ML20037B344
| ML20037B344 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/13/1973 |
| From: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Abel J COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20037B345 | List: |
| References | |
| NUDOCS 8009150613 | |
| Download: ML20037B344 (3) | |
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O SEF p3M Docket No. 50-10 Commonwealth Edison Company I
ATIN:
Mr. J. S. Abel Nuclear Licensing AA=in4 =trator -
Boiling Water Reactors Post Office Box 767 Chicago, Illinois 60690 Change No. 26 Gentlemen:
License No. DPR-2 We have revie4ed your Proposed Change No. 26 dated January 3,1973, and supplement datsd May 4,1973, which would authorize the use of Type IX fuel i
assemblies in Cycle 9 of the Dresden Unit I reactor. According to your plan, up to 50 Type II assemblies will replace an equal nuser of assecielies currently in use.
1 Since the design of Type II fuel is essentially identical to Types VI, i
VII and VIII currently in use, the thermal, hydraulic and nucicar characteristics of the reload core will not be significantly different from previous cores. The accident analyses previcualy performed will, therefore, remain valid and no additicnal evaluation is required by us at this time.
A total of 37 rods in 2 assemblies will use an anodizing process on the zirconium cladding instead of the more typical autoclavinE process. We have reviewed the Gulf United Nuclear proprietary report MIL-9211B submitted with your latter of May 4,1973, which presents justification for the use of anodized Zircaloy 2 clad fuel rods. Although the information relating to the susceptibility to hydriding is limited, the data indicate that anodizing should not have a detrimental effect upon the corrosion resistance or the c.echanical integrity of the cladding over the fuel rod's lifetime. We have, therefore, concluded that the use of anodized zirconiun clad fuel elements in Cycle 9 reload is acceptable. Please provide us with the results of the post-irradiation investigations of these fuel elements.
o 80091 50
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1 Commonwealth Edison Company SEP 131973 isy letter dated liay 16, 1973, ycu have submitted a fuel quality assurance (QA) program in conjunction with your refueling application.
The QA program has delegated the respor.sibility for design review anni quality contrcl to the fuel vendors, while Co:raonwealth retains provisions for the auditing and surveillance of the quality control functions utilized during fuel manufacture. Based on our review, we have found the fuel QA program acceptable.
On the basis of our preliminary review of the Eulf United Nuclear Fuele Corporation (GUuFC) densification model, we have concluded that fuel densification will not affect the Technical Specifications or operating limits of Dresden 1 for cperation with Core IX fuel. Although the fuel densification addendum to the ALC Safety Evaluation Report for Dresden i
1 has not yet been published,ve expect that it will be issued prior to Startup of Core IX.
based on-the above considerations, we have concluded that refueling
'and subsequent operation of the Dresden Unit I reactor with Type IX
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fuel elements does not present a significant hazards consideration and s
' there is reasonable assurance that the health and safety of the public A'
'will not be en.fangered.
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ccordingly, Technical Specifications of Facility License No. DPR-2
'are hereby changed as se* forth in Attachment A to this letter.
I Sincerely,
~
Douald J. Skovholt x
Assistant Director s
for Operating Reactors
~4 Directorate of Licensinc s
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Technical Specifications AEC PDR NDube Branch Reading RMDiggs cc w/ enclosure:
RP Reading RDSilver John W. Rowe, Esquire JRBuchanan JSapir Isham, Lincoln & Beale DJSkovholt Ccuaselors at Law ACRS (16)
One First National Plaza Ro (3)
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Consnonwealth Edison Company 2-By letyer dated liay 16, 1973, you have submitted a fuel quality assurance (QA) program in conjunct 1on with your refueling application.
The QA phogram has delegated the responsibility for design review and quality control to the fuel vendors, while Commonwealth retains provisions f'or the auditing and surveillance of the quality control functions util zed during fuel manufacture. Based on our review, we have found the 1 QA program acceptable.
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Our review has cono uded that fuel densification 11 not affect the Technical Specifica ons or operating limits of the Dresden 1 reactor.
Based on the above e derations, we have con uded that refueling and subsequent operation of the Dresden Unit 1,/ reactor with Type IX fuel elements does not pr ent a significant hazards consideration and there is reasonable assurance that the he'alth and safety of the public will not be andangere'.
Accordingly, Technical Specifi tions of Facility License No. DPR-2 are hereby changed as set forth Attachdant A to this letter.
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Donal J. Skovholt Assist t Director
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for Op ating Reactors Directora of Licensing Distribution Attachnaent & - Change to Specifications /
Dodet Mle ESilver
- Tech'nicaA AEC PDR JSapir cc w/ enclosure:
Branch Reading John W. Rocc, Esquire e ding JRBuchanan e
Ishan, Lincoln L Beale EPA (3)
Counselors at Law /
DJSkovholt One l'irst hational Plaza ACRS (16)
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