2CAN030601, Steam Generator Tube Inservice Inspection Report Arkansas Nuclear One - Unit 2

Steam Generator Tube Inservice Inspection Report Arkansas Nuclear One - Unit 2

ML060880337
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/16/2006
From:	James D Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2CAN030601
Download: ML060880337 (8)

Text

_

Eint z 77 t

{ 5 ZRussellville, Entergy Oerations, Inc.

1448S.R.333 S.R 72802 Tel 501 858 5C00 2CAN030601 March 16, 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Steam Generator Tube Inservice Inspection Report Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6

Dear Sir or Madam:

Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specification 6.6.7.b requires that the complete results of ANO-2 steam generator (SG) tubing in-service inspections be reported within 12 months following the completion of the inspection. Attached is the SG Tubing In-service Inspection Report which presents the results from ANO-2's scheduled refueling outage (2R17) inspection. These inspections were conducted during April 2005.

The 2R17 inspection performed on both SGs involved an initial full-length bobbin coil examination of 54%. The Rotating Pancake Coil (RPC) used consists of a plus-point ccil.

Initially, 20% of the hot leg top-of-tubesheet expansion transitions were tested. This was later expanded due to the identification of loose part damage. The plus-point was also utilized for confirmation of bobbin coil indications.

This submittal contains no commitments. Should you have any questions regarding this report, please contact Fred Van Buskirk of my staff at (479) 858-3155.

iqcerely, 1James iger, Licensing DEJ[fpv Attachment ..

'N 2CAN030601 Page 2 cc: Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Drew Holland Mail Stop 0-7 DI Washington, DC 20555-0001

Attachment 2CAN030601 ARKANSAS NUCLEAR ONE, UNIT 2 STEAM GENERATOR TUBING INSERVICE INSPECTION REPORT

Attachment to 2CAN030601 Pace 1 of 5 ARKANSAS NUCLEAR ONE, UNIT 2 STEAM GENERATOR TUBING INSERVICE INSPECTION REPORT I INTRODUCTION Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specification (TS) 6.6.7.b requires Entergy Operations to submit a report to the NRC that provides the results of steam generator (SG) tubing in-service inspections. The report is to be submitted within 12 months following the completion of the inspection and shall include:

1. Number and extent of tubes inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugged or sleeved.

The operating period for this report includes one outage, a refueling inspection (2R.17) in April 2005.

The unit developed a primary-to-secondary leak approximately three weeks prior to the scheduled start of the refueling outage. The plant was taken offline five days early due to the increasing trend of the leakage with a maximum value of 35 gallons per day from steam generator "A". The source of the leakage was later identified as a loose part that had caused wear on the adjacent tube (R70C169).

All performance criteria were met.

2 DESIGN The replacement steam generators for ANO-2 are Westinghouse (W) Model Delta 109's. They consist of Inconel 690 thermally-treated tubing that is 11/16" in diameter with a 0.040" wall thickness. The tubes are expanded full depth hydraulically in the tubesheet. The tube supports are constructed of stainless steel and are a broached trefoil-hole design. The upper bundle supports consist:

of Five sets of staggered stainless steel anti-vibration bars (AVB's) that are numbered A01-A20.

Att3chment to 2CAN030601 Page 2 of 5 3 REPORT REQUIREMENTS 3.1 Number and Extent of Tubes Tested (2R17)

Table 3.1 lists the inspection scope of 2R17.

Table 3.1 2R17 Inspection Scope SG "A\"

Examination Tvoe Insnections Conducted  % Scone Extent Tested Bobbin Initial 5761 54 TEC to TEH Hot Leg TTS Initial 2118 20 +/-3 inches HLTT',

Hot Leg TTS Expansion 1 2247 21 +/- 3 inches HLTT',

Hot LIBg TTS Expansion 2 1265 12 +/- 3 inches HLTT';

Cold leg TTS Expansion 1 3314 31 +/- 3 inches CLTT',

Cold Leg TTS Expansion 2 1498 14 +/- 3 inches CLTT',

Bobbin I-Codes 19 N/A N/A SG "13" Examination Type Inspections Conducted %Scope Expansion Req'd Bobbin Initial 5748 54 TEC to TEH Hot Leg TTS Initial 2128 20 +/- 3 inches HLTT',

Hot Leg TTS Expansion 1 2350 21 +/- 3 inches HLTT',

Hot Leg TTS Expansion 2 300 N/A +- 3 inches HLTT',

Cold leg TTS Expansion 1 3289 31 +/- 3 inches CLTT-7 Cold leg TTS Expansion 2 300 N/A +1-3 inches CLTT',

Bobbin I-Codes 19 N/A N/A

Ao Attachment to 2CAN030601 Page 3 of 5 3.2 Location and Percent of Wall-Thickness Penetration for each Indication of an Imperfection.

This topic is addressed in Table 3.2.1 for SG "A" and Table 3.2.2 for SG "B" below.

TABLE 3.2.1 SG "A" INDICATION LIST FOR 2R17 Item No. Row Column Percent Through-Wall Location Mechanism 1 59 60 13 A07 AVBWear I 2 62 13 14 A05 AVBWear 3 63 46 11 A14 AVB Wear I 4 70 169 100 TSH Loose Part Wear 5 70 169 86 TSH Loose Part Wear I 6 71 170 57 TSH Loose Part Wear I 7 72 169 46 TSH Loose Part Wear 8 72 169 54 TSH Loose Part Wear I 9 74 15 16 A18 AVBWear I 10 87 108 17 A09 AVB Wear 11 119 76 19 A09 AVB Wear 12 121 86 21 A09 AVB Wear 13 135 78 16 TSC Loose Part Wear 14 135 102 15 A09 AVB Wear 15 135 102 14 A15 AVB Wear 16 142 119 5 TSH Loose Part Wear 17 142 119 10 TSH Loose Part Wear 18 144 119 7 TSH Loose Part Wear 19 146 113 10 TSH Loose Part Wear 20 146 115 4 TSH Loose Part Wear 21 146 115 6 TSH Loose Part Wear Legend:

AVB - Anti-Vibration Bar TSH - Tubesheet Hot TSC - Tubesheet Cold A01- A20 - Anti-Vibration Bar Nomenclature

- Attichment to 2CAN030601 Page 4 of 5 TABLE 3.2.2 SG "B" INDICATION LIST FOR 2R17 Item INo. Row Column Percent Through-Wall Location Mechanism 1 52 109 7 A07 AVB Wear 2 100 25 16 TSC Loose Part Wear 3 102 25 4 TSC Loose Part Wear 4 109 92 26 All AVB Wear 5 112 149 10 A12 AVB Wear 6 112 149 14 A18 AVB Wear 7 113 92 15 A14 AVB Wear 8 113 92 7 A17 AVB Wear 9 116 99 14 A09 AVB Wear 10 116 99 13 A12 AVB Wear 11 124 129 11 TSH Loose Part Wear 12 125 92 14 A15 AVB Wear 13 133 48 13 A13 AVB Wear 14 133 48 17 A15 AVB Wear 15 133 48 8 A17 AVB Wear 16 133 48 5 A19 AVB Wear 17 138 119 8 TSH Loose Part Wear 1E 138 119 10 TSH Loose Part Wear I 139 120 43 TSH Loose Part Wear Legend:

AVB - Anti-Vibration Bar TSH - Tubesheet Hot TSC - Tubesheet Cold A01- A20 - Anti-Vibration Bar Nomenclature

A Attachment to 2CAN030601 Page 5 of 5 3.3 Identification of Tubes Plugged or Sleeved.

There were no sleeves installed during 2R17. There were four tubes in SG "A" and seven tubes in SG "B" repaired by mechanical plugging during 2R17 due to loose part damage. These are listed in Tables 3.3.1 and 3.3.2:

Table 3.3.1 Steam Generator A Plugged Tubes ROW LINE IND LOCATION 1 70 169 SVI TSH + 0.25 2 72 169 SVI TSH + 0.87 3 71 170 SVI TSH + 0.92 4 135 78 SVI TSC + 0.04 Table 3.3.2 Steam Generator B Plugged Tubes ROW LINE IND LOCATION 1 6 97 PLP TSC + 0.19 2 5 98 PLP TSC + 0.13 3 7 98 PLP TSC + 0.15 4 20 173 PLP TSH + 0.11 5 21 172 PLP TSH + 0.13 6 22 173 PLP TSH + 0.09 7 139 120 SVI TSH + 0.10 The cumulative number and percent plugged and sleeved following 2R17 is listed in Table 3.3.3:

Table 3.3.3 Cumulative Plugs and Sleeves in Service SG "A" SG "B" Pre-service Sleeves 0 0 2R17 Sleeves Installed 0 0 Total Sleeves Installed 0 0 Pre-service 1-690 Welded 0 1 2R17 Plugs Installed 4 7 Total Plugged 4 8 Percent Plugged 0.0376 % 0.0752 %