ML19347C523
| ML19347C523 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/12/1963 |
| From: | Bryan R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19347C522 | List: |
| References | |
| NUDOCS 8011200093 | |
| Download: ML19347C523 (2) | |
Text
e UNITED STATES ATO"IC ENERGY C0\\ MISSION HA:'ARDS ANALYSIS BY THE RESEARCH AND POWER REACTOR SAFETY BRANOl DIVISION OF LICENSING AND REGULATION IN THE MATTER OF
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YANKEE ATOMIC ELECTRIC COMPANY
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b PROPOSED QMNGE NO. 44 DOCKET NO. 50-29 i
Introduction Pursuant to the provisions of Section S0.59 of the Commission's
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regulations, Yankee Atomic Electric Company in a letter to the Com-
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mission dated August 30, 1963, requested authorization of Proposed Change No. 44 in the Technical Specifications attached as Appendix A to Facility License No. DPR-3.
His Proposed Change would provide for the installation of a fuel assembly storage rack in the reactor fuel trans fer pit. The rack would have space for the storage of 26 fuel element assemblies.
Discussion Change No. 37 was recently issued authorizing the installation of a new storage rack with positions for 110 assemblies. When this new storage rack was delivered to the reactor site, it was found to have numerous but small weld defects.
Yankee has reported that these defects cannot be repaired in time for the second reactor refueling when use of I
the storage rack would be required.
Accordingly, they have requested authorization to install and use a smaller capacity rack which would provide space for the storage of 26 fuel assemblies.
The smaller fuel element storage rack which Yankee is now request-ing authori:stion to install would rely on the spacing of the fuel elements to prevent the inadvertent attainment of criticality. The
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fuel elements would have a center to center spacing of 13.75" and would be physically constrained so that the surface to surface distance
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between adjacent fuel assemblies is at least 5.5".
Yankee has calcu-lated the keffective of unirradiated 4.1% enriched uranium fuel (the highest enrichment presently used) in the storage racks to he.725 and has determined that keffective will be below.88 for any fuel likely to be used in the Yankee reactor. We believe that the results of these calculations in conjunction with the neutron monitoring requirements presently in effect regarding loading fuel into storage racks are ade-cuate to ensure that criticality will not be inadvertently attained while using the proposed new rack.
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Conclusion u.:
Based on the above, we have concluded that Proposed Change No. 44
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does not present significant hazards considerations not described or
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h'e have further concluded that
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there is reasonable assurance that the health and safety of the public will not be endangered.
C" :' f: :d t) T..1 H. :ry'3 Robert H. Bryan, Chief Research 5 Power Reactor Safety Branch Division of Licensing 5 Regulation Date: $E?12 E03
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