ML20198H342
| ML20198H342 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1997 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | Dugger C ENTERGY OPERATIONS, INC. |
| References | |
| TAC-M98325, NUDOCS 9801130257 | |
| Download: ML20198H342 (5) | |
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December 31. 1997 y
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Mr. Charles M. Dugger Vk:e President Operations.
Entergy Operations, Inc.
j P. O. Box B Kilions, LA 70066 f
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE SPENT FUEL POOL RERACKING AT WATERFORD STEAM ELECTRIC STATION, UNIT 3 (TAC NO M98325)
Dear Mr. Dugoer:
The Nuclear Regulatory Commission (NRC) staff is reviewing your letter dated March 27,1997, as supplemented by letter dated October 23,1997, requesting to increase the spent fuel storage capacity at the Waterford Steam Electric Station, Unit 3. As discutsed in the enclosure, your response dated October 23,1997, did not provide adequate information to our previous request.
Additior al information is required from Entergy Operations, Inc., in order for the staff to complete its review regarding the structural aspects of the request.
We request that you provide response within 30 days from the date of th?? ;,rttJr. If you have any questions, please call me on (301)-415 3025.
Sincerely, ORIGINAL SIGNED BY:
Chandu P. Patel, Project Manager Project Directorate IV-1 Division of Reactor Projects llulV Office of Nuclear Reactor Regulation Docket No. 50 382
Enclosure:
Request for AdditionalInformation
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. December 31,1997
. Mr. Charles M. Dugger Vlos President Operations Entergy Ooorations, Inc.-
P. O. Box B '
Mllona, LA 70066
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION F:EGARDING THE SPENT FUEL =
POOL RERACKING AT WATERFORD STEAM ELECTRIC STATION, UNIT 3
- (TAC NO. M98325)
Dear Mr. Dugger:
t The Nucisar Regulatory Commission (NRC) staff is reviewing your letter dated March 27,1997, as suppleme'ited by letter dated October 23,1997, requesting to increase the spent fuel storage
. capadty at the Waterford Steam Electric Station, Unit 3. As discussed in the enclosure, your response dated October 23,1997, did not provide adequate information to our previous tsquest.
Additional information is required from Entargy Operations, Inc., in order for the staff to complete i
its review regarding the structural aspccts of the request.
3 We request that you provide response within 30 days from the date of this letter, if you have any questions, please calline on (301)-415 3025.
Sincerely,
- f. f Chandu P. Patel, Project Manager Project Directorate IV 1-Division of Reactor Projects til/lV Office cf Nuclear Reactor Pegulation theket No. 50 382-
Enclosure:
Request for Additionalinformation oc::: See next page A
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Mr. Charles M. Dugger Entergy Operations, Inc.
Waterford 3 oc:
Administrator Regional Administrator, Region IV -
Louisiana Radiation Protection Division U.S. Nuclear Regulatory Commission Post ONice Box 82135 611 Ryan Plaza Drive, Suite 1000 Bwton Rouge, LA 70664 2135 Artington,TX 76011 Vice President, Operations Resident inspector /Waterford NPS Support l'ost Otfw:e Box 822 Entergy Operations, Inc.
Killona, LA 70066 P. O. Box 31995 '
Jackson, MS 39286 Parish President Council St. Charles Parish Director P. O. Box 302 Nuclear Safety & Regulatory ANairs Hahnville, LA 70057 Entergy Operations, Inc.
P. O. Box B Executive Vice-President Kiilona, LA 70066 and Chief Operating ONicer Entergy Operations, Inc.
Wise, Carter, Child & Caraway P. O. Box 31995 P, O. Box 651 Jackson, MS 39286-1995 Jackson, MS 39205 Chairman General Manager Plant Operationa Loulslana Public Service Commission Entergy Operations, Inc.
One American Place, Suite 1630 P. O. Box B Baton Rouge, LA 70825-1697 KiNona, LA 70066
- Licensing Manager Entergy Operations, Inc.
P. O Box B Kilions, LA 70066 Wmston & Strawn 1400 L Street, N.W.
Washington, DC 20005-3502
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1 REQUEST FOR ADDITIOtML INFORMATION D
- WATERFOi4D 3 SPENT FUEL POOL RERACKING -
1.
In the staffs first request for additional information (RAI), you were requested to provide detailed discussions as to how the dynamic ruid coupling was modoied in your analyses.
using the DYNARACK code. You provided a response in Refererece 1. -The staff understands that your approach may be one approximate way of modeling the fluid-structure interaction for the single-rack analysis. However, the staff has reservations as to whether it is applicable for accurately medeling the structure-fluid-structure interaction of the multi-rock analysis considering the fact that the fluid and structural responses of the multi-rack system are somewhat random and independent between rack to rock in a three dimensional space under safe shutdown earthquake (SSE) loading. You are requested to provide the following:
(a) Detailed explanations of how the dynamic fluid coupling was considered for modeling the structure-fluid structure interaction in the multi-rack analysis and u
technical justifications for using such modeling.
(b) What were the initial gaps between the racks used to calculate hydrodynamic masses? Were those initial gaps assumed to be cor'stant during the mck movements under a SSE? If constant gaps were assumed, justify your assumption.
If the gaps were not conatant during a SSE, how did you incorporate the changed -
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hydrodynamic masses ic your calculations?
(c) Submit a model drawing with complete information (i.e., element and node numbers with their locations in the global coordinate system, spacinD hettveen racks, etc ).
Also, submit the complete DYNARACK input data used for the 3-D multi-rack analysis in ASCil on a 3.5 inch diskette.
2.
In the staffs first RAl, you were requested to provide the results af any existing expenmental studies that verify the correct or adequate simulation of the fluid coupling utilized in the DYNARACK analyses for the fuel assemblies, racks and walls. You 4
provided a comparison study between the results of a DYNARACK analysis and an experimental test. The staff reviewed the comparison study and concluded that the study is not sufficient enough to demonstrate the oefoquacy of the DYNARACK code used to simulate the dynamic fluid coupling and the structure-fluid-structure interactions due to; (l)
- the conditions of the experimental setup (i.e., boundary conditions, dimensions and -
shapes of the structum, application of the load, etc.) are so different from the real -
4 ENCLOSURE
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conditions of the rock structures and (ii) very limited test data were obtained and '
presented. in order to further demonstrate the adequacy of your code, you are requested to provide a comparison study between the results of ths DYNARACK predictions and the j
experimental tests shown in References 2 and 3. Also, submit the DYNARACK input data in ASCil on a 3.5-inch diskette for the comparison analysis.
3.
In the staffs first RAI, you '.;wre requested to provide technical explanation as to the 4
somewhat inconsistent anu irregular displacement predictions shown in a table on page -
6-24 of Reference 4. You provided possible attributes, but did not fully address the staffs concoms. Provide detailed qualitative and quantitative technical discussions based on the results obtained (i.e., pedestal force, hydrodynamic force, etc.) and other studies (i.e.,
parametric sensitive study, etc.). - Also, provide predicted maximum displacements in x,
l y and z-directions for the cases of EVENT (DBE and OBE) and COF (0.8,0.2 and
- RANDOM) for all racks in the spent fuel pool, the cask pit and the refueling canal.
l 4.
In the staff's first RAI, you were requested to provide your plan regarding installation of a support system to minimize displacement and impact force between the rock to-pool wall and rock-to-rack since your analysis shows that there are rock to-pool wall and rack-to-rock impacts. You provided a response that you are not planning to install any support l
system to eliminate the rack impacts based on the results of the DYNARACK e.. clysis.
l Provide technical discussions of why your simple DYNARACK analysis is the mosi l
conservative approach and how it assures no further structural safety considerations are required Justify your discussions by confirming your DYNARACK predictions with actual rack experimental test results.
5.
In the staff's first RAI, you were requested to explain how the interface between the liner and concrete slab was modeled, and also, how the liner anchors were modeled. You provided a response that the pool concrete structure was modeled without considering the liner system. Provide a physica! description of the actual anchorage system between the liner and concrete slab. Are plug wolds used to anchor the liner plates to the plates embedded in the concrete slab? If plug welds are used, submit your calet.lations that demonstrate ;5ere are no axial and shear failures in the liner and plug weld at the temperature of 212'F used in your thermal analysis.
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Reference:
1.-
"Waterford 3 SES, Docket No. 50 382, License No. NPF-38. Request For Additional information (RAI) Regarding Technical Specification Change Request NPF-38-193,"
Letter dated October 23,1997 from Entergy Operations, Inc. to U.S. NRC.
2.
Scavuzzo, R.J., et al., " Dynamics Fluid Structure Coupling of Rectangular Modules in Rectangular Pools," ASME Publication PVP-39,1979, pp. 77-87.
l 3.
Radke, Edward F., "Expenmental Study of immersed Rectangular Solids in Rectangular Cavities," Project for Master of Science Degree, The University of Akron, Ohio,1978.
4 4.
"Waterford 3 SES, Docket No. 50-382, Ucense No. NPF-38, Technical Spec;fication Change Request NPF-38-193," Letter dated March 27,1997 from Entergy Operations, inc. to U.S. NRC.
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