W3F1-2002-0040, Ses - 15 - Day Special Report SR-02-001-00 on the 11th Refueling Outage Steam Generator Tube Inservice Inspection

Ses - 15 - Day Special Report SR-02-001-00 on the 11th Refueling Outage Steam Generator Tube Inservice Inspection

ML021330459
Person / Time
Site:	Waterford
Issue date:	04/22/2002
From:	Peters R Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
A4.05, SR-02-001-00, W3F1-2002-0040
Download: ML021330459 (5)

Text

Entergy Operations, Inc.

'O ~ntoWKillona, 17265 River Road LA 70066 Tel 504 739 6650 W3F1-2002-0040 A4.05 PR April 22, 2002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 15-Day Special Report SR-02-001-00 on the 11th Refueling Outage Steam Generator Tube Inservice Inspection Gentlemen:

Attached is Special Report (SR) Number SR-02-001-00, Steam Generator Eddy Current Examination (11th Refueling Outage), from Entergy Operations, Inc (EOI)

Waterford Steam Electric Station Unit 3. This report provides the results of the Refuel 11 Steam Generator Tube Inservice Inspection in accordance with Technical Specifications 4.4.4.5.a and 6.9.2.

This letter contains no commitments. If you have any questions concerning the above, please contact R.L. Williams at (504) 739-6255 or B.R. Fitzsimmons at (504) 739-6546.

Very truly yours, R.D. Peters Acting, Director Nuclear Safety Assurance RDP/RLW/cbh Attachment cc: E.W. Merschoff, (NRC Region IV), N. Kalyanam, (NRC-NRR),

J. Smith, N.S. Reynolds, NRC Resident Inspectors Office, Louisiana DEQ/Surveillance Division

Attachment I Special Report SR-02-001 -00

Special Report SR-02-001-00 Steam Generator Eddy Current Examination (11th Refueling)

This report is submitted in accordance with Technical Specification (TS) 4.4.4.5.a, which requires reporting the number of tubes plugged in each Steam Generator (S/G) within 15 days following completion of S/G tube Inservice Inspection (ISI) in accordance with TS 6.9.2.

On April 5, 2002, Waterford 3 completed a 98% inservice eddy current bobbin coil full length examination of each S/G and a 100% examination of the hot leg top of the tubesheet (+2" and - 5" tubesheet plane interface) utilizing an EPRI Appendix H approved technique "Plus Pt." rotating probe technology. The remaining 2% of each S/G's low rows 1, 2, and 3 were examined with the bobbin coil in the straight sections and 100% of the U-bends were (7Cold to 7Hot) inspected with the "Plus Pt." rotating probe. The S/G primary side inspection for Refuel #11 was completed on April 12, 2002.

A more detailed annual follow-up report will be submitted to the NRC Staff in accordance with TS 4.4.4.5.b by April 12, 2003.

The total number of tubes plugged in each S/G is shown below:

SIG #1 S/G #2 Man ufacturing/Preservice 6 20 Batwing (Preventive Plugging) 149 149 First Refueling 0 1 Second Refueling 3 0 Third Refueling 10 9 Fourth Refueling

- Preventive Plugging as a result of ECT 4 5

- Batwing Preventive Plugging 156 156 Fifth Refueling 4 5 Sixth Refueling

- Preventive Plugging as a result of ECT 1 2 J:\BRIAN\RF111SPRPT.DOC Page 1 of 3

Special Report SR-02-001-00 Steam Generator Eddy Current Examination (11th Refueling)

Seventh Refuelinq SIG #1 S/G #2

- Preventive Plugging as a result of ECT 6 3

- >40% thru-wall indications 2 0

- Single circumferential indications 6 1 Eighth Refuelinq

- Top of the tubesheet Loose Part Indications 3 3 Multiple Circumferential Indications 2 0 Single Volumetric Indications 2 1 Multiple Axial Indications 1 0 Single Circumferential Indication 12 7 Single Axial Indications 9 7

- Wear Indications _ 40% Thru Wall 0 7 Ninth Refueling

- Top of the tubesheet:

Single Volumetric Indications 0 1 Single Circumferential Indications 2 3 Single Axial Indications 3 0

- Indications at Eggcrates:

Single Axial Indications 5 3 Single Circumferential Indications 0 1

- Wear Indications >_40% Thru Wall 1 1

- Wear Indications < 40% Preventively Plugged I I J:\BRIAN\RF1 1SPRPT.DOC Page 2 of 3

Special Report SR-02-001 -00 Steam Generator Eddy Current Examination (1 1th Refueling)

Tenth Refuelinq S/G#1 S/G#2

- Top of the tubesheet:

Single Volumetric Indications 0 4 Multiple Volumetric Indications 1 0 Single Circumferential Indications 4 8 (All Circumferential Indications were Stabilized and Plugged.)

Single Axial Indications 21 20 Multiple Axial Indications 0 2

- Indications at Eggcrates:

Single Axial Indications 2 0 Single Circumferential Indications 0 0

- Wear Indications >_ 40% Thru Wall 0 3

- Wear Indications < 40% Preventively Plugged 0 1 The Total number of tubes plugged Refuel 10 28 38 Eleventh Refueling

- Top of the tubesheet:

Single Circumferential Indications 12 3 (All Circumferential Hot Leg Top of Tubesheet Indications within the Expansion Transition Region were Stabilized and Plugged.)

Single Axial Indications 9 1

- Indications at Eggcrates:

Single Axial Indications 2 0 Wear Indications _> 40% Thru Wall 0 1 Wear Preventively Plugged 1 1

- Freespan DING 1 1

- Permeability 1 0

-Inner Diameter Chatter 0 3 The Total number of tubes plugged RF#11 26 10 The Total number of tubes that have been plugged 444 (4.7%) 434 (4.6%)

to date in each S/G:

J:\BRIAN\RF1 1SPRPT. DOC Page 3 of 3