ML17179A932
| ML17179A932 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities |
| Issue date: | 06/07/1993 |
| From: | Chandu Patel Office of Nuclear Reactor Regulation |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML17179A933 | List: |
| References | |
| REF-GTECI-046, REF-GTECI-NI, TASK-A-46, TASK-OR TAC-M69442, TAC-M69443, TAC-M69476, NUDOCS 9306100337 | |
| Download: ML17179A932 (4) | |
Text
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June 7, 1993
- Docket Nos. 50-237, 50-249 and 50-254, 50-265 OFC NAME DATE Mr. D. L. Farrar Manager, Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West III, Suite 500 1400 OPUS Place Downers Grove, Illinois 60515
Dear Mr. Farrar:
SUBJECT:
EVALUATION OF DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 AND QUAD CITIES STATION, UNITS 1 AND 2, PROCEDURE FOR DEVELOPING IN-STRUCTURE RESPONSE SPECTRA FOR RESOLUTION OF USI A-46 (TAC NOS. M69442, M69443, M69476, AND M69477)
We have completed the review of the information provided by Commonwealth Edison Company (CECo) by letter dated January 15, 1993, pertaining to the development of in-structure response spectra for Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Station, Units 1 and 2.
Based on our review of the information submitted by you and the information available in the Updated Final Safety Analysis Report (UFSAR), we have concluded that the in-structure response spectra developed by the indicated procedure are acceptable as "conservative, design" for the purpose of verifying the adequacy of equipment.
Our safety evaluation is enclosed.
Also, in your letter dated March 9, 1993, you indicated that CECo is committed to both the implementation guidance and Seismic Qualification Utilities Group (SQUG) commitments in their entirety; including the clarifications, interpretations, and exceptions identified in the SSER-2 with the understanding that any deviations from Generic Implementation Procedure (GIP) will be performed as outlined in Part 1, Section 1.3, of the GIP.
This is acceptable to the staff. If you have any questions concerning this review, please contact me.
Enclosure:
Safety Evaluation cc w/enclosure:
See next page l LA:PDIU:::b I CMOORE L/,fry
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- 0/4/93 Sincerely,
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June 7, 1993 ~
Docket Nos. 50-237, 50-249 and 50-254, 50-265 OFC NAME DATE Mr. D. L. Farrar Manager, Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West III, Suite 500 1400 OPUS Place Downers Grove, Illinois 60515
Dear Mr. Farrar:
SUBJECT:
EVALUATION OF DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 AND QUAD CITIES STATION, UNITS 1 AND 2, PROCEDURE FOR DEVELOPING IN-STRUCTURE RESPONSE SPECTRA FOR RESOLUTION OF USI A-46 {TAC NOS. M69442, M69443, M69476, AND M69477)
We have completed the review of the information provided by Commonwealth Edison Company (CECo) by letter dated January 15, 1993, pertaining to the development of in-structure response spectra for Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Station, Units 1 and 2.
Based on our review of the information submitted by you and the information available in the Updated Final Safety Analysis Report (UFSAR), we have concluded that the in-structure response spectra developed by the indicated procedure are acceptable as "conservative, design" for the purpose of verifying the adequacy of equipment.
Our safety ~valuation is enclosed.
Also, in your letter dated March 9, 1993, you indicated that CECo is committed to both the implementation guidance and Seismic Qualification Utilities Group (SQUG) commitments in their entirety; including the clarifications, interpretations, and exceptions identified in the SSER-2 with the understanding that any deviations from Generic Implementation Procedure (GIP) will be performed as outlined in Part 1, Section 1.3, of the GIP.
This is acceptable to the staff.
If you have any questions concerning this review, please contact me.
Enclosure:
Safety Evaluation cc w/enclosure:
See next page i LA: POI Il::::p i CMOORE 4ftv
- 614/93 Sincerely, OrlgfriaJ Sbn~~ ~ 1t Chandu P. Patel, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation DISTRIBUTION Docket File PDIII-2 r/f JZwolinski CMoore JStang ACRS(lO) iPM:PDIII-2 i JSTANGCffj/
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Mr. D. L. Farrar Commonwealth Edison Company cc:
Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60690 Mr. C. Schroeder Plant Manager 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 Chairman Board of Supervisors of Grundy County Grundy County Courthouse Morris, Illinois 60450 Regional Administrator Nuclear Regulatory Commission, Region III 799 Roosevelt Road, Bldg. #4 Glen Ellyn, Illinois 60137 Illinois Department of Nuclear Safety Utt~te ot Nuclear rac1 l1ty ~atety 1035 Outer Park Drive Springfield, Illinois 62704 Robert Neumann Office of Public Counsel State of Illinois Center 100 W. Randolph Suite 11-300 Chicago, Illinois 60601 Dresden ~uclear Power Station Unit Nos. 2 and 3
Mr. D. L. Farrar Commonwealth Edison Company cc:
Mr. Stephen E. Shelton Vice President Iowa-Illinois Gas and Electric Company P. 0. Box 4350 Davenport, Iowa 52808 Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60690 Mr. Richard Bax Station Manager Quad Cities Nuclear Power Station 22710 206th Avenue North Cordova, Illinois 61242 Resident Inspector U. S. Nuclear Regulatory Commission 22712 206th Avenue North Cordova, Illinois 61242 Chairman Rock Island County Board of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.
Rock Island, Illinois 61201 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road, Bldg. #4 Glen Ellyn, Illinois 60137 Robert Neumann Office of Public Counsel State of Illinois Center 100 W. Randolph Suite 11-300 Chicago, Illinois 60601 Quad Cities Nuclear Power Station Unit Nos. 1 and 2