ML20244D902
| ML20244D902 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/18/1989 |
| From: | Shemanski P Office of Nuclear Reactor Regulation |
| To: | Bliss H COMMONWEALTH EDISON CO. |
| References | |
| TAC-62832, NUDOCS 8904240192 | |
| Download: ML20244D902 (6) | |
Text
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April 18, 1989 Docket No: 50-374 Mr. Henry E. Bliss Nuclear Licensing Manager Consonwealth Edison Company.
P.O.. Box 767 Chicago, Illinois 60690 Cear Mr. Bliss:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - PROPOSED LICENSE AMENDMENT FOR LASALLE UNIT 2 HICH DENSITY SPENT FUEL RACKF - TAC NO. 62832 Based on the April 6,1989 meeting with Commonwealth Edison Company and U.S.
Tool and Die, the staff finds that additional information is required in the seismic area in order to complete the review. Enclosed please find the additional information required.
If you should have any questions, please contact Paul Shemanski, Project Manager,at(301)492-3101.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely,
( E Paul C.~ Shemanski, Project Manager Project Directorate III-2 Division of Reactor Projects III, IV, V, and Special Projects
Enclosure:
As stated cc: See next page DISTRIBUTION TDocketsf11e9 NRC & Local PDRs PDIII-2 r/f GHolahan NVirgilio LLuther OGC s.
DHagan Edordan BGrimes TMeek (f)
WJones EButcher ACRS GPA/PA ARM /LFMB Plant file PShemanski PDIIIf.f.
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April.18, 1989' Docket No: 50-374 Mr. Henry E. Bliss Nuclear Licensing Manager Commonwealth Edison Company P.O. Box 767 Chicago, Illinois' 60690 l
Dear Mr. Bliss:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - PROPOSED LICENSE AMENDMENT FOR LASALLE UNIT 2 HIGH DENSITY SPENT FUEL RACKS - TAC NO. 62832 Based on the April 6,1989 meeting with Commonwealth Edison Company and U.S.
Tool and Die, the staff finds that additional information is required in the seismic area in order to complete the review.
Enclosed please find the additional information required.
If you should have any questions, please contact Paul Shemanski, Project Manager,at(301).492-3101.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely,
(
Paul C. Shemanski, Project Manager Project Directorate III-2 Division of Reactor Projects III, IV, V, and Special Projects
Enclosure:
As stated cc: See next page DISTRIBUTION Docket file NRC & Local PDRs PDIII-2 r/f GHolahan MVirgilio LLuther OGC 4
DHagan EJordan BGrimes TMeek (f)
WJones EButcher ACRS GPA/PA ARM /LFMB Plant file PShemanski PDIIIf.f.
2 PDIII-2 PDIII-2 PShemanski: km LLuthe g -
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- ,c, April 18, 1989
.i Docket Ho: 50-374 Mr. I:enry E. Bliss Nuclear Licensing Manager Commonwealth Edison Company P.O. Box 767 Chicago, Illinois 60690
Dear Mr. Bliss:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - PROPOSED LICENSE AMENDMENT FOR LASALLE UNIT 2 HIGH DENSITY SPENT FUEL RACKS - TAC NO. 62832 Based on the April 6, 1989 meeting with Commonwealth Edison Company and U.S.
Tool and Die, the staff finds that additional information is required in the seismic area in order to complete the review. Enclosed please find the additional information required.'
If you should have any questions, please contact Paul Shemanski, Project Manager,at(301)492-3101.
The reporting and/or recordkeeping requirements contained in this letter af fect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, ad C.
U m
Paul C. Shemenski, Project Manager Project Directorate III-2 Division of Reactor Projects III, IV, V, and Special Projects
Enclosure:
As stated cc: See next page
Mr. Henry E. Bliss LaSalle County Nuclear Power Station Commonwealth Edison Company Units 1 & 2 s
cc:
Phillip P. Steptoe, Esquire John W. McCaffrey Sidley and Austin Chief. Public Utilities Division-One First National Plaza S0IC 6
Chicago, Illinois 60603 100 West Randolph Street Chicago, Illinois 60601 Assistant Attorney General 100 West Randolph Stre'et Suite 12 Chicago, Illinois 60601 Resident Inspector /LaSalle, NPS U.S. Nuclear Regulatory Comission Rural Route No. 1
'P. O. Box 224 Marseilles, 1111ncis 61341 Chairman LaSalle County Board of Supervisors LaSalle County Courthouse Ot;'wa, Illinois 61350 Attorney General 500 South 2nd Street Springfield, Illinois 62701 Chairman Illincis Comerce Comission Leland Building 527 East Capitol Aver.ue Springfield, Illinois 62706 fir. Michael C. Parker, Chief Division of Engineering Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 Regional Administrator, Region III U. S. Nuclear Regulatory Comission 799 Roosevelt Road, Bldg. 64 Glen Ellyn, Illinois 60137
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION REGARDING LASALLE COUNTY STATION UNIT 2 SPENT FUEL P0OL RERACK MODIFICATION 1.
Description of the Spent Fuel Pool and Racks (a) Provide typical fuel rack design drawings which indicate all weld-details.
(b) Provide.a typical fuel assembly drawing indicating details of rack interface areas.
(c) Provide detailed fuel pool-drawings which show the liner weld seams, the leak detection system channel and any modifications.
(d) Will.any shim plates be used between the rack feet and the pool floor?
(e) Discuss the rack installation with center support pedestals which would ensure the required contacts of the pedestals even when the floor slab may be uneven or sloping or deflected under the loads. Discuss hc the rack model (sliding contact) would include such conditions.
2.
Spismic and Impact Loads (a) Provide a detailed description of the methodology and analytical models used to generate the new floor response spectra.
(b) Provide a detailed description of the methodology used to generate the pool floor time histories and provide the time histories in each of three directions show that the two horizontal time histories are st6tistically independent and they posses sufficient power at the frequencies of interest.
(c) Discuss the effect of pool sloshing on the coolant inventory and radiation shielding under the postulated seismic events.
(d) Have impacts between the fuel racks and the pool walls and the floor slab been considered? Do the walls and slab have sufficient margin to accommodate these loads? Provide a tabulation showing the actual loads (stresses), allowables and the ratios.
3.
Design and Analysis Procedures (a) Provide a list of values of modeling parameters used in the fuel rack analysis including:
1 1
Inter-rack impact element properties Rack / fuel impact element properties l
i i..
.3.
Design and Analysis Procedures (CONTINUED)
Support foot properties Friction element properties Mass of. rack and fuel L
Dimensions Gaps between racks and wall, racks and fuel, and rack to rack Fluid coupling coefficients (b) ProvQ the calculations which defined the key modeling parameters.
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(c) Do the spring stiffnesses.used in the fuel rack model represent calculated values? If not, provide justification.
(d) Provide the natural frequencies of the fuel racks in both the vertical and horizontal (rocking) directions. Consider variations in geometry, fluid immersion, and fuel load condition.
(e) Provide justification for using a single rack model of a fuel rack.
How are the three components of. earthquakes considered in the single rack as well as multiple rack analyses?
(f) Provide a description of the program and sample outputs. Discuss how the program was verified.
(g) Provide additional information on how fluid coupling effects are incorporated into the equations of motion for standard fuel assemblies.
(h) Did the fuel-to-wall fluid coupling coefficients consider.the flow.
area through the fuel assemblies? If not, provide calculations demonstrating the conservatism of the model.
(1) How was structural damping incorporated into the fuel rack model?
Describe the method and list specific elements in which damping is included.
(j) Provide justification for assuming the same friction coefficient for both static and sliding rack conditions.
(k) Discuss the basis of selection of the fuel to cell impact spring elevations. Are these only locations where fuel to cell impacts are anticipated? Demonstrate through analysis the integrity of the fuel s
assemblies under postulated seismic events.
(1) Perform 4-rack multi-rack analyses as discussed during the April 7, 1989 meeting.
(m) Are the fuel drop or rack drop accidents consicered during reracking or during handling of fuel (provide sumary of results)?
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