ML17180A386

American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owners Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 19

ML17180A386
Person / Time
Site:	Browns Ferry
Issue date:	06/29/2017
From:	Bono S Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML17180A386 (7)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 June 29, 2017 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 Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs

- Owner's Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 19 Operation The Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant (BFN), American Society of Mechanical Engineers (ASME), Section Xl, Owner's Activity Report for BFN, Unit 2, Cycle 19 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 Inservice Summary Report Preparation and Submission, Section Xl, Division 1.

The report is an overview of the inservice examination results that were performed on components within the ASME Section Xl boundary, up to and including the BFN, Unit 2, Cycle 19 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 19 refueling outage ended on March 31, 2017. Accordingly, this submittal is due by June 29, 2017.

U.S. Nuclear Regulatory Commission Page 2 June 29, 2017 There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact J. L. Paul, Nuclear Site Licensing Manager, at (256) 729-2636.

Respe

Ily, S. M. Bono Vice President

Enclosure:

American Society of Mechanical Engineers, Section Xl, 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 19 Operation cc (Enclosure):

NRC Regional Administrator-Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant

Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 2 American Society of Mechanical Engineers, Section Xl, Fifth 10 Year Inspection Interval, lnservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs, Owner's Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 19 Operation See Enclosed

FORM OAR-I OWNER'S ACTIVITY REPORT Report Number BFNU2R19 Plant Browns Ferry Nuclear Plant, P.0. Box 2000. Decatur, AL 35609 Unit No.

2 Commercial service date March 1. 1975 Refueling Outage no.

Refueling Outage 19 (if applicable)

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

Current Inspection Period First Period (1st, 2nd, 3rd)

Edition and Addenda of Section Xl applicable to the inspection plans 2007 Edition.

2008 Addenda Date and Revision of inspection plan 2-Sl-4.6.G. Revision 0055, 03/0412017 Edition and Addenda of Section Xl applicable to repairs and replacements, if different than the inspection plan N/A Code Cases used for inspection and evaluation: N508-4. N-513-3, N-526, N-532-5, N-586-1. N-613-1, N-648-1, N-716-1. N-735. N-747. and N-751 (if applicable, including cases modeled by case N-532 end later revrslnns)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of U2R19 conform to the requirements of Section Xl.

(refueling outage number)

Signed 5y5cEt M Date_____________

/I Ownerer Owner's Designee, (tIle 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 this Owners Activity Report and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning 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 in'ury or pr arty damage or a loss of any kind arising from or connected with this Inspection.

(4?' 2 Commissions t ii ti Inspector's SIgnature Nallenel enard Number and Endorsement Date_______________

FORM OAR-I OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2RI9 Plant Browns Ferry Unit No.

2 Commercial service date 03/01/1975 Refueling outage no.

19 Current inspection interval 5th Current inspection period 1st TABLE I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description NONE NONE NONE

FORM OAR-I OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2RI9 Plant Browns Ferry Unit No.

2 Commercial service date 03/01/1975 Refueling outage no.

19 Current inspection interval 5th Current inspection period 1St TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Class Item Description Description of Work Date Completed Repair/Replacement Plan Number 2

Through wall leak in piping section Replace piping section between FCV-O1-0058 and FCV-001-0059 3/31/2017 118614658 I

BFN-2-SNUB-001-5064, damaged extension, not service induced.

Replace extension piece (strut) 3/13/2017 117032111

FORM OAR-I OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2RI9 Plant Browns Ferry Unit No.

2 Commercial service date 03/01/1975 Refueling outage no.

19 Current inspection interval 5th Current inspection period 1st Summary of IWE Indications for U2R19 The summary table below is provided in accordance with the requirements of 10 CFR 50.55a(b)(2)(ix)(A) and 10 CFR 50.55a(b)(2)(ix)(D).

Examination Category and Item Number Component Identifier Indication Description Acceptability/Corrective Action Inaccessible Area (Location and Evaluation)

Additional Samples E-A, Item El.i I PSC EXT 2-B-2 Peeling of EVALUATED ACCEPTABLE None None PSC EXT 2-B-3 protective coatings, (No Corrective Measures Required.)

PSC EXT 2-8-8 pitting, gouges, arc Peeling of protective coatings due to PSC EXT 2-8-9 strikes, and dents, leakage was addressed by

[NOt U2Ri9-001]

reapplication of protective coatings.

Pitting, gouges, arc strikes, and dents with insignificant wall loss were identified. One indication on the ECCS Ring Header, consisting of various arc strikes with the deepest measuring 0.125 inches, required engineering evaluation. This location was determined to be acceptable based on the small area affected; the 0.0025 inch difference between the localized minimum measurement and the manufacturer tolerance; and that the surface depression will have negligible effect on the pipe stiffness and the piping stresses documented in the existing pipe analysis calculation. This location has been identified for successive examination in accordance with IWE-2420(b) and (c).

E-A, Item El.30 MSB-2-l Areas of EVALUATED ACCEPTABLE None None Moisture Seal Separation.

None of the areas penetrated the full Barrier

[NOl U2R19-002]

depth of the seat. Seal adhesion was good and there was no seal failure.

Portions of the seal identified for repair were excavated and the exposed liner beneath the seal VT-i examined. This examination revealed no reportable conditions and confirmed the seal membrane was not breached and that seal failure did not occur. All indications are the result of mechanical damage from previous outage activities or separations at the seal surface previously identified, but within 0-Tl-41 7 acceptance criteria. The exposed liner was cleaned and prepared, and the MSB was then re-poured in these areas and re-examined.

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