ML17332A886

Summary of 950810 Meeting W/Aep in Rockville,Md to Discuss SG Tube Repair Boundary for Parent Tube Indications in Hybrid Expansion Joint Sleeved Tubes

ML17332A886
Person / Time
Site:	Cook
Issue date:	08/11/1995
From:	Kim T NRC (Affiliation Not Assigned)
To:	NRC
References
NUDOCS 9508170035
Download: ML17332A886 (15)

Text

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~n UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055~1 August 11, 1995 LICENSEE:

American Electric Power Company FACILITY:

D.

C.

Cook Nuclear Plant, Unit 1

SUBJECT:

MEETING

SUMMARY

STEAM GENERATOR TUBE REPAIR BOUNDARY FOR PARENT TUBE INDICATIONS IN HYBRID EXPANSION JOINT SLEEVED TUBES A meeting was held at NRC Headquarters on August 10,

1995, between American Electric Power Company (licensee) and the NRC to discuss the D.

C. Cook, Unit 1, steam generator tube repair boundary for parent tube indications in hybrid expansion joint (HEJ) sleeved tubes in conjunction with the licensee's application, dated August 4, 1995, for an exigent technical specification amendment request.

The licensee and Westinghouse, the licensee's primary contractor for this project, described their proposed repair program in detail including the redefined repair boundary limits for HEJ tube sleeve, Kewaunee's tube sleeve examination with the test results, and the tube inspection program.

The licensee is proposing to revise the technical specifications (TS) to redefine the HEJ sleeved tube repair boundary limits for indications of degradation in the parent tube at or below the upper HEJ hardroll lower transition region of steam generator tubes which have HEJ sleeves installed.

Under the current TS, steam generator tubes with eddy current indications in the area of the hydraulically expanded region of the sleeve attachment joint must be repaired by plugging.

The staff indicated that the new information based on examination results of the tubes removed from Kewaunee provided a stronger basis than prior industry proposals on this subject.

However, there are some questions that remain to be answered:

(1) the comparison/quantification of the chemistry environment between the crevices above and below the hardroll, (2) inherent uncertainties involved in the measurement of the crack locations, and (3) any additional inspection information that could help to establish the crack growth rates, The licensee agreed to provide this information to the staff as it becomes available.

'P508i700$ 5. 9508ii I I

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A list of attendees is provided as Attachment 1.

Attachment 2 contains the non-proprietary portion of the slides presented at the meeting.

If there are any questions regarding this meeting

summary, please contact me at (301) 415-1392.

Original signed by Docket No. 50-315 Attachments:

As stated (2) cc w/att:

See next page Tae Kim, Project Manager Project Directorate III-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation ocket File PUBLIC PD 3-1 Reading H. Phillips J.

Hickman W. Russell/F.

Miraglia R.

Zimmerman J.

Roe E.

Adensam (E-mail)

OGC E. Jordan M. Holmberg, RIII J.

Jacobson, RIII A. Thadani G. Holahan B. Sheron R.

Hermann E. Murphy G. Hornseth J.

Donoghue H. Hayfield A. Hansen S.

Dembek ACRS (4)

B. HcCabe, 017G21.

DOCUMENT NAME:

G:IIWPDO~C (COOK)HEJ)C000810.SUM To receive a copy of this document, Indicate In the boxu C I Copy without attachment/enclosure E

~

Copy with attachment/enclosure "N" Ir No copy

'SEE PREVIOUS CONCURRENCE OFFICE NAME DATE LA 31 r

CJa erson PH: PD31 TJKim dy BC:EMCB*

with comments JStrosnider 08/10/95 D'PD JHa n

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Indiana Michigan Power Company CC:

Regional Administrator, Region III U,S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Attorney General Department of Attorney General 525 West Ottawa Street

Lansing, Michigan 48913 Township Supervisor Lake Township Hall P.O.

Box 818 Bridgman, Michigan 49106 Al Blind, Plant Manager Donald C.

Cook Nuclear Plant 1 Cook Place Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspector's Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire

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

W.

Washington, DC 20037 Mayor, City of Bridgman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol

Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N ~

Logan Street P. 0.

Box 30195

Lansing, Michigan 48909 Donald C.

Cook Nuclear Plant Mr. S.

Brewer American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43215 Mr. E.

E. Fitzpatrick, Vice President Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza

Columbus, OH 43215 April 1995

MEETING ATTENDEES August 10, 1995 NAME T. Kim J.

Hannon R.

Hermann A. Hansen S.

Dembek M. Holmberg E. Murphy G. Hornseth J.

Donoghue J. Strosnider J.

Jensen S.

Brewer J. Williams W. Cullen R. Keating R. Lapides S. Bernhoft S. Katradis L. 2err T. Sutter R. Bennett K. Toth D. Hafer D. Malin K. Arneson AFFILIATION NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC AEP AEP Westinghouse Westinghouse Westinghouse Westinghouse WPSC NUS Corporation STS Bechtel AEPSC AEPSC AEPSC AEPSC WEPCo ATTACHMENT 1

DONALD C. COOK NUCLEAR PMXT UNIT 1 STEAM GENERATOR TUBE REPAIR BOUNDARY FOR PARENT TUBE INDICATIONSIN HEJ SLEEVED TUBES August 10, 1995 ATTACHl"1ENT 2

AGENDA Introduction Overview of Repair Program Eewaunee Sleeve Tube Sample Results S. J. Brewer J. R. Jensen J. F. Williams Sleeve Repair LimitDevelopment R. F. Keating Inspection Program Summary NRC Feedback J. R. Jensen J. R. Jensen

PLANT STATUS REFUELING OUTAGE SCHEDULE Originally planned to start September 15, 1995 Transformer failure moved start date to August ll, 1995 Rescheduled steam generator activities Eddy current starts about August 20, 1995 Tube repair starts about August 29, 1995

MEETING OBJECTIVE Discuss technical basis of Donald C. Cook Nuclear Plant Unit 1 submittal Present HEJ tube sleeve redefined repair boundary limits Present supporting Kewaunee HEJ tube sleeve examination and test results

PLANT STATUS Currently 1840 HEJ tube sleeves installed SGll 827 SG12 180 SG13 459 SG14 374 Current cumulative level of plugging, 9.6%

SGl1 12.8%

SG12 9.2%

SG13 - 7.6%

SG14-8.9%

REASONS FOR TlS REQUEST Maintain serviceable HEJ sleeved tubes inservice Continue to maintain S/G plugging levels

~ Tube Hydraulic Expansion Upper Transition (HEUT) 3 Sleeve l

Hardroll Upper Transition (HRUT)

Hardroll i

Hardroll Lower Transition (HRLT)

Bottom of the transition.

Hydraulic Expansion Hydraulic Expansion Lower Transition (HEL'T) h l

Repair Boundary for HEJ Sleeved Tubes HRUT 1.1" below the bottom of the BRUT.

Roll Expanslon I

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I Existing repair limits apply to the parent tube and the sleeve.

We are asking to extend this much.

Currently up to this point.

Revised repair limitboundary applies to sleeve only.

'. --=- -.)

Repair limits

.:. applyto the sleeve 8 tube.

~ INSPECTION PROGRAM The NDE program for tive next outage willinclude 100% inspection of all HEJ sleeved tubes using the Cecco-5 probe with location characterization using the 3-coil RPC.

o Cecco-5 has been qualified to EPRI Appendix H guidelines and is consistent with industry practice.

~ Qualification testing indicates 100% detection of circumferential and axial Qaws >50% deep Cecco-5 can be used for location characterization also, but additional testing would be required to establish consistent capabilities as 3-coil for location characterization o 3-coil RPC used only for location determination of flaws with regard to bottom of hardroll upper transition 0.080" coil diameter of 3-coil RPC probe should be less sensitive to geometric discontinuities of hardroll than other surface riding probes

> Uncertainty of 0.06" is applied to the 3-coil RPC inspection

~ APPLICATION OF THE BOUNDARYLEAKAGE For tubes with postulated 360" throughwall degradation located >1.1 inch but <1.3 inch below the bottom of the hardroll upper transition; o A bounding SI B leakage allowance of 0.033 gpm per tube willbe applied.

o This allowance applies to all tubes left in service by application of the rede6ned tube repair boundary.

o Established by applying a safety factor of 2 to the largest test result for severance -1.12" below the bottom of the HRUT.

o Faulted loop leakage limitof 12.6 gpm willconsider both HEJ and IPC tubes.

o "Across the board" allowance is conservative.