ML20212L006

Discusses GL 97-06 Issued by NRC on 971231 & Gpu Response for Three Mile Island .Staff Reviewed Response & Found No New Concerns with Condition of SG Internals or with Insp Practices Used to Detect Degradation of SG Internals

ML20212L006
Person / Time
Site:	Three Mile Island
Issue date:	10/01/1999
From:	Colburn T NRC (Affiliation Not Assigned)
To:	Colburn T GENERAL PUBLIC UTILITIES CORP.
References
GL-97-06, TAC-MA0954, NUDOCS 9910070127
Download: ML20212L006 (4)

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. , \ October 1, 1999 i Mr. Jim:s W. Langenbach, Vice Prrsid:nt I cnd DirIctor, TMI J GPU Nuclear, Inc.  ;

P.O. Box 480 )

Middletown, PA 17057 '

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SUBJECT:

THREE MILE ISLAND NUCLEAR GENERATING STATION UNIT 1 RE: 1 CLOSEOUT OF GENERIC LETTER 97-06, " DEGRADATION OF STEAM l

GENERATOR INTERNALS" (TAC NO. MA0954)

Dear Mr. Langenbach:

On December 31,1997, the staff issued Generic Letter (GL) 97-06, " Degradation of Steam Generator Internals." The purpose of GL 97-06 was to obtain information that would enable the staff to verify that the condition of licensees' steam generator internals complies with and l conforms to the current licensing bases for their respective facilities. By letter dated March 30, I 1998, you responded to GL-97-06. The staff's review of your response to the GL did not identify any new concerns with the condition of the steam generator internals. The staff did not  ;

identify any concerns with the inspection practices employed at your facility to detect degradation of steam generator internals. The staff, therefore, concludes that your response to the GL provides reasonable assurance that the condition of your steam generator internals are l In compliance with the current licensing bases for your facility. j The detailed technical basis that supports the staff's determination for all facilities will be published in a NUREG report expected to be published in December 1999. This completes the staff's effort on TAC No. MA0954. For clarity, the staff notes that it is still evaluating your July 30, and August 20,1999, responses to the staff's request for additional information regarding the once-through steam generator kinetic expansion region inspection acceptance l criteria. This issue is not considered by the staff to be within the scope of GL 97-06.

Sincerely, Original signed b/:

Timothy G. Colburn, Sr. Proj ect Manager, Section 1 Project Directorate i Division of Licensing Proje:t Menagernent Office of Nuclear Reactor Regulation Docket No: 50-289 I cc: See next page 40FRF M iN W /

O DISTRIBUTION: Docket File ACRS ESullivan SCoffin PDI-1r/f ' PUBLIC MOprendek, RI MO'Brien TColburn GWunder CBeardslee OGC l

SBajwa D DOCUMENT NAME: G:\PDI-1\TMI-1\Ltra0954.wpd *See Previous Concurrence

! To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with ettachment/ enclosure "N" = No copy ,

OFFICE PDI-1/PM M lE PDI-1/LA ff[f,(/,Q- l PDI 1/SC M l EMCB/SC* l NAME TColburn:1ci J0'Brien 4'// / " 5Bajwa )Y%' ( ESullivan DATE 3'/'99 Mf//99 3 /#/ /99 09/23/99 0FF1ClAL RECORD CDPY

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9910070127 991001 PDR ADOCK 0 l

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.," October 1, 1999 i Mr. Jim:s W. Lang:nb ch, Vics Presid:nt

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cnd Dir:ctor, TMl GPU Nuclear, Inc. I P.O. Box 480 Middletown, PA 17057. ,

l

SUBJECT:

THREE MILE ISLAND NUCLEAR GENERATING STATION UNIT 1 RE:

CLOSEOUT OF GENERIC LETTER 97-06, " DEGRADATION OF STEAM l GENERATOR INTERNALS" (TAC NO. MA0954) l l

Dear Mr. Langenbach:

l l

On December 31,1997, the staff issued Generic Letter (GL) 97-06," Degradation of Steam Generator Internals." The purpose of GL 97-06 was to obtain information that would enable the staff to verify that the condition of licensees' steam generator internals complies with and j conforms to the current licensing bases for their respective facilities. By letter dated March 30,  ;

1998, you responded to GL-97-06. The staff's review of your response to the GL did not identify any new concerns with the condition of the steam generator internals. The staff did not identify any concerns with the inspection practices employed at your facility to detect degradation of steam generator internals. The staff, therefore, concludes that your response to i the GL provides reasonable assurance that the condition of your steam generator internals are in compliance with the current licensing bases for your facility.

1 The detailed technical basis that supports the staff's determination for all facilities will be l published in a NUREG report expected to be published in December 1999. This completes the  ;

staff's effort on TAC No. MA0954. For clarity, the staff notes that it is still evaluating your 1 July 30, and August 20,1999, responses to the staff's request for additional information regarding the once-through steam generator kinetic expansion region inspection acceptance criteria. This issue is not considered by the staff to be within the scope of GL 97-06.

Sincerely, Original signed by:

Timothy G. Colburn, Sr. Project Manager, Section 1 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No: 50-289 cc: See next page DISTRIBUTION: Docket File ACRS ESullivan SCoffin PDI-1r/f PUBLIC MOprendek, RI MO'Brien TColburn GWunder CBeardslee OGC SBajwa ,

DOCUMENT NAME: G:\PDI-1\TMI-1\Ltra0954.wpd *See Previous Concurrence To receive a copy of this document, indicate in the box: "C" = Copy without attachment /enclosuro "E" = Copy with cttachment/ enclosure "N" = No copy ,

OFFICE PDI-1/PM M. l E PDI-1/LA[t/M//) l PDI-1/SC M l EMCB/SC* l NAME TColburn:1cc M,0'Brien W// / " SBa]wa .) W ( ESu111 van DATE g //99 L/XU99 /F/ /99 - 09/23/99 0FFICIAL RECORD COPY l

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.....p October 1, 1999 Mr. James W. Langenbach, Vice President and Director, TMI GPU Nuclear, Inc.

P.O. Box 480 Middletown, PA 17057

SUBJECT:

THREE MILE ISLAND NUCLEAR GENERATING STATION UNIT 1 RE:

CLOSEOUT OF GENERIC LETTER 97-06, " DEGRADATION OF STEAM GENERATOR INTERNALS" (TAC NO. MA0954)

Dear Mr. Langenbach:

l l

On December 31,1997, the staff issued Generic Letter (GL) 97-06, " Degradation of Steam '

Generator Internals." The purpose of GL 97-06 was to obtain information that would enable the staff to verify that the condition of licensees' steam generator internals complies with and conforms to the current licensing bases for their respective facilities. By letter dated March 30, 1998, you responded to GL-97-06. The staff's review of your response to the GL did not identify any new concerns with the condition of the steam generator internals. The staff did not identify any concerns with the inspection practices employed at your facility to detect degradation of steam generator internals. The staff, therefore, concludes that your response to l

the GL provides reasonable assurance that the condition of your steam generator internals are l in compliance with the current licensing bases for your facility. )

The detailed technical basis that supports the staff's determination for all facilities will be published in a NUREG report expected to be published in December 1999. This completes the staff's effort on TAC No. MA0954. For clarity, the staff notes that it is still evaluating your July 30, and August 20,1999, responses to the staff's request for additional information regarding the once-through steam generator kinetic expansion region inspection acceptance criteria. This issue is not considered by the staff to be within the scope of GL 97-06.

Sincerely, l b

Timothy G. Colburn, Sr. Project Manager, Section 1 Project Directorate l l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No: 50-289 cc: See next page i

fi , i. \ l' ljl Thrre Mils Island Nucl::r Station, Unit No.1

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! cc:

l' ' Michael Ross David J. Allard, Director Director, O&M, TMl Bureau of Radiation Protection GPU Nuclear, Inc. Pennsylvania Department of 4 P.O. Box 480 Environmental Resources Middletown, PA 17057 P.O. Box 2063  ;

John C. Fornicola Director, Planning and Dr. Judith Johnsrud l Regulatory Affairs National Energy Committee ,

GPU Nuclear, Inc. Sierra Club i 100 Interpace Parkway 433 Orlando Avenue Parsippany, NJ 07054 State College, PA 16803 Edwin C. Fuhrer Peter W. Eselgroth, Region I l Manager, TMI Regulatory Affairs U.S. Nuclear Regulatory Commission.

GPU Nuclear, Inc. 475 Allendale Road P.O. Box 480 King of Prussia, PA 19406 Middletown, PA 17057

~ Ernest L. Blake, Jr., Esquire Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW. l Washington, DC 20037 l Chairman Board of County Commissioners . .

of Dauphin County I Dauphin County Courthouse i Harrisburg, PA 17120 Chairman Board of Supervisors of Londonderry Township R.D. #1, Geyert Church Road Middletown, PA 17057 Wayne L. Schmidt Senior Resident inspector (TMI-1)

U.S. Nuclear Regulatory Commission P.O. Box 219 Middletown, PA 17057

. Regional Administrator

. Region i U.S. Nuclear Regulatory Commission

, 475 Allendab Road King of Prussia, PA 19406 Robert B. Borsum B&W Nuclear Technologies I Suite 525 1700 Rockville Pike Rockville, MD 20852 l J