ML17173B005
| ML17173B005 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/25/1979 |
| From: | Janecek R COMMONWEALTH EDISON CO. |
| To: | Oconnor P Office of Nuclear Reactor Regulation |
| References | |
| TASK-09-01, TASK-9-1, TASK-RR NUDOCS 7908010470 | |
| Download: ML17173B005 (2) | |
Text
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e Common91th Edison One First National Plaza, Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 July 25, 1979 Mr. Paul W. 0 'Connor H£CU/A~
Operating Reactors - Branch 2
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Washington, DC 20555 t
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Subject:
Dresden Station Units 1 and 2 Response to Informal Request for Information for Systematic Evaluation (SEP) Topic IX-1, "Fuel Storage" NRC Docket Nos. 50-10/237
Dear Mr. O'Connor:
The following is provided in response to an informal request for information concerning the SEP review of new fuel storage areas for Dresden Units 1 and 2 (SEP Topic IX-1).
Dresden 1 Question 1:
How is the Keff verified?
How often is it verified?
Response
The Keff for Dresden 1 was pre-established and is maintained by spacing.
Question 2:
What features can be used to detect a criticality in the new fuel storage area?
Are there alarms associated with these features?
Response
A gamma sensitive monitor is installed in the Dresden 1 new fuel storage area and alarms in the control room.
Question 3:
What U-235 enrichment (or gm U-235/cm
Response
of fuel assembly) was assumed in the criticality analysis of the new fuel racks?
This information is not readily available.
If the information is necessary for your further evaluation, it may be possible to obtain it from the General Electric Co.
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Commonwealth Edison NRC Docket Nos. 50-10/237 Mr. Paul W. O'Connor:
2 -
July 25, 1979 Question 4:
What features prevent flooding of the new fuel racks?
Response
The new fuel storage area is located 3 feet above grade elevation, is in a separate room, and there are no water sources in the room.
Dresden 2 Question 1:
How is the Keff verified?
How often is it verified?
Response
The Keff value was pre-established and is maintained by spacing.
Question 2:
What U-235 enrichment (or gm U-235/cm of fuel assembly) was assumed in the criticality analysis of the new fuel racks?
Response
- This information is not readily 2vailable.
If the information is necessary for your further evaluation, it may be possible to obtain it from the General Electric Co.
Question 3:
Where does the storage vault radiation monitor read out? Alarm?
Response
The monitor has a read out and alarm in the main control room.
Please address any additional questions you may have concerning this matter to this office.
Very truly yours,
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.["_;;*-f.r_,.. f;t..* *... --:..:..--<-C'~**C Robert F./Janecek Nuclear Licensing Administrator Boiling Water Reactors