ML20002A371
| ML20002A371 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/16/1963 |
| From: | Case E US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML20002A370 | List: |
| References | |
| NUDOCS 8011140335 | |
| Download: ML20002A371 (2) | |
Text
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.O-z UNITED STATES ATOMIC ENERGY COMMISSION HAZARDS M?ALYSIS BY THE RESEARCH AND PO'ER REACTOR SAFETY BRANCH DIVISION 0? LICENSING AND REGULATION
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IN THE MATTER OF YANKEE ATCMIC ELECTRIC COMPA';Y
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PROPOSED CHANGE NO. 37 DOCKET NO. 50-29 L..;:.+
Introduction Pursuant to the provisions of Section 50.59 of the Com=ission's regulations, hk Yankee Atomic Electric Company in Proposed Change No. 37, dated June 28, 1963,
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requested authorization to increase the storage capability of their Fuel Transfer Pit. Additional information regarding this matter was submitted by Yankee in supplement to Proposed Change No. 37, dated August 13,1963, and in M.::,_
a related letter from Yankee to the Division of Licensing and Regulation, dated August ik,1963.
Discussion The proposed increase in the storage capability of the Puel Transfer Pit
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vould be acco=plished by adding a storage rack with space for 110 fuel assemblies, thereby increasing the capacity of the Fuel Transfer Pit to 190 assemblies. This addition to the storage capacity is required as a result of an agreecent with the Atomic Energy Commission under the terms of which Yankee is to provide storage for spent fuel removed from the Yankee reactor.
Such storage vill minimize handling and shipment prior to future chemicsl reprocessing of the spent fuel.
The proposed new rack is to have a center spacing of 8.78" x 9.5".
Each fuel assembly will be enclosed in a boral sheath to contral the criticality of the fuel elenent array.
The boral, which is approximately.2" thick, consists of 35 veight per cent BgC in an aluminum = atrix and is clad with aluminum.
Yankee has reported that the calculated k effective of the storage f acility is less than.835 for the unirradiated 4.1% enriched uraniu= fuel which vill be utilized by Yankee in Core III, and less than.88 for any fuel anticipated to be used in their reactor. These calculations were made assuming an infinite array of fuel.
In order to provide an additional safeguard against accidental criticality, the neutron count rate vill be monitored at any time when fuel is being added to the storage rack. It is our opinien that if the calculated k effective of the infinite array is maintained belov'.88 and the neutren count rate is =enitored on fuel additica, as proposed by Yankee, there is adequate assurance against the possibility of inadve'rtent criticality while using the proposed fuel storage rack.
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. Conclusion Subject to the condition that the calculated k effective is maintained less than.88, ucing the calculaticnal cethod described in the application, ve have concluded that Proposed Change No. 37 does not present significant hazards considerations not described or icplicit in the hazards suneary report.
'de have further concluded that there is reasonable assurance that the health and safety of the public will not be endangered.
i Edson G. Case, Assistant Director for Facilities Licensing Division of Licensing and Regulation Date:
August 16, 1963
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