ML20037D161
| ML20037D161 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/18/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Abel J COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8105220076 | |
| Download: ML20037D161 (7) | |
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UNITED STATES y '
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[q{cg)h jh May 18,1981 Docket Nos. 50-254 50-265 A
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% d'2 Mr. J. S. Abel Ofrector of Nuclear Licensing b
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Commonwealth Edison Company 6'^N A
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Dear Mr. Abel:
Your application dated March 26,1981 for expanding the spent fuel storage capacity at Quad Cities Station is currently under review. The additional infonnation requested in Enclosure 1 is needed to proceed with the review.
As we have discussed with your staff, our expeditious review depends upon your cooperation in resolving questions as they arise during our review.
Sincerely,
/
r Thomas'K. Ippolito,
- Chief Operating Reactors Branch #2 Division of Licensing
Enclosure:
Request for Additional Information l
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See next page l
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8105220076,
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1 Mr. J. S. Abel
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Commonwealth Edison Company cc:
Mr. D. R. Stichnoth President Iowa-Illinois Gas and Electric Company 206 East Second Avenue Davenport, Iowa 52801 Mr. John W. Rowe Isham, Lincoln & Beale Counselors at Law One First National Plaza, 42nd Floor Chicago, Illinois 60603 Mr. Nick Kalivianakas Plant Superintendent Quad Cities Nuclear Power Station 22710 - 206th Avenue - North Cordova, Illinois 61242 Mo'41ne Public Library 504 - 17th Street Moline, Illinois 61265 Susan N. Sekuler Assistant Attorney General Environmental Control Division 188 W. Randolph Street Suite 2315 Chicago, Illinois 60601 Resident Inspector U. S. Nuclear Regulatory Connission 22712 206th Avenue N.
Cordova, Illinois 61242 t'
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1, Enclosure c
l REQUESTF5RADDITIOALINFORMATION QUAD CITIES UNITS 1 AND 2 SPENT FUEL POOL EXPANSION TAC 43759 AND 43760 DOCKET 50-254/265 1.
When Section 5.1, Heat Generation Calculations, is provided, include the following information:
a)
Indicate the minimum elapsed time between shutdown and when the discharged fuel is in the spent fuel pool for all anticipated fuel discharge cycles.
b) For Units 1 and 2 spent fuel pools, indicate the number of fuel assemblies and their respective' decay times of all 7:e1 that will be in the pools when reracking occurs.
c)
It is noted in th'e FSAR that portions of the RHR system may be used to augment the spent fuel pool cooling system by inserting spool pieces in the spent fuel pool cooling lines shown in Figu,re 10.2.1.
In this regard indicate the length of time required to install these spool pieces and describe the capability cf the RHR system to remove heat from the spent fuel pool over a range of pool temperatures and with and without the spent fuel pool cooling system in operation.
d)
For Units 1 and 2 indicate the length, width and depth of the spent fuel pools and the minimum volume of water in each when all storage racks are filled with fuel assemblies.
e) Figures 2.1 and 2.2 of the March 26, 1981 submittal shows that the down-comer region, i.e. space between the racks and walls of the pool, is quite small.
Further, the vertical dimension of the wateh plenum formed by the
c 1
o base plate of storage racks and the pool bottom is 6-1/2 inches. Assuming the maximum heat load is adversely located in the storage racks demonstrate that sufficient circulation will occur to preclude nucleate boiling.
2.
Assuming the reactor is operating at power when it becomes necessary to utilize the RHR system to cool the spent fuel pool, describe and discuss the steps that must be taken and the elapsed time before the RHR system can be placed in the fuel pool cooling mode of operation.
3.
For both Units 1 and 2 speht fuel pool reracking operations provide the following additional information:
a) Assuming a load drop, describe and discuss, with the aid of drawings, the travel paths of the new and existing storage racks with respect to plant equipment that may be needed to attain a cold safe shutdown or to mitigate the consequences of an accident.
b) Provide the weights of the racks.
Describe and demonstrate the adequacy of the lifting rig attachment points,on the new and old racks, to withstand the maximum forces that will be experienced during the load handling opera-tions.
c) With the aid of a drawing, describe the lifting rigs that will be employed in handling the racks and demonstrate their adequacy.
d) Assuming stored spent fuel is in the pool when the storage racks are being
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removed or installed, demonstrate that the stored spent fuel is not within the area of influence of dropped racks shou.1d one or more of legs of the lifting i
rig fails.
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i e) FSAR Figures 12.1.1 and 12.1.2 shows a transfer canal joining Unit 1 pool with Unit 2 pool. Assuming a significant number of loads are transferred between the two pools, describe the merits of p'roviding additional pro-tection in the form of a cover over those storage racks directly under this frequently travelled path.
f)
For both Units 1 and 2,with the aid of drawings, sequentially describe the movement of the stored spent fuel assemblies and storage racks in order to reduce the possibili,ty of fuel damage in the event of a load drop during the reracking operations.
g) Considering the limited space between the storage racks and the pool walls describe the travel paths and laydown area for various pool gates. Demon-strate that the consequences of a dropped gate are acceptable or that one can reasonably assume that dropping of the gates is very unlikely, h) Using Figure 3.7 describe and discuss the ability of the high density storage racks to protect the stored spent fuel assemblies from damage following a load drop.
l 1)
In regard to the potential for damage to stored spent fuel resulting from light load drops (i.e. one fuel assembly and its associated handling tool when dropped from its maximum carrying height),
t it was assumed that all lesser loads that are handled above stored spent fuel would cause less damage if dropped. Verify that this assumption was correct e.g. indicate that all lesser loads when dropped from their maximum elevation would impart less kinetic energy upon impact with the tops of the fuel assemblies and or storage racks.
1 4.
Since Figure 2.2 shows that essentially all available space in Unit 2 pool will be occupied by storage racks, therefore, all Unit 2 stored spent fuel must be moved to Unit 1 pool via the transfer canal before it can be loaded into the shielded shipping cask. Describe and discuss what measures will be taken to reduce the possibility of fuel assembly damage resulting from these additional fuel handling operations.
5.
For both Unit 1 and Unit 2 storage pools, starting with the total decay heat load that will exist in each pool fg11owing the reracking operations, provide the fol. lowing information:
a) a plot of the pool's maximum anticipated total decay heat load resulting from nont,a1 discharges versus time until each pool has reached its storage capacity.
b) Verify that all decay heat calculations have been made in accordance with ASB technical position 9-2.
c) a plot of the pool's water tengerature versus time for each discharge where the total decay heat exceeds the capacity of the spent fuel pool cooling system.
Indicate what cooling systems are in operation and their respective capacities.
d) a plot of maximum decay heat load in each pool, assuming a full core dis-charge at each of the normally scheduled refueling periods.
l e) a plot of the pool's water temperature versus time following each full 1
core discharge assumed in item d above.
Indicate what cooling systems are in operation and their respective capacities.
i 1
o 5-f) Assuming the maximum heat load exists in Unit 1 and Unit 2 pools when all external cooling was lost, indicate the time interval before boiling occurs and the boil off rate.
g) Describe and discuss the sources of makeup water, the quantity available, their respective makeup rates and the steps that must be carried out and the elapsed time before the makeup water will be available at the pools.
6.
Since the RHR system will be required to augment the spent fuel cooling syster; for some period of time following a disch'arge, describe and discuss how it will be verified that the decay heat load has decayed to a value within the capacity of the spent fuel pool cooling system and, therefore, allowing the RHR system to be safely returned to its safety function mode of operation.
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