ML20046C640
| ML20046C640 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/21/1993 |
| From: | Colburn T Office of Nuclear Reactor Regulation |
| To: | Gipson D DETROIT EDISON CO. |
| References | |
| GL-88-11, GL-92-01, GL-92-1, TAC-M83463, NUDOCS 9308110278 | |
| Download: ML20046C640 (3) | |
Text
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July 21, 1993 I
Docket No. 50-341 Mr. Douglas R. Gipson DISTRIBUTION:
Senior Vice President Docket File CJamerson Nuclear Generation NRC & Local PDRs SSheng Detroit Edison Company PD 3-1 Reading File CFairbanks 6400 North Dixie Highway JRoe JStrosnider Newport, Michigan 48166 JZwolinski DMcDonald WDean' OGC
Dear Mr. Gipson:
TColburn ACRS (10)
WShafer, RIII cci
'nt Service List
SUBJECT:
RESPONSE TO GENERIC LETTER (GL) 92-ui, REVISION 1, " REACTOR VESSEL STRUCTURAL INTEGRITY," FERMI-2 (TAC NO. M83463)
The subject GL was issued on March 6, 1992, to compile information necessary to confirm that licensees and permit holders satisfy the requirements for ensuring reactor vessel integrity.
In the GL, the staff requested responses to three-i questions. These three questions requested that information be provided regarding:
- 1) Appendix H to 10 CFR Part 50, 2) Appendix G to 10 CFR Part 50, and 3) Commitments _.
made in responses to GL 88-11.
By [[letter::NRC-92-0074, Forwards Response to Rev 1 to Generic Ltr 92-01 Re Reactor Vessel Structural Integrity.All Reactor Pressure Vessel Shell Plates,Used in Fabrication of Reactor Pressure Vessel, Were ASME SA 533-65,Grade B|letter dated June 30, 1992]], Detroit Edison Company (DECO) responded to GL 92-01, Revision 1, by providing the information requested in the Required Information portion of the GL. The staff has completed its initial review of your response and has determined that additional information is needed.
Enclosed is a request for additional information (RAI).
We request that the response to the RAI be provided within 60 days from receipt of this letter.
The information requested by this letter is within the scope of the overall burden estimated in GL 92-01, Revision 1, " Reactor Vessel Structural Integrity,10 CFR
~
50.54(f)." The estimated average number of burden hours is 200 person hours for each addressee's response. This estimate pertair.> only to the identified response-related matters and does not include the time regaired to implement actions required by the regulations.
This action is covered by ti.2 Office of Management and Budget i
Clearance Number 3150-0011, which expires June 30, 1994.
Sincerely, ORIGINAL SIGNED SY Timothy G. Colburn, Sr. Project Manager Project Directorate III-l' Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation i
Enclosure:
Request for Additional Information cc w/ enclosure:
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See next page 0FFICE LA:PDIII-1, PM:PDIII-l PD:PDIII-l amersch Kohb ' h an d 9308110278 930721 1
p DATE 7 /II/93 h 7 //6/93
'7 /Zlf93 DR ADOCK 0500 COPY fffS/N0 YOyN0 YES/NO f
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Mr. Douglas R. Gipson Fermi-2 Detroit Edison. Company cc:
John Flynn, Esquire Senior Attorney Detroit Edison Company l
2000 Second Avenue i
Detroit, Michigan 48226 Nuclear Facilities and Environmental i
Monitoring Section Office Division of Radiological Health t
Department of Public Health 3423 N. Logan Street P. O. Box 30195 Lansing, Michigan 48909 Mr. Wayne Kropp U.S. Nuclear Regulatory Commission Resident Inspector Office t
6450 W. Dixie Highway Newport, Michigan 48166 Monroe County Office of Civil Preparedness 963 South Raisinville Monroe, Michigan 48161 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. William E. Miller Director - Nuclear Licensing Detroit Edison Company Fermi-2 6400 North Dixie Highway Newport, Michigan 48166 l
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FERMI-2 ENCLOSURE i
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4 REQUEST FOR ADDITIONAL INFORMATION FERMI-2 GENERIC LETTER 92-01, REVISION 1, TAC NO. M83463 Ouestion 2b in GL 92-01 I
Your response indicates that data from the drop weight test and Charpy test for beltline materials is either absent or incomplete for initial RT, determination.
1 uo An alternative method developed by General Electric (GE) was ied in deriving the j
initial RT,33 for these materials.
In the GE method, the establishment of the i
i slope for the transition zone of the Charpy curve is crucial in deriving the t
initial RT,3, from incomplete test' data.
Provide all plate and weld Charpy test curves compiled by GE for establishing the 2*F per ft-lb slope from materials t
equivalent to (i.e., same vendor, fabrication time frame, fabrication process, i
material specification, etc.) the beltline materials of this-reactor vessel.
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