ML19190A072

American Society of Mechanical Engineers, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner'S Activity Report for Browns Ferry Nucle

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

Tennessee Valley Authority, Post Offi ce Box 2000, Decatur, Alabama 35609-2000 July 9, 2019 10 CFR 50.55a ATTN : Document Control Desk U.S. Nuclear Regulatory Commission Washington , D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260

Subject:

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 , Division 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 of the completion of each refueling outage. The BFN , Unit 2, Cycle 20 refueling outage ended on April 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 ..,,B'-'-F_,_N,..,U"-'2"--'-R,,2°"0'----------------------------------------

Plant Browns Ferry Nuclear Plant P 0 . Box 2000 Decatur AL 35609 Unit No. - - ~ 2 ~ - - Commercial service date March 1 1975 Refueling Outage no. --~R=e=fu=e=li=n~g~O=u=t=ag~e~2=0_ __

(it applicable)

Current Inspection Interval Fifth Ten Year Inspection Interval (1st, 2nd , 3rd, other)

Current Inspection Period .,,S"'e"'c"-on'""d,,__,__P_,,e.,_,ri"-od,,__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

(1st , 2nd , 3ro) 2007 Edition , 2008 Addenda (ISi)

Edition and Addenda of Section XI applicable to the inspection plans =20~1~3~E=d= iti=o~n~(C=IS=I~}_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

0-TPP-ENG-376 , Revision 0000 , 09/06/2018 0-Tl-364 , Revision 0022 , 09/ 19/2018 Date and Revision of inspection plan 0-Sl-4 .6.G Revision 0003 09/14/2018 Ed ition and Addenda of Section XI applicable to repairs and replacements , 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 (if applicable , including cases modified by Case N-532 and later revisions)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in th is report are correct; (b) the examinations and tests meet the Inspection Plan as requ ired by the ASME Code , Section XI ; and (c) the repair/replacement activities and evaluations supporting the completion of U2R20 (refue ling outage numbe r)

D~-2~ bl~'1-CERTIFICATE OF INSERVICE INSPECTION I, the undersigned , holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford Connecticut have inspected the items described in th is Owner's Activity Report and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by th is 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 , concern ing the repair/replacement activities and evaluation described in this report. Furthermore , neither the Inspector nor his employer shall be liable 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 _ -~ 1 /~

7 / __,_ /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 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description CR 1496212, NOi U2R20-002 A constant force support was observed to be outside of the cold range setting. Civil Main Steam System constant force F-A/ F1 .10C Engineering evaluated the conditions identified support, 2-4 7B400S0021 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. - -

Current inspection interval 5th Current inspection period 2nd TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Date Repair/Replacement Item Description Description of Work Class Completed Plan Number Replace 4" piping/fittings immediately downstream of the 0-SHV-067-0675 valve Through wall leak was 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 elbows between valve BFN-Through wall leak was 3 2-SHV-023-0532 and the 6/23/2018 119667790 identified .

RHRSW header 16"X 1-1/2" weld-o-let.

Rep lace 1-1 /2" piping and elbows between valve BFN-Through wall leak was 3 2-DRV-023-0511 and the 6/23/2018 119667746 identified .

RHRSW header 16"X 1-1/2" weld-o-let.

Replace 4" piping between Through wall leak was 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 ing outage no. - -

Current inspection interval 5th

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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 inaccessible 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 inaccessible areas .

During BFN U2R20, the moisture seal barrier (MSB) of the SCV was identified to have conditions requiring examination of inaccessible areas beneath the barrier. The inaccessible 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 .