ML20037B215
| ML20037B215 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/05/1971 |
| From: | Silver R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML20037B212 | List: |
| References | |
| NUDOCS 8009080606 | |
| Download: ML20037B215 (1) | |
Text
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6, UNITED STATES I'
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ATOMIC ENERGY COMMISSION
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WASHINGTON. D.C. 20545
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. Ziemann, Chief, ORB #2, DRL SAFETY EVALUATION OF PROPOSED CHANGE NO. 22 IDR DRESDEN 1 Proposed Change No. 22 of January 18, 1971, and supple = ental information dated March 24, 1971, would authorize loading up to 120 Type VIII fuel assemblies in the Dresden Unit No. 1 reactor.
Commonwealth Edison (CE) has stated that the design and fabrication specifications of the Type VIII asse=blies are identical to Type VII which were authorized by Change No. 18 dated September 11, 1969. Types VI, VII and VIII assemblies have been fabricated by UNC. Although Docket 50-10 contains no documen-tation regarding the quality assurance (QA) program for UNC f abricated l
Dresden 1 elements, W. Stiede of CE has informed me that CE has 2 men from its construction department who examine UNC's QA program and conduct audits at UNC. Neither man has had prior specific experience with fuel QA.
However, there were no failures of UNC fuel detected after cycle VI and there are no present indications of trouble with UNC fuel.
This f avorable experience provides some assurance that QA for this fuel is adequate.
The loading pattern for cycle VIII is essentially 2-in-4 scatter reload rather than 1-in-4 scatter reload used in cycle VI and VII.
- However, the methods of nuclear and thermal analysis are identical to those used i
in cycle VII and almost identical to cycle VI.
The calculational methods have been successfully checked against measured data. Nuclear and thermal 4
performance predicted by CE will be within presently authorized limits.
Based on the above considerations, we have concluded that operation of Dresden Unit No. I with the Type VIII fuel assemblies as proposed does i
not present significant hazards considerations not described or implicit in the Dresden 1 Safety Analysis Report (Hazards Summary Report) and that there is reasonable assurance that the health and safety of the public will not be endangered.
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j_L R. D. Silver Operating Reactors Branch #2 Division of Reactor Licensing cc:
D. J. Skovholt R. D. Silver R. H. Vollmer R. M. Diggs I
D. L. Ziemann M. Jinks (2) 80090 80 (CP6
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