ML19260C014
| ML19260C014 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 11/30/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Groce R Maine Yankee |
| References | |
| NUDOCS 7912180233 | |
| Download: ML19260C014 (4) | |
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%'.'.*,/a November 30, 1979 Docket No. 50-309 Mr. Robert H. Groce Licensing Engineer Maine Yankee Atomic Power Company 20 Turr. pike Road Westboro, Massachusetts 01581
Dear Mr. Groce:
We have reviewed your submittals of November 22, 1978, and September 18, 1979, concerning modified spent fuel pin storage at the Maine Yankee Nuclear Facility.
We find tnat we will need additional information before we can complete our eview and evaluation. The enclosure addresses engineering concerns, but as previously discussed, additional information requests will be fortncoming regarding environmental and radiological concerns. Please submit the infor-mation requested within 30 days of receipt of this letter to permit timely review of this issue.
Sincerely, lJ~
3:
Robert W. Reid, Chief Operating Reactors Branch *4 Division of Operating Reactors
Enclosure:
Request for additional information cc: w/ enclosure See next page L33; P 1~614 018 7 9 ea so A
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w Yankee Atonic Electric Company cc:
E. W. Thurlow, President fir. Robert R. 3.adcli f fe flaine Yankee Atonic Power Company Office of Energy Resources 9 Green Street 55 Capitol Street Augusta,itaine 04330 Augusta, tiaine 04330 fir. Donald E. Vandenburgh Vice. President - Engineering Yankee Atonic Electric Company 20 Turnpike Road Westbot o, flassachusetts 01561 John A. Ritsher, E3 quire Ropes and Gray 225 Franklin Street Boston, tiassachusetts 02110 lir. Jcha 11. R. Paterson Assistant Attorney General State of Maine Augusta, itaine 04330 Mr. Nicholas Barth Executive Director Sheepscot Valley Conservation Association, Inc.
P. O. Box 125 Alna, Maine 04535 Wiscasset Public Library Association High Street Wiscasset,!!aine 04578 ttrs. L. Patricia Doyle, President SAFE POWER FOR Malt 4E Post Of fice Box 774 Canden, liairie 04843 1614 019
ENCLOSURE MAINE YANKEE ATOMIC POWER COMPANY MAINE YANKEE ATOMIC POWER PLANT SPENT FUEL PIN STORAGE MODIFICATION REQUEST FOR ADDITIONAL INFOR*GTION 1.
Specify whether all provisions, including the January 18, 1979 addenda, to " Review and Acceptance of Spent Fuel Storage and Handling Applications" have been considered and to what extent all provisions are me'.
2.
Provide a more detailed description and sketches of a typical fuel rack and fuel pin storage skeleton including details of the spacer and support grids and the tie rods.
Describe the modifications which are required to the present racks.
Explain in detail the load path along which all postulated forces are transmitted to the spent fuel pool structures.
3.
Describe the storage cage lor.ation and structural support while it is partially filled, prior to placing it in the fuel rack.
Verify that it can withstand all loads a.id load combinations for which the rack is designed, with no loss of integrity or impact to other items in the spent fuel pool.
4.
Verify that the increased compressive loads on the ABC plastic insulator have been considered and that no degradation occurs which would decrease its insulating integrity.
5.
Provide the results of the pool wall design re-evaluation. Verify that the pool wall integrity is maintained, considering the additional seismic restraints.
6.
Provide the total increase in weight supported by the floor which will result from using the pin storage concept. Verify that the effect of this increase on the dynamic response characteristics of the spent fuel pool has been considered.
7.
Verify that the racks have been analyzed for seismic and impact loads.
Provide details of the analysis. Discuss any interaction or impacting between fuel assemblies, storage cages, and racks during maximum seismic excitation, and verify that their integrity is not compromised.
3.
Provide a detailed description of the model, and its development, used in the dynamic analysis.
Specifically describe the properties of connect-ing members, the gap elements, and the independent modes, and describe how they were developed.
In addition, justify the direct use of the ground spectra with the rack model.
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9.
Provide technical bases to justify the dynamic loac fa:: r ;sec : rspre-sent the effect of fuel assembly impact.
Provide a rore de ailst description of your analyses and results.
- 10. Verify that the drop of a compacted fuel assembly on a ec pac e: or dis-assembled storage cage has been considered.
Verify that -he in egrity of both the fuel assembly and the storage cage is not cocoromised, and that the storage cage will not overturn or impact other stcrage cages.
11.
Provide the weight of a fully compacted fuel rack.
In acdition, specify the heaviest load that will be transported over the spe.t fuel racks and the maximum possible drop height.
Verify that the wo st case drop of a compacted fuel rack on another rack will not adversel.e affect the integrity of the racks.
12.
Discuss whether the movement of any racks will be necessary during fuel consolidation.
Describe the handling procedures and the precau-ions which will be taken to prevent damage to the spent fuel and the racks.
13.
Demonstrate that the values of water level in the pool, the coo:ing water velocity and the water temperature will be identical to tne values used in developing the original thermal design loads.
Discuss at least the following items:
influence of increased thermal load on stresses / strains in concrete walls and bottom of the pool and in the liner and also of the racks.
influence of the increased weight of the spent fuel stored in the pool of the virtual mass of the water, horizontal forces on the bottom and the walls during an earthquake and the influence of the liner and racks.
Discuss the potential need for improved surveillance during normal operation of the plant and after seismic and/or tornadic occurrences.
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