ML20132F850
| ML20132F850 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/23/1996 |
| From: | Norris J NRC (Affiliation Not Assigned) |
| To: | James Knubel GENERAL PUBLIC UTILITIES CORP. |
| References | |
| GL-92-01, GL-92-1, TAC-M92741, NUDOCS 9612260113 | |
| Download: ML20132F850 (5) | |
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30E06-0001
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December 23, 1996 Mr. James Knubel Vice President and Director - TMI GPU Nuclear Corporation Post Office Box 480 Middletown, PA 17057-0480
SUBJECT:
CLOSEOUT FOR GPU RESPONSE TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1 FOR THREE MILE ISLAND UNIT 1, (TAC NO. M92741)
Dear Mr. Knubel:
On May 19, 1995, the NRC issued Generic Letter 92-01, Revision 1, Supplement I (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural Integrity."
In GL 92-01, Rev. 1, Supp. 1, the NRC requested that nuclear licensees perform a review of their reactor pressure vessel structural integrity assessments in order "to identify, collect, and report any new data pertinent to [the]
analysis of [the] structural integrity of their reactor pressure vessels (RPVs) and to assess the impact of that data on their RPV integrity ' analyses relative to the requirements of Section 50.60 of Title 10 of the Code of federal Regulatfons (10 CFR 50.60), 10 CFR 50.61, Appendices G and H to 10 CFR Part 50 (which encompass pressurized thermal shock (PTS) and upper shelf energy (USE) evaluations), and any potential impact on low temperature overpressure (LTOP) limits or pressure-temperature (P-T) limits."
More specifically, in GL 92-01, Rev. 1, Supp. 1, the NRC requested that addressees provide the following information in their responses:
(1) a description of those actions taken or planned to locate all data relevant to the determination of RPV integrity, or an explanation of why the existing data base is considered complete as previously submitted; 1
(2) an assessment of any change in best-estimate chemistry based on consideration of all relevant data; (3) a determination of the need for the use of the ratio procedure in accordance with the established Position 2.1 of Regulatory Guide 1.99, Revision 2, for those licensees that use surveillance data to provide a basis for the RPV integrity evaluation; and (4) a written report providing any newly acquired data as specified above and (1) the results of any necessary revisions to the evaluations of RPV 4
integrity in accordance with the requirements of 10 CFR 50.60, 10 CFR 50.61, Appendices 6 and H to 10 CFR Part'50, and any potential impact of the LTOP and P-T limits in the technical specifications, or (2) a certification that previously submitted evaluations remain valid. g h
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James Knubel Revised evaluations and certifications were to include consideration of Position 2.1 of Regulatory Guide 1.99, Revision 2, as applicable, and any new data. The information in Reporting Item (1) was to be submitted within 90 days of the issuance of the GL. The information in Reporting Items (2) - (4) was to be submitted within 6 months of the issuance of the GL.
The staff has noted that GPU submitted the information' requested in Reporting Item (1) on August 16, 1995, and requested in Reporting Items (2) - (4) on i
November 20, 1995. Since GPU has submitted the requested information and has indicated that the previously submitted evaluations remain valid, the staff considers the RPV integrity data for the Three Mile Island, Unit I to be complete at this time and have closed TAC No. M92741 The staff has noted that the most recent reactor vessel integrity assessment for the Three Mile Island, Unit 1 is covered by the scope of Babcock and Wilcox (B&W) Topical Evaluation BAW-2257, Revision 1.
This topical report was the subject of an April 30, 1996 meeting between the staff and representatives of the Babcock and Wilcox Owners Group (BWOG). The topical report indicates that all licensees addressed in the report have determined the best estimate l
copper and nickel contents of their plant's beltline and surveillance welds.
The report also indicates that the ratio procedure described in Position 2.1 (pages 1.99-3 and 1.99-4) of Regulatory Guide (RG) 1.99, Rev. 2, need not be applied to the pressurized thermal shock assessments and upper shelf energy assessments of RPV beltline welds made from Linde 80 fluxes.
At a meeting on April 30, 1996, representatives of the BWOG provided the bases for the conclusions in the topical report. The staff informed the BWOG l
personnel that the information presented was insufficient to support the owners group's proposal. The BWOG representatives indicated that the owners group would consider performing additional work to address the staff's i
concerns, and would consider submitting another topical report for NRC review.
The staff does not consider the BWOG proposal to be acceptable at this time.
The topical report also included analyses to demonstrate that application of the ratio procedure would not cause the RT values for the limiting materialsinB&WfabricatedRPVstoexceedThePTSscreeningcriteria l
specified in 10 CFR 50.61. However, the report did not address potential impact of applying the ratio procedure to the development of pressure-temperature limit curves and L-TOP limits. Therefore, you are requested to provide an assessment of the application of the ratio procedure, as described in Position 2.1 of Regulatory Guide 1.99, Revision 2 (May 1988), to your pressure-temperature limit curves and L-TOP limits. This assessment should include an evaluation relative to the margins specified in applicable codes l
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l James Knubel and standards (i.e., Appendix G to Section III of the ASME Code).
You are requested to provide this assessment by D::cember 31, 1996. Thank you for your cooperation.
Sincerely, J
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an A. Norris, Sr. Project Manager P oject Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-289 1
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James Knubel ' eceder 23, M 6 and standards (i.e., Appendix G to Section III of the ASME Code)..You are requested to provide this assessment by December 31, 1996.
Thank you for your cooperation.
Sincerely,
. (Oricjinal Sig' ed By) ~
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Jan.A. Norris, Sr. Project Manager-4
, Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-289 cc: See next page Distribution Docket File PUBLIC PDI-3 Plant SVarga JZwolinski PMilano JNorris EDunnington OGC ACRS PEselgroth, RI DOCUMENT NAME: G:
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Three Mile Island Nuclear Station, Unit No. I cc:
Michael Ross Robert B. Borsum Director, O&M, TMI B&W Nuclear Technologies GPU Nuclear Corporation Suite 525 P.O. Box 480 1700 Rockville Pike Middletown, PA 17057 Rockville, MD 20852 John C. Fornicola William Dornsife, Acting Director Director, Planning and Bureau of Radiation Protection Regulatory Affairs Pennsylvania Department of GPU Nuclear Corporation Environmental Resources 100 Interpace Parkway P.O. Box 2063 Parsippany, NJ 07054 Harrisburg, PA 17120 Jack S. Wetmore Dr. Judith Johnsrud Manager, TMI Regulatory Affairs National Energy Committee GPU Nuclear Corporation Sierra Club P.O. Box 480 433 Orlando Avenue Middletown, PA 17057 State College, PA 16803 Ernest L. Blake, Jr., Esquire Mr. James Knubel, Vice President Shaw, Pittman, Potts & Trowbridge and Director - TMI-l 2300 N Street, NW.
GPU Nuclear Corporation Washington, DC 20037 P.O. Box 128 Forked River, NJ 08731 Chairman 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 Michele G. Evans Senior Resident Inspector (TMI-1)
U.S. Nuclear Regulatory Commission P.O. Box 311 Middletown, PA 17057 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 l
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