ML20196G065
| ML20196G065 | |
| Person / Time | |
|---|---|
| Site: | 07200022 |
| Issue date: | 06/24/1999 |
| From: | Srinivasan R AFFILIATION NOT ASSIGNED |
| To: | |
| Shared Package | |
| ML20196F952 | List: |
| References | |
| ISFSI, NUDOCS 9907010043 | |
| Download: ML20196G065 (9) | |
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of
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PRIVATE FUEL STORAGE L.L.C.
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Docket No. 72-22
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(Private Fuel Storage Facility)
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DECLARATION OF RAM SRINIVASAN Ram Srinivasan states as follows under penalties of perjury:
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I am Manager of Design Engineering at BNFL Fuel Solutions (formerly Sierra Nuclear Corporation).. In that position I am responsible for the analysis and design of TranStor storage and transportation casks and related components. I am providing this affidavit in support of a motion for partial summary disposition of Contention Utah R in the above captioned proceeding to describe the ability of the TransStor spent fuel storage cask, to be used at the Private Fuel Storage Facility (PFSF), to withstand heat and temperatures under fire conditions.
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My prcfessional and educational experience is summarized in the curriculum vitae attached as Exhibit I to this affidavit. I have over 25 years of experience in the design of nuclear power plants. I have panicipated in and coordinated the design and analysis of dry cask spent fuel storage and transportation systems, including the TranStor and the VSC-24 designs, and I have contributed to the Safety Analysis Repons of both the TranStor*
and VSC-24.
S 3.
I panicipated in, and am knowledgeable regarding, the design of the TransStor system spent fuel storage cask, in particular its capability to withstand heat and temperatures under fire conditions. Specifically, the TranStor storage casks, to be used 9907010043 990628 PDR ADOCK 07200022 C
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at the PFSF, are highly resistant to the effects of fire, as described in the Safety Analysis Report (SAR) for the TranStor Storage Cask at section 2.3.6 (attached as Exhibit 2).
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The TranStor spent fuel storage cask system consists of a sealed, cylindrical, steel basket or canister (containing the spent fuel assemblies and pressurized helium gas) standing on end inside a ventilated, steel-lined, hollow concrete cylinder. The cask is 222.5 in. high and 136 in. in diameter. The concrete cylinder is 29 inches thick. The TranStor spent fuel storage cask system is depicted in the PFS SAR in Figure 4.2-4.
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As described in section 2.3.6 of the TranStor* storage cask SAR, the thick concrete walls of the TranStor* storage cask protect the spent fuel from the effects of fire. While I
exposing the storage cask to an ambient air temperature of about 1500 F. might cause the concrete near the surface of the cask to lose some ofits strength, it would not threaten the integrity of the casks or the spent fuel inside them. It would take a continuous exposure for a period much greater than the duration of a fire that might result from a spill of 50 gallons of diesel fuel before much of the cask wall thickness would experience a temperature above its design limit, due to the low thermal conductivity and the high specific heat of the concrete. Thus, the storage cask would protect the canister and the spent fuel from the effects of any fire at that temperature for that duration.
6.
The potential for a TranStor" spent fuel storage cask to be damaged by the heat from a fire depends on the total amount of energy absorbed by the cask from the fire. I have reviewed PFSF SAR Section 8.2.5, which analyzes the effects of a fire resulting from a spill of 50 gallons of diesel fuel from the PFSF spent fuel storage cask transporter vehicle, and the declaration of Jeffrey Johns, in which he analyzes the effects of a fire resulting from diesel fuel spills. A 50-gallon diesel fuel fire encircling a TranStor spent fuel storage cask either inside or outside the PFSF canister transfer building would be expected to result in temperatures ofless than 1475 'F. at the surface of the TranStor cask for no j
more than five minutes. S AR at 8.2-25, -27; Johns Dec. at 17. While such a fire might cause the very surface of the hollow concrete cylinder surrounding the spent fuel canister to lose a portion ofits strength, the concrete would not disintegrate from an exposure to L
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flame temperatures ofless than 1475 F; nor would the fire threaten the integrity of the i
spent fuel inside the canister. Furthermore, because the duration of a 50-gallon diesel fuel fire would be so shon, very little of the concrete would even suffer this effect. Therefore, such a fire would have no detrimental effect whatsoever on any other components of the TranStor* cask system or the spent fuel contained inside and it would not cause a release ofradioactivity.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on June %_,1999.
Me Ram Srinivasan
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SRINIVASAN Exhibit 1 i
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l INDIVIDUAL EXPERIENCE RECORD Dr. Ram Srinisasan 1168 Lone Pine Lane San Jose, CA 95120 Telephone: (408) 268 ?985 E mail: RSnnisasa aaol com EDUCATION:
BE in Civil Engineenng (with honors). University of Madras MS m Civil Eagmeenng. University ofIllinois MS in Business and Taxation. San Jose State University Ph.D m Civil Engineenng University ofIllinois PROFESSIONAL ACTIVITIES:
Member. American Society of Civil Engineers PROFESSIONAL REGISTRATION:
Professional Engineer. Illinois and California Structural Engmeer, State ofIllinois PUBLICATIONS AND REPORTS:
Several technical papers in ASCE and other technical societies on vanous topics. including Piping Analysis. Seismic Soil Structure Interaction. Post-Earthquake Analysis, Blast Analysis, inelastic Seismic Analysis of Fossil Fuel Boiler Structure, Limit Design Fatigue Strength of High Strength Steel, etc.
(See attached List of Publications.)
EXPERIENCE
SUMMARY
Dr. Ram Srinivasan is presently the Manager of Design Engineering at BNFL Fuel Solutions. He has participated in and coordinated the design and analysis of dry cask spent fuel storage and transportation systems. The systems include the Transtor* and VSC 24 designs. He has also contnbuted to the vanous secnons of the safety analysis reports of the TranStor* and VSC 24 systems.
Dr. Srinivasan has a PL.D. in Civil Engineering from the University ofIllinois, Urbana - Champaign, Illinois. He has over 25 years of experience in the design of nuclear power plants. For ten years he has been a consultant to the Electric Power Research Institute, Palo Aho, Califomia. He has actively participmad in the various phases of the Advanced Light Water Reactor ( ALWR) Program. This experience includes the preparation of the Utility Requirements Document (Evolutionary and Passive Plants), Design Certificanon of the various vendor designs, and Conformance Assessment of the vendor designs to the utility requirements. He has also pamcipated in the Life Cycle Cost Reduction Programs, l
meluding Operation and Maintenance Costs.
Dr. Srmivasan has extensive experience in engineenng and project management of power plant structures i
and components. He held positions as Head of Structural Engineerms Specialist Section at Sargent and I
Lundy, Cnicago (1972 - 1980); Project Manager of several piping projects at Quadrex Corporation, Campbell, CA (1980-1982); and Senior Consultant at S. Levy Inc. (1984-1994). Exponence includes structural and engineering mechanics, structural dynamics including seismic analysis and design, piping i
and pipe supports, ar ~ yptication of ASME, ACl, ASCE, ANSI Codes and Standards.
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Page 2 Provided technical training and project man.gement for a number of utility and utilities in several costs savtng projects: elimmating unnecessary requirements from p spectftcations, efficient design of small bore piping, snubber reduction programs, etc.
SPECIFIC PROJECTS Day Cask Storage and Transportation Casks Partteipated in and coordinated the d cask spent fuel storage and transportation systems. The systems melude the TranStor* a designs. The design meludes the consideration of pressure, thermal. handling and canhquake, flood etc.). He has also contnbuted to the vanous sections of the safety Transtor$ and VSC 24 systems.
EPR/ Advanced Light Water Reactor Program. Key participant in the development of Requttements Document (URD) and assessment of vendor designs (ABWR SBWR. and A conformance to the URD.
Third Party Review ofthe Commanche PeakSteam Electric Station. As a Group Leader of the Civ ti, Structural discipline, reviewed the design of tne various structures. seismic (equipment, cable tray, conduit. etc.) supports. Also reviewed the structural design interfac NSSS Vendorand Architect Engineer.
Pipe Support Reduction program. Reviewed existing desip of Small Bore Piping based on Engineer Simplified Dynamic Analysis (SDA). Analyzed sample lines using the compute and identified removal of those supports not required. Summanzed conservatisms and limi SDA.
Review ofASME Class / Piping Stress Reports. Prepared detailed checklists based on ASM requirements (NA-3300) for Owner Review of Stress Reports Reviewed all ASME Clas Reports using the checklists.
/nde' endent Aaview ofMark / ContainmentStudy:
p Reviewed Plant Unique Assessment Report (PUAR) for the Duane Arnold Energy Center. The review included comparison of the NRC req utility commitments. The reports were then reviewed in light of the NRC requirements commitments.
Review o/Saismic Qual #Icarion o/Mschanical Egwipment. Performed an independent review requalification of mechanscal equipment (ECCS pumps, fuel racks, etc.).
i Technical Training. Established and presensed training courses to utility engmeenng staff. S were presented to different utilities. The source material included (1) Introduction to the ASME C Piping Design and Analysas;(3) Pressure Vessel and Component Desip.
i Litigerson Accord Aaview. Reviewed the litiganon records for Houston Lighting and Powe identification of any deficiencies in ths J.;ign and construction of the South Texas Plants.
In-depth enehmma Review of Piping Stress Analysis and Support Design performed by Brown &
conneenon with litiganon of the South Texas Project (client Houston Light and Power \\
Technical assistance to Commonwealth Edison Co. on their Snubber Reduction Programs for LaSall County Stations (BWR) and Byron Stanons (PWR).
PUBLICATIONS 1.
"On-Site Staffing Requirements for a Simplified Boiling Water Reactor (SBWR)," presented at the ICONE 4 Conference in New Orleans, Louisiana, March 1996.
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Dr. Ram Srinisasan
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"A Snubber Reduction Pilot Program." presented at the ASME Pressure Vessel and Piping Conference, Chicago, June 1986.
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" Economic Application of Computer Analysis to Small Bore Pipmg Design." Presented at ASME Pressure Vessel and Pipmg Conference. Portland, Oregon, June 1983.
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- Application of Frequency Response Method in Post Earthquake Analysis.' Presented at Sixth SMtRT Conference, Paris. August 1981.
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-Blast Effecu on Safety-related Structures." Presented at Second ASCE Specialty Conference on Structural Design of Nuclear Plant Facilities, New Orleans. Louisiana, December 1975.
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" Response of Suspended Boilers to Earthquake Motions." Presented at ASCE, Power Division, Specialty Conference on Electne Power and the Civil Engmeer, Boulder, Colorado, August 1974 7.
"Three Dimensional Soil Structure Seismic Analysis Using Finite Elements." Presented at ASCE Conference on Structural Design of Nuclear Plant Facilities, Chicago, December 1973.
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"!nelastic Response of Steel Frames to Simulated Earthquake Motions." Ph.D. Doctoral Dissertation, Department of Civil Engineering, University of Illinois, Urbana, May 1972.
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" Fatigue Strength of Bolted High Strength Structural Steel."Jornal ofthe Struerwal Division.
3 Proceedings of ASCE. March 1971.
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SRINIVASAN Exhibit 2 l
p-I SAR-TranSt:r* Storage Cask Revision C Docket No. 72-1023 November 1998 2.3.6 FIRE AND EXPLOSION PROTECTION No significant fires are expected at the ISFSI. No combustible materials are stored in its proximity. The only transient combustible used within the ISFSI would be the gasoline or diesel fuel in towing vehicles used to move the casks. When these vehicles are in use, they move at very slow speeds and are accompanied by the plant personnel who would detect and suppress any small fires associated with fuel leaks. The ISFSI is protected from industrial and forest fires by the distance between combustibles and the ISFSI casks and by the open areas surrounding the ISFSI. Therefore, significant fires would not be credible at most ISFSI sites.
I Nevertheless, the TranStor* Storage System design is highly resistant to the effects of fire. He thick concrete walls are capable of protecting the basket containing irradiated fuel. Although the exposed layer of concrete may lose a portion of its strength, it would not disintegrate from an exposure to flame temperatures on the order of 1,500 'F (as specified in 10 CFR 71). In addition, any fire would be required to bum for a long time (days) before much of the wall thickness would be affected. Derefore, the cask is capable of being safely unloaded should it be determmed that a fire was significant enough to warrant such an action.
Likewise, no explosions of any significance are possible at the ISFSI site. However, the cask resistance to explosion overpressure is evaluated in Chapter 11.0. As demonstrated by the analysis, the cask can withstand any potential explosion that could occur at an industrial facility located reasonably close to the ISFSI.
2.4 DECOMMISSIONING CONSIDERATIONS c
The first step in decommissioning the TranStor" Storage System is to move the fuel. His can be done in a number of ways. Various potentials are discussed in References 2.3 and 2.4.
The baseline d=v===ianianing plan for a TranStor" Storage System site is to transfer the basket into a TranStor* Shippmg Cask and ship the basket and the empty storage cask to a federal or private C"V9.yQ facility. This decommismoning method involves the least burden on the utilities because it avoids opening the basket and re-handling of fuel assemblies, minmuzes radiation does to workera, and provides a usable storage cask to the downstream facility.
However, this is only one of many altamatives, as discussed in Refcences 2.3 and 2.4.
If the worst case scenario evolves and the downstream facility is not available, the TranStor*
Storage System would be unlandai (in the sequence that is==*intly the reverse ofloading) into the fuel pool. After that the storage cask and basket could be reused for other on-site waste storage or disposed ofin a normal InndA11 (the storage cask) and at a low-level waste burial facility (the basket). Because the basket exterior is clean and doesn't contact the storage cask intenor, no 2-19
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