Upload
others
View
2
Download
0
Embed Size (px)
Citation preview
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000
January 21, 201610CFR 50.55a
U.S. Nuclear Regulatory CommissionATTN; Document Control Desk
Washington, D.C. 20555-0001
Watts Bar Nuclear Plant, Unit 1Facility Operating License No. NFP-90NRC Docket No. 50-390
Subject: AMERICAN SOCIETY OF MECHANICAL ENGINEERS, SECTION XI,SECOND 10-YEAR INSPECTION INTERVAL, INSERVICE INSPECTIONOWNER'S ACTIVITY REPORT FOR CYCLE 13 OPERATION
The Tennessee Valley Authority is submitting the Watts Bar Nuclear Plant, Unit 1, AmericanSociety of Mechanical Engineers (ASME), Section XI, Owner's Activity Report for Unit 1Cycle 13 operation as required by Article IWA-6000, Section XI, Division 1. The report iscontained in the enclosure to this letter and is in accordance with the requirements of ASMECode Cases N-532-4 and N-532-5, "Repair/Replacement Activity DocumentationRequirements and Inservice Inspection Summary Report Preparation and Submission."
The report is an overview of the results from inservice examinations that were performed oncomponents within the ASME Section XI boundary, up to and including the Unit 1 Cycle 13refueling outage, during the third inspection period of the second 10-year inspection interval.The applicable provisions of the ASME Code require that this report be submitted 90 daysfrom the end of the applicable outage, i.e., by January 22, 2016.
U.S. Nuclear Regulatory CommissionPage 2January 21, 2016
There are no new regulatory commitments in this letter. Ifyou have questions regarding thisletter, please call Gordon Arent, Director of Watts Bar Site Licensing, at (423) 365-2004.
Respectfully,
Kevin T. Walsh
Site Vice President
Watts Bar Nuclear Plant
Enclosure: American Society of Mechanical Engineers, Section XI, Second 10-Yearinservice Inspection Interval, Inservice Inspection Owner's Activity Report forCycle 13 Operation
cc (Enclosure):
NRC Regional Administrator - Region IINRC Senior Resident Inspector - Watts Bar Nuclear Plant, Unit 1NRR Project Manager - Watts Bar Nuclear Plant
ENCLOSURE
TENNESSEE VALLEY AUTHORITY
WATTS BAR NUCLEAR PLANT, UNIT 1
AMERICAN SOCIETY OF MECHANICAL ENGINEERS, SECTION XI,SECOND 10-YEAR INSPECTION INTERVAL,
INSERVICE INSPECTION OWNER'S ACTIVITY REPORT
FOR CYCLE 13 OPERATION
FORM OAR-1 OWNER'S ACTIVITY REPORT
Report Number U1C13
Plant WATTS BAR NUCLEAR PLANT, P.O. Box2000, Spring City. TN 37381-2000
Unit No. 1 Commercial servicedate May 27.1996 Refueling outage no. U1C13(Ifapplicable)
Current inspection interval 2nd(r, 2"". 3™. 4", other)
Current inspection period 3rd(1« 2™ 3")
Edition and Addenda ofSection XI applicable totheinspection plans 2001 Edition. 2003 Addenda
Date and revision of inspectionplans October 23. 2015 / 1-TRI-0-10.2. Revision 14
Edition and Addenda ofSection XI applicableto repair/replacement activities, ifdifferent than the inspection plans same
Code Cases used: N-460, N-526, N-532-4, N-532-5, N-566-2, N-586-1, N-578-1, N-624, N-685. N-686-1, N-700, N-706-1,N-722-1. N-729-1. N-731. N-753. and N-770-1
CERTIFICATE OF CONFORMANCE
Icertify that (a)the statements made In this report are connect; (b)the examinations and tests meet the Inspection Plan required by
the ASME CodeXI and (c)the repair/replacement activities and evaluations supporting the completion of U1C13
conform to the requirements ofSection XI. , i ^ ; (refueling outage number)
4^ 7//V//4 owns;-. Design., /AhUcC 'J " 'O
CERTIFICATE OF INSERVICE INSPECTION
I.the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectorsand employed by The Hartford Steam Boiler Inspection and Insurance Company of Connecticut of Hartford. Connecticut
have Inspectedthe itemsdescribed inthis Owner's Activity Report,and state that, to the best of myknowledge and belief, theOwner has performedallactivities represented by this report in accordance with the requirements ofSection XI.
Bysigningthiscertificate neither the Inspector nor hisemployermake any warranty, expressed or implied, concerningtherepair/replacement activities and evaluationdescribed inthis report. Furthennore, neitherthe Inspectornor his employershall beliable in manner for personal Injury or property damage or a loss of any kind arising from or connected with this inspection.
Commissions Hxl-z,National Board and Endorsements
Date VWA'o
ASME Code Section XI Exception - Reference TVA Condition Report 1124988, Subject: ASME Category B-G-1 (RPVstuds and RCP hydrastuds). Description: Using EPRI guidance, tlie performance demonstration completed for theseexams was not perfbnned as a "blindtesf as required by ASMESection XI, Appendix VIM, Supplement 8, paragraph2.0. This CR documents the issue and references the NRC-issued EGM-14-003 as sufficient technical basis foraccepting the examinations.
Page E-1 of 3
TABLE 1
ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT
REQUIRED EVALUATION FOR CONTINUED SERVICE
Examination
Category andItem Number
Item Description Evaluation Description
None None None
TAEiLE 2
ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES
REQUIRED FOR CONTINUED SERVICE
Code
Class
Item
DescriptionDescription
of Work
Date
CompletedRepair/Replacement
Plan Number
E-A
E1.30
Thermoshield,functioning as a
Containment
Moisture Barrier
Repaired gouges and other minorphysical damage incurred during
outage work in Containment
10/16/15 Work Order (WO)116640689
Page E-2 of 3
REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A)ASME Section XI, Subsection IWE
Steel Containment Vessel Inspection Program
10 CFR 50.55a(b)(2)(ix)(A) requires reporting of the degradation assessment forinaccessible areas when conditions are identified in accessible areas during theperformance of the ASME Section XI, Subsection IWE Steel Containment Vessel (SCV)Inspection Program that could indicate the presence of, or result in, degradation to suchinaccessible areas.
The condition identified during the Unit 1 Cycle 13 refueling outage on the SCVThermoshield in an accessible area was repaired by Work Order 116640689, "Repair ofsheetmetal flashing in Reactor Building", and does not affect the degradation assessmentfor inaccessible areas. The conditions were documented in Notification of Indication
N0I-U1R13-001, and are reported in Table 2 above.
Page E-3 of 3