ML16176A284

American Society of Mechanical EngineersSection XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owners Activity Report for Cycle 17 Operation

ML16176A284
Person / Time
Site:	Browns Ferry
Issue date:	06/24/2016
From:	Bono S Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML16176A284 (7)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 June 24, 2016 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Renewed Facility Operating License No. DPR-68 NRC Docket No. 50-296

Subject:

American Society of Mechanical EngineersSection XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owners Activity Report for Browns Ferry Nuclear Plant, Unit 3, Cycle 17 Operation The Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant (BFN), American Society of Mechanical Engineers (ASME),Section XI, Owners Activity Report for BFN, Unit 3, Cycle 17 Operation. 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 Documentation Requirements and Inservice 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 3, Cycle 17 refueling outage, during the first inspection period of the Fourth 10 Year Inspection Interval. The applicable provisions of the ASME Code Case N-532-4 require that this report be submitted within 90 calendar days of the completion of each refueling outage. The BFN, Unit 3, Cycle 17 refueling outage ended on March 27, 2016. Accordingly, this submittal is due by June 27, 2016.

U.S. Nuclear Regulatory Commission Page 2 June 27, 2016 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.

Enclosure:

American Society of Mechanical Engineers,Section XI, Fourth 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 3, Cycle 17 Operation cc (Enclosure):

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

Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 3 American Society of Mechanical Engineers,Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 3, Cycle 17 Operation See Enclosed

FORM OAR-1 OWNER'S ACTIVITY REPORT Plant Browns Ferry Nuclear Plant P 0. Box 2000 Decatur AL 35609 Unit No. ___ 3~--

Commercial service date March 1 1977 Refueling Outage no. ______

1'-'7 _ ___ _

(it applicable)

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

Current Inspection Period

~F~ir~st~P~e~r~io~d~-------------~~-~------------------

(1 st, 2nd. 3rd)

Edition and Addenda of Section XI applicable to the inspection plans 2007 Edition 2008 Addenda Date and Revision of inspection plan 3-Sl-4.6.G Revision 0049 02/16/2016 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan _,_N"'/A,_,_ __

Code Cases used: N-508-4 N-513-3 N-526 N-532-5 N-586-1 N-600 N-613-1 N-648-1 N-661 -2 N-735 N-747 and N-751 (if applicable)

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 U3R17 conform to the requirements of Section XI.

(refueling outage number)

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 Connecticut of Connecticut have inspected the items described in this Owner's 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 XI.

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 injury or property damage or a loss of any kind arising from or connected with this Inspection.

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FORM OAR-1 OWNERS ACTIVITY REPORT TABLES Report Number BFNU3R17 Plant Browns Ferry Unit No.

3 Commercial service date 03/01/1977 Refueling outage no. 17 Current inspection interval 4th Current inspection period 1st Table 1 Items with Flaws or Relevant Conditions That Require Evaluations For Continued Service Examination Category and Item Number Item Description Evaluation Description F-A, Item F1.20C Variable Spring setting out of range.

Range 373 to 389 lbs. As-Found 360 lbs.

(3HPAS-3-H-03) [NOI U3R17-001]

EVALUATED ACCEPTABLE (No Corrective Measures Required.)

The spring support was determined to be able to perform its intended design function and there is no adverse effect on the pipe support components or the associated piping with the out of range spring load setting (13 pounds). The spring setting was restored to the design range of 373 to 389 lbs. under Work Order 117632998 and re-examined.

F-A, Item F1.20C Variable Spring setting out of range.

Range 5300 to 5584 lbs. As-Found 5938 lbs.

(MS-3-H-13) [NOI U3R17-003]

EVALUATED ACCEPTABLE (No Corrective Measures Required.)

The dual spring support was determined to be able to perform its intended design function and there was no adverse effect on the pipe support components or the associated piping with the spring load setting 354 pounds out of range on both springs.

The spring settings were restored to the design range of 5300 to 5584 lbs.

under Work Order 117632997 and re examined.

F-A, Item F1.20C Variable Spring setting out of range.

Range 14,123 to 14,789 lbs. As Found 16,121 lbs.

(MS-3-H-17) [NOI U3R17-005]

EVALUATED ACCEPTABLE (No Corrective Measures Required.)

The spring support was determined to be able to perform its intended design function and there was no adverse effect on the pipe support components or the associated piping with the out of range spring load setting (1332 pounds). The spring setting was restored to the design range of 14,123 to 14,789 lbs. under Work Order 117642861 and re-examined.

FORM OAR-1 OWNERS ACTIVITY REPORT TABLES Report Number BFNU3R17 Plant Browns Ferry Unit No.

3 Commercial service date 03/01/1977 Refueling outage no. 17 Current inspection interval 4th 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 1

BFN-3-RPV-068-1000 REACTOR VESSEL Repair indication found on U3 Vessel Flange @ Stud 40 during inspection.

3/31/2016 117609591 3

BFN-3-SHV-067-0804 SD BD RM CHILLER 3A-2 INLET SOV Replace valve BFN-3-SHV-067-0804.

2/16/2016 114167613 3

BFN-3-HEX-082-000B1 DG-3B COOLING WTR HEAT EXCHANGER 3B1 DG 3B indication of undercut in weld on 3B1 heat exchanger.

7/13/2014 115951030 3

BFN-3-HEX-082-000A1 DG-3A COOLING WTR HEAT EXCHANGER 3A1 Replace 3A DG heat exchangers BFN-3-HEX-082-000A1 and BFN-3-HEX-082-000A2.

8/5/2015 116566153 3

BFN-3-CHR-031-1951 WATER CHILLER 3B Repair EECW leak at solder joint, 3B CB Chiller piping to 3-TCV-67-518.

7/13/2015 116901846 3

BFN-3-SHV-067-0557, SOUTH HDR SPLY VLV TO SW RHR RM Replace valve due to corrosion.

7/17/2015 116930078

FORM OAR-1 OWNERS ACTIVITY REPORT TABLES Report Number BFNU3R17 Plant Browns Ferry Unit No.

3 Commercial service date 03/01/1977 Refueling outage no. 17 Current inspection interval 4th Current inspection period 1st Summary of IWE Indications for U3R17 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 E1.11 PSC EXT 3-B-1 Gouge

[NOI U3R17-002]

EVALUATED ACCEPTABLE (No Corrective Measures Required.)

The indication consisted of a dime size 3/32 deep surface condition on the exterior of the Suppression Chamber produced by mechanical means during or after assembly and not an extended under thickness.

The indication was evaluated and determined to be acceptable and documented in calculation CDQ0999970114.

None None E-A, Item E1.30 MSB-3-1 Moisture Seal Barrier Areas of Separation.

[NOI U3R17-007]

EVALUATED ACCEPTABLE None of the areas penetrated the full depth of the seal, and seal adhesion was good in all locations, there was no seal failure. Portions of the seal identified for repair were excavated and the exposed liner beneath the seal VT-1 examined. This examination revealed no reportable conditions and confirmed the seal membrane was not breached and seal failure did not occur. The exposed liner was cleaned and prepared, and the MSB was then re-poured in these areas and re-examined under Work Order 115811154.

None None