ML17333A629

Summary of 961022 Meeting W/Aep in Rockville,Md Re Licensee Plans for Insp & Repair of Unit 1 SGs During 1997 Refueling Outage.List of Meeting Attendees & Slides Encl

ML17333A629
Person / Time
Site:	Cook
Issue date:	10/31/1996
From:	John Hickman NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9611060233
Download: ML17333A629 (20)

Text

October 31, 1996 LICENSEE:

American Electric Power Service Corporation (AEP)

(Indiana Michigan Power)

FACILITY:

D.C. Cook, Unit 1

SUBJECT:

STEAM GENERATOR INSPECTION AND REPAIR PLANS FOR THE 1997 REFUELING OUTAGE A meeting was held at NRC Headquarters on October 22, 1996, to discuss the licensee's plans for inspection and repair of the Unit 1 steam generators during the 1997 refueling outage.

The licensee presented a summary description of the steam generator (S/G)

design, the current S/G tube repair status, primary degradation mechanisms, remedial measures currently in place, and the results of the last 2 S/G inspections.

The licensee then discussed with the staff the inspections planned for the 1997 outage and the proposed repair plans.

The status of related license amendments was discussed and the licensee was advised to review the Topical Reports on repair methodologies previously approved to assure consistancy with any proposed repairs.

Original signed by:

John B. Hickman, Project Manager Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket No. 50-315

Enclosures:

1.

List of attendees 2.

Slides cc w/encls:

See next page

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October 31, 1996 LICENSEE:

American ETectric Power Service Corporation (AEP)

(Indiana Michigan Power)

FACILITY:

D.C. Cook, Unit 1

SUBJECT:

STEAM GENERATOR INSPECTION AND REPAIR PLANS FOR THE 1997 REFUELING OUTAGE A meeting was held at NRC Headquarters on October 22, 1996, to discuss the licensee's plans for inspection and repair of the Unit 1 steam generators during the 1997 refueling outage.

The licensee presented a summary description of the steam generator (S/G)

design, the current S/G tube repair status, primary degradation mechanisms, remedial measures currently in place, and the results of the last 2 S/G inspections.

The licensee then discussed with the staff the inspections planned for the 1997 outage and the proposed repair plans.

The status of related license amendments was discussed and the licensee was advised to review the Topical Reports on repair methodologies previously approved to assure consistancy with any proposed repairs.

Original signed by:

John B. Hickman, Project Manager Project Directorate III-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-315

Enclosures:

1.

List of attendees 2.

Slides cc w/encls:

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-OI41 October 31, 1996 LICENSEE:

American Electric Power Service Corporation (AEP)

(Indiana Michigan Power)

FACILITY:

D.C. Cook, Unit 1

SUBJECT:

STEAM GENERATOR INSPECTION AND REPAIR PLANS FOR THE 1997 REFUELING OUTAGE A meeting was held at NRC Headquarters on October 22, 1996, to discuss the licensee's plans for inspection and repair of the Unit 1 steam generators during the 1997 refueling outage.

The licensee presented a summary description of the steam generator (S/G)

design, the current S/G tube repair status, primary degradation mechanisms, remedial measures currently in place, and the results of the last 2 S/G inspections.

The licensee then discussed with the staff the inspections planned for the 1997 outage and the proposed repair plans.

The status of related license amendments was discussed and the licensee was advised to review the Topical Reports on repair methodologies previously approved to assure consistancy with any proposed repairs.

Docket No. 50-315 John B. Hickman, Project Manager Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Enclosures:

1.

List of attendees 2.

Slides cc w/encls:

See next page

Indiana Hichigan Power Company CC'egional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Marrenville Road Lisle, Illinois 60532-4351 Attorney General Department of Attorney General 525 Mest Ottawa Street Lansing, Hichigan 48913 Township Supervisor Lake Township Hall P.O.

Box 818 Bridgman, Hichigan 49106 Al Blind, Site Vice President Donald C. Cook Nuclear Plant 1 Cook Place Bridgman, Hichigan 49106 U.S. Nuclear Regulatory Commission Resident Inspector's Office 7700 Red Arrow Highway Stevensville, Hichigan 49127 Gerald Charnoff, Esquire

Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.

M.

Mashington, DC 20037 Hayor, City of Bridgman Post Office Box 366 Bridgman, Hichigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Hichigan 48909 Drinking Mater and Radiological Protection Division Hichigan Department of Environmental guality 3423 N. Hartin Luther King Jr Blvd P. 0.

Box 30630 CPH Hailroom Lansing, Hichigan 48909-8130 Donald C.

Cook Nuclear Plant Hr. Steve J.

Brewer Indiana Hichigan Power Nuclear Generation Group 500 Circle Drive

Buchanan, Hichigan 49107 Hr. E.E. Fitzpatrick, Vice President Indiana Hichigan Power Nuclear Generation Group 500 Circle Drive

Buchanan, HI 49107

MEETING ATTENDEES FOR OCTOBER 22, 1996 D.C.

COOK, UNIT 1, STEAN GENERATOR INSPECTION AND REPAIR PLANS HEETING John B. Hickman Gail H. Marcus Edmund Sullivan Kenneth Karwoski John Tsao Coretta Y. Saadu Cheryl D. Beardslee Steve Brewer John R. Jensen Frank R. Pisarsky John C. Hatarazzo David A. Howell Helita P. Osborne FF IATION NRC, Project Directorate 3-3 NRC, Project Directorate 3-3 NRC, Materials and Chemical Engineering NRC, Materials and Chemical Engineering NRC, Haterials and Chemical Engineering NRC, Materials and Chemical Engineering NRC, Materials and Chemical Engineering AEP, Regulatory Affairs AEP, Engineering and Projects AEP, Production Engineering Westinghouse, Engineering Westinghouse, NSD Westinghouse, NSD Branch Branch Branch Branch Branch ENCLOSURE 1

Unit 1 Steam Generators Inspection/Repair Plans For 1997 Refueling Outage October 22, 1996 NRC Presentation

~

Prepared by: J. R. Jensen Projecf Manager, SG Programs

DISCUSSION TOPICS

~ Objective

~ Overview SG Design

~ Current SG Tube Conditions

~ Overview Last Two Inspections

~ Plans for U1R97

OBJKCTIVK:

Provide the NRC with a status of UIR97 SG Inspection Plan/Repair.

STEAM GENERATOR DESIGN

~ Four Westinghouse Model 51 SGs

~ Alloy600 MillAnnealed Tubing

~ 3388 Tubes Per SG

~ 7/8 Inch Diameter Tubes

~ Carbon Steel Drilled Support Plates

~ Partial Depth Rolled Tubes

STEAM GENERATOR TUBE CONDITIONS n T R

ir SG~It 11 12 13 14 Total Plugged Sleeved 391 306 193 826 180 459 296 374 1186 1839 Equivalent

% Plugged 12.6 9.3 6.3 9.2

STEAM GENERATOR TUBE CONDITIONS Degradation Mechanisms

~ Cold Leg Thinning - TSP

~ Fretting Wear - Anti Vibration Bar

~ ODSCC

- HL-TSC/TTS

- HL-TSP

~ PWSCC

-HL - RT

-Low Row U-bend

STEAM GENERATOR TUBE CONDITIONS Remedial Measures In Place

~ Boric Acid Addition

~ Reduced TemplPress Operation

~ Crevice Flushing

~ Boric Acid Soaks Start-up

~ Use of CarbohydrazidelETA

~ Use of Reverse Osmosis Unit

~ EPRI Chemistry Guidelines

STEAM GENERATOR INSPECTIONS Technique 1994 100%, FL 1995 100%, FL MRPC - 3 Coil Crosswound Cecco - 5 (C-5) 100'/0, HL - TTS 2 Volt IPC 100% Sleeves N/A All HL-ReRolls, F*

All C-5 Indications R1 8 2 U-bends, 1 SG 2-Volt IPC N/A 100%, HL-TTS 100%, Sleeves

STEAM GENERATOR INSPECTION RESULTS Degradation Mechanism CL-TSP AVB Fretting Wear ODSCC

~ HL-TSC/TTS

~ HL-TSP PWSCC

~ HL-RT AU-bend 23 237 42 57 24 828

U1R97 Repair Plan

~ Implement GL 95-05, 2 VoltARC

~ Implement HEJ Revised Repair Boundary ARC

~ Plug Defective Tubes

~ Sleeving contingency

U1R97 INSPECTION SCOPE BC MRPC

~ 3 Coil

~ Plus Point 1 00%,

FL 100%, HL-TTS 100%, HL-RT R1 8 2 U-bend, 1SG 2 VoltARC Sample 100%, In-Service Sleeves

Abbreviafions and Acronyms ARC AVB BC CL ETA Alternate repair criteri Anti-vibrationbars Bobbin coil Cold leg Ethanolamine F

(read as "F-star"); specified minimum distance below fube hard rolltransition which provides structural integrit HEJ HL IPC MRPC Hybrid expansion joint Hot leg Infenm plugging criteria Motorized rotating pancake coil ODSCC Outside diameter stress conosion cracking PWSCC Primary water stress conosion cracking RT SG TSC TSP U¹R9X Roll transition Steam generator Tubesheef crevice Tube support plafe Top-of-tubesheet Unit 1 or 2 refueling outage in 199X

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