ML19345A460
| ML19345A460 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/01/1966 |
| From: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19345A459 | List: |
| References | |
| NUDOCS 8011210658 | |
| Download: ML19345A460 (2) | |
Text
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O llh SAFETY EVALUATION BY THE RESEARCH AND POWER REACTOR SAFETY BRANCH DIVISION OF REACTOR LICENSING IN THE MATTER OF YANKEE ATOMIC ELECTRIC COMPANY PROPOSED CHANGE NO. 76 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. 76, dated October 20, 1966, requested authorization to change the Technical Specifications attached as Appendix A to License No. DPR-3.
This change would authorize the irradi-ation in Core VI of two previously irradiated stainless steel clad fuel assemblies in place of the two zircalloy clad test assemblies that were irradiated in Core V and scheduled to be recycled in Core VI.
This change was requested because inspection of the test assemblies during the current shutdown indicated that some damage to the stainless steel wrappers had occurred during irradiation in Core V.
Discussion The fuel load pattern for Core VI was authorized by Change No. 74.
This change authorized the irradiation in Region A (Center) of two zircalloy clad fuel assemblies that had previously been irradiated in Core V.
These test assemblies were inspected during the current shutdown to load Core VI, and some damage to the stainless steel wrappers was observed. Since the cause of the damage has not yet been determined, Yankee has decided not to recycle these assemblies in Core VI.
Yankee has proposed to recycle two stainless steel _ clad fuel assemblies in place of the two previously authorized zircalloy clad fuel assemblics. These stainless steel clad assemblies were originally 4.1% enriched, have an average exposure of approximately 13,700 MWD /T, and are essentially identical to the two other assemblics that have been authorized for irradiation in Region A during Core VI.
Yankee has reported that the irradiation of these assemblies will not significantly effect the power distribution or hot channel factors previously evaluated and determined to be satisfactory for Core VI.
There-fore, we believe that the irradiation of the two stainless steel clad assemblies in place of the test assemblies will not significantly affect the safety of reactor operations.
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Conclusion We have concluded that the proposed change does not present significant hazards considerations not described or iniplicit in the hazards sucur.ary
- report, and that there is reasonable assurance that the health and safety of the public will not be endangered.
Original signed bg:
Roger S.Boyd Roger S. Boyd, Chief Research & Power Reactor Safety Branch Division of Reactor Licensing NOV 1 1966 Date:
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