ML17033B164

American Society of Mechanical EngineersSection XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement - Cycle 11 Operation Programs

ML17033B164
Person / Time
Site:	Browns Ferry
Issue date:	02/02/2017
From:	Bono S Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML17033B164 (7)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 February 2, 2017 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington , D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-33 NRC Docket No. 50-259

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 1, Cycle 11 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 1, Cycle 11 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 1, Cycle 11 refueling outage, during the first inspection period of the Third 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 1, Cycle 11 refueling outage ended on November 4, 2016. Accordingly, this submittal is due by February 2, 2017.

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

Enclosure:

American Society of Mechanical Engineers,Section XI , Third 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 1, Cycle 11 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 1 American Society of Mechanical Engineers,Section XI, Third 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 1, Cycle 11 Operation See Enclosed

FORM OAR-1 OWNER'S ACTIVITY REPORT Plant Browns Ferry Nuclear Plant P.O. Box 2000 Decatur AL 35609 Unit No. --=----,,___,~ Commercial service date August 1 1974 Refueling Outage no. - - -'-R"'e"'fu.,e"'li"'n"'g_,O""u"'t"'a"'g""e_,1w1_ __

(if applicable)

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

Current Inspection Period _..1_,,st._P,_e"'-r..,,io.,d,___ _ _ _ _ _ _ _ _ _ _ _ ____,,...,...7""C-,-.,,.--------------------

(1st, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the inspection plans 2007 Edition through 2008 Addenda Date and Revision of inspection plan _ _.._1-_,S'"l-..;:4,_..6"'."'G...__._R,,e,_,v"'is,,,io.,n-'-"-00"'3"'4""---'-10"'/_,_1_,,3"/'2"'0'-'-1_,,6_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

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-526 N-532-5 N-586-1 N-600 N-613-1 N-648-1 N-661-2 N-716-1 N-735 N-747 N-751 and N-753 (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 ----'U"--"1R._,_,_1_,_1_ __

(refueling outage number)

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid comm ission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company 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 moooo'. Im ooy peraoo*I loj~* "*I~* of'"' klod '""'from" 000 :::~*,ith this Inspection .

~~ lflSi)eCtC)is Signature Commissions NB. ..l'l ""t,!'> , (l.,

National Boa rd Number and Endorsements Date _ _ \ ""-'/1"-D--i/'--1~]_ __

FORM OAR-1 OWNER'S ACTIVITY REPORT Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Category and Item Number Item Description Evaluation Description B-D, Item 83.90 Subsurface indications detected during EVALUATED ACCEPTABLE

[NOl-U1 R11-010] automated ultrasonic (UT) examination of (No Corrective Measures Required .)

N4A Feedwater Nozzle to Vessel weld. The subsurface indications detected during automated UT examination of the N4A Feedwater Nozzle to Vessel weld in the vicinity of N4A Feedwater Nozzle were characterized in General Electric (GE) inspection report R-078.

Each individual indication was determined to meet the acceptance standards of American Society of Mechanical Engineers (ASME) Code Section XI IWB-3500, however, when the indications were grouped using the proximity standards of IWA 3300, several groups of indications required further evaluation per the flaw evaluation methods of IWB-3600.

An ASME Code Section XI Flaw Evaluation of Indications in N4A Feedwater Nozzle to Vessel Weld was performed. This evaluation concluded the indications found during the inservice inspection of the N4A Feedwater Nozzle to Vessel weld were acceptable and meet the requirements of ASME Code,Section XI , IWB 3610.

Successive examinations as required by ASME Section XI, IWB-2420(b) and (c) are not required per ASME Section XI , Code Case N-526.

FORM OAR-1 OWNER'S ACTIVITY REPORT Table 2 Abstract of Repair/replacement Activities Required for Continued Service Code Date Repair/Replacement Item Description Description of Work Class Completed Plan Number Replace East SCRAM BFN-1-LA-085-0045M, Discharge Volume Rod 2 EAST SDV LEVEL HIGH 12/11/2014 116264259 Withdrawal Block Level ROD BLOCK Sensor Switch Replace 1-1 /2 inch Demineralized Water to BFN-1-SHV-023-0571 , Residual Heat Removal 3 RHR HX 1D DEMIN Service Water (RHRSW) 8/20/2015 117081832 WATER INLET piping and elbow downstream of 1-SHV-23-571 .

Replace Unit 1C Residual Heat Removal Service BFN-1-SHV-023-0552 , Water (RHRSW) Heat 3 RHR HTX 1C DEMIN Exchanger Demineralized 5/6/2016 117235018 WATER INLET Water Branch Line (piping and elbows) downstream of BFN-1-SHV-023-0552 BF N-1-ACC-085-718/0243 , Replace Scram Water 2 SCRAM WATER Accumulator with NOVA 10/17/2016 117085221 ACCUMULATOR Stainless Steel Accumulator BFN-1-ACC-085-718/1807, Replace Scram Water 2 SCRAM WATER Accumulator with NOVA 11/6/2016 114977939 ACCUMULATOR Stainless Steel Accumulator

FORM OAR-1 OWNER'S ACTIVITY REPORT Summary of IWE Indications for U1 R11 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 PSC INT-1-18 to 168 Pitting , EVALUATED ACCEPTABLE None None

[NOl-U1 R11 -002] (Pressure Mechanical (No Corrective Measures Required. )

Suppression Damage, The condition identified is pitting, mechanical damage, and corrosion Chamber Interior - and identified in Bay 1: 132.7 mils, Bay 12: 77 Wetted Surfaces of Corrosion mils, Bay 13: 80.3 mils and 75.3 mils, and Submerged Areas) Bay 15: 149 mils. The pitting and localized spot corrosion identified is the result of coating failures in the areas noted in Bays 1, 13, and 15. The coating failures are consistent with surface preparation deficiencies, irregular surfaces, and inadequate coating application. Minor mechanical damage to the coating caused by work activities impacting the coated surface is a contributing factor. One indication in Bay 12 was the result of mechanical damage affecting the substrate.

The indication was 0.25" wide and 1" long consistent with damage caused by work activities impacting the coated surface. An evaluation of each area was conducted.

This evaluation determined that the indications were acceptable and continue to meet applicable code requirements .

Protective coating was reapplied where localized pitting was identified with a pit depth greater than 30 mils to prevent further deqradation.

E -A , Item E1 .20 PSC MVH 1 16 Mechanical EVALUATED ACCEPTABLE None None

[NOl-U1 R11 - 006] (Pressure Damage (No Corrective Measures Required .)

Suppression The indication identified on the Unit 1 Torus main vent header (MVH) exterior surface is Chamber - Main Vent surface mechanical damage that does not Header) represent an adverse condition to the wall thicknesses of the MVH. There is little discernable corrosion present where the base metal that has been revealed , and no appreciable depth to the mechanical marks.

Therefore, no adverse condition exists and evaluation of inaccessible areas is not required .

E -A, Item E1 .30 MSB 1 Mechanical EVALUATED ACCEPTABLE None None

[NOl -U1 R11 -007] (Moisture Seal Damage (Affected Portions of MSB Replaced)

The indications were the result of Barrier) mechanical damage from outage related work activities. The indications identified did not affect the ability of the moisture seal barrier (MSB) to prevent intrusion of moisture against the inaccessible areas of the steel containment vessel below the MSB. The affected portions of the seal were cut out, the exposed drywell liner was examined, and the cut out seal sections re-poured. Therefore, no adverse condition exists and evaluation of inaccessible areas is not required .