ML19319E143
| ML19319E143 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/10/1976 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Davis E SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 8003310662 | |
| Download: ML19319E143 (5) | |
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Docket No.: 50-312 L PDR Docket Fi T10 ORB #4 Rdg g
VStello KRGoller
. Sacramento Municipal Utility District TJCarter i
ATrN:
Mr. E. K. Davis ~
OELD General Manager
. OISE (3) 6201 S Street RReid P. O. Box 15830
'VRooney 8
Sacram: ento, California _
95813
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DEisenhut Centlemen:
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~JRBuchanan
~ TBAbernath'y
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.We are reviewing your proposed Rancho Seco spent fuel storage enlarge-3 j ment submitted by, letter dated December 19, 1975, and have concluded that the additional information' reqtiested in the enclosure is necessary to continue'our review.
It 1s requested that you provide this information
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' within 30 days of receipt of.this letter..Please send us 40 copies including three signed.and notariied ~ originals. -
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> Robert.W.tReid,' Chief _.
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-Operating" Reactors < Branch #4
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Enclosure:
' Request for Additional
'Inforration cc w/ enclosure:. See'next page
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RReid' iem*.2/9/76.....,12/$./16 Form ABC 318 (Bew. p.5)) ABCM 0240 W un en oovannessur pasurine oPrecas te74.ose.see
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v Sacramento Municipal ~~ Utility District 2-cc: David S. Kaplan, Secretary and~
- General Counsel'
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- 6201 S Street-Post OfficeLBox 15830'
' Sacramento, California 95813~
Business and')funicipal Department-Sacramento City-County Library
. 828 I Street
__ Sacramento, California' 95814 v
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- RFSEST FOR INFOTGTION FER 9 G73 Rancho Seco Unit 1 Docket 50-312 Fuel Pool Modification Ifnen is the next refueling date End what is the proposed 1.
' schedule for subsequent refueling?
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.2.
How many fuel _ assemblies will be replaced during each~ refueling?
3.
hhat is the total ' construction cost associated with the proposed modification of the spent fuel pool (SFP)?
'4. -hhat are the alternatives to increasing the storage capacity of
.the SFP?. The alternatives considered should include, but not necessarily be limited to, the following~ options:
Shipment to a fuel reprocessing facility.. Provide ' status, a.
-if any, of any contractual agreements.
b.
Shipment to another reactor site.
c.
Terminatien of operation of the reactor.
These options snould-include a cost comparison in tems of dollars per kilogram of uranita stored and the cos' t for providing replacement power kithin.or outside of the licensecs' generating system.
5.
Provide data on the. quantity of stainless steel used in the new racks.
6.
Provide the following infomation related.to the toter purification system:
Ja.- What:is the volume of water in;t'he SFP?
b., How.many demineralizers are used and what length of time is
. required to cican up the total volt =c of toter in the pool?
c.- What is the expected increase in quantity of solid wastes from.
demineralizers and filters resulting from the expansioa?
i.
7 Provide a discussion'of the models and calculations used to estimate
~ doses to personnel from radionuclide concentrations in the spent. fuel pool including ~the following:
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134Cs, 137 s, of fuel pool water source tems including C
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b.
The dose rate above the spent-fuel pool resulting.from these-source terms.-
c.
The total dose rate above the pool from (b) plus the contribution from the stored spent fuel pool elements
-in the expanded pool.
d.
The annual can-rem dose equivalent based on all opera-tions performed by personnel in the pool area.
8.
Provide a discussL:, of the models and calculations used to estimate releases of radioactive materials to the environment from the modified spent fuel pool.
9.
Discuss the potential for fuel-handling and fuel-cask accidents, such as movement of transfer cranes over the storage area, that would be affected by the expansion.
- 10. Discuss the storage or disposal of the original fuel racks.
11.
Please provide details as to the location of the failed fuel sto; age locations in the pool.
If they are not part of the array, discuss the reactivity effect of their presence.
If they are part of this array, provide-assurance that they contain at least as much neutron absorber as the regular storage location.
12.
Provide sufficient detail as to location and arrangement of tenporary storage modules in the transfer canal to support the assertion that they are safe as regards criticality.
In particular provide assurance that the transfer path is far enough from these locations to provide negligible Neutron coupling between transferred and stored asse& lies.
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- 13. _ Assuming the' loss of all cooling systems',' resulting in a bulk tempera-ture of 212oF at the surface of the pool:
- a.. calculate the outlet conditions of the coolant from the hottest subchannel of the hottest bundle, This should include coolant temperature and pressure and, if applicable, steam quality and
. void fraction;
- b'.
show that the cladding will not swell or rupture due to the cladding temperature and the internal pressure from fission gas present.in' the fuel rod at end of life;. and
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c.
show that the ' void fraction of the water is zero inside and
-between the fuel bundles.over their entire length, or else that
- keff is 'at a safe level when bo_iling occurs inside and between the stainless steel storage tubes.
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- 14. Re-evaluate the consequences of dropping of the fuel cask, taking into account the closer spacing for-the proposed spent fuel locations.- This evaluation should include the possibility of the fuel cask tipping or rolling into the spent fuel. Also provide
. diagrams showing the location of the spent fuel racks in the pool and area of, impact in the event the cask tips or rolls into the pool.
15. - Provide a list of all seismic and non-seismic systems which can be used as make-up in the event the spent fuel pool cooling systems fails and it cannot be repaired within the time limits specified in your proposal of."acember 19, 1975.
- 16. Diagrams or sketches of the new spent fuel storage racks have not been provided.
Provide such diagrams which indicate the general arrangements of the lateral bracing, and the locations and details of vertical and horizontal supports.
17.
Provide a diagram which schematically represents the dynamic model
.used in_the seismic analysis.
Indicate the support points, gaps, locations of translational and rotational springs, if utilized, and the method employed to account for the dynamic effects of the pool water.
- 18. - On page 7, a discussion of the lateral clearance of 1/8" for thermal expansion is presented.
State the pool temperature at which contact with the wall is anticipated, and the contact p. essure during normal operation. Specify whether or not these conne:tions are relied upon to transmit shear.
Provide a description of the frictional resistance of such connections and tb a effect of this resistance on the seismic analysis.
19.
Regulatory Guide l.61 is referenced for detemining the daging -values of the welded steel storage racks. However, this guide does not discuss structures immersec in a fluid.
If damping values are in-correctly assessed, a shift in the response frequency may occur, which could lead to an unconseIvative evaluation of the system response.
Discuss this. possibility and demonstrate that such a shift in system response would not adversely affect the fuel storage racks.
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