ML20002A304
| ML20002A304 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/16/1965 |
| From: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML20002A302 | List: |
| References | |
| NUDOCS 8011110618 | |
| Download: ML20002A304 (2) | |
Text
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UNITED STATES ATOMIC ENERGY CG9tISSION SAFETY EVALUATION BY THE RESEARCH AND POWER REACTOR SAFETY BRANCH DIVISION OF REACTOR LICENSING IN THE MATTER OF YANKEE ATG(IC ELECTRIC CGIPANY PROPOSED CHANGE No. 65 DOCKET NO. 50-29 Introduction Pursuant to the provisions of Section 50.59 of the Commission's regulations, Yankee Atomic Electric Company in Proposed Change No. 65, dated June 23,
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1965, requested authorization of a change in the Technical Specifications attached as Appendix A to License No. DPR-3.
This proposed change would authorize the use of two stainless steel clad silver-indium-cadmium control rods to evaluate the corrosion resistance of the cladding in the borated primary coolant environment.
Discussion The Yankee control system presently contains 22 hafnium control rods and two
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inconel-clad silver-indium-cadmium (Ag-In-Cd) control rods.
These control rods are exposed to the environment of the primary coolant and the corrosion resistance properties of Ag-In-Cd require the use of a protective cladding of inconal. Yankee has reported that the corrosion re'sistance s,f_ stainless i
steel may be superior to inconel in the presence of boric acid, and.has pro.-
posed to evaluatedtwo prototype stainless steel clad Ag-In-Cd contr61 rods.
The control rods to be replaced by the prototype units will be determined following inspection of the control rods presently in service during the Core V refueling shutdown.
The reactivity worth and external dimensions of the prototype stainless steel clad control rods will be similar to the inconel clad control rods presently in service (the thickness of the stainless steel cladding is 0.030 inch).
Stainless steel is widely used in reactors, including use as a cladding for c'ontrol rods, and its use for this purpose in tha Yankee reactor should present no significant safety problems.
Therefore, we believe that the safety of reactorroperations t wil1<act be; adversely :af fected by 'thiscchange.
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2-Conclusion We have concluded that the Proposed Change does not present significant hazards considerations not described or implicit in the hazards summary report, and that there is reasonable assurance that the health and safety of the public will not be endangered.
Original signed by:
Roger S.Bc;d Roger L. Boyd, Chief Researc t & Power Reactor Safety Branch Division of Reactor Licensing Date:
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