ML14169A404

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 Plant, Unit 3, Cycle 16 Operati

ML14169A404
Person / Time
Site:	Browns Ferry
Issue date:	06/16/2014
From:	Polson K Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML14169A404 (8)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 June 16, 2014 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 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 3, Cycle 16 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 3, Cycle 16 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 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 3, Cycle 16 refueling outage, during the third inspection period of the third 10-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. The BFN, Unit 3, Cycle 16 refueling outage ended on March 18, 2014. Accordingly, this submittal is due by June 16, 2014.

U.S. Nuclear Regulatory Commission Page 2 June 16, 2014 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.

Respectfully, K. J. Poison Vice President

Enclosure:

American Society of Mechanical Engineers, Section Xl, Third 10-Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner's Activity Report for Browns Ferry Nuclear Plant, Unit 3, Cycle 16 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 3 American Society of Mechanical Engineers,Section XI, Third 10-Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs, Owner's Activity Report for Browns Ferry Nuclear Plant, Unit 3, Cycle 16 Operation See Enclosed

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU3R16 Plant Browns Ferry Unit No.

3 Commercial service date 03/01/1977 Refueling outage no.

16 Current inspection interval 3rd Current inspection period 3rd FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number BFNU3R16 Plant Browns Ferry Nuclear Plant, P.O. Box 2000. Decatur, AL 35609 Unit No.

3 Commercial service date March 1. 1977 Refueling Outage no.

Refueling Outage 16 (if applicable)

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

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

Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition through 2003 Addenda Date and Revision of inspection plan 3-SI-4.6.G, Revision 046 10/24/2013 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan 2004 Edition, No Addenda Code Cases used: N-460. N-504-4 N-528-1, N-532-4, N-552, N-586-1. N-613-1. N-648-1. N-686-1. N-702 (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 U3R16 conform to the requirements of Section Xl.

(refueling outage number) n.or Owner's Designee, Tille CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Alabama and employed by HSB Global Standards of Hartford 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 requirement of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, repairs, replacements, evaluations, and corrective measures described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for an personalinjury or property damage or a loss of any kind arising from or connected with this Inspection.

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National Board, Slate, Proinnce and Endorsements Date 160 Lti

FORM OAR-I OWNER'S ACTIVITY REPORT TABLES Report Number BFNU3R16 Plant Browns Ferry Unit No.

3 Commercial service date 03/01/1977 Refueling outage no.

16 Current inspection interval 3rd Current inspection period 3rd TABLE I 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 As-Found Variable Spring support EVALUATED ACCEPTABLE setting out of range. Range 4275 to (No Corrective Measures Required.)

4525 lbs. As-Found 4675 lbs.

Review of Calculation (3-47B455-626) [NOI U3R16-001]

CDQ3073910863 and the Power Piping Company Catalog indicated that the working load range setting of a Model 614 Type C variable spring support is 3500 lbs. to 7000 lbs.

The "as-found" spring load setting of 4675 lbs. was within the working load range setting of a Model 614, Type C variable spring support. Review of Calculation CDQ3073910863 indicated that there is sufficient design margin in the pipe support design to accommodate the out of range spring load setting.

Based on the above, it was concluded that the spring support would 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.

Implementation of DCN (Design Change Notice) 70577 re-set the spring load setting to a range of 3899 lbs. to 4149 lbs.

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU3R16 Plant Browns Ferry Unit No.

3 Commercial service date 03/01/1977 Refueling outage no.

16 Current inspection interval 3rd Current inspection period 3rd TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Date Repair/Replacement Class Description of Work Completed Plan Number 3

Through wall leak in 2" and Remove degraded 08/10/2012 112814720 1.5" EECW Piping from piping and replace with 3-CKV-67-738 and new pipe 3-CKV-67-739 to Unit 3 Chiller (8-10 dpm) 3 Through wall leak in EECW Remove degraded 08/10/2012 113474832 piping downstream of the 3A2 piping and replace with Diesel Generator Shutdown new pipe Board Room Chiller (16 dpm) 3 Through wall leak in EECW Remove degraded 11/30/2012 114113534 piping downstream of 3A2 piping and replace with Diesel Generator Shutdown new pipe Board Room Chiller between 3-SHV-67-804 and 3-SHV-67-742.

3 Repair through wall leak Replace 6 ft of the 16" 09/21/2013 115091497 found on the 3C RHRSW 3C RHRSW inlet piping Inlet piping due to through wall leak.

2 BFN-3-FCV-073-0035, HPCI Repair cracked welds 03/16/2014 115474051 Condensate Test Valve 2

3-47B455-631-IA Remove indication and 03/18/2014 115569837 (Integral Attachment Weld) repair.

1 BFN-3-NM-092-0007/41 E, Replacement of Drytube 03/20/2014 115561248 INTERMEDIATE RANGE

/ Shuttle Tube / IRM-3E I MONITOR IRM-3E

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFN Plant

-Browns Ferry U3R16 Unit No.

3 Commercial service date 03/01/1977 Refueling outage no.

16 Current inspection interval 3rd Current inspection period 3rd Summary of IWE Indications for U3R16 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 Component Indication Acceptability/Corrective Action Inaccessible Area Additional Category Identifier Description (Location and Samples and Item Evaluation)

Number E-A / E1.30 MSB-3-1 Loss of Adhesion.

Moisture Seal Barrier (MSB)

The indications None Moisture Seal

[NOI U3R16-002]

indications were the result of identified did not Barrier mechanical damage from affect the ability of the either the U3R15 outage moisture seal barrier demobilization or mobilization to prevent intrusion of for U3R16 outage work. None moisture against the of the seal indications inaccessible areas of represent a seal failure. None the steel containment of the depressions penetrated vessel below the the full depth of the seal, and MSB. Therefore, no seal adhesion is good in all adverse condition locations, there was no seal exists and evaluation failure. Therefore, moisture of inaccessible areas cannot penetrate/bypass the is not required.

seal and get between the concrete floor and drywell liner. The affected portions of the seal were cut out, the drywell liner was examined, and the cut out seal sections re-poured. After curing, a VT-3 examination was conducted of the repaired areas

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNL Plant Browns Ferry Unit No.

3 Current inspection interv J3R1

~R1 6 Commercial service date 03/01/1977 Refueling outage no.

16 al 3rd Current inspection period 3rd Summary of IWE Indications for U3R16 (Continued)

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

Number E-A / E1.11 DW LNR 1A Drywell Liner (Below MSB)

Pitting and surface discontinuities.

[NOI U3R16-004]

Indications consisting of minor pitting due to corrosion 1/32" in depth and one pit due to mechanical damage 1/16" in depth were identified on the SCV (Steel Containment Vessel / Drywell) liner in the normally inaccessible area under the moisture seal barrier (MSB). These surface discontinuities were identified during a VT-1 examination of the liner where portions of the MSB was excavated for repair and were supplemented with Ultrasonic Thickness (UT) examinations to determine the thickness of the liner in these areas. Pitting has previously observed in the area below the MSB and evaluated in calculation CDQ0303970088.

The remaining wall thickness in the location of the minor pitting due to corrosion was 1.10775" to 1.12575" and 1.0535" in the area of mechanical damage. The remaining wall thickness in these areas remains above the minimum shell thickness of 1.0" provided in CDQ0303970088. The conditions identified are expected based on the age and service conditions of the SCV. None of the conditions noted were suspect. No detrimental flaws have been observed.

The indications noted are expected based on the age and service conditions of the SCV in the area under the MSB and do not affect the structural integrity of leak tightness of the of the SCV. Based upon this information, there is no indication that an adverse condition exists that may be present in inaccessible areas.

The liner in the area under the MSB will continue to be monitored when portions of the MSB are removed for repair.

None