ML20248E800
| ML20248E800 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/01/1998 |
| From: | Williams J NRC (Affiliation Not Assigned) |
| To: | James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| TAC-M99824, NUDOCS 9806030455 | |
| Download: ML20248E800 (7) | |
Text
_ - _
s-Mr. James Krsubel Junw 1, 1998
- G Chir,f Nuctur Officar Power Authanty of tha Stata of New York 1
' 123 Main Street LWhite Plains,' NY-10601, GUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT-REQUEST FOR l
ADDITIONAL INFORMATION REGARDING INSTALLATION OF ADDITIONAL GPEiNT FUEL POOL RACKS (TAC NO. M99824) ya
Dear Mr. Knubel:
By letter dated October 14,1997, the New York Power Authority requested amendment of the operating license of the James A. FitzPatrick Nuclear Power Plant to permit installation of -
additional spent fuel rack capacity. The NRC staff has determined that additional information will be required in order to complete its review of the structural design to the additional rack capacity.
i The additional information required is discussed in the enclosure.
l Your prompt response to this request will assist the staff in its effort to complete this review in a l
timely fashion.; Please contact me at (301) 415-1470 if you have any questions on this topic.
Sincerely.
Original Signed by:
Joseph F. Williams, Project Mar'ager Project Directorate I-1 i
Division of Reactor Projects - 1/Il i
i Office of Nuclear Reactor Regulation l
l Docket No. 50 333 I
Enclosure:
Request for Additional
- Information cc w/ encl: See next page i
DISTRIBUTION:
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PDR ADOCK 05000333 P
Mr. Jrmss Knubel Junu 1, 1998 Chl:f Nucizr Officer
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Power Authority of the State of s
New York 123 Main Street White Plains, NY 10601
SUBJECT:
JAMES A. FiTZPATRICK NUCLEAR POWER Pl. ANT-REQUEST FOR ADDITIONAL INFORMATION REGARDING INSTALLATION OF ADDITIONAL SPENT FUEL POOL RACKS (TAC NO. M99824)
Dear Mr. Knubel:
By letter dated October 14,1997, the New York Power Authority requested amendment of the operati.g license of the James A. FitzPatrick Nuclear Power Plant to permit installation of additional spent fuel rack capacity. The NRC staff has determined that additionalinformation will be required in order to complete its review of the structural design to the additional rack capacity.
The additionalinformation required is discussed in the enclosure.
Your prompt response to this request will assist the staff in its effort to complete this review in a timely fashion. Please contact me at (301) 415-1470 if you have any questions on this topic.
Sincerely, Original Signed by:
Joseph F. Williams, Project Manager Project Directorate 1-1 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
Request for Additional information cc w/ encl: See next page DISTRIBUTION:
Docket File S. Little PUBLIC J. Williams P.I.-1 R/F OGC J. Zwolinski ACRS S. Bajwa C. Hehl, Region I Y. Kim DOCUMENT NAME: G:tFITZ\\M99824.RAI To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with j
attachment / enclosure "N" = No copy l
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[****+,o June 1, 1998 Mr. James Knubel Chief Nuclear Officer Power Authority of the State of New York i
123 Main Street White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT-REQUEST FOR ADDITIONAL INFORMATION REGARDING INSTALLATION OF ADDITIONAL SPENT FUEL POOL RACKS (TAC NO. M99824)
Dear Mr. Knubel:
By letter dated October 14,1997, the New York Power Au;hority requested amendment of the operating license of the James A. FitzPatrick Nuclear Power Plant to permit installation of additional spent fuel rack capacity. The NRC staff has determined that additional information will be required in order to complete its review of the structura! design of the additional rack capacity.
The additionalinformation required is discussed in the enclosure.
Your prompt response to this request will assist the staff in ite effori to complete this review in a timely fashion. Please contact me at (301) 415-1470 if you have any questions on this topic.
Sincerely, Joseph F. Williams, Project Manager Project Directorate I-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
Request for Additional Information cc w/ encl: See next page
f James Knubei James A. FitzPatrick Nuclear Power Authority of the State Power Plant of N.sw York cc:
Mr. Gerald C. Goldstein Regional Administrator, Region i Assistant General Counsel U S. Nuclear Rogulatory Commission Power Authority of the State 475 Allendale Road of New York King of Prussia, PA 19406 1633 Broadway New York, NY 10019 Mr. F. William Valentino, President New York State Energy, Research, Resident inspector's Office and Development Authority U. S. Nuclear Regulatory Commission Corporate Plaza West P.O. Box 136 286 Washington Avenue Extension Lycoming, NY 13093 Albany, NY 122034 399 Mr. Harry P. Salmon, Jr.
Mr. Richard L. Patch, Director Vice President - Engineering Quality Assurance Power Authority of the State Power Authority of the State of New York of New York 123 Main Street 123 Main Street White Plains, NY 10601 White Plains, NY 10601 Ms. Charlene D. Faison Mr. Gerard Goering Directer Nuclear Licensing 28112 Bayview Drive Power Authority of the State Red Wing, MN 55066 of New York 123 Main Street Mr. James Gagliardo White Plains, NY 10601 Safety Review Committee 703 Castlewood Avenue Supervisor Arlington, TX 76012 4
Town of Scriba Route 8, Box 382 Mr. Arthur Zaremba, Licensing Manager Oswego, NY 13126 James A. FitzPatrick Nuclear Power Plant Mr. Eugene W. Zeltmann P.O. Box 41
' President and Chief Operating Lycoming, NY 13093 Officer Power Authority of the State Mr. Paul Eddy of New York New York State Dept. of 99 Washington Ave., Suite No. 2005 Public Service l
Albany, NY 12210-2820 3 Empire State Plaza,10th Floor Albany, NY 12223 Charles Donaldson, Esquire Assistant Attomey General New York Department of Law 120 Breadway New York, NY 10271 i
.M
t ftEQUEST FOR ADDITIONAL INFORMATION INSTAlt.ATION OF ADDITIO_NAL SPENT FUEL STORAGE RACKS 1
JAMES A. FITZPATRICK NUCLEAR POWER PLANT 1.
You indicated on page 6-3 of Reference 1 that two-dimensional (2-D) single rack analyssa were performed. However, Appenoix A of Chapter 6 of Reference 1 has three dirnensional (3-D) single rack analyses results without providing the displacements in the z-direction. Did you perform the 3-D single rack cnalyses? If you did, provide the displacements in the z-direction, if you did not, provide the 3-D single rack analyses results.
1 2.
Run I.D. djaf-n3.if8 of Reference 1 predicts the maximum displacement of 0.1313 inch in x-direction at the top comer of a rack. Provide: (1) the physica! dimensions of the rack, j
(2) ali calculated displacernents in x, y-and z-directions at the top anc' baseplate comers when the maximum displacement in x-direction equals 0.1313 inch, and (3) masses, i
velocities, natural frequencies of the rack when the maximum displacement in x-direction equals 0.1313 inch.
3.
Provide the complete input data for Run I.D. djaf-n3.!!2, Run I.D. djaf-n3.ifC, Run LD. djaf-n3.ih2 and Run I.D. djaf-n3.ih8 in ASCil format on a 3.5-inch di:,kette and in hard copy.
1 4.
In general, a 3-D multi-rack analysis provides more criticalinformation for ovaluating structural integrity of racks than a 3-D single rack analysis does. However, you did not provide 3 D multi-rack analyses results. Provide them.
5.
Provide the time historv input data for the operating basis earthquake (OBE) and design basis earthquake (DBE) used in the rack analyses on a 3.5-inch diskette in ASCll format and in hard copy. Discess how you developed the actual and target power spectra densities (PSD).
6.
With respect to the dynamic fluid-structure interaction enslysis using the computer code, DYNARACK, in Reference 1, provide the following:
a) Since a cornposite stick inodel can not represent accurately and realistically the actual highly complicated nonlinear hydrodynamic fluid-rack structure interactions and behav;or of the fuel assemblies and the box-type rack structures in a dynamic analysis, indicate whether you or your contractors actually have performed fluid-rack structure interaction analyses with 3-D finite element plate, beam and fluid elements, b) Provide the results of any existing realistic experimental study that verifies the correctness or adequacy of the simulaticn Of the fluid coupling utilized in the numer! cal analysec for the fue! assemblies, racks and walls, if there is no full scale experimental study available, provide information to demonstrate thot the current level of the DYNARACK code verification is adequate for engineering application. if ava:lable, submit the results of the stick and continuum (plate / beam) model analyses. These results are needed to establish areas of maximum stresses, and the detailed structural design.
Enclosure
1 a
.I
!. l c) Indicate whether you had any numerical convergence and/or stability problem (s) l during the nonlinear, dynamic single-and multi-rack analyses using the DYNARACK code. If so, how did you overcome the problem? Also, indicate whether the l
DYNARACK program can correctly evaluate the nonlinear material behavior of structures. If not, how the program evaluates the nonlinear structural problems?
d) Indicate whether or not you have performed fluid-rack structure interactions where the fluid was tmated as air to verify the accuracy and capability of the DYNARACK code. If you have done this, provide the results of the study and any conclusions you have made from the study (i.e., numerical stability, convergence, etc.).
7.
The staff is also reviewing an application for the modification of the spent fuel pool storage racks for Vogtle Electric Generating Plant submitted by Southem Nuclear i
L Operating Corspany, Inc. (Reference 2). In Reference 2, your contractor, HOLTEC, predicts negative dynamic pressure using the DYNARACK program. Indicate whether or not negative dunamic pressure was predicted in your rack analyses. !f yes, provide the following:
a) Explain the physical meaning of the negative dynamic pressure.
b) Explain how the DYNARACK program calculates the negative dynamic pressure.
l c) Indicate whether or not you have observed any negative absolute pressure (static plus dynamic pressures) from your rack analysis, if you have, explain the physical l
meaning of the negative absolute pressure.
d) The staff believes that absolute, static and dynamic pressures should be continuous along the rack structure. If the analysis for your racks predicted discontinuity of hydrodynamic pressures, explain the physical meaning of the discontinuity and what causes it. Provide a calculation that demonstrates the correctness of such discontinuity. This may be a simple hand calculation.
8.
With respect to the analytical simulation of the rattling fuel assembly impacting against the cell for the racks:
a) How was the magnitude of the largest impact force and the location of the impact in L
the fuel assembly and the cell wall calculated?
b) How did you determine and analyze the fuel assembly and cell wall integrity?
Provide sample calculations for a fuel assembly, c)
Discun the considerations given to the effects of the fluid between the fuel assembly and ccil wall during the interactions.
d) Provide available experimental studies that verify the reasonableness of the numerical simulation adopted to represent the fuel assembly and cell wall interaction.
e) Provide the maximurri kinetic en'ergy between the fuel assembly and cell wall during the impact including masses, accelerations, velocities, natural frequencies and impact forces.
l
m.
e
. f)
Provide the physical dimensions of the fuel assemblies, and gaps between the fuel assenblies and the cell walls.
)
9.
With respect to the spent fuel pool (SFP) structural analysis, provide the following:
a) Plan view of the SFP and physical dimensions of the reinforced concrete slab and walls, liner plate and liner anchorage.
i b) A copy of the mesh used in the analysis, c)
Boundary conditions used.
d) Material properties (i.e., modulos of elasticity, shear modules, poison's ratio, yield stress and strain, ultimate stress and strain, etc.) of the liner plate and liner anchorage used in the analysis, e) Applied loading conditions including the magnitudes and their locations in the mesh.
f)
An explanation of how the interface between the liner and concrete slab is modeled, how the liner anchors are modeled, and the basis for using such modeling with respect to how they accurately represent the real structural behavior, g) The complete analysis results in a tabular form including: (1) factors of safety with respect to bending, shear and axial forces for SFP walls and slab and (ii) shear stress, strain, deflection and reaction forces for the liner plate and liner anchor.
10.
Discuss the quality assurance and inspection programs to preclude installation of any irregular or distorted racks, and to confirm the actual fuel rack gap configurations with respect to the gaps assumed in the DYNARACK analysos afterinstallation of the racks.
11.
Indicate whether or not you are planning to place an overhead platform on the racks pemlanently or for temporary storage during the installation of the racks.
12.
Describe the plan and procedure for the post operating basis earthquake inspection of fuel rack gaps and configurations.
References:
1.
" James A. FitzPatrick Nuclear Power Plant, Docket No. 50-333, Proposed Change to the Technical Specifications Regarding Design Features (JPTS-96-012)," Letter dated October 14,1997, from New York Power Authority to U.S. NRC.
2.
"Vogtle Electric Generating Plant Request for Revise Technical Specifications Additional Fuel Storage Racks for Unit 1 Fuel Storage pool," Letters dated September 4 and November 20, t997, from Southem Nuclear Operating Company, Inc. to U.S. NRC.
,