ML19190A072
| ML19190A072 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/09/2019 |
| From: | Hughes D Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19190A072 (7) | |
Text
Tennesse e Valle y Authority , Pos t O ffi ce B ox 2000 , D ec atur , A l a bam a 356 0 9-200 0 July 9 , 2019 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington , D.C. 20555-0001
Subject:
Browns Ferry Nuclear Plant , Unit 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260 American Society of Mechanical Engineers,Section XI, Fifth 10 Year Inspection Interval, lnservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner's Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 20 Operation The Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant (BFN), American Society of Mechanical Engineers (ASME),Section XI , Owner's Activity Report for BFN , Unit 2 , Cycle 20 Operation. 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 Documentation Requirements and lnservice Summary Report Preparation and Submission ,Section XI , Divis i on 1. The report is an overview of the inservice examination results that were performed on components within the ASME Section XI boundary , up to and including the BFN , Unit 2 , Cycle 20 refueling outage , during the first inspection period of the Fifth 10 Year Inspection Interval.
The applicable provisions of the ASME Code Case N-532-5 require that this report be submitted within 90 calendar days o f the completion of each refueling outage. The BFN , Unit 2 , Cycle 20 refueling outage ended on Apr i l 10 , 2019. Accordingly , this submittal is due by July 9 , 2019.
U.S. Nuclear Regulatory Commission Page 2 July 9 , 2019 There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact J. L. Paul , Site Licensing Manager , at (256) 729-7874. D. L. Hughes Site Vice President
Enclosure:
American Society of Mechanical Engineers,Section XI , Fifth 10 Year Inspection Interval, lnservice Inspection , System Pressure Test, Containment Inspection , and Repair and Replacement Programs , Owner's Activity Report for Browns Ferry Nuclear Plant , Unit 2 , Cycle 20 Operation cc (Enclosure):
NRC Regional Administrator-Region II NRC Senior Resident Inspector
-Browns Ferry Nuclear Plant NRC Project Manager -Browns Ferry Nuclear Plant Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 2 American Society of Mechanical Engineers,Section XI, Fifth 10 Year Inspection Interval, lnservice Inspection, System Pressure Test, Containment lnservice Inspection, and Repair and Replacement Programs, Owner's Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 20 Operation See Enclosed FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number Plan t Browns Ferry Nuclear Plant P 0. Box 2000 Decatur AL 35609 Unit No. (it appli c ab l e) Commercial service date March 1 1975 Refueling Outage no. --~R=e=fu=e=li=n~g~O=u=t=ag~e~2=0
__ _ Current Inspection Interval F i fth Ten Year Inspection Interval (1 s t , 2nd , 3r d , o t he r) Current Inspection Pe r iod .,,S"'e"'c"-on'""d,,__,__P_,,e.,_,ri"-od,,_
___________________________________
_ (1 st , 2 nd , 3ro) 2007 Edition , 2008 Addenda (ISi) Edition and Addenda of Section XI applicab l e to the inspection plans =20~1~3~E=d=
i ti=o~n~(C=IS=I~}
__________________
_ 0-TPP-ENG-376 , Rev i s i on 0000 , 09/06/2018 0-Tl-364 , Revision 0022 , 09/19/2018 Date and Revis i on of inspect i on plan 0-Sl-4.6.G Revision 0003 09/14/2018 Ed i tion and Addenda of Section XI applicable to repairs and rep l acements , if different than the inspection plan N/A Code Cases used for inspection and evaluation N-532-5 N-613-1 N-648-1 N-716-1 N-751 and N-795 (i f applic a ble , i n c lu d i ng cases m o d i fi e d by Case N-532 and l a t e r r ev i s i ons) CERTIFICATE OF CONFORMANCE I cert i fy that (a) the statements made in th i s report are correct; (b) the examinations and tests meet the Inspection Plan as requ i red b y the ASME Code , Sect i on XI; and (c) the repa i r/replacement act i vities and evaluations support i ng the completion of U 2 R20 (r efue l ing o u t age numbe r) D~-2~bl~'1-CERTIFICATE OF INSERVICE INSPECTION I , the undersigned , holding a valid commission i ssued by the National Board of Bo i ler and Pressure Vesse l Inspectors and employed b y The Hartford Steam Boiler Inspection and Insurance Company of Hartford Connecticut have inspected the i tems described in th i s Owne r's Activi t y Report and state that , to the best of my knowledge and belief , the Owner has performed all activities represented by th i s report i n accordance with the requirements of Section XI. By signing this certificate neither the Inspector nor his employe r makes any warranty, expressed or imp li ed , concern i ng the repair/replacement act i v i t i es and evaluation described in this report. Furthermore , neither the Inspector nor h i s emp l oye r sha ll be li ab l e in any manner for any personal inJury or property damage or a loss of any kind arising from or connected with this Inspection Comm,~,oo, .. ~!;,~2,,.,;!,:!:;: ,-Date _-~7 /__,_1 /~/7 __ _
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2R20 ------------------------------
PI ant Browns Ferry Unit No. 2 Commercial service date 03/01/1975 Refueling outage no. 20 ----Current inspection interval 5th -----Current inspection period _2_nd ____ _ TABLE 1 Examination Category and Item Number F-A/ F1.10C ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Item Description Evaluation Description CR 1496212, NOi U2R20-002 A constant force support was observed to be Main Steam System constant force outside of the cold range setting. Civil support, 2-4 7B400S0021 Engineering evaluated the conditions identified and concluded that the spring support would still be able to perform its intended design function due to mechanical tolerances in the support. The constant spring cold setting was reset to be within the design range and reexamined.
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2R20 ------------------------------
PI ant Browns Ferry Unit No. 2 Commercial service date 03/01/1975 Refueling outage no. 20 ----Current inspection interval 5th -----Current inspection period 2nd -------TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Description of Work Date Repair/Replacement Class Completed Plan Number Replace 4" piping/fittings immediately downstream of Through wall leak was the 0-SHV-067-0675 valve 3 on the discharge side of the 4/30/2018 116489865 identified.
Unit 1/2 Emergency Condensing Unit to remove throuqh wall leak areas. Replace 1-1 /2" piping and Through wall leak was elbows between valve BFN-3 2-SHV-023-0532 and the 6/23/2018 119667790 i dentified. RHRSW header 16"X 1-1/2" weld-o-let.
Rep l ace 1-1 /2" piping and Through wall leak was elbows between valve BFN-3 2-DRV-023-0511 and the 6/23/2018 119667746 identified. RHRSW header 16" X 1-1/2" weld-o-let.
Through wall leak was Replace 4" piping between 3 elbows downstream of valve 8/21/2018 119798026 identified.
BFN-0-SHV-067-0643.
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2R20 ----------------------------
PI ant Browns Ferry Unit No. 2 Commercial service date 03/01/1975 Refuel i ng outage no. 20 ----Current i nspection interval 5th Current inspection period 2nd ----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 for i naccessible areas when conditions are identified in accessible areas during the performance of the ASME Section XI, Subsection IWE Steel Containment Vessel (SCV) Inspection Program that could indicate the presence of or result in degradation to such i naccessible areas. During BFN U2R20, the moisture seal barrier (MSB) of the SCV was identified to have condit i ons requiring examination of inaccessible areas beneath the barrier. The i naccessible areas of the SCV beneath the MSB were determined to be acceptable by visual examination and evaluation. These conditions were identified and resolved under NOi U2R20-003. No corrective actions are required.