ML15190A330

ASME Section XI, Lnservice Inspection, System Pressure Test, Containment Lnservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 18 Operation

ML15190A330
Person / Time
Site:	Browns Ferry
Issue date:	07/09/2015
From:	Bono S Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML15190A330 (8)

Text

T ennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 July 9, 2015 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 EngineersSection XI, 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 18 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 18 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 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 18 refueling outage, during the second 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 2, Cycle 18 refueling outage ended on April 10, 2015. Accordingly, this submittal is due by July 9, 2015.

U.S. Nuclear Regulatory Commission Page 2 July 9, 2015 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 2, Cycle 18 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, 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 18 Operation See Enclosed

FORM OAR-1 OWNER'S ACTIVITY REPORT Plant Browns Ferry Nuclear Plant. P .0 . Box 2000 Decatur Al 35609 Unit No _ __,,2_ __ Commeroal service date MarCIJ 1 1975 Refueling Outage no. _ _R

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Current Inspection Interval Fourth Ten Year Inspection Interval

( 1$1 , 2nd. ln::t . Olher)

Current Inspection Penod =S=eco=n~d~P'-e=riOd~* ~------------~--0-.,-.,..-,,--------------------

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Edit.ion and Addenda or Section XI applicable to the inspection plans ~20=04 ~= E=di= ti~on

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Date and Rev1s1on of inspection plan 2-Sl-4 .6 .G Revision 0053 02/1 1/2015 Ed1t1on 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 r* oppica!H)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the lnspec\Jon Plan as required by the ASME C ode.Section XI ; a nd (c) the repair/replacement activi ties and eval uations supporting the completion of U2R T8 conform to the requirements of Section XI CERTIFICATE OF INSERVICE INSPECTION I. the undersigned . holding a valid comm1sS1on 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 Harttord Connecticut have inspected the items described in U11s Owne( S Activity Report and stale that, to the best of my knowledge and belief. tne 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 manne r for any perso, 1ury or propeny damage or a loss of any kind ansmg from or connected with this Inspection

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FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2R18

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Plant Browns Ferry Unit No. 2 Commercial service date 03/01/1975 Refueling outage no. - 18- - -

Current inspection interval - 4th Current inspection period 2nd 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 Loose pipe clamp bolt and a bound EVALUATED ACCEPTABLE hanger rod weldless eye nut. (No Corrective Measures Required .)

(2-47B452H0064) [NOi U2R18-001] Although, there is a loose bolt on one side of the pipe clamp, the second bolt remained intact so that the pipe lugs are engaged with the pipe clamp, allowing the pipe support to continue performing its design function in the as-found condition. The hanger rod weldless eye nut was aligned and restored to its original design configuration and the loosened pipe clamp bolt was tightened under Work Order 116662196 and re-examined .

F-A, Item F1 .20C Variable Spring setting out of range. EVALUATED ACCEPTABLE Range 2628 to 2773 lbs. As-Found (No Corrective Measures Required.)

2800 lbs. There is no adverse effect on the pipe (2-47B452H0158) [NOi U2R18-002] support components or the associated piping with the out of range spring load setting. The spring setting was restored to the design range of 2628 to 2773 lbs. under Work Order 116694412 and re-examined.

F-A, Item F1 .1OB Loose bolt/nut assembly on the W33 EVALUATED ACCEPTABLE beam. (No Corrective Measures Required.)

(2-47B400S0007) [NOi U2 R18-003] Main Steam pipe support/whip restraint 2-47B400S0007 was capable of performing its design function in the "as found" condition . The loose bolting was tightened under Work Order 116671745 and re-examined.

D-A , Item 01 .20 Missing welds on one side of four EVALUATED ACCEPTABLE integral attachments to Emergency (No Corrective Measures Required .)

Equipment Cooling Water(EECW) There was sufficient design margin for the pipe support to be able to piping .

perform its design function in the (2-47 B451 R0009-IA) [NOi U2R18-005] "as-found" condition. Affected drawings and calculation CDQ2067891522 to be revised to document the as-found configuration under Condition Report (CR) 1006597

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2R18

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P1ant Browns Ferry Unit No. 2 Commercial service date 03/01/1975 Refueling outage no. - 18- - -

Current inspection interval 4th Current inspection period -2nd------

Examination Category and Item Number Item Description Evaluation Description F-A, Item F1 .1OC Variable Spring setting out of range. EVALUATED ACCEPTABLE Range 12458 to 13124 lbs. As-Found (No Corrective Measures Required.)

13457 lbs. There is no adverse effect on the pipe (2-478452$0239) [NOi U2R18-006] support components or the associated piping with the out of range spring load setting. The spring setting was restored to the design range of 12458 to 13124 lbs. under Work Order 116310767 and re-examined.

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2R18

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Plant Browns Ferry Unit No. 2 Commercial service date 03/01 /1975 Refueling outage no. - 18- - -

Current inspection interval 4th

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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 BFN-O-HEX-082-000C2 Emergency Diesel Replace Water Box 3 7/10/2014 115946315 '

Generator Cooling Water (Tee end)

Heat Exchanger C2 BFN-2-SHV-07 4-0850 Residual Heat Removal Repair Unit 2 RHR system (RHR) Shutdown Cooling 1 leak identified downstream 8/8/2014 116022653 Supply Header, Chemical of 2-FCV-074-0048 Injection and Drain Shutoff Valve BFN-2-ACC-085-718/5827 Replace Hydraulic Control 1 8/13/2014 116022785 Scram Water Accumulator Unit Water Accumulator BFN-2-CLR-064-0069 Repair Leaking U-Bend on 2 Reactor Building RHR 11/11/2014 116306134 2B RHR Room Cooler Coil Pump 'B' Room Cooler BFN-2-CLR-064-0073 Repair brazed joint on Reactor Building Core 2 copper tube on B CS Room 11/10/2014 116306135 Spray (CS) Pump 'B' Room Cooling Coil Cooler BFN-2-CLR-064-0070 Repair leak at welded 3 Reactor Building RHR connection on coil, supply 12/3/2014 116366514 Pump 'C' Room Cooler side.

BFN-2-CLR-064-0073 Reactor Building CS Pump 3 Reactor Building CS Pump 12/17/2014 116387178

'B' Room Cooler

'B' Room Cooler BFN-2-CLR-064-0072 Repair tube leak on 2A CS 3 Reactor Building CS Pump 12/30/2014 116437239 Room Cooler

'A' Room Cooler

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLES Report Number BFNU2R18 P 1ant Browns Ferry Unit No. 2 Commercial service date 03/01/1975 Refueling outage no. ---

Current inspection interval 4th

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Current inspection period 2nd Summary of IWE Indications for U2R18 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 Additional Category and Identifier Description Area Samples Item Number (Location and Evaluation)

E-A, Item E1 .12 PSCINT Pitting, EVALUATED ACCEPTABLE None None 2-8-1 B through mechanical (No Corrective Measures Required .)

2-B-168 damage, and The indications primarily consisted of rusting. pitting in areas of upset of the

[NOi U2R18-007] protective coating by mechanical damage or from coating failure.

Pitting ranged from 0.012" to 0.074".

Civil Engineering Evaluation determined the indications are acceptable and continue to meet all code allowable stress limits in accordance with calculation CDQ09999701 14, Attachment A.

Inspected areas exhibited no signs of flaking , blistering, peeling, or other signs of distress. There was no degradation present which affects the structural integrity or containment function of the Pressure Suppression Chamber (PSC). The submerged coated surfaces of the PSC are accessible for examination.

Therefore, no adverse condition exists which may be present in inaccessible areas. Protective coating was reapplied for pits greater than 0.035" to limit further deqradation.