ML17326B263

Summary of 860916 Meeting W/Utils & Westinghouse Re Steam Generator Corrosion Rate & Replacement Program.Viewgraphs & Attendees List Encl

ML17326B263
Person / Time
Site:	Cook
Issue date:	09/18/1986
From:	Wigginton D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8609230082
Download: ML17326B263 (15)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 18 sEP iM6 E

Docket No.

50-316 LICENSEE:

FACILITY:

SUBJECT:

Indiana and Michigan Electric Company Donald C.

Cook Nuclear Plant, Unit No.

2

SUMMARY

OF MEETING HELD ON SEPTEMBER 16 s 1986 WITH INDIANA AND MICHIGAN ELECTRIC COMPANY, AMERICAN ELECTRIC POWER SERVICE CORPORATION (AEPSC)

AND WESTINGHOUSE (W)

TO DISCUSS THE UNIT 2 STEAM GENERATORS CORROSION RATE A~EPLACEMENT The staff met with the licensee and representatives of AEPSC and W to discuss the results from the 1986 refueling outage examination of the steam generator tubes and replacement program of the steam generators.

The list of attendees is attached as Enclosure 1.

The licensee and representatives made their presentations from viewgraphs.

The non-proprietary viewgraphs, are attached as Enclosure 2.

The viewgraphs claimed by W to be proprietary have'-been separately docketed and the licensee has been requested to formally resubmit both a proprietary and non-proprietary set for appropriate handling and review.

The principal investigations of steam generator tube degradation were performed in 1985 and 1986.

The results were not directly comparable by the number of tubes plugged because the tube plugging criteria were changed.

The licensee presented the results of studies and tests to support the new criteria.

The licensee also compared the 1985 data against the 1986 criteria and determined that the rate of degradation has substantially decreased.

From a preliminary review of the licensees presentation, the staff feels that the licensee understands the tube degradation and has sufficient control of the contributing factors that operation thru the remainder of the fuel cycle without further testing can be permitted.

The licensee was requested to submit their evaluations formally so that a review can be performed.

If the rate of degradation continues, the eventual solution to tube failures may be steam generator replacement.

Cook plans to use the loop cut replacement technique wherein the steam generator is cut in two pieces with the upper portion and its internals to be refurbished and reused.

The lower portion with steam generator tubes will be stored on site.

A second 150 ton crane will be installed to handle the steam generator parts.

The licensee has purchased a

Model 54F from Westinghouse which features inconel 690 thermally treated

tubes, three anti-vibration bars rather than two, flow distribution baffles to reduce sludge 8609~~0082 86o9x8 Wl, PDR

• DOCK '0500031 6(

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buildup, fully expanded tubes in the tubesheet, and about 6X more thermal, capacity than the original steam generators.

A preliminary schedule for replacement in 1988 has been developed but is not firm.

These and other details are expected in the Steam Generator Repair Report due to be submitted by the licensee in the near future.

Enclosure:

As stated D.W. Wigginton, Project Manager PWR Project Directorate ¹4 Division of PWR Licensing-A PWR¹4 PWR-A DWigginton/rad 09/ g/86 PWR¹4/

PWR-A BJYoungblood O9/lP/86

Lg)i F'i, I

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MEETING

SUMMARY

DISTRIBUTION 18 SEP 1986 Docket File NRC PDR L PDR NSIC PRC System PWR¹4 Reading File DWigginton M. Duncan OGC J. Partlow E. Jordan B. Grimes ACRS (10)

NRC Participants ee E. Sullivan C.Y.

Cheng D. Neighbors L.B. Marsh R. Serbu bcc:

Licensee 8 Service List

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buildup, fully expanded tubes in the tubesheet, and about 6X more thermal capacity than the original steam generators.

A preliminary schedule for replacement in 1988 has been developed but is not firm.

These and other details are expected in the Steam Generator Repair Report due to be submitted by the licensee in the near future.

Enclosure:

As stated D.

Wigg n, Project Manager PWR Project Directorate P4 Division of PWR Licensing-A

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I Enclosure 1

D.C.

Cook Steam Generator Meeting September 16, 1986 NAME igginton S.

Lee E. Sullivan C.Y.

Cheng S.

Brewer T. Harshbarger James G. Feinstein G. Whiteman K. Huffman D. Hafer J.

Kobrya S.

Brown M.P. Alexich K.F. Matthews F. Scapellato R.C. Bilyeu C.D. Sellers W.R. Greenaway D. Neighbors P. Kokolakis P. Peloquin S.D.

Routh L.B. Marsh R.J.

Serbu ORGANIZATION KWl%H NRR-PWR-A-EB NRR-PWR-A-EB NRR-PWR-B-EB AEPSC-Manager Rod Support AEPSC-Rad Support Enc.

AEPSC-Manager NSSL W-NS U-NDE Center 7KPSC-Asst.

Manager Heat Exchange AEPSC-Med Staff Engineer W-NDE Center RP Service Corporation W-NS 9-Nuclear Safety Virginia Power, Richmond NRC-PWR-A-EB NUS NRR-PAD3 NYPA NYPA Bechtel-EPC NRR-DPLB-EB NRR-DPLA-PSB

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Propoeed Ccecrete Removal For S/G Replacement Unit 2 Steam Generator Enclosure, Piping, and Shell Plate Cut Locations Mafn S Pipe Cut Lfne Feedwater Pipe Cut Une S/G Mell Plate Cut Une Primary Loop Plp Cu

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~ t Steam Generator Repair Report Table of Contents Section 1

Introduction Section 2 Replacement Component Design Section 3 Repair Program Section 4 Plant Security Section 5 Quality Assurance Section 6 Safety Evaluation and Analysis of Significant Hazards Consideration Section 7 Environmental Report

STEPS NECESSARY TO OBTAIN A LICENSE AMENDMENT FOR THE UNIT' STEAM GENERA.VOR AEPAIA NRC Issues License Amendment NRC Staff Prepares Draft and Final Environmental Impact Statements and Safety Evaluation Reports NRC Publishes Notice of the Proposed Issuance for the Amendment to the License in the Federal Register

. Submit Appllcatlon for License Amendment-and the Steam Generator Repair Report, Including Analysis of the Issue of No Significant Hazard Concerns to the Nuclear Regulatory Commission Determined that the Repair Report Should Be Divided into Two Parts:

1) Description of the Repair Activity and Safety Evaluations

2) Environmental Impact Assessments of the Repair Program Reviewed Previous Repair Program Applications for License Amendments and Determined that Previous Applications for License Amendments Included a Document Entitled "Steam Generator Repair Report"

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Pre Qutage Construction Upgrade of Existing Roads and Pyrking Lots Construction of the Site Access

.'ontrol Building Construction of the Fabrication Shop/Warehouse Construction of the Containment Access Building Construction of the Temporary OnSite Steam Generator Lower Assembly Storage Facility

Licensing Milestone Schedule In Support Of The D.C. Cook Steam Generator Repair Program (Beginning August, 1988)

'i/86 3/86 6/86 9/86 12/86 3/87 6/87 9/87 12/87 3/88 6/88 9/88 12/88 3/89 Bega Writi g Ste m

Ge erato Repar Rep Purch sed esting ouse bmit !Steam pplication f R e pl a cern en t Generator R

r Ame'ndmen Begin 'Site Support Rep P alf ttoL eport cense to th NRC tion N

repara ir Project cessa y To Lower Asse ilies C Issues Dr ft En ironm atement 8e afety Evalu ntal I

tion R

pact port NRC Iss S)atem And Lic es Fi nt 8c nse al En afety blend Sta ironm Evalu ent t Out ntal Impact tion Report ge

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