ML20196J574
| ML20196J574 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/30/1999 |
| From: | Colburn T NRC (Affiliation Not Assigned) |
| To: | Langenbach J GENERAL PUBLIC UTILITIES CORP. |
| References | |
| GL-92-01, GL-92-1, TAC-MA0578, TAC-MA578, NUDOCS 9907070354 | |
| Download: ML20196J574 (5) | |
Text
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UNITED STATES g
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- s-NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30ess 0001
~ June 30, 1999 Mr. James W. Langenbach, Vice President and Director, TMI.
GPU Nuclear, Inc.
P.O. Box 480
' Middletown, PA 17057
SUBJECT:
CLOSURE OF TAC NO. MA0578 - RESPONSE TO THE REQUESTS FOR INFORMATION IN GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1,
" REACTOR VESSEL STRUCTURAL INTEGRITY," FOR THREE MILE ISLAND, UNIT 1
Dear Mr. Langenbach:
On May 19,1995, the U.S. Nuc! ear Regulatory Commission (NRC) Issued Generic Letter 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural Integrity,"
to holders of nuclear operating licenses. In issuing the GL the staff required addressees of the GL to:
(1) to identify, collect and report any new data pertinent to the analysis of structural integrity of the reactor pressure vessels (RPVs) at their nuclear plants, and (2) to assess the impact of that data on their RPV integrity analyses relative to the requirements of Sections 50.60 and 50.61 to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR 50.60 and 10 CFR 50.61), and to the requirernents of Appendices G and H to Part 50 of Title 10 of the Code of FederalRegulations (Appendices G and H to 10 CFR Part 50).
On November 20,1995, you submbed your initial response to GL 92-01, Rev.1, Supp.1, and
' provided the requested information relative to the structural integrity assessments for Three
' Mile Island, Unit 1. The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its conclusions relative to your response on December 23,1996. However, since the time of the staff's closure letter, the Babcock and Wilcox (B&W) Owners Group has submitted i
additional data regarding the alloying chemistries of beltline welds in B&W fabricated vessels.
j The additional alloying data were submitted in Topical Report BAW 2325, Revision 1, for B&W g
During NRC staff review of a license amendment to revise the pressure-temperature limits of Three Mile Island, Unit 1 (which was issued on October 5,1998), you provided your assessment of the information available for the materials in the reactor pressure vessel at
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Three Mile Island, Unit 1. The staff has reviewed the information that you submitted and
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determined that it adequately reflects the information contained in BAW 2325, Revision 1, for h B&W fabricated RPV welds.
9907070354 990630 PDR ADOCK 05000289 P
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3 J.Langenbach 2
June 30, 1999 As a result of the staff's review of your responses to GL 92-01, Revision 1, GL 92-01, Rev.1, Supp.1, the information provided in su) tort of the pressure-temperature limits license amendment, and the B&W topical report, the staff has revised the information for Three Mile Island, Unit 1, in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2. The new database diskettes are posted on the world-wide-web at a location which is lint:ed to the NRC home page (http://www.nrc. gov /NRR/RVID/index.html). We recommend that you review this information. If the staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID are acceptable for your plant. No additional j
information is necessary with regard to the structuralintegrity assessments. Future submittals on P-T limits, PTS, or upper shelf energy should reference the most current information.
This closes the staff's efforts in regard to TAC No. MA0578. The staff appreciates your efforts in regard to this matter.
Sincerely, original signed by:
Timothy G. Colburn, Senior Project Manager, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289 cc: See next page -
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-J.Langenbach 2
. As a result of the staff's review of your responses to GL 92-01, Revision 1, GL 92-01, Rev.1, Supp.1, the information provided in support of the pressure-temperature limits license amendment, and the B&W topical report, the staff has revised the information for Three Mile Island, Unit 1, in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID
' Version 2.. The new database diskettes are posted on the world wide-web at a location which is linked to the NRC home page (http://www.nrc. gov /NRR/RVID/index.html). We recommend that you review this information. If the staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID are acceptable for your plant. No additional information is necessary with regard to the structural integrity assessments. Future submittals on P-T limits, PTS, or upper shelf energy should reference the most current information.
This closes the staff's efforts in regard to TAC No. MA0578. The staff appreciates your efforts in regard to this matter.
Sincerely,
//.
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Timothy G. Colburn, Senior Project Manager, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289 cc: See next page i
1
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- s Three Mile Island Nuclear Station, Unit No.1 cc:
Michael Ross Director, O&M, TMI
. GPU Nuclear, Inc.
Robert B. Borsum j
. P.O. Box 480 B&W Nuclear Technologies Middletown, PA 17057 Suite 525 1700 Rockville Pike John C. Fornicola Rockville, MD 20852 Director, Planning and Regulatory Affairs -
David J. Allard, Director
{
GPU Nuclear, Inc.
Bureau of Radiation Protection 100 Interpace Parkway Pennsylvania Department of Parsippany, NJ 07054 Environmental Resources P.O. Box 2063 Edwin C. Fuhrer Harrisburg, PA 17120 i
Manager, TMI Regulatory Affairs
)
GPU Nuclear, Inc.
Dr. Judith Johnsrud P.O. Box 480 National Energy Committee Middletown, PA 17057 Sierra Club 433 Orlando Avenue Emest L. Blake, Jr., Esquire State College, PA 16803 Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW.
Peter W. Eselgroth, Region I
]
Washington, DC 20037 U.S. Nuclear Regulatory Commission 475 Allendale Road Chairman King of Prussia, PA 19406 Board of County Commissioners of Dauphin County Dauphin County Courthouse Harrisburg, PA 17120 Chairman Board of Supervisors of Londonderry Township R.D. #1, Geyers Church Road Middletown, PA 17057 Wayne L.'Schmidt Senior Resident inspector (TMI-1) i U.S. Nuclear Regulatory Commission P.O. Box 219 Middletown, PA 17057:
Regional Administrator Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 I
J.Langenbach 2
June 30, 1999 As a result of the staff's review of your responses to GL 92-01, Revision 1, GL 92-01, Rev.1, Supp.1, the information provided in support of the pressure-temperature limits license amendment, and the B&W topical report, the staff has revised the information for Three Mile Island, Unit 1, in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2. The new database diskettes are posted on the world-wide-web at a location which is linked to the NRC home page (http://www.nrc. gov /NRR/RVID/index.html). We recommend that you review this information. If the staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID are acceptable for your plant. No additional information is necessary with regard to the structuralintegrity assessments. Future submittals on P-T limits, PTS, or upper shelf energy should reference the most current information.
This closes the staff's efforts in regard to TAC No. MA0578. The staff appreciates your efforts in regard to this matter.
Sincerely, original signed by:
Timothy G. Colburn, Senior Project Manager, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289 cc: See next page DISTRIBUTION Docket File ACRS KWichman Alee SBajwa PUBLIC RBlough, RI MO'Brien OGC PDI-1 r/f AHiser TColburn BElliot DOCUMENT NAME:
G:\\PDi-1\\TMI-1\\a05781tr.wpd
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To receive a copy of this document, indicate in the box:
"C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy 0FFICE PDI-1/PM l
PDI-1/LA,plf2 M l PDI-1/SC,d11 I
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NAME TColburn P M0'Brieq// /4/49 SBajwa M%
lDATE g fs/99
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