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Category:Letter type:L
MONTHYEARL-20-006, Unit 2, Emergency Plan Implementing Procedure Revision2020-02-10010 February 2020
Unit 2, Emergency Plan Implementing Procedure Revision
L-12-001, Revised Response to NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System2019-12-26026 December 2019
Revised Response to NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System
L-19-061, Unit 2 - Emergency Plan Implementing Procedure Revision2019-12-16016 December 2019
Unit 2 - Emergency Plan Implementing Procedure Revision
L-19-058, Statement of Payment of Civil Penalty2019-12-11011 December 2019
Statement of Payment of Civil Penalty
L-19-054, Unit 2 - Emergency Plan Implementing Procedure Revision2019-12-0505 December 2019
Unit 2 - Emergency Plan Implementing Procedure Revision
L-19-046, Notification of Readiness for NRC Independent Review to Confirm Chilling Effect Letter and Cross-Cutting Issue Closure Criteria Have Been Met2019-10-0303 October 2019
Notification of Readiness for NRC Independent Review to Confirm Chilling Effect Letter and Cross-Cutting Issue Closure Criteria Have Been Met
L-19-052, Revision 47 to Emergency Plan Implementing Procedure EPIP 12, Emergency Equipment and Supplies2019-09-30030 September 2019
Revision 47 to Emergency Plan Implementing Procedure EPIP 12, Emergency Equipment and Supplies
L-19-048, Response to Apparent Violation in NRC Inspection Report 05000390/2019013 and 05000391/2019013, EA-19-0422019-09-12012 September 2019
Response to Apparent Violation in NRC Inspection Report 05000390/2019013 and 05000391/2019013, EA-19-042
L-19-041, Cycle 2 Steam Generator Tube Inspection Report2019-08-27027 August 2019
Cycle 2 Steam Generator Tube Inspection Report
L-19-045, American Society of Mechanical Engineers, Section XI, First 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 2 Operation2019-08-14014 August 2019
American Society of Mechanical Engineers, Section XI, First 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 2 Operation
L-19-044, Unit 2 - Forward Emergency Plan Implementing Procedure Revisions2019-08-0808 August 2019
Unit 2 - Forward Emergency Plan Implementing Procedure Revisions
L-19-036, Notification of Readiness for NRC Inspection Procedure 95001 Inspection2019-06-20020 June 2019
Notification of Readiness for NRC Inspection Procedure 95001 Inspection
L-19-034, Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2019-06-18018 June 2019
Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report
L-19-031, Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2019-02 - Preparation and Scheduling of Operator Licensing Examinations2019-05-15015 May 2019
Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2019-02 - Preparation and Scheduling of Operator Licensing Examinations
L-19-016, Annual Radiological Environmental Operating Report - 20182019-05-15015 May 2019
Annual Radiological Environmental Operating Report - 2018
L-19-029, Submittal of Revision 0 of Cycle 3 Core Operating Limits Report2019-04-24024 April 2019
Submittal of Revision 0 of Cycle 3 Core Operating Limits Report
L-19-015, Annual Non-Radiological Environmental Operating Report - 20182019-04-11011 April 2019
Annual Non-Radiological Environmental Operating Report - 2018
L-19-026, Revised Pressure and Temperature Limits Report (PTLR)2019-04-0404 April 2019
Revised Pressure and Temperature Limits Report (PTLR)
L-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual2019-03-19019 March 2019
Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual
L-19-024, Unit 2 - Emergency Plan Implementing Procedures Revision2019-03-0707 March 2019
Unit 2 - Emergency Plan Implementing Procedures Revision
L-19-019, Transmittal of 10 CFR 50.46 - 30-Day and Annual Report for Watts Bar Nuclear Plant, Units 1 and 22019-03-0707 March 2019
Transmittal of 10 CFR 50.46 - 30-Day and Annual Report for Watts Bar Nuclear Plant, Units 1 and 2
L-19-011, Plant, Unit 1 - Revision 1 of the Cycle 16 Core Operating Limits Report (COLR)2019-01-29029 January 2019
Plant, Unit 1 - Revision 1 of the Cycle 16 Core Operating Limits Report (COLR)
L-19-008, American Society of Mechanical Engineers, Section Xl, Third 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 15 Operation2019-01-24024 January 2019
American Society of Mechanical Engineers, Section Xl, Third 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 15 Operation
L-18-001, Notification of Readiness for NRC Inspection Procedure 95001 Inspection2018-11-26026 November 2018
Notification of Readiness for NRC Inspection Procedure 95001 Inspection
L-04-001, Completion of Action Required in Response to NRC Bulletin 2004-01: Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors2018-01-25025 January 2018
Completion of Action Required in Response to NRC Bulletin 2004-01: Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors
L-11-001, Submittal of 30-Day Response to NRC Bulletin 2011-01, Mitigating Strategies.2015-09-24024 September 2015
Submittal of 30-Day Response to NRC Bulletin 2011-01, Mitigating Strategies.
L-11-011, Transmittal of Response to NRC Bulletin 2011-01, Mitigating Strategies.2015-06-29029 June 2015
Transmittal of Response to NRC Bulletin 2011-01, Mitigating Strategies.
L-88-017, Response Clarification to Generic Letter 88-0172013-08-13013 August 2013
Response Clarification to Generic Letter 88-017
L-03-004, Tennessee Valley Authority Response to Nuclear Regulatory Commission Bulletin 2003-04, Rebaselining of Data in the Nuclear Materials Management and Safeguards System, Dated October 8, 20032003-12-18018 December 2003
Tennessee Valley Authority Response to Nuclear Regulatory Commission Bulletin 2003-04, Rebaselining of Data in the Nuclear Materials Management and Safeguards System, Dated October 8, 2003
2020-02-10
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Text
Tennessee Valley Authority, Post Office Box 2000 Spring City, Tennessee 37381 January 25,2018 10 cFR 50.4 10 CFR 50 55(a)
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 Facility Operating License No. NPF-96 NRC Docket No. 50-391
Subject:
Watts Bar Nuclear Plant Unit 2 - Gompletion of Action Required in Response to NRC Bulletin 2004-01: lnspection of A!!oy 8211921600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors
Reference:
TVA letter to NRC, "Watts Bar Nuclear Plant WBN) - Unit 2 - lnitial Responses to Bulletins and Generic Letters," dated September 7,2007 (M1072570676) ln the referenced letter, the Tennessee Valley Authority (TVA) provided information on how the Watts Bar Nuclear Plant WBN) Unit 2 would meet the requirements of Nuclear Regulatory Commission (NRC) Bulletin 2004-01, ltems 1(c) and 2. Specifically, for Item 1(c), the referenced letter stated:
"TVA will perform a bare metal visual (BMV) inspection of the upper pressurizer Alloy 600 locations at the first refueling outage. This inspection will be performed utilizing the "in-house" procedure titled "Visual lnspection of Alloy 6001821182 Pressure Boundary Components." ln accordance with plant procedures, personnel performing the inspection will be certified NDE inspectors qualified in the ASME Section Xl, VT-2 method. The extent of examination will be 100 percent of each weld circumference and will be documented on written reports which may include photographs or video."
Accordingly, during the first WBN Unit 2 refueling outage, TVA performed a direct Visual Examination (VE) of the bare-metal surface of the upper pressurizer Alloy 600 locations and the surge line connection on the bottom of the pressurizer. The qualified examiners (i.e., certified NDE inspectors qualified in the ASME Section Xl, VT-2 method) obtained 100 percent coverage of the required examination area and the extent of the examination was properly documented.
U.S. Nuclear Regulatory Commission Page2 January 25,2018 Regarding Bulletin 2OO4-01, ltem (2), the visuat examination identified no leakage, no areas of corrosion resulting from leakage and no crack-like indications. The examination was performed at a distance of less than four feet.
This summary complies with the requirement of NRC Bulletin 2004-01 ltem 2 to report the results of this inspection to NRC within 60 days of completion of the first WBN Unit 2 refueling outage.
There are no new regulatory commitments in this letter. Should you have questions regarding this submiftal, please contact Kim Hulvey, Manager of Watts Bar Site Licensing, at (423) 365-7720.
Respectfully, Pau! Simmons Site Vice President Watts Bar Nuclear Plant cc:
NRC Regional Administrator - Region ll NRC Senior Resident lnspector - Watts Bar Nuclear Plant NRR Project Manager - Watts Bar Nuclear Plant
