CNL-20-031, Supplement to Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 2 Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-1913)

Supplement to Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 2 Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-1913)

ML20098D779
Person / Time
Site:	Watts Bar
Issue date:	04/06/2020
From:	Jim Barstow Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-20-031, EPID L-2019-LLA-0219, WBN-TS-391-19-13
Download: ML20098D779 (2)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-20-031 April 6, 2020 10 CFR 50.90 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 Docket No. 50-391

Subject:

Supplement to Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13) (EPID L-2019-LLA-0209)

References:

1. TVA Letter to NRC, CNL-19-067, Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13), dated September 30, 2019 (ML19274C003 and ML19274C005)

2. TVA Letter to NRC, CNL-19-114, Supplement to Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13), dated November 21, 2019 (ML19326C091 ML19326C094)

3. NRC Electronic Mail to TVA, FW: Question for Watts Bar 2 Regarding SG Sleeve TS Change, dated March 12, 2020 (ML20076A043)

In Reference 1, Tennessee Valley Authority (TVA) submitted a request for an amendment to Facility Operating License No. NPF-96 for the Watts Bar Nuclear Plant (WBN), Unit 2. The proposed license amendment request (LAR) revises WBN Unit 2 Technical Specifications (TS) 3.4.17, SG Tube Integrity, 5.7.2.12, Steam Generator (SG) Program, and TS 5.9.9, Steam Generator Tube Inspection Report, to allow the use of Westinghouse leak-limiting non-nickel banded Alloy 800 sleeves to repair degraded SG tubes as an alternative to plugging the tube. Enclosure 2 to Reference 1 provided a copy of the Westinghouse Electric Company (Westinghouse) Report Proprietary Class 2 WCAP-15918-P, Revision 3, and Enclosure 3 to Reference 1 provided a copy of the Non-Proprietary version of the report (WCAP-15918-NP, Revision 3). In Reference 2, TVA submitted a supplement to Reference 1 that included Revision 4 to WCAP-15918-P, which contained a revised Figure 5-3 and corresponding changes to Section 5.0, Sleeve Examination Program, of WCAP-15918-P.

U.S. Nuclear Regulatory Commission CNL-20-031 Page 2 April 6, 2020 The following information also supplements Reference 1. In Reference 3, NRC inquired as to whether the reference in Revisions 3 and 4 to WCAP-15918-P to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Division 1, Rules for Inspection and Testing of Components of Light-Water Cooled Plants, Subsection IWA-4420, Heat Exchanger Tube Sleeving, should be IWA-4720, Sleeving.

In response to Reference 3, TVA has been informed by Westinghouse that WCAP-15918, including Revisions 3 and 4; is generic in nature and is written as though sleeving field activities will be performed in accordance with the requirements of Section XI of the ASME Code, 1995 Edition, with no Addenda, which contained IWA-4420. The code paragraph numbering for sleeving changed from IWA-4420 to IWA-4720 when the 1997 addenda to the 1995 Edition of Section XI of the ASME Code was published on December 31, 1997.

The code of record for WBN Unit 2 is the ASME Section XI B&PV Code 2007 Edition with the 2008 Addenda, which also contains IWA-4720. TVA has performed a comparison between IWA-4420 in Section XI of the ASME Code, 1995 Edition, with no Addenda to that of IWA-4720 in Section XI of the ASME Code, 2007 Edition with the 2008 Addenda. Other than paragraph numbering, there is no change to the technical content of the code between the 1995 Edition, No Addenda version, IWA-4420, and the 2007 Edition with the 2008 Addenda of Section XI, IWA-4720.

This letter does not change the conclusions, the no significant hazards consideration, nor the environmental considerations contained in Reference 1. Additionally, in accordance with 10 CFR 50.91(b)(1), TVA is sending a copy of this letter and the enclosure to the Tennessee Department of Environment and Conservation.

There are no new regulatory commitments associated with this submittal. If you have any questions about this proposed change, please contact Kimberly D. Hulvey, Fleet Licensing Manager, at (423) 751-3275.

I declare under penalty of perjury that the foregoing is true and correct. Executed on this 6th day of April 2020.

Respectfully, James Barstow Vice President, Nuclear Regulatory Affairs & Support Services cc:

NRC Regional Administrator - Region II NRC Project Manager - Watts Bar Nuclear Plant NRC Senior Resident Inspector - Watts Bar Nuclear Plant Director, Division of Radiological Health - Tennessee State Department of Environment and Conservation