ML13253A139

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

ML13253A139
Person / Time
Site:	Browns Ferry
Issue date:	08/02/2013
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13253A139 (9)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 August 2, 2013 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 17 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 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 Xl boundary, up to and including the BFN, Unit 2, Cycle 17 refueling outage, during the first inspection period of the fourth 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 2, Cycle 17 refueling outage ended on May 4, 2013. Accordingly, this submittal is due by August 2, 2013.

A c-r Printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 August 2, 2013 There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact J. E. Emens, Jr., Nuclear Site Licensing Manager, at (256) 729-2636.

Respec y,

ce President, Nuclear Licensing

Enclosure:

American Society of Mechanical Engineers, Section Xl, Fourth 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 2, Cycle 17 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 XI, Fourth 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 2, Cycle 17 Operation See Enclosed

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2R17 Plant Browns Ferry Unit No.

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

17 Current inspection interval 4th Current inspection period 1st FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number BFNU2R17 Plant Browns Ferry Nuclear Plant, P.O. Box 2000. Decatur, AL 35609 Unit No.

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

Refueling Outage 17 (I applicable)

Current Inspection Interval Fourth Ten Year Inspection Interval Ifst. 2nd. 3rd. other)

Current Inspection Period First Period (t t. 2nd. 3rd)

Edition and Addenda of Section XI applicable to the inspection plans 2004 Edition, No Addenda Date and Revision of inspection plan 2-SI-4.6.G. Revision 0051 04/24/13 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan N/A 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 U2R17 conform to the requirements of Section Xl.

refueling outage number)

Signed

-Dale

-7____-29____- ___1__

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 CT 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 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 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2R17 Plant Browns Ferry Unit No.

2 Commercial service date 03/01/1975 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 Description Evaluation Description Item Number F-A, Item F1.20C As-Found constant spring support setting out-of-range. Range 1575 to 1650 lbs. As-Found 1550 lbs.

(2-47B455H0061) [NOI U2RF17-001]

EVALUATED ACCEPTABLE (No Corrective Measures Required.)

The load used in the pipe stress analysis (CD-Q2073-880990) is 1600 lbs. Acceptable variability from the analysis load is 25% per BFN-50-C-7107. Therefore, for the analysis the load may range between 1200 lbs to 2000 lbs and remain acceptable. The working range of the spring is 1050 lbs to 2100 lbs per the support calculation (CD-Q2073-881771). The thermal piping movement is slightly more than 1/8 inch in the up direction and less than 1/32 inch in the down direction.

The spring has a spring constant of 300 lbs/in. The as-found setting and any variability of the spring due to pipe movements will leave the spring within the requirements of the analysis and the working range of the spring. The as-found setting of 1550 lbs is approximately at mid-point of the spring working range, with considerable margin from topping or bottoming out. The earthquake movement vertically is approximately 0.154 inch; therefore, topping or bottoming out from seismic movements will not occur and does not require further consideration. The as-found spring can ceiling is slightly more than 1/16 inch outside the spring ceiling range.

Therefore, the as-found setting had no detrimental effect on the 10 inch High Pressure Coolant Injection steam supply piping or adjacent pipe supports.

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2R17 Plant Browns Ferry Unit No.

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

17 Current inspection interval 4th Current inspection period 1st Examination Category and Item Description Evaluation Description Item Number F-A, Item F1.20C Loose nut on pipe clamp load pin bolt.

EVALUATED ACCEPTABLE (2-47B455H0060) [NOI U2RF17-002]

(No Corrective Measures Required).

The bolted connection associated with the loose nut identified is on the 6 inch diameter pipe clamp shown on drawing 2-47B455H0060. Given the configuration of the connection, the bolt would be loaded only in shear and its shear capacity is not affected by the loose nut. The primary fun'ction of the nuts would be to ensure the bolts do not become dislodged. Therefore, the connection remains capable of performing its design function in the as-found condition. The nut was tightened during the U2R17 outage and re-examined.

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

Plant Browns Ferry Unit No.

2 Current inspection interv J2R1 R1 7 Commercial service date 03/01/1975 Refueling outage no.

17 al 4th Current inspection period 1st TABLE 2 ABSTRACT OF REPAIRIREPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Description of Work Date Repair/Replacement Class Completed Plan Number Replace the C3 Emergency BFN-0-PMP-023-0091, Equipment Cooling Water Residual Heat Removal (EECW) pump, 3

Service Water (RHRSW)

BFN-0-PMP-023-0091, 6/8/2011 111972393 Pump C3 column assembly with the rebuilt spare column assembly Install branch connection 3

BFN-0-MISC-067, EECW and blind flange on EECW North Header Supply 18 inch 9/22/2011 112148977 North Header Supply C3 supply line in the RHRSW tunnel.

3 BFN-0-MISC-067, EECW Install branch connection 3

BFN-0-MISu-067, EECW and blind flange on EECW 10/20/2011 112171827 South Header Supply South Header Supply Replace piping at a through 3

BFN-2-PIPE-023-0001/036, wall leak in 2B RHRSW inlet 10/30/2011 112817797 16 inch pipe piping inside 2B/D RHRSW tunnel.

3 BFN-0-CKV-067-0502, Disassemble, inspect, and South Header Check Valve repair/replace EECW check 3/20/2012 113310490 valve.

3 BFN-2-PIPE-023-0001/039, Repair through wall leak in 4/14/2012 113400655 16 inch pipe 2C RHRSW inlet piping BFN-2-MISC-023, Replace piping located at a 3

1-1/2 inch piping through wall leak in RHRSW 5/9/2012 113474377 piping 3 BFN-2-PIPE-023-0001/039, Replace approximately 3

16Finch-PIE-023-0001/039 3 feet of 16 inch piping on 8/13/2012 113775300 16 inch RHRSW inlet piping 2C RHRSW inlet.

Replace section of RHRSW 3

BFN-2-MISC-023, 1.5 inch piping drain line 11/13/2012 114111251 1-1/2 inch piping (upstream of drain valve 2-DRV-023-0551).

3 BFN-2-MISC-023, Install by welding a 4 inch weld-o-let and cap onto the 2/28/2013 114432497 16 inch RHRSW piping 16 inch 2A RHRSW supply.

2 BFN-2-HEX-074-0900D, Cut out and replace partition plate in RHR Heat 4/17/2013 112074180 RHR Heat Exchanger 20 Exchanger 2D.

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2R17 Plant Browns Ferry Unit No.

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

17 Current inspection interval 4th Current inspection period 1st Code Item Description Description of Work Date RepairlReplacement Class Completed Plan Number BFN-2-SHV-067-0640, North 3

Header Supply Shutoff Valve Repair thru wall leak in 4/26/2013 113946144 to Unit 2 Reactor Building EECW system piping.

Closed Cooling Water Remove the seal weld on 3

BFN-2-HEX-074-0900A, the RHR Heat Exchanger 2A 4/28/2013 08-719409-000 RHR Heat Exchanger 2A floating head and replace with a new floating head.

BFN-2-PCV-001-0151, Replace the existing valve 2

Steam Jet Air Ejector (SJAE) body, BFN-2-PCV-001-0151.

.114525652 A Stage 1_bod,_BN-2P__-01-151 BFN-2-PCV-001-0153, Replace the existing valve 2

SJAE B Stage 1 body, and refurbish internals 5/5/2013 114527967 SJAEBStage__1 of BFN-2-PCV-001-0153.

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFN Plant Browns Ferrv U2R17 Unit No.

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

17 al 4th Current inspection period 1st Summary of IWE Indications for U2R17 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).

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

-Item Number and Evaluation)

E-A, Item Moisture Seal Mechanical Seven damaged areas of the None None E1.30 Barrier (MSB) damage.

MSB were identified for repair.

MSB-2-1

[NOI U2RF17-005]

The damage found was the result of mechanical damage from either the U2R16 outage demobilization or mobilization for U2R1 7 outage work. None of the depressions penetrated the full depth of the seal and seal adhesion was good in all locations. Therefore, moisture could not penetrate or bypass the seal and get between the concrete floor and drywell liner.

The indications noted did not affect the ability of the seal to prevent intrusion of moisture against the inaccessible areas of the steel containment vessel below the MSB. A visual examination (VT-1) of the drywell liner was conducted in areas excavated for repair. No indications were noted in these areas. Therefore, no adverse condition exists that may be present in I inaccessible areas.