ML13025A234
| ML13025A234 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 01/25/2013 |
| From: | Cleary T Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| Download: ML13025A234 (7) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 January 25, 2013 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 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, Inservice Inspection, System Pressure Test, Containment Inservice lnspection, and Repair and Replacement Programs - Owner's Activity Report for Gycle 11 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 11 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-532-4, "Repair/Replacement Activity Documentation Requirements and Inservice 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 1 1 refueling outage, during the second inspection period of the second 1O-year 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 27,2013.
U.S. Nuclear Regulatory Commission Page 2 January 25, 2013 There are no new regulatory commitments in this letter. lf you have questions regarding this letter, please call Rusty Stroud, Program Manager at (423) 365-1435.
Respectfully, 4P\\
Timothy P. Cleary Site Vice President Watts Bar Nuclear Plant
Enclosures:
American Society of Mechanical Engineers, Section Xl, Second 10-Year Inspection Interval, Inservice Inspection Owner's Activity Report for Cycle 11 Operation cc (Enclosures):
NRC Regional Administrator - Region l1 NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRR Project Manager - Watts Bar Nuclear Plant
Enclosure Tennessee Valley Authority Watts Bar Nuclear Plant, Unit I American Society of Mechanical Engineers, Section Xl, Second 1O-Year Inspection Interual, Inseryice Inspection Orner's Activity Report for Gycle 11 Operation
Form OAR-I Owners Activity Report E-1 of 4
FORM OAR.1 OWNER'S ACTIVIfi REPORT Report Number Plant Unit No.
u1c1l RFO CommercialSerulce Date May 27,1996 Refueling Outage No.
(if appliczble)
Current Inspection lnterval 2nd Current Inspection Period (1*,2*,3',41 otherl 2nd 1t",2*,3t 1 Edition and Addenda of Section Xlapplicable to the Inspection Plans 2001 Edition with 2003 Addenda Dete / Revlsion of fnspectlon Plans Septembef 18, 20LZ I L:IRI{,-IO.2, Revlsion 7 Edition and Addenda of Sectbn Xl applkable to repair/Ephcement actlvltles, lf dlfferent than the Inspectlon plans same RFO11 Watts Bar Nuclear Plant, P.O. Box 2000 ring City, TN 37381-2000 crde cases used:
N460, N-5193, il-525, r$532-4, N-5662, r$586-L N-624, tS695, t{-6E61, it-7oGt" it-722-1+tt72yl CERTIFICATE OF COI{FORMAT{CE I certify that (a) tha statements made ln thts repon are corrcq (bl the examlnatlons and tests, met the Inspectlon Plan as requtred by the ASME Code, Section Xl; and (c) the repalrlreplacement activi6es and evaluations supporting the completion of RFOl1 conform to the requlrements of Section (refuellng outage nurnberl Signed
,.," - t[l.{/rol:
s designee, Title CERNFICATE OF ]NSERVICE INSPECNON l, the undersiSned, holdlng a vtlld commlsslon lssued bythe Natlonal Board of Boller and Pressur Vessel lnspectors and the State or Province of Tennessee and employed by HSB CT of Hartford, C,onnecticut have Inspected the ltem5 descrlbed In thls owner'r Activlty Report, and state that to the best of nry knowledte and bellef, the Owner has performed all activlties represented by this report in accordance with the requirements of Section Xl 8y slSnlng this certificate nEitherthe Inspestor nor his employer makes any warranty e,pressed or implled concemlrythe rcpair/ replacement attlvides and evaluation desribed ir this report. Furthermore, neither the Inspector nor his employer shrll be liabb In any mannerfot any prsonel injury or property damage or a loss of any kind arising from or connected with this inspection
/
commisstons 74/ JSJ Y rN2s34 National Board, State, Provlnce, and Endorsements
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E-2 of 4
Examination Category and ltem Number Item Description Evaluation Description None Table {
Items with flaws or relevant conditions that required evaluation for continued service Table 2 Abstract of Repair/Replacement Activities required for continued seruice Code Class Item Description Description of Work Date Completed Repair/Replacement Plan Number Class 3 Pinhole leak in reducer on the Unit 1 side of U 1lU2 ERCW interface valve 2-lSV-67-6038.
ERCW System Replaced Reducer 11120t2011 wo 112535592 Class 3 Pinhole leak in elbow downstream of valve 1-FCV-67-146.
ERCW System Replaced Elbow 10t15t2012 wo 112833358 Class 3 Pinhole leak in reducer on the Unit 1 side of U 1lU2 ERCW interface valve 2-lSV-67-603A.
ERCW System Replaced Reducer 07 t13t2012 wo 112925948 Class 3 Pinhole leak in piping located I inches from valve 0-lSV-26-648 on the bottom of the pipe.
HPFP System Replaced Piping 10t17 t2012 wo 113723089 E-3 of 4
REPORTING REQUIRED BY 10 cFR 50.55a(b)(2)(ix)
ASME Section Xl, Subsection IWE Steel Gontainment Vessel lnspection Program 10 CFR 50.55a(b)(2)(ix) requires the reporting of inaccessible areas and additional examinations identified during the performance of American Society of Mechanical Engineers (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.
For the examinations performed during the Unit 1 Cycle 11 refueling outage, there were no degraded conditions identified in accessible portions of the SCV which would require additional examinations or evaluation of inaccessible areas.
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