ML17264B145
| ML17264B145 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/16/1997 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-M95759, NUDOCS 9712300340 | |
| Download: ML17264B145 (7) | |
Text
Oecember 16, 1997 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONALINFORMATIONON THE STRUCTURAL ASPECTS OF THE SPENT FUEL POOL STORAGE RACK MODIFICATIONAT GINNA NUCLEAR POWER PLANT (TAC NO. M95759)
Dear Dr. Mecredy:
The NRC staff reviewed the report with respect to the application for the modification of the spent fuel pool storage racks submitted by the Rochester Gas and Electric Corporation (RG8 E) for Ginna Nuclear Power Plant and issued a request for additional information (RAI). RG8E submitted responses to our RAI and the staff reviewed the responses.
Based on the review, we need additional information as shown in the enclosure to complete our review.
Please provide your response as soon as you can to support your schedule for completion of this action.
Sincerely, Original Signed by:
Guy S. Vissing, Senior Project Manager Project Directorate 1-1 Divison of Reactor Projects - I/II Docket No. 50-244
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
Docket File PUBLIC PDI-1 R/F BBoger SBajwa SLittle GVissing CHehl, Region I
OGC ACRS DOCUMENT NAME: G:<GINNA>M95759-2.RAI To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No co OFFICE PM:PDI-1 E
LA:PDI-1 D:PDI-1 NAME Gvissing/Icc/
SLittI 12/
/97 DATE 12/
/97 SBQ MB 12/
/97 Official Record Copy 12/
/97 12/
/97 97i2300340 97i2ib PDR ADQCK 05000244 P
I P
1
December 16, 1997 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONALINFORMATIONON THk STRUCTURAL ASPECTS OF THE SPENT FUEL POOL STORAGE MCK MODIFICATIONAT GINNANUCLEAR POWER PLANT (TAC NO. M95759)
Dear Dr. Mecredy:
The NRC staff reviewed the report with respect to the application for the modification of the spent fuel pool storage racks submitted by the Rochester Gas and Electric Corporation (RG&E) for Ginna Nuclear Power Plant and issued a request for additional information (RAI). RG&E submitted responses to our RAI and the staff reviewed the responses.
Based on the review, we need additional information as shown in the enclosure to complete our review.
Please provide your response as soon as you can to support your schedule for completion of this action.
Sincerely, Original Signed by:
Guy S. Vissing, Senior Project Manager Project Directorate I-1 Divison of Reactor Projects - I/II Docket No. 50-244
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
Docket File PUBLIC PDI-1 R/F BBoger SBajwa SLittle GVissing OGC ACRS CHehl, Region I
DOCUMENT NAME: G:<GINNA(M95759-2.RAI To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure
-"E" = Copy with attachment/enclosure "N" = No co OFFICE PII:PDI-I E
LA:PDI-1 D:PDI-1 IIANE Gvissing/Icc Si.ital 12/
/97 DATE 12/
/97 SBa wa 12/
/97 Official Record Copy 12/
/97 12/
/97
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++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 2055&4001 Deceriber 16, 1997 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONALINFORMATIONON THE STRUCTURAL ASPECTS OF THE SPENT FUEL POOL STORAGE RACK MODIFICATIONAT GINNA NUCLEAR POWER PLANT (TAC NO. M95759)
Dear Dr. Mecredy:
The NRC staff reviewed the report with respect to the application for the modification of the spent fuel pool storage racks submitted by the Rochester Gas and Electric Corporation (RG&E) for Ginna Nuclear Power Plant and issued a request for additional information (RAI). RG8 E submitted responses to our RAI and the staff reviewed the responses.
Based on the review, we need additional information as shown in the enclosure to complete our review.
Please provide your response as soon as you can to support your schedule for completion of this action.
Sincerely, uy S. Vissing, Senior Project Manager Project Directorate I-1 Divison of Reactor Projects - I/II Docket No. 50-244
Enclosure:
Request for Additional Information cc w/encl: See next page
Dr. Robert C. Mecredy R.E. Ginna Nuclear Power Plant CC:
Peter D. Drysdale, Senior Resident Inspector R.E; Ginna Plant U.S. Nuclear Regulator Commission 1503 Lake Road Ontario, NY 14519 Regional Administrator, Region I
U.S. Nuclear Regulatory Commission 475 Altendale Road King of Prussia, PA 19406 Mr. F. William Valentino, President New York State Energy, Research, and Development-Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Nicholas S. Reynolds Winston & Strawn 1400 L St. N.W.
Washington, DC 20005-3502 Ms. Thelma Wideman Director, Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31 Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 111 West Fall Road, Room 11 Rochester, NY 14620 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, Tenth Floor Albany, NY 12223
RE UEST FOR ADDITIONALINFORMATIONON THE STRUCTURAI ASPECTS OF THE SPENT FUEL POOL STORAGE RACK MODIFICATIONAT GINNANUCLEAR POWER PLANT DOCKET NO. 50-244 1.
In the staffs September 5, 1997, request for additional information (RAI), you were requested to provide detailed discussions as to how the dynamic fiuid coupling (FLUID38 of the ANSYS Code) was modeled in your single-and multi-rack analyses.
In your response (Reference 1),
you indicated that the dynamic fluid coupling used is based on a rectangular body vibrating in fluid contained in an annulus created by a rectangular outer body. The staff understands that your approach may be one approximate way of modeling the fluid-structure interaction for the single-rack analysis.
However, your approach may not be applicable for modeling the structure-fluid-structure interaction of the multi-rack analysis considering the fact that the fluid and structural responses of the multi-rack system are somewhat random and independent between rack to rack in a three dimensional space under safe shutdown earthquake (SSE) loading.
RG&E is 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 technical justifications for using such modeling.
(b) An example calculation of a multi-rack analysis that demonstrates the adequacy of your dynamic fluid coupling model explained in item (a) above.
(c) You indicated on page 108 of Reference 2 that the nodal points of a rack used in the multi-rack analysis are shown in Figure 3.5-40 of Reference 2. However, Figure 3.5-40 does not show any information related to the nodes and elements of the rack models used.
Submit a model drawing with complete information (i.e., element and node numbers with their locations in the global coordinate system, spacing between racks, common node numbers, etc.). Also, submit the ANSYS input data in ASCII for the 3-D multi-rack analysis with complete information (i.e., artificial time history input motions, loading conditions, boundary conditions, material properties, loading steps, etc.) on a 3.5-inch diskette.
2.
In the staffs RAI dated September 5, 1997, you were requested to provide a power spectral density (PSD) of the artificial time history to demonstrate the adequacy of the time history.
You provided a PSD of the time history (SSE1-X) with a PSD function developed from Regulatory Guide (RG) 1.60 spectrum (NRC-0.2G shown on page A-8 of Reference 1). It is interesting to note that the SSE1-X PSD contains energy that is more than about 1.4 to 1.8 times the energy of the NRC-0.2G PSD.
RG&E is requested to provide the following:
Enclosure (a) Technical discussion of the details as to how the NRC-0.2G PSD was developed.
- Also, provide sample calculations.
(b) The time histories used for the development of the two (SSE1-X and NRC-0.2G) PSD on a 3.5-inch diskette.
(c) A comparison between the response spectra (RS) developed using the two time histories indicated in item (b) above.
3.
In the staffs RAI dated September 5, 1997, you were requested to provide the results of any existing experimental studies that verify the correct or adequate simulation of the fluid coupling utilized in the ANSYS analyses for the fuel assemblies, racks and walls. You provided a comparison study between the results of an ANSYS analysis and an experimental test. The staff reviewed the comparison study and concluded that the study is not sufficient to demonstrate the adequacy of the ANSYS code used to simulate the dynamic fluid coupling and the structure-fluid-structure interactions due to; (i) the conditions of the experimental setup (i.e., boundary conditions, dimensions and shapes of the structure, application of the load, etc.) are so different from the real conditions of the rack structures and (ii) very limited test data are obtained and presented.
It is the staffs understanding that RGB E's contractor, Framatome, has been conducting two series of the rack tests in France since August of 1994. The first series of tests is to study the fluid-structure interaction in a storage pool and the second series of tests is to study the behavior of storage racks (one full-scale and one 1/2-scale model).
RGB E is requested to submit:
(i) the detailed testing descriptions, (ii) the status of the test program, and (iii) comparison studies between the results of the experimental tests and the ANSYS predictions.
Reference:
"Response to Request for Additional Information - Spent Fuel Pool (SFP) Modification-Structural Design Considerations (TAC No. M95759), R.E. Ginna Nuclear Power Plant, Docket No. 50-244," Letter dated October 20, 1997, from RG&E to U.S. NRC.
2.
"Application for Amendment to Facility Operating License, Revised Spent Fuel Pool Storage Requirements, Rochester Gas and Electric Corporation, R.E. Ginna Nuclear Power Plant, Docket No. 50-244," Letter dated March 31, 1997, from RG8 E to U.S. NRC.