Regarding Implementation of an Online Monitoring Methodology
ML24269A0062024-10-0303 October 2024
Correction to Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the TVA Nuclear Quality Assurance Plan
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
ML24228A2652024-08-20020 August 2024
Summary of Public Pre-Submittal Meeting with Tennessee Valley Authority Regarding a Future Sequoyah Nuclear Plant and Watts Bar Nuclear Plant LAR Related to TS 3.5.2. ECCS - Operating
ML24221A0132024-08-19019 August 2024
July 10, 2024, Summary of Meeting with Tennessee Valley Authority Regarding a Proposed Change to the Tennessee Valley Authority Nuclear Quality Assurance Plan
ML24173A2122024-06-27027 June 2024
Summary of Public Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request Regarding Adoption of TSTF-276-A, Revision 2 to Clarify Requirements for Diesel Generator Testing
ML24158A3002024-06-11011 June 2024
Summary of May 6, 2024, Public Meeting with Tennessee Valley Authority to Discuss the Potential for a License Amendment Request Regarding the Control Room Envelope and Selective Use of an Alternative Source Term
ML24089A0712024-04-0101 April 2024
3/20/24 & 3/27/24 2023 TVA Public Annual Assessment Meeting Summary
ML24057A0582024-02-27027 February 2024
Summary of February 15, 2024, Public Meeting with Tennessee Valley Authority Regarding Proposed License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2
ML24008A1592024-01-18018 January 2024
Summary of December 13, 2023, Meeting with Tennessee Valley Authority Regarding a Proposed Change to the Tennessee Valley Authority Nuclear Quality Assurance Plan
ML23304A0682023-11-0606 November 2023
Summary of October 24, 2023, Public Mtg W/Tennessee Valley Authority Regarding Proposed License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2, and Sequoyah Nuclear Plant, Units 1 and 2 to Revise Function 5, Turbine Trip and F
ML23265A1512023-09-28028 September 2023
Summary of September 12, 2023, Partially Closed Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request
ML23198A3102023-07-20020 July 2023
July 10, 2023, Summary of Public Meeting with Tennessee Valley Authority Regarding Proposed License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2
ML23142A2132023-05-22022 May 2023
Public Meeting Summary - 2022 Annual Assessment Meetings for Browns Ferry, Sequoyah and Watts Bar Nuclear Plants
ML23068A1532023-03-16016 March 2023
Summary of February 22, 2023, Meeting with Tennessee Valley Authority Regarding Proposed License Amendment Request to Increase Allowable Number of Tritium Producing Burnable Absorber Rods at Watts Bar Nuclear Plant, Units 1 and 2
ML23055A4562023-03-0909 March 2023
Summary of February 15, 2023, Public Meeting with Tennessee Valley Authority Regarding Proposed Expedited License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2
ML22329A1382022-12-0505 December 2022
Summary of Meeting with Tennessee Valley Authority Related to Planned Alternative Request WBN-2-ISI-01 for Watts Bar Nuclear Plant, Unit 2
ML22168A1642022-06-27027 June 2022
Summary of June 9, 2022, Meeting with TVA Regarding a Proposed License Amendment Request Related to Low Temperature Overpressure System and Cold Overpressure Mitigation System for Sequoyah and Watts Bar Nuclear Plants
ML22104A2252022-04-20020 April 2022
Summary of Meeting with Tennessee Valley Authority Regarding a Proposed Exemption Request for Watts Bar Nuclear Plant, Unit 2
ML22109A0042022-04-20020 April 2022
Summary of Meeting with Tennessee Valley Authority Regarding a Proposed Alternative Request Related to Testing of the Motor-Driven Auxiliary Feedwater Pumps at Sequoyah and Watts Bar Nuclear Plants
ML22108A1842022-04-18018 April 2022
TVA 2021 Annual Assessment Public Meeting Summary
ML22042B3262022-02-14014 February 2022
Summary of February 8, 2022, Meeting with Tennessee Valley Authority Regarding a Proposed License Amendment Request to Revise the Allowable Value for Trip of Turbine-Driven Main Feedwater Pump at Watts Bar Nuclear Plant, Unit 1
ML22025A3112022-02-0909 February 2022
Summary of January 19, 2022, Meeting with Tennessee Valley Authority Regarding a Proposed Schedule for Development of a License Amendment Request for Increased Tritium Production
ML21349A3642022-01-0404 January 2022
Summary of December 14, 2021, Teleconference with Tennessee Valley Authority Regarding a Proposed Change to the Capsule Withdrawal Schedule for Watts Bar Nuclear Plant, Unit 2
ML21279A0902021-11-0303 November 2021
Summary of Conference Calls Regarding the Fall 2021, Mid-Cycle Steam Generator Tube Inspections
ML21291A0092021-11-0303 November 2021
Tennessee Valley Authority Fleet - Summary of October 13, 2021, Teleconference with Tennessee Valley Authority to Discuss Planned License Amendment Requests Related to the Emergency Action Level Scheme
ML21253A0872021-09-15015 September 2021
Summary of August 19, 2021, Partially Closed Meeting with Tennessee Valley Authority to Discuss Mid-Cycle Outage Contingencies for Watts Bar Nuclear Plant, Unit 2
ML21245A4252021-09-15015 September 2021
Summary of August 19, 2021, Teleconference with Tennessee Valley Authority Regarding Planned License Amendment Request Related to the Watts Bar Nuclear Plant, Units 1 and 2
ML21165A1482021-06-30030 June 2021
Summary of Closed Meeting with Tennessee Valley Authority to Discuss Planned Requests for Exemption from Certain Requirements of 10 CFR Part 37
ML21137A0022021-05-17017 May 2021
Public Meeting Summary - Browns Ferry, Sequoyah and Watts Bar Nuclear Plants, Docket Nos. 50-259, 50-260, 50-296, 50-327, 50-328, 50-390, and 50-391, Meeting Number 20210392
ML21120A2192021-05-0404 May 2021
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2024-09-23
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 December 19, 2017 Mr. Joseph W. Shea Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801
SUBJECT:
WATIS BAR NUCLEAR PLANT, UNIT 2-
SUMMARY
OF OCTOBER 27, 2017, CONFERENCE CALL WITH TENNESSEE VALLEY AUTHORITY RE: FALL 2017 STEAM GENERATOR INSPECTIONS (EPID L-2017-LR0-0050)
Dear Mr. Shea:
On November 13, 2017, the U.S Nuclear Regulatory Commission staff participated in a conference call with representatives of the Tennessee Valley Authority (the licensee) regarding the ongoing steam generator inspection activities at the Watts Bar Nuclear Plant, Unit 2. A list of participants is provided as Enclosure 1. A summary of the conference call is provided as , which includes a list of questions and the licensee's draft responses discussed during the call.
If you have any questions regarding this matter, I may be reached at (301) 415-6020 or Robert.Schaaf@nrc.gov.
Sincerely,
~Rgj_!
Robert G. Schaaf, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosures:
- 1. List of Participants
- 2. Conference Call Summary cc: Distribution via Listserv
LIST OF PARTICIPANTS NOVEMBER 13, 2017, CONFERENCE CALL WITH TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 2 FALL 2017 STEAM GENERATOR INSPECTIONS U.S. Nuclear Regulatory Commission Farideh Saba Alan Huynh Paul Klein Andrew Johnson Alexander Butcavage Tennessee Valley Authority Kim Hulvey Russell Wells Jeremy Mayo Dan Folsom Jesse Baron Enclosure 1
SUMMARY
OF NOVEMBER 13, 2017, CONFERENCE CALL WITH TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 2 FALL 2017 STEAM GENERATOR TUBE INSPECTIONS DOCKET NO. 50-391 On November 13, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with Tennessee Valley Authority (the licensee), regarding the ongoing steam generator (SG) tube inspection activities at Watts Bar Nuclear Plant (Watts Bar), Unit 2.
Several topics regarding the ongoing inspections were discussed during the conference call. A summary of the discussion follows.
- This was the first refueling outage for the Watts Bar, Unit 2, SGs following the recently completed operating cycle of 0.74 effective full power years. At the time of the call, the licensee was almost finished with eddy current exams but still had some additional SG inspections (e.g., SG 4 foreign object search and retrieval) to complete.
- The licensee provided an overview of the design of its SGs during the call. The Watts Bar, Unit 2, Westinghouse Model D3 SGs were fabricated in the early 1970s. Each SG has 4,674 mill-annealed Alloy 600 tubes that have a nominal outer diameter of 0.75 inches and nominal wall thickness of 0.043 inches. The tubes are supported by drilled carbon steel tube support plates (TSPs) and were hard roll expanded for the full depth of the tubesheet. The licensee stated that some tubes were pulled prior to operation to aid loose parts retrieval efforts.
- The licensee stated that there was no primary-to-secondary leakage observed during the recently completed operating cycle, no secondary side pressure tests were performed, and no in-situ pressure tests or tube pulls were planned.
- The licensee stated that there were two deviations taken to the industry guidelines. One was related to the Water Chemistry guidelines for high ionic impurities at startup, due to the long shutdown during the operating cycle. This deviation was closed at the time of the call. The other deviation was due to the performance of preservice inspections prior to hydrostatic tests instead of after the hydrostatic tests. This deviation was to be closed after the outage.
- The licensee provided the scope of its inspections, which included:
o 100 percent full-length bobbin o +Point' inspections of U-bends in rows 1-4 o Special interest inspections for non-resolved bobbin indications o 100 percent hot leg (HL) top of tubesheet o 50 percent X-probe up to the sixth TSP Gust above the preheater inlet) on cold leg (CL) sid~ for loose parts o +Point' or X-probe of dents/dings ~ 5 volts (HL to top CL TSP)
Enclosure 2
o 20 percent +Point' or X-probe of dents/dings ~ 2 volts o Channel head inspections o Foreign object search and retrieval (FOSAR) o Sludge lancing o Steam drum inspections
- The licensee stated that tube wear from anti-vibration bars was the only form of degradation detected. The maximum depth was 15 percent through-wall for all indications.
- The licensee stated that in-situ pressure tests and tube pulls were not performed.
- Regarding loose parts, the licensee stated that X-probe inspections, FOSAR, and sludge lancing were performed. The licensee stated that one loose part was not removed from the SGs and tubes surrounding it would be plugged. There were no wear indications associated with loose parts. The licensee also stated that while sludge lancing is typically performed prior to FOSAR, it performed some FOSAR prior to sludge lancing.
The licensee removed 24.5, 22.5, 27.5, and 35 pounds of sludge from SGs 1, 2, 3, and 4, respectively.
The NRC staff did not identify any issues that required followup action at this time; however, the NRC staff asked to be notified in the event that any unusual conditions were detected during the remainder of the outage.
SUBJECT:
WADS BAR NUCLEAR PLANT, UNIT 2 -
SUMMARY
OF OCTOBER 27, 2017, CONFERENCE CALL WITH TENNESSEE VALLEY AUTHORITY RE: FALL 2017 STEAM GENERATOR INSPECTIONS (EPID L-2017-LR0-0050)
DATED DECEMBER 19, 2017 DISTRIBUTION:
PUBLIC RidsRgn2Mai1Center Resource RidsACRS_MailCTR Resource RidsNrrDssStsb Resource RidsNrrDorlLpl2-2 Resource RidsNrrLABClayton Resource RidsNrrDmlrMccb Resource RidsNrrPMWattsBar Resource AHuynh, NRR PKlein, NRR AJohnson, NRR SWalkery, R-11 AButcavage, R-11 JNadel, R-11 ADAMS A ccess1on N o.: ML17339A090 *b>Y memoran d um OFFICE D0RULPL2-2/PM D0RULPL2-2/LA DMLR/MCCB/BC* D0RULPL2-2/BC D0RULPL2-2/PM BClayton NAME RSchaaf SBloom UShoop RSchaaf (LRonewicz for)
DATE 12/11/2017 12/08/2017 11/27/2017 12/19/2017 12/19/2017 OFFICIAL RECORD COPY
