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Summary of 990715 Meeting with ABB-CE Re Issues on SG Welded Sleeve Problem Identified in 1996.Attendance List & Handout Encl
	ML20211F382
Person / Time
Issue date:	08/17/1999
From:	Donohew J; NRC (Affiliation Not Assigned)
To:	Richards S; NRC (Affiliation Not Assigned)
References
	PROJECT-692 TAC-M93239, NUDOCS 9908300318
	Download: ML20211F382 (48)
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August 17, 1999 l

MEMORANDUM TO: Stuart A. Richards, Project Director Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM:

Jack N. Donohew, Senior Project Manager, Section 2 Project Directorate IV & Decommissioning l

Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

SUMMARY

OF JULY 15,1999, MEETING WITH ABB-COMBUSTION l

ENGINEERING ON STEAM GENERATOR WELDED SLEEVE PROBLEM IDENTIFIED AT PRAIRIE ISLAND UNIT 1 (TAC NO. M93239)

On July 15,1999, representatives of the ABB-Combustion Engineering (ABB-CE) met with members of the Nuclear Regulatory Commission (NRC) to discuss issues related to the steam generator welded sleeve problem that was identified at Prairie Island Unit 1 (PI) in 1996. The meeting was held at the request of ABB-CE to present their results from testing welded sleeve i

tubes that were removed from the Pl steam generators in 1996 and 1999. The information on these steam generator tubes is not part of any licensing action review being conducted by the staff. The meeting notice was issued June 18,1999. is the list of attendees. Attachment 2 is the handout provided by ABB-CE. There l

was no handout from the NRC staff. The agenda for the meeting is page 2 of Attachment 2.

There were pictures of the tested PI welded sleeve tubes that were shown to the staff. The results shown in these pictures are owned by ABB-CE and are considered proprietary by them.

These pictures are not included in the ABB-CE handout in Attachment 2.

ABB-CE addressed their steam generator welded sleeve design in pages 3 through 8 of. The welded sleeve design is used to span defects in steam generator tubes.

f Pictures are given for the 7/8-inch and 3/4-inch programs on pages 7 and 8 of Attachment 2.

These programs refer to the diameter of the tubes in the steam generator at the plant.

I[

The issues associated with the welded sleeve problem at Pi are addressed in pages 9 through 16 of Attachment 2. Page 10 of Attachment 2 is on the weld inclusions and weld suck back in q

the five Pl sleeves that were removed in 1996 from the steam generator. ABB-CE showed the C 0/

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picture to the staff in the meeting, but the picture is not included in Attachment 2.

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ReMgpa W 0*U August 17, 1999 ABB-CE presented the results of investigating two tubes pulled in 1999 at Pl. The results for the two pulled tubes are given on pages 17 through 37 of Attachment 2. These are the tubes in the following locations within the steam generator: row 23/ column 21 and row 29/ column 53.

Pages 18,19,21,22,23,24,27,28,30,31,32,33,34,35, and 36 had pictures of the results of testing the two pulled tubes. ABB-CE showed the pictures to the staff in the meeting, but, because the pictures are not included in Attachment 2.

The results for the two pulled tubes were that deposits in the annulus of the welded sleeve design were the cause of the eddy current testing (ECT) indications found in the welded f

sleeves, and no tube or sleeve degradation were found. The ECT indications of supposed tube wall flaws in the tubes were actually false indications caused by the deposits in the annulus region. Based on the results from the examination of the two pulled tubes, ABB-CE stated that both pulled tube could have been left in service.

ABB-CE addressed inspection implications on pages 38 through 43 and presented their conclusions on page 44 of Attachment 2. Pages 40,41,42, and 43 showed pictures of ECT using a standard probe and with partial saturation. ABB-CE showed the picture to the staff in the meeting, but the picture is not included in Attachment 2.

The experience from plants other than Pl are given on page 39. ABB-CE ended the meeting with the following conclusions:

ECT indications in the PI welded sleeve tubes were caused by deposits in the e

sleeve / tube annulus.

Sparsely dispersed oxide particles found in weld areas are not structurally detrimental.

e Diagnostic tests and revised analysis guidelines need to be developed for indications in e

the pressure boundary.

l Project No. 692 Attachments: 1. List of Attendees

2. ABB-CE Handout cc w/atts: See next page DISTRIBUTION Hard Coov E-Mail Docket File JZwolinski/SBlack EMurphy PUBLIC SRichards PRush PDIV-2 Reading VHodge OGC JDonohew ACRS EPepon To receive a copy or mes cocumem, anox:ste v in tne box OFFICE PDIV@

PDIV-2/LA EMCB/BC PDIV-2/SC PDIV&D/D NAME JDMwTrb EPehoI' EMurpkh SDembeh SRichards[ g DATE h /12/99 2 /R/99 f / /(/99 f //7 /99

[ //) /99 DOCUMENT NAME: G:\\PDIV-2\\CEOG\\MTS7-15.wpd OFFICIAL RECORD COPY

CE OWNERS GROUP Project No. 692 cc:

Mr. Gordon C. Bischoff, Project Director CE Owners Group ABB Combustion Engineering Nuclear Power l

M.S. 9615-1932 2000 Day Hill Road Post Office Box 500 Windsor, CT 06095 Mr. Ralph Phelps, Chairman CE Owners Group Omaha Public Power District j

F.O. Box 399 Ft. Calhoun, NE 68023-0399 Mr. lan C. Rickard, Director Nuclear Licensing ABB Combustion Engineering Nuclear Power 2000 Day Hill Road Post Office Box 500 Windsor,CT 06095 Mr. Charles B. Brinkman, Manager Washington Operations ABB Combustion Engineering Nuclear Power 12300 Twinbrook Parkway, Suite 330 Rockville, MD 20852 i

I l

l I

j

LIST OF MEETING ATTENDEES STEAM GENERATOR WELDED SLEEVE PROBLEMS AT PRAIRIE ISLAND UNIT 1 JULY 15.1999 NAME AFFILIATION J. Donobew NRC/NRR/PDIV-2 P. Rush NRC/NRR/EMCB V. Hodge NRC/NRR/REXB E. Murphy NRC/NRR/EMCB J. Lareau '

ABB-CE E. Kurdziel ABB-CE D. Stepnick ABB-CE R. Pearson Northem States Power ABB-CE = ABB-Combustion Engineering NRC

= Nuclear Regulatory Commission NRR

= Office of Nuclear Reactor Regulation PDIV-2

= Project Directorate IV, Section 2 EMCB

. = Materials and Chemical Engineering Branch REXB

= Events Assessment, Generic Communications, Non-Power Reactors Branch ATTACHMENT 1 g.

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