ML20235P557
| ML20235P557 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/10/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235P552 | List: |
| References | |
| NUDOCS 8707200527 | |
| Download: ML20235P557 (3) | |
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UNITED STATES o
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NUCLEAR REGULATORY COMMISSION c
W ASHINGT ON, D. C. 20555
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i SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.107 TO FACILITY OPERATING LICENSE NO. DPR-51 ARKANSAS POWER AND LIGHT COMPANY ARKANSAS NUCLEAR DHE, UNIT NO. I DOCKET NO. 50-313
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l INTRODUCTION j
By letter dated May 6, 1987, Arkansas Power and Light Conpany (AP&L or the licensee) requested amendment to the Technical Specifications (TSs) appended to Facility Operating License No. OPR-51 for Arkansas Nuclear One, Unit No. 1 (AND-1).
The proposed amendment would grant to the licensee a one time exception from Section 3.8.15 of the AND-1 TS to allow the auxiliary building crane to be used to transport, in a spent fuel shipping cask, six spent fuel rods. The fuel rods are part of the Department of Energy's j
Extended Burnup Test Program. At present Section 3.8.15 prohibits use of the auxiliary building crane for movement of spent fuel casks pending staff review and approval of the licensee's analysis of the spent fuel j
cask drop accident.
DISCUSSION Specialized equipment will be transferred to ANO-1 by E4W from the Oconee Nuclear Station as part of the planned ca>sk movement. This equipment will be installed in the cask pit where the selected fuel rods will be removed from the extended burnup test fuel assemblies ar.d stored in a special basket in the spent fuel pool. The specialized equiprent will then be disassembled and removed from the cask pit after which the rhipping cask will be installed in the cask pit by means of the auxiliary building crane and will be loaded with the special basket containing the extended burnup fuel rods.
The licensee stated in letters dated June 8 and June 23, 1987 that the following provisions will be provided in order to reduce the possibility of a cask drop accident and the potential adverse consequences that may result:
1.
Ao sutomatic limit switch and a power disconnect from the main contact rails will be provided on the auxiliary building crane to preclude cask travel over the spent fuel storage pool.
8707R00527 O'70710 PGR ADOCK 05000313 P
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. Interlocks will also be used to limit the height.to which the cask is raised above the floor.
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3.
Further hoist operation will oe prevented by an electrical interlock and the crane hoist control circuits will;br disabled under administrative controls once the cask has been raised to the proper height.
Consequently, changes in cask height will be prevented during horizontal movement.
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Cask travel within safe load areas is limited by strict i
administrative controls in combination with interlocks which limit crane travel to within normal crane load handling areas.
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The auxiliary building crane is rated at 110 tons compared to l
the cask which weights 25 tons, thus providing a factor of l
safety of greater than 4.
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The staff notes that provisions similar to those above were made previously i
l (Amendment 36, October 5, 1978) in order to allow,use of the auxiliary building crane to move a'25 ton cask (NAC-1) on a one-time basis for the purpose of shipping irradiated boron carbide (8 0) test rods which were 4
stored in the fuel storage pool.
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EVALUATION Based on a review of the above information, the staff finds that the j
potential for a cask drop accident is a highly unlikely occurrence because I
of the one time use, particularly in view of the added measures provided to preclude a possible cask drop.
Thc con equences yould b6 ininimal because of the small nuniber of fuel rods being transported and because the cask j
will not travel over stored spent fuel.
For that reason, a cask drop 1
accident evaluation is not required.
The prohibition on cask movement i
over the spent fuel pool will be maintained during this operation.
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Based on the above, the staff concludes that Technical Specifications 3.8.15 i
can be suspended temporarily to permit use of the auxiliary building crane to move the DOE cask when empty and when containing six specially irradiated fuel rods.
When such actions requiring the use of the auxiliary building i
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crane have been completed, Technical Specification 3.8.15 will again be l
placed in force.
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ENVIRONMENTAL CONSIDERATION 1
l The amendment relates to changes in installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents l
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that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that this amendment involves-no significant hazards consideration and there has been no public coma.ent t
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. on such finding.
Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
CONCLUSION The staff has con (laded, based on tne considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner and (2) such activities will be conducted in compliance with the Commission's regulations ar.d the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated:
July 10,1987 Principal Contributor:
N. Wagner l
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