WBL-20-042, American Society of Mechanical Engineers, Section XI, Third 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 16 Operation

American Society of Mechanical Engineers,Section XI, Third 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 16 Operation

ML20247J532
Person / Time
Site:	Watts Bar
Issue date:	09/03/2020
From:	Anthony Williams Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
WBL-20-042
Download: ML20247J532 (7)

Text

II!fil Tennessee Valley Authority , Post Office Box 2000, Spring City, Tennessee 37381-2000 WBL-20-042 September 3, 2020 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390

Subject:

American Society of Mechanical Engineers,Section XI, Third 10-Year Inspection Interval, lnservice Inspection Owner's Activity Report For Cycle 16 Operation The Tennessee Valley Authority is submitting the Watts Bar Nuclear Plant, Unit 1, American Society of Mechanical Engineers (ASME),Section XI, Owner's Activity Report for Unit 1 Cycle 16 operation as required by Article IWA-6000,Section XI, Division 1. The report is contained in the enclosure to this letter and is in accordance with the requirements of ASME Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission."

The report is an overview of the results from in service examinations that were performed on components within the ASME Section XI boundary, up to and including the Unit 1 Cycle 16 refueling outage, during the second period of the third inspection interval. The applicable provisions of the ASME Code require that this report be submitted 90 days from the end of the applicable outage, i.e., by September 3, 2020 .

There are no new regulatory commitments associated with this submittal. If you have questions regarding this letter, please contact Tony Brown at (423) 365-7720.

Anthony L. Williams IV Site Vice President Watts Bar Nuclear Plant

U. S. Nuclear Regulatory Commission WBL-20-042 Page 2 September 3, 2020

Enclosure:

American Society of Mechanical Engineers,Section XI, Third 10-Year Inservice Inspection Interval, Inservice Inspection Owner's Activity Report for Cycle 16 Operation (Form OAR-1) cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector NRR Project Manager

ENCLOSURE TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS, SECTION XI, THIRD 10-YEAR INSPECTION INTERVAL, INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR CYCLE 16 OPERATION

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number U1Rl6 Plant Watts Bar Nuclea r Plant, P.0. Box 2000, Spring City, TN 37381 -2000 Unit No. 1 Commercial Service Date May 27, 1996 Refuelin g Outage No. U1Rl6 (if applicable)

Current In spection Interval 3rd (1 st , 2"', 3, 4th , other)

Current In spectio n Period 2nd (1 st , 2"', 3 )

I51/SPT - 2007 Edition , 2008 Addenda Edition and Addenda of Section XI applicable to the Inspection Plans IWE - 2013 Editio n ISi - March 30, 2020 / l -TRl 10.3, Revision 006 IWE - September 07, 2018 / O-Tl-100.012, Revision 000 Date/ Revision of In spection Plans SPT -Apri l 29, 2017 / O-Tl-100.009 Revision 002 Edition and Addenda of Section XI applicable to repair/rep lacement activities, if different t han the inspection plans 2007 Edition, 2008 Addenda Code Cases used: N-532-5, N-586-1, N-716-1, N-722-1, N-729-6, N-770-5 CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests, meet the Inspection Plan as re quired by the ASME Code,Section XI; and (c) the repair/rep lacement activities and eva lu ations supporting the completion of U1R16 conform to the requirements of Section XI (refueling outage numbe r)

Signed 9-e-.a / Jo-~r\ Nor-""'J"/ R.ep-,ir P,.,pt,,~... tlll- fro._,?,4' ..D:i:"_r_r-_ _<l'_/_~_6'_/_~_*_-z._o___

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the und ers igned, holding a va lid commiss ion issued by the National Board of Boiler and Pressure Vessel Inspectors The Hartford Steam Boiler Inspection and In surance and employed by Company of _H_a_rt_fo_r_d_,_c_o_n_ne_c_t_ic_u_t _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

have inspected the items described in this Owner's Activity Report, and stat e that, to the best of my knowledge and belief, the Owner has performed all activitie s represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/ replacement activities and evaluation described in th is report. Furthermore, neither the Inspector nor his employer sha ll be li able in any manner for any personal ag or a loss of any kind arising from or connected with this in spection Commissions I it7 Z~ ,,o, l J?..

Inspector's Signature (National ifoard i?u mber and Endors ement)

Date E-1 of 4

TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description None None None E-2 of 4

TABLE 2 Abstract of Repairs/replacement Activities Required for Continued Service Item Description Date Repair/Replacement Code Class Description of Work Completed Plan Number Replaced ERCW flex 3 ERCW Flex Hose 2/26/2020 121008113 hose due to damage.

Containment Lower Replaced lea king coil 3 5/28/2020 119905584 Compartment Cooler with new coil.

Containment Lower Replaced leaking co il 3 5/28/2020 119955793 Compa rtment Cooler with new coi l.

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REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)

ASME Section XI, Subsection IWE Steel Containment Vessel Inspection Program 10 CFR 50.55a(b)(2)(ix) requires the reporting of inaccessible areas and additional examinations identified during the performance of ASME Section XI , Subsection IWE Steel Containment Vessel Inspection Program when conditions exist in accessible areas that could indicate the presence of or result in degradation to such inaccessible areas.

(1) bolted connection that was disassembled, (18) Leak Chase Channel Boxes, and the Thermal flashing was inspected in accordance with IWE Containment Vessel Inspection Program during this cycle .

The thermal flashing on the outer wall of the raceway on elevation 702 is inspected as a moisture barrier(E-A, El.30). Multiple areas of the flashing were observed to be damaged at the seams. In all occurrences the damage was indicative of damage related to outage activities within the raceway. The damage was not indicative of service induced flaws nor was there indication of moisture intrusion that would result in damage to the inaccessible area behind the thermal flashing.

Du ring performance of the visual examination of the primary moisture barrier for the Leak Chase Channel(LCC) system water was discovered inside some of the boxes above the LCC. The primary moisture barrier is described as the gasket material and sealant that is intended to prevent moisture intrusion into inaccessible areas of the containment liner. If water is discovered inside of the box during performance of this examination it is considered a flaw or degradation of the prima ry moisture barrier. The water intrusion into the LCC box is considered a condition in an accessible area that could indicate the presence of, or result in, degradation in an in -accessible area, therefore an engineering evaluation of the in-accessible area has been performed in accordance with IWE-2500(d) . The engineering evaluation concluded these areas are not likely to experience accelerated degradation or aging. There are no corrective actions required for the inaccessible areas .

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