ML20057G246
| ML20057G246 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 10/15/1993 |
| From: | Pulsifer R Office of Nuclear Reactor Regulation |
| To: | Leslie Liu IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| References | |
| TAC-M86284, NUDOCS 9310210086 | |
| Download: ML20057G246 (4) | |
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r Docket No. 50-331 Mr. Lee Liu Chairman of the Board and Chief Executive Officer Iowa Electric Light and Power Company P. O. Box 351 Cedar Rapids, Iowa 52406
Dear Mr. Liu:
SUBJECT:
DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONAL INFORMATION FOR THE SPENT FUEL P0OL RERACK APPLICATION (TAC M86284)
The NRC staff is continuing to perform a preliminary review of the spent fuel pool reracking amendment request submitted on March 26, 1993, for the Duane Arnold Energy Center (DAEC). We are submitting the enclosed request for additional information (RAI) in order to continue our revies.
Please provide your response as soon as practical, in order for the staff to complete this review and meet your project schedule.
If additional i
information is required, please contact me at (301) 504-3016.
This request for information affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, ORIGINAL SIGNED BY Robert M. Pulsifer, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
Request for additional information cc w/ enclosure:
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Mr. Lee Liu lowa Electric Light and Power Company Duane Arnold Energy Center cc:
Jack Newman, Esquire Kathleen H. Shea, Esquire Newman and Holtzinger 1615 L Street, N.W.
Washington, D.C.
20036 Chairman, Linn County Board of Supervisors Cedar Rapids, Iowa 52406 lowa Electric Light and Power tompany ATTN:
David L. Wilson Plant Superintendent, Nuclear 3277 DAEC Road Pala, Iowa 52324 Mr. John F. Franz, Jr.
Vice President, Nuclear Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324 Mr. Keith Young Manager, Nuclear Licensing Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324 U.S. Nuclear Regulatory Commission Resident Inspector's Office Rural Route F1 Palo, Iowa 52324 j
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Stephen N. Brown Utilities Division Iowa Department of ComT.erce Lucas Office Building, 5th Floor Des Moines, Iowa 50319 l
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4 ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION ON THE SPENT FUEL POOL STORAGE RACK APPLICATION AT DUANE ARNOLD 1.
The licensee, Iowa Electric Light and Power Company (IELP), states that artificial time histories were used for dynamic analysis. However, IELP does not clearly state how the time histories were developed.
In addition, the response spectra generated by using the artificial time histories shown in the submittal do not envelop the licensing basis design response spectra of the Final Safety Analysis Report (FSAR).
IELP is requested to provide the following:
a)
Provide number of sets of artificial time histories developed and used for the dynamic analysis, and indicate whether response spectra developed by each time history envelopes the design response spectra of the FSAR.
If not, indicate whether the average response spectra generated from the time histories envelop the design response spectra of the FSAR.
b)
If the average response spectra do not envelop the licensing basis design response spectra, IELP is requested to demonstrate adequacy of the artificial time histories used in the analyses (e.g., the extent of conformance to a target power spectral density (PSD) function of the artificial time histories).
c)
From the time histories used for the analyses of the submittal (Reference I), provide the cross-correlation coefficients P g
between time histories i and j for the safe shutdown earthquake (SSE), and demonstrate compliance with the statistical independence requirement for the SSE.
d)
Submit the digitized time histories used for the analyses of the submittal (Reference 1).
2.
No detailed quantitative information related to the integrity of the pool liner were provided in the submittal.
IELP is requested to provide the following:
a)
Analytical approaches or methodologies, b)
Loading conditions, j
c)
Failure (tear and rupture) criteria, d)
Material properties used including concrete bearing strength and 1
friction between the pedestal and liner, and e)
Provide complete summary of the findings in a tabular form.
3.
IELP utilized compression gap elements in the dynamic analyses to I
provide for opening and closing of interfaces such as the pedestal-to-bearing pad interface.
Provide the magnitude of the largest compression 1
force and the location of the gap element and the time when that event i
occurred for the case of RUN I.D.-DRRSSE.RF2 of the submittal.
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4.
Provide the largest magnitude of the fluid pressure distribution along the height of the rack and pool wall during the fluid and rack interactions for each case of the 3-D single and multi-rack analyses.
Explain physical meaning of the negative dynamic pressures and physical phenomenon of almost zero average dynamic pressures on pool walls shown in Table 6.8.5 of the submittal.
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5.
Provide clearances (gaps) between racks, and the racks and the spent fuel pool walls in Figure 6.4.9.
6.
Provide an assessment of stress at the seam weld in the cell under the worst condition of the postulated seismic loading.
i 7.
IELP states that all computer programs utilized in performing the rerack i
analysis were verified in accordance with Holtec International's nuclear Quality Program (QP).
Indicate whether the QP was reviewed and approved by the NRC staff.
Also, indicate whether or not the QP documentation is i
available for staff audit.
8.
Describe the plan and procedure for the post operating basis earthquake j
(0BE) inspection of fuel racks gap configurations.
t 9.
Discuss the key procedures and assumptions for generation of the three dimensional multi-rack model used in the analysis and the basis for using the random friction coefficients rather than a single coefficient of 0.2 or 0.8 to be consistent with single rack analysis.
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10.
In a whole pool multi-rack (WPMR) analysis, was a randomly selected j
friction coefficient at a given instant applied to all racks identically?
If one were to select random friction coefficient for each rack at each instance, would the results be appreciably changed?
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11.
Maximum displacements, pedestal vertical load and stress factor in Table 6.8.4 contradict those values in Table 6.7.2 and th. results of some single rack analyses. Clarify the discrepancu Describe the factors attributable to the large difference in the maximum displacements l
between the whole pool multi-rack (WPMR) analysis and the single rack analyses.
4 12.
Was there any physical rack design change necessitated by the results of the WPMR analysis? If yes, describe the change (s).
13.
IELP states laboratory experiments were conducted to validate the multi-rack fluid-coupling theory.
Provide information related to these t
experiments, and discuss how the Fritz's two-body fluid-coupling model
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was extended to be applicable to the multi-body applications.
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Reference:
" Application for Amendment of Operating License," letter dated March 26, 1993, from Iowa Electric Light and Power Company to NRC.
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