L-19-008, American Society of Mechanical Engineers, Section Xl, Third 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 15 Operation

American Society of Mechanical Engineers, Section Xl, Third 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 15 Operation

ML19024A383
Person / Time
Site:	Watts Bar
Issue date:	01/24/2019
From:	Simmons P Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
WBL-19-008
Download: ML19024A383 (7)

Text

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 wBL-19-008 January 24,2019 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 Xl, Third 10-Year lnspection lnterual, lnservice lnspection Owner's Activity Report For Cycle 15 Operation The Tennessee Valley Authority is submitting the Watts Bar Nuclear Plant, Unit 1, American Society of Mechanical Engineers (ASME), Section Xl, Owner's Activity Report for Unit 1 Cycle 15 operation as required by Article IWA-6000, Section Xl, 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 lnspection Summary Report Preparation and Submission."

The report is an overview of the results from inservice examinations that were performed on components within the ASME Section Xl boundary, up to and including the Unit 1 Cycle 15 refueling outage, during the first 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 January 25,2019.

There are no new regulatory commitments associated with this submittal. lf you have questions regarding this letter, please contact Kim Hulvey at @23) 365-7720.

Respectfully, n

Paul Simmons Site Vice President Watts Bar Nuclear Plant

U. S. Nuclear Regulatory Commission Page 2 January 24,2019

Enclosure:

American Society of Mechanical Engineers, Section Xl, Third 1O-Year lnservice lnspection lnterval, lnservice lnspection Owner's Activity Report for Cycle 15 Operation (Form OAR-1) cc (Enclosure):

NRC RegionalAdministrator - Region ll NRC Senior Resident lnspector NRR Project Manager

ENCLOSURE TEN NESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT {

AMERICAN SOCIETY OF II'IECHANICAL ENGINEERS, SECTION XI, THIRD 1 O.YEAR INSPECTION INTERVAL, INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR CYCLE 15 OPERATION

FORM OAR-I OWNER,S ACTIVIW REPORT Report Number U1R15 Plant Watts Bar Nuclear Plant, P.O. Box 2000, Spring City, TN 37381-2000 Unit No. Commercial Service Date May 27, 1996 Refueling Outage No. U1R15 (if applicable)

Current lnspection lnterval

'r4 Current lnspection Period L st (l*,2no, 3t )

lSl/SPT - 2007 Edition, 2008 Addenda Edition and Addenda of Section Xl applicable to the lnspection Plans IWE - 2013 Edition lSl - January L7,20L9 / 1-TRl-0-10.3, Revision 003 lWE - September 07,2018 I O-tl-t00.012, Revision 000 Date / Revision of lnspection Plans SPT - April 29,20t7 I 0lt-t00.009 R002 Edition and Addenda of Section xl applicable to repair/replacement activities, lf different than the lnspection plans 2OO7 Edition 2008 Addenda Code Cases used: N-513-3, N-532-5, N-586-1, N-716-1, N-722-L, N-729-4, N-770-2 CERTIFrcATE OF COI{FORMAilCE I certify that (a) the statements made in this report are correcg (b) the examinations and tests, meet the lnspection Plan as required by the ASME Code, Section Xl; and (c) the repair/replacement activities and el,aluations supporting the completion of U1R15 (refueling outagc nurn ber) confurm to the requirements of Sectlon Xl Signed Shane Norton, Rep6ir Replacement and lnservice lnspection Program Owner

,/rt/,. _

CERNFrcAIE OF II{SERVICE INSPECTION l, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel lnspectors and the State or The Hartford Stam Boiler of lnspection and lnsurance Province of Tennessee and employed by Company Hartford, Connecticut have inspected the ftems described in this Owner's Actlvlty Report, and state that to the best of my knowledge and belief, the Owner has performed all actMtles represented by this report in accordance with the requirements of Section Xl By s'rgning this certificate nelther the lnspector nor hls employer makes any warranty expressed or implied concerning the repair/ replacement activities and evaluation descrlbed in this report. Furthermore, neither the lnspector nor his employer shall be liable ln any manner for any personal Commissions NB 14057tNR, TN 4132 Signature National Board, State, Province, and Endorsements

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TABLE 1 ITEMS W]TH FI.AWS OR RETEVANT COI{DITIOT{STHAT REQUIRED EVATUATION FOR CONNilUED SERVICE Examination Category and Item Number ltem Description Eval uation Description cR 1437950 A through wall leak in a 10" diameter Class 3 pipe was evaluated in accordance with ASME Code Case N-513-3. The leak rate was minimal and would have no effect on the D-B lD2.L0 10" High Pressure Fire Protection Piping safety function of the system. This condition is within the bounding condition for a flooding impact. therefore flooding is not a concern. Civil Analysis showed that structural integrity was maintained and there was no concern for a line break at the leak location.

cR 1333681 A through wall leak in a 10" diameter Class 3 pipe was evaluated in accordance with ASME Code Case N-513-3. The leak rate was minimal and would have no effect on the D-B / D2.L0 10" High Pressure Fire Protection Piping safety function of the system. This condition is within the bounding condition for a flooding impact. therefore flooding is not a concern. Civi! Analysis showed that structural integrity was maintained and there was no concern for a line break at the leak location.

cR 14s387r A rigid support was observed to be loose in the field. Civil Engineering evaluated the support drawings and concluded the support was not designed to provide support in the direction that it moved. Due to the flat base F-A I Fl.100 Safety lnjection System Rigid Hanger plate of the support being attached to a curved surface, there exists a small gap between the base plate and the wall on both sides. This small gap allows the support to move in the axial direction. Per design output, this support is not designed to resist movement in the axial direction.

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TABLE 2 ABSTRACT OF REPAIRS, REPIACEMENNi, OR CORRECTIVE MEAISURES REqUIRED FOR CONTITIUED SERVICE Item Description Date Repair/Replacement Code Class Description of Work Completed Plan Number containment Lower Replaced leaking coil with 3 L0/2212018 1186467L4 Compartment Cooler new coil.

10" High Pressure Fire Repaired through wall 3 0210s/2018 119003 4s7 Protection Piping leak.

Containment Lower lnstalled blank off plates 3 LLl06/2018 119954518 Compartment Cooler on (3) coils to stop leaks.

10" High Pressure Fire Repaired through wall 3 ru28/2018 119798618 Protection Piping leak.

MC Equipment Hatch Bolting Replaced rnissing washer. r0los/2018 119049319 Loop 2 Steam Generator 2 Upper Lateral Support Tightened Loose Bolting. LOlL2l2018 Lr992L087 Splice Plate Containment Lower lnstalled blank off plates 3 Ll08l201e Lr9877091 Compartment Cooler on (1) coils to stop leaks.

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REPORTING REQUIRED BY 10 cFR 50.ssa(bX2Xix)

ASME Section Xl, Subsectlon IWE Steel Contalnment Vesse! lnspection Program 10 CFR 50.55a(bX2Xix) requlres the reporting of inaccessible areas and additional examinations identified during the performance of ASME Section Xl, Subsection IWE Steel Containment Vessel lnspection Program when conditions exist in accessible areas that could indicate the presence of or result in degradation to such inaccessible areas.

The accessible portion of the interior and exterior surface of the containment vessel, including (7) bolted connections that were disassembled, were inspected in accordance with IWE Containment Vessel lnspection Program during this cycle. There were no conditions observed that would lndicate the presence of or result in degradation to inaccessible areas of the containment vessel during performance of those examinations.

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