ML20092L397

Forwards Licensee to NRC Re Recently Detected Steam Generator Leakage.Certificate of Svc Encl.Related Correspondence

ML20092L397
Person / Time
Site:	Three Mile Island
Issue date:	06/27/1984
From:	Churchill B METROPOLITAN EDISON CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To:	Hetrick D, John Lamb, Wolfe S Atomic Safety and Licensing Board Panel
References
CON-DSP-937 83-491-04-OLA, 83-491-4-OLA, OLA, NUDOCS 8406290379
Download: ML20092L397 (5)

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SHAW, PITTMAN, POTTs & TROWBRIDGE A PARTNEmSMir Or PeoFES$iONAL ComPOmATIONS ISOO M STREETe N. W.

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June 27, 1984 WRITE M S DinECT O'AL 8eusseE m (202) 822-1051 BY FEDERAL EXPRESS HAND DELIVERED Sheldon J. Wolfe Dr. David L. Hetrick Administrative Judge Administrative Judge Atomic Safety and Licensing Board Chairman, Atomic Safety and Professor of Nuclear Engineering Licensing Board U.S. Nuclear Regulatory University of Arizona Tucson, Arizona 85271 Commission Washington, D.C. 20555 BY FEDERAL EXPRESS Dr. James C. Lamb, III Administrative Judge Atomic Safety and Licensing Board 313 Woodhaven Road Chapel Hill, North Carolina 27514 In the Matter of Metropolitan Edison Company, Et A1.

(Three Mile Island Nuclear Station, Unit No. 1)

Docket No. 50-289-OLA and ASLBP 83-491-04-OLA (Steam Generator Repair)

Dear Administrative Judges:

For the information of the Hearing Board and the parties, I am enclosing a copy of a letter sent today by Licensee 8406290379 940627 PDR ADOCK 05000289 G PDR n

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' CHAW, PITTMAN, PoTTs & TROWBRIDGE A pamTNERSMip OF pmOFEttecesAL CON 80eAftONS Sheldon J. Wolfe Dr. David L.~Hetrick Dr. James C. Lamb, III June 27, 1984 Page Two to the NRC staf f reporting on steam generator leakage recently detected at TMI-1.

Sincerely, tw h CAucCsill St2 e

Bruce W. Churchill i BWC/pp Enclosure cc: Service List L_

. - I UNITED. STATES OF AMERICA 1 NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board i

)

In the Matter of )

METROPOLITAN. EDISON COMPANY, ET AL. ) Docket No. 50-2 8 9- OLA

) ASLBP 83-491-04-OLA

) (Steam Generator Repair)

(Three Mile. Island Nuclear )

Station, Unit No. 1) ,

1 SERVICE LIST 1 Atomic Safety and Licensing Sheldon J. Wolfe Board Panel Administrative Judge

.U.S. Nuclear Regulatory Commission Chairman, Atomic Safety and

-Licensing Board Washington, D.C. 20555 U.S. Nuclear Regulatory

, Docketing : and Service Section (3)

Commission  %

Office of the Secretary Washington, D.C. 20555 U . S'. Nuclear Regulatory Commission l Dr. David L. Hetrick . Washington, D.C. 20555 Administrative Judge Jodnne,Doroshow, Esq.

Atomic Safety and Licensing B6ard '

Professor of-Nuclear Engineering. Louise Bradford

-Three Mile Island Alert, Inc.

University of Arizona l~

Tucson, Arizona 85271 7+ 3151Peffer Street 17102

- 'Harrisburg, Pennsylvania Dr. James C. Lamb, III Jane Lee Administrative Judge Atomic Safety and Licensing Board 183 Valley Road Etters, Pennsylvania 17319 313 Woodhaven Road >

'i Chapel Hill, North Carolina 27514

Norman Aamodt 3

s R. D. 5, dox 428. ,

Richard J. Rawson, Esq. Coatesville, Pennsylvania 19320 Mary E. Wagner, Esq.

Office of' Executive Legal Director. '

U.S. Nuclear Regulatory Commission'

• Washington, D.C. 20555 '

s ,

3 Atomic Safety and-Licensing Appeal Board Panel U U.S. Nuclear Regulatory Comission (* ,

t Washington, D.C. 20555

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GPU Nuclear Corporation

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=PU luclear Middletown, Pennsy!vania 17057 0191 717 944 7621 TEl.EX 84 2386 ,

Writer's Direct Olal Number:

t 5211-84-2161 l

June 21, 1984

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Office of Nuclear Reactor Regulations Attn: John F. Stolz, Chief Operating Reactors Branch No. 4-  ;

U. S. Nuclear Regulatory Comission Washington, D.C. 20555

Dear Mr. Stelz:

Three Mile Island Nuclear Station, Unit I (TMI-1)

Operating License No. OPR-50 Docket No. 50-289 l THI-1 Steam Generator Leakage Testing l

This letter is to provide you with additional infonnation now availab the condition of the TMI-1 steam generators.

As you are aware, secondary chemistry data are routinely monit evaluated for trends at TMI-1 as part of our steam d to genera ;

monitoring program.

tritium concentrations, as well as slight decreases "B" steam generator. in ThepH,leakwere foun indicate a small increase in leakage in the ld RCS l

rate was determined to be approximately 1.5 gph under the cu conditions (about'300 psig).  ;

l conditions indicates a primary-(to-secondary leak rate bel '

administrative limit of 7 gphsph), additional investigations of th conducted. '

Bubble tests of tubing abovesteam approximately generators. Onethe tube eleventh (80-45)

Tube tube s f

have been conducted steam in thewas generator "A" identified and "B" as bubbling significantly. By  ;

in the "B" 80-45 has bubbled slightly and intermittantly during past bubble te using stoppers at various levels in the bubbling tube,i it has been determined that primary coolant can pass through a crack ver I

upper tube sheet, then down through the tight tube-to-tubeshee t idiaryof the General Public Utilities Corporation

I '

5211-84-2161 Mr. John F. Stolz .

i Some leakage via comprising the new joint, and into the secondary l tub.e-to-tubesheet system. ill be such joints.

pathways has always been predicted for the mechan plugged before return to service. i fibroscope.

Additional inspection of the leaking joint isli planned d to identify s of the steam us ng a l Drip tests of the "B" lower tubesheet area are also schedu e '

significant leakage contributors, if t any, from lower inf other the lower reg on in ,

generator.

plannedWhile as confirmation the ECT that leakageisisinpast equipment place, the joint, a sample no populat the tube.

tubes will also be monitored.

this week or early next week. i 14 other In the course of performing the highly faintly visib bubble test ng,le, ver sensitive tubes, 6 plugged and 8 unplugged were seen to haveSeven h mis.try tubes i

were in t slight bubble formation.

"A" OTSG (which had no evidence monitoring).

This type ofeptable ofa leakt.ge increa and leakage past the tube-to-tubesheet joint in all cases. sion and the bubbling has been seen in past tests, and is considered to be acc not unexpected for mechanical joints such as the kinetic expanN ial observation mechanical rolled plug.these tubes, but their locations have been noted fo during any future bubble tests. l ted, GPU has Subject to review as further testing andf theexaminations steam generators are comp e concluded that earlier evaluations of acceptability ofo Sincerely.

H.D.Hukkl1 Directce 'J-1

- HDH/MJG/CWS/mle cc: R. Conte C. McCracken H. Silver