ML17180B086
| ML17180B086 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/03/1995 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML17180B087 | List: |
| References | |
| TAC-M91099, TAC-M91100, NUDOCS 9502080070 | |
| Download: ML17180B086 (3) | |
Text
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ti Mr. D. L. Farrar Manager, Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite 500 Downers Grove, IL 60515 February 3, 1995 DISTRIBUTION PUBLIC JRoe CMoore JStang ACRS(4)
CHarwood, DISP Docket File RCapra PDIII-2 r/f OGC PHiland,RIII EPoteat, DISP
SUBJECT:
REVIEW OF PLANT-SPECIFIC APPLICABILITY OF GE TOPICAL REPORT NED0-32205-A, REVISION 1 - DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 (TAC NOS. M91099 AND M9ll00)
Dear Mr. Farrar:
In letter dated December 6, 1994, the Commonwealth Edison Company (ComEd) submitted for staff review and approval, its assessment of the plant-specific applicability of General Electric Company's (GE) topical report, NED0-32205-A, Revision l, "10 CFR 50, Appendix G, Equivalent Margin Analysis for Low Upper Shelf Energy in BWR/2 Through BWR/6 Vessels," to its Dresden reactor vessels.
The NRC staff has completed its review of this information.
In the enclosed safety evaluation, the staff has determined that the analyses in the GE topical report NED0-32205-A, Revision 1, are applicable to the Dresden Nuclear Power Station, Unit 2 and 3, reactor vessels.
Based on currently available surveillance data and estimated end-of-license fluence, the vessels should maintain margins of safety against fracture equivalent to those required by Appendix G of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code at the expiration of its license, as required by Appendix G to 10 CFR Part 50 for reactor vessels with upper-shelf energy less than 50 ft-lb.
This completes staff action on TAC Nos. M91099 and M91100.
Docket Nos. 50-237, 50-249
Enclosure:
Safety Evaluation cc w/encl:
see next page Sincerely, original signed by:
Robert A. Capra, Project Director Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation DOCUMENT NAM~*
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OFFICE NAME DATE Mr. D. L. Farrar Manager, Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite 500 Downers Grove, IL 60515 February 3, 1995 DI STR IBUT ION PUBLIC JRoe CMoore JStang ACRS(4)
CHarwood, DISP Docket File RC a pr a PDIII-2 r/f OGC PHiland,RIII EPoteat, DISP
SUBJECT:
REVIEW OF PLANT-SPECIFIC APPLICABILITY OF GE TOPICAL REPORT NED0-32205-A, REVISION 1 - DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 (TAC NOS. M91099 AND M91100)
Dear Mr. Farrar:
In letter dated December 6, 1994, the Commonwealth Edison Company (ComEd) submitted for staff review and approval, its assessment of the plant-specific applicability of General Electric Company's (GE) topical report, NED0-32205-A, Revision 1, 11 10 CFR 50, Appendix G, Equivalent Margin Analysis for Low Upper Shelf Energy in BWR/2 Through BWR/6 Vessels," to its Dresden reactor vessels.
The NRC staff has completed its review of this information.
In the enclosed safety evaluation, the staff has determined that the analyses in the GE topical report NED0-32205-A, Revision l, are applicable to the Dresden Nuclear Power Station, Unit 2 and 3, reactor vessels.
Based on currently available surveillance data and estimated end-of-license fluence, the vessels should maintain margins of safety against fracture equivalent to those required by Appendix G of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code at the expiration of its license, as required by Appendix G to 10 CFR Part 50 for reactor vessels with upper-shelf energy less than 50 ft-lb.
This completes staff action on TAC Nos. M91099 and M91100.
Docket Nos. 50-2-37, 50-249
Enclosure:
Safety Evaluation cc w/encl:
see next page Sincerely, original signed by:
Robert A. Capra, Project Director Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
,/
- \\CMRCJR\\DRESDEN\\DR91099.LTR nclL.E" = Copy with enclosures "N" = No copy D:PDIII-2 e
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02/ Z- /95 02/ 3 /95 02/ /95
D. L. Farrar Commonwealth Edison Company cc:
Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60690 Mr. Thomas P. Joyce Site Vice President Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 Mr. J. Eenigenburg Station Manager, Unit 2 Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 Mr. D. Bax Station Manager, Unit 3 Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 U.S. Nuclear Regulatory Commission Resident Inspectors Office Dresden Station 6500 North Dresden Road Morris, Illinois 60450-9766 Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, Illinois 60532-4351 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Chairman Grundy County Board Administration Building 1320 Union Street Morris, Illinois 60450 Dresden Nuclear Power Station Unit Nos. 2 and 3