ML20205P398
| ML20205P398 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1987 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20205P343 | List: |
| References | |
| FOIA-87-156 NUDOCS 8704030258 | |
| Download: ML20205P398 (28) | |
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_FY 1986 PHASE I AWARDS CCtTRACT NUMBER CONTRACTOR AND Cor: TRACT TITLC CONTF:ACT AMOUNT
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- h !!RC-04-86-129 Structural Analysis Technologies, Inc.
$47,795.0'O "Igrovement of Safety of Piping.
Systems Using Nonlinear Analysis Nethods" NRC-04-86-130 REN Technologies. Inc.
S49,500.00 f
" Test l'.ethod for Identifying Shaf t Y
Cracks" NRC-04-86-131 Future Resources Associates, Inc.
$50,000.00 "Extencing a HCLPF-Based Seismic Margin Review to Analyze Plent Demege States and the Role of Human Factors and Non-Seismic Failures" HRC-04-86-132 Geoscience. Ltd.
149,82$.00 "A Proposal for a Radioactive Waste Accountability System Based on Heat Release Monitoring: A Demonstration Program"
'#""" MNRC-04-86-133 Weste Management Group S48,000.00
" Evaluation of Uncertainties in Irradiated Hantware Characterization" i
NRC-04-86 134 Pickard Lowe and Garrick, Inc.
$49,949.00 i
" Calibrating Hethods for Export Opinion Use in Risk Studies" NRC-04-86-135 Pentek, Inc.
$50,000.00 "Developent of Testing and Analysis Hethodology to Determine Functional l
Condition of Scienoid-Operated Valves Used in Nuclear Power Plant Sefety f2C-04-85-1X Analysis nnd !4asuresid;nt Services
$49.037.00 Corporatioi:
"Pegradetion et Nuclear Plant Teapcrature Seiisors" j
f:RC-04-86-137 Quantex Corporation
$49,637.00 "Integroting Fiber Optic Radiatic,n Ucsimeter" Fo/ A 15' B704030258 870331 PDR FOIA A/t l
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I APPENDlX 6 U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS ]NNOVATION RESEARCH PROGRAM (SBIR-8dp)
.1 PHASE I - FY 19ff I
PROJECT
SUMMARY
FOR NRC USE ONLY j
Program Of fice TIM Proposal No.
Jopic ho.
TO BE COMPLETED 8Y PROPOSER Name and Ac' dress of Proposer Structural Analysis Technologies, Inc.
1 10440 South De Anza Boulevard, Suite D7 Cupertino, California 95014 Name and Title of Principal Jnvestigator Dr. Hasan Kamil, President Title of Project Improvement of Safety of Piping Systems Using Nonlinear Methods
_ Safety of Piping Systems Subjected to Dctreme W_ingsTechn
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Technical Abstract (Limit to 200 words) 1 The purpose of the proposed research is to improve the safety of the A
piping systems subjected to loadings with a wide range of frequency content (e.g.
pressurized thermal shock, water hammer, and seismic loadings).
This will be done by showing that the safety of the piping systems can be significantly improved by using nonlinear (inelastic) procedures because of utilization of the significant additional energy absorption capacity available.
The proposed Phase I efforts will include investigation of the feasibility, licensability, ease of use, and economics of nonlinear methods for analysis of piping systems, development of a strain-based acceptance criterion, and development of a simplified nonlinear analysis. procedure.
A detailed development will be continued in Phase II.
Ant c pa ed Result If cation of the Approach (both Phase I and II/ Potential Conynercial It is anticipated that after completion of Phase II efforts, it may be possible to convince NRC to allow nonlinear procedures to be used for piping systems on a routine basis.
This will significantly help improve the safety margins for piping systems by showing that the realistic forces in piping systems are significantly lower than the linear procedures show, by helping significantly reduce snubbers, and by producing realistic, rational, economic and safer designs of piping cy-t --
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Paga 2 APPEN0!X 8 U.S. NUCLEAR REGULATORY COMNIS$10N SMALL BUSINESS ]NNOVAT10N RESEARCH PROGRAN
- ates4S% (sBIR-86)
PHASE I - WO999F FY 1986 PROJECT
SUMMARY
i FOR NRC USE ONLY Program Office TTM Proposal No.
Topic No.
Name and Address of Proposer TO BE COMPLETED BY FROPOSER REM Technologies. Inc.
1913 Central Ave.
Albany. N.Y.
12205 Name and Title of Principal Investigator William H. Miller. P.E.
Title of Project Principal Engineer-Mechanical Design Testing Method for Identifying Shaft Cracks' Technology. Research Thrust and/or Potentf41 Commercial Applicat f
RCP Shef t Crack Detection /All Nuclesr Power Plantm Technical Abstract (Limit to 200 words)
A test method for reliably and easily evaluating the condition of a the nuclear industry to evaluate these shaft systems on-site reactor coolant pump g*,,
ng would enable method which can be applied to identify 'the presence, size and loca tion ofThis proj a vertical RCP shaft system.
shaf t cracks in necessary " tools" will permit the definition of a test method wh cbjectives while accounting for the boundary conditions Particular to an RCP sh ect It is anticipated that a procedure will result that may be used in any n s ys't em.
to assess the RCP shaf t system.
uclear power plant App 1tcation of ResearchAnticipated Results/Impitcation of the Approach (both mercial Phase I will verify the theoretical analysis and demonstrate that be u ed to identify the presence of a vertical shaft. crack.
the test procedure can s
Phase II will refine the test method and account for the boundary co diti with an RCP shaft system.
n ons associated cpplied to any RCP shaf t system. Phase II will result in a test method which can ea ily be s
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APPENDIX 8 U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-86)
PHASE 1 - FY 1986 PROJECT
SUMMARY
FOR NRC USE ONLY Progree Office iTM Proposal No.
Topic,No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer
^
Future Resources Associates, Inc.
2000 Center Street, Suite 418 Berkeley, California 94704 Hame and Title of Principal Inv,stigator 4
Robert J. Budnitz, President Title of Project
" Extending a HCLPF-Based Seismic Margin Review to Analyze Plant Damage States and the Role of Human Factors and Non-Seismic Failures" Technology, Research Thrust and/or Potential Commercial Application (Lim Improved methodology for seismic margin reviews of reactors Technical Abstract (Limit to 200 words)
Techniques have recently been developed to analyze the ' seismic margin' of a nuc Starting with an earthquake level chosen for margin review c'
whether the plant can or cannot withstand the review-earthquake without core here ' withstand' means ' withstand with a high confidence of low probability of failur full-scope seismic PRA.This HCLPF-based method can screen a plant's seism However, the insights from the method are limited, partly because those accident sequences that dominate the HCLPF-based analysis are not t selves analyzed further.
HCLPF-based analysis one step further will be explored.In this proposed pro feasible, each key seismic accident sequence could be assigned a plant dam (containing information sbout offsite release magnitude, timing, and probability) the role of human factors and of non-seismic-induced failures could without the need or exnense of a full-scone seismic PRA.
App 1fcation of ResearchAnticipated Results/Impilcation of the Approach (both Pha If the proposed research is successful, the usefulness of NRC's new HCLPF-based and at only slightly greater cost. logy for ' seismic margin reviews' of nuc Decision-makers in both the NRC and the utility will have great use for the additional information produced (about source terms, non-seism induced contributors, and the role of human factors in the key accident sequences.
Several comercial firms that have the capability to perform seismic margin reviews would benefit from this improved methodology.
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APPiND]XB U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINES$ INNOVATION RES(ARCH PROGRAM(SBIR-d)
PHASE I - FY 1989 PROJECT
SUMMARY
FOR NRC USE ONLY
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Prograa Office TTM Proposal No.
Topic hd.
10 BE COMPLE1ED BY PROPOSER Name and Address of Proposer Geoscience Ltd i
410 South Cedros Avenue Solana Beach, CA 92075 Name and litle of Principal investigator i
Heinz F. Poppendiek, President Title of Project f
A Proposal For A Radioactive Waste Accountability System Based On Heat Release Monitoring: A Demonstration Program Technology, Research Thrust and/or Potential Comercial Application (Limit to 8 words)
Long-term remote radwaste monitoring / Radioactive waste accountability Technical Abstract (Limit to 200 words)
The proposed program consists of the development of a technique and a system to measure the radioactive decay of radwaste contained in storage canisters, casks and vaults.
The system being considered deals with the direct measurement of the afterheat being generated in the radwaste volumes. The system to be used to accomplish such measure-ments consists of a heat flux sensor envelope that surrounds a radwaste storage con-tainer so that all heat being generated within the radwaste is accurately monitored as it flows through such a sensor envelope. The envelope also contains a calibra-tion heater system so that the calibration constant (rate of heat release per millivolt l
output signal) for this monitoring system can be determined and verified at any time.
i The millivolt output signal generated by the heat flux envelope is recorded as a function of time.
A series of radwaste heat release demonstrations would be per-f formed utilizing a simulated radioisotope heat source (an electrical heater located
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in a cylindrical container; the container would be positioned underground simulating i
_oractical aoolications).
Application of ResearchA:;ticipated Results/ Implication of the Approach (both Phase I and 1 It is anticipated that the demonstration effort outlined in this proposal will show that the new measurement system will accurately monitor the heat release (and radwaste content) in storage volumes.
It will also be shown that this new accountability method will complement current nuclear radiation techniques in use and satisfy the long-term remote monitoring requirement identified by the government.
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APPENDIX 8 U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-8)
PHASE I - FY 19dp PROJECT
SUMMARY
4 FOR NRC USE ONLY Program Office TTH Proposal No.
Topic No.
Name and Address of Proposer
^
Waste Management Group, Inc.
P. O. Box 579 Crompond, NY 10517 Name and Title of Principal Investigator Peter T. Tulte - President Title of Project Evaluation of Uncertaintics in Irradiated Haroware Characterization Technology, Research Thrust and/or Potential Cormiercial Application (Limit t6' 8 Technical Abstract (Limit to 200 words)Imnrovement of DOE / commercial pract At present, the industry uses many different methods to characterize hardware in terms of its radionuclide content at the time of disposal. All of these methods involve some' form of component raciation profiling to obtain Co-60 estimates A
coupled with scaling of 10CFR Part 61 long lived nuclides found in hardware.
Underwater radiation profiles are obtained under different conditions, with different instruments.
Thus, there are no standards, or criteria, for characterization, which leads to relatively large uncertainties in estimating thc major nuclides which effect classification under Part 61.
Phase I of the proposed project woulo identify current practices ano methods, the data used to support shipment classification, and the uncertainties associated 'with these practices, and bound them. Phase II woulo resuit in the development and field testing of methods which would add consistency to characterization practices and significantly reduce classification uncertainties.
Application of ResearchAnticipated Results/ Implication of the Approach (both Phase Phase I will culminate in the identification of methoc uncertainties and areas where uncertainties can be substantially reduced. This will benefit commercist hardware generators, government regulators at the State and Federal level, and the DOE which will be both a generator and a reelpient of irraolated hardwarc for disposal.
Phase II would demonstrate the standards and improvements to current practices through field testing.
The results of these ficio demonstrations could lead to a revision to the current regulatory criteria applicable to irradiated hardware
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APPEH3IK 6 U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PRO PHASE I - FY 1985 (SBIR-85)
PROJECT
SUMMARY
Program Office FOR NRC USE ONLY TIM Proposal No.
Topic No.
Name and Address of Proposer 10 bl COMPLETED BY PROPOSER Pickard, Lowe and Garrick, Inc.
2260 University Drive Newport Beach, CA 92660 Name anc litle of Principal Investigator Ali Mosleh, Consultant litle of Project Calibrating Methods for Expert Opinion Use in Risk Studies Tecnnology, Research ihrust ano/or Potential C6mercia f
Technical Abstract (Limit to 200 words) Nuclear Industry
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judgment due to the scarcity of empirical data. Assessm reliance on expert the opinions of single and multiple experts will be evaluated in li hIn data.
experts' estimates, as well as the models used fo g t of empirical '
of the comparative analysis of expert opinion and empirical data w s
e define areas for refinement in the existing formal methods s.
The result en be used to applicability in practice.
and in enhancing their events for which both expert estimates and empirical data are a A p1 cation of R 's I ic ti the Approach (both Phase I and II/ Potential CoM t
I Improvements in methods for use of expert opinion in risk studies al l
practical' guidelines for aggregation of conflicting opinions for decisinn
, development of i
ng.
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APPENDIX B U.S. HUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PR0' GRAM (581R-
)
PHASE I - FY 198f6 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TTM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Pentek, Inc.
1026 Fourth Avenue Coraopolis, PA 15108 Name and Title of Principal Investigator Dennis Bodziak, Project Engineer Title of Project Development of. Testing and Analysis Methodology to Determine functional Condition of Solenoid-Operated Valves Used in Nuclear Power Plant Safety Applications Technology, Research Thrust and/or Potential Conmercial Application (Cimit to 8 words)
Improved Testing Methods
. Technical Abstract (Limit to 200 words)
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Pentek will develop and. test a technique to detennine the functionality of solenoid-operated valves in a nuclear power plant based on the-measurement and 9.
analysis of in-rush current. The technique will be developed so that all measurements can be made from outside the reactor building without disturbing any electrical connections. The analysis methods will be developed for on-line use with a personal computer.
i Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercia{
Application of Research i
The results of this study will 1) provide a viable surveillance method for the nuclear' industry to determine the degree of functionality of a solenoid-operated valve and therefore allow appropriate preventive maintenance, and 2) provide the technical basis to extend this technology to other electro-mechanical systems in a nuclear power plant.
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i APPEN0ix 8 U.S. NUCLEAR R[GULA10RY COMMISSION
,35 MALL BU51NE55 INNOVAll0N RE5[ ARCH PROGRAM (581R-26)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office 1TM Proposal No.
Topic No.
TO BE COMPLE1EO 8Y PROPOSER Name and Address of Proposer Analysis and Measurement Services Corporation 4706 Papermill Road Knoxville, TN 37909 Name and Titic of Principal Investigator H.' M. Hashemian, Director of Nuclear Engineering Title of Project Degradation of Nuclear Plant Temperature Sensors Technology. Research Thrust and/or Potential Consnercial Application (LimJt to 8 words)
Degradation; Aging, Response Time, Calibration, In-situ ffonitoring Technical Abstract (Limit to 200 words)
Safety system ' temperature sensors in nuclear power plants are subject to performance degradation because of aging effects.
A program of laboratory testing and in-situ testing is needed to ensure that aging does not lead to reduced safety and availability.
Much of the technology needed for this program now exists as isolated methods and procedures.
These will be used in this project to perform an aging assessment on temperature sensors of the type used in commercial nuclear power plants.
In addition, the currently available in-situ testing methods will be evaluated for on-line monitoring of performance of these sensors.
The results of this project are intended to provide a reasonable interval for periodic testing to ensure that the safety limits are met as the sensors age in the process.
Anticipated Results/Isp1fcation of the Approach (both Phase I and !!/ Potential Connercial Application of Research i
The project will provide typical data on the rate of change of response time and calibration of aging temperature sensors.
In addition, testing methods and testing periods will be identified for monitoring of these changes.
If carried out to phase II, the project will provide the much-needed comprehensive approach to temperature sensor aging assessment.
This will Icad to improved plant safety and availability and will provide sensor manufacturers with useful data for better design of temperature sensors.
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2-u U.S. NUCLEAR REGULATORY COMMISSION.
SMALL. BUSINESS INNOVATION RESEARCH PROGRAM _
(581R-85) i
' PHASE I - FY 1986-PROJECT
SUMMARY
Program Office FOR NRC USE ONLY TTM Proposal No.
t Topic,No.
Name and Address _of Proposer TO 8E COMPLETED BY PROPOSER Quantex Corporation 2 Research Court <.
Rockville. harvland 20850 Name and Title of Principa' Investigator e
Charles Wrigley, Director of Technology 1TipeofProject
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In tegra ting Fiber Optic Radiation Dosimeter Technology Research Thrust and/or Potential Consnercia m
o 8 words Technical Abstract (Limit to 200 words)
The proposed project will demonstrate the feasibility of employing electron trapping- (ET) materials with fiber op i
microprobe radiation dosimeters. TheETmaterialsgic fi1==aats for use as can be interrogated by 4
near-infrared to _ produce visible output scalable to radiation doses at the-fiber tip.- Phase I will assess the performance of such materials as microprobe radiation detectora integrated with fiber optics. During Phase I physical arrangements for integrating the ET materials 2 with the fibers will be defined, sample microprobes will be fabricated and evaluated'for sensitivity, saturation
- levels, storage retention in the ionization environment, read and erase characteristics, long-term materials, and preliminary assessment of radiation hardness. integrity of the' Application of ResearchAnticipated Results/ lap 11 cation of the Approach (both P a
omercial The development of photonic materials for fiber optic dosimeters i
can lead to. new radiation measurement instrumentation. Fiber microprobe dosimeters could have both commercial and governmental applications to determine radiation levels in power generating reactor environs, medical isotope detection, microvolume remote sensing, etc.
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s FY 1986 PHASE II ANARdS' CONTRACT NUMBER CONTRACTOR AND CONTRACT TITLE CONTRACT AMOUNT NRC-04-86-125 SEA Consultants, Inc.
$240,000.00
" Application of Methodology to Evaluate Aging and Service Effects on Plant Performance"
,.s NRC-04-86-126 ESA. Inc.
184,380.00 "In-Vessel Hydrogen Generation for Severe Accidents" NRC-04-86-127 CREARE, Inc,.;
's 208,233.00
" General Model.tng of Conde.nsation N
for Reactor, Applications" NR,C-04-86-127 0'Donnell " Consulting Engineers, Inc.
75,000.00
" Extended Fatique Life haluation Methods for Aged LWR Components" l
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11Et4 6 U.S. NUCL[AR REGUtATORY COMMISSION-SMAtt BUSINESS INNOVA 110N RESEARCH PROGRAM (SBIR 66)
PNAst -11 FY 199 PROJ[tl
SUMMARY
4 f0R NRC USE ONLY Prograrn(Of f ice IIM Proposal No.
lopic-No.
Name and Address of Iroposer 10 BE COMPLETED BY PROPOSER ESA,.Inc.
836 Claire view Street Idaho Falls, Idaho 83402.
I Name and litle of Principal Investigator Dr. August W. Cronenberg, President ESA, Inc.
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Title of Project 1n-Vessel Hydrogen Generation for Severe Accidents:
Phase-Il Reufa poht OF b"I [oka$"n$t SNs[rke har eWhitYo$ 50[bm Des
- y Technical Abstract (Limit to 200 words) 4 The accident at TMI demonstrated that large quantities of hydrogen can be as a result of zirconium-steam oxidation reaction, which poses a hydrogen burn threat LWR containments.
depends upon the zirconium-steam reaction rate, which in tu steam starvation and core geometry reconfiguration effects.
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, of processes af fecting hydrogen ~ generation.is to perfom a syn starvation ef fects, changes in zircaloy surface-to-volume ratio, oxidation b diversion ef fects upon loss-of-rod geometry. temperatures exce will be the formulation of a technical basis for estimation of the hydrogen sourc for a range of severe accident conditions and resolution of outstanding 10COR/N enn technical issues.
Such work is in support of Nuclear Regulatory Research to advance analysis methodology on fuel assembly behavior for severe accidents, and asse for and design Ifmits of containment hydrogen control systems for present and fut
- pcwer plants, particularly BWR-Mark III containments.
Enticipated Results/ Implication of the Approach (both Phase I and ll/ Poten Corinercial Application of Research NRU, and LOFT-FP2 hydrogen generation data and fonnu y
estimation of the hydrogen source term for severe accidents.
assessment of the IDCOR contention of flow-blockage / s Results will be directed fo{WR fuel assemblies.
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NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM PHASE II - FY 1986 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TTM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer SEA Consultants, Inc.
2001 Gateway Place, Suite 610-West San Jose, California 95110 Name and Title of Principal Investigator James W. Cleveland President d.
Title of Project Application of Method to Evaluate Aging and Service Wear Effects on System Performance.
Technology, Research Thrust and/or Potential Commercial Application Assist plant operators in maintaining original design quality.
Technical Abstract This proposal presents a comprehensive approach for evaluating complex aging effects on systems performance and systeias interaction.
This approach consists of the combined application of an interactive modeling technique, the N-Square diagram, and systems engineering.
The resulting methodology facilitates analysis of complex systems interaction.
Emphasis is placed on evaluating the effects of component aging and service stress on functional and spatial systems interaction models representative of actual plant functions such as pressure and temperature control.
The systems interaction methodology consists of development of several levels of N-Square diagrams to obtain a dynamic plant model.
Consecutive levels of N-Square models are developed to reduce the system to the component level and then reduce the component to the lowest unit with aging significance (LUWAS).
From here the
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effects of postulated and empircally generated age and service wear stress can be assessed, as interactions are identified. potentially critical systems and component The results of a comprehensive model of the systems and component interactions required to complete a plant function could be used to identify inspection, surveillance, and actions needed to assure plant performance. monitoring methods or corrective Anticipated Results/ Implication of. the Approach (both Phase I
and II/ Potential Commercial Application of Research)
As the existing plants age, environmental stress can combine to create unanticipated situations.
Plant modifications and equipment replacements or substitutions have the' potential to create unanticipated adverse systems interactions.
A systems interaction model of the systems important to safety and operations provides an analytical and design tool to evaluate long term postulated conditions and determine the acceptability of necessary plant modifications and maintenance.
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- t APPEN0!X 6~
U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM RPP No. RS-RES-86-127 (SBIR Phase II)
PROJECT
SUMMARY
FOR NRC USE ONLY
-Program Office 11M Proposal No.
Topic No.
N:me and Address of Proposer Creare Inc.
P.O. Box 71 Hrnover, Nil 03755 Har2 and litle of Principal Investigator Dr. Paul H. Rothe, Vice President lille of Project GUIDEBOOK POR CONDENSATION-INDUCED WATERHAMMER IN NUCLEAR POWER PLANTS
. Technology, Research ihrust and/or Potential Comercial Apolication (Limit to 8 words)
CONDENSATION WATERHAMMER NUCLEAR REACTOR DESIGN Technical Abstract (Limit to 200 words) _
A guidebook will be prepared to incorporate state of the art methods for analysis and mitigation of ccndensation-induced waterhammer in nuclear power plants. Ease of comprehension and use will be emphasized.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Comercial Application of Research The intended guidebook will be both a manual and a reference document to support diagnosis, evaluation, cnd correction of unacceptable events or designs. Objectives include the increased safety and availability of nuclear power plants.
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APPENDIX 8 U.S. NUCLEAR REGULATORY COMMISSION
- SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-86 )
PHASE I - FY 1986 PROJECT
SUMMARY
'l.
FOR NRC USE ONLY Program Of fice TTM Proposal No.
Topic No.
10 BE COMPLETED BY PROPOSER Name and Adoress of Proposer O'Donnell Consulting' Engineers, Inc.
3611 Maplevue Drive Bethel Park, Pa.
15102 Hame and Title of Principal Investigator William J. O'Donnell, President Title of Project EXTENDED FATIGUE LIFE EVALUATION METHODS FOR AGED LWR COMP Technology, Research Thrust and/or Potential Commercial Application (
Fatigue, fracture, safety evaluation methods, aged nuclear facilities Technical Abstract (Limit to 200 words)
Stresses due to pressure ~and repeated thermal cycling cause progressive material damage during the operation of LWR components and piping systems.
Task I of Phase II focuses on the resolution of issues related to the proposed elastic-plastic fracture mechanics methods used to include environmental and aging effects in the fatigue life evaluation methods.
The revised methodology will then be used to develop new curves for A106 material.
An optional Task 2 is also described.
It extends the application of the method to include weldments containing'. code acceptable imperfec-tions and residual stresses, based on the Results of Task 1 will beModifications to the. methodology of Task 2 resolved pri'or to initiction of Task 2.
Application of ResearcliAnticipated Results/Inp11 cation of the Approach (both Ph omercial The evaluation method research product to be developed in this Project will provide a key element of the technical and Code bases for extending the safe useful life of aged LWR plants.
The inclusion of environmental effects and weldments in the evaluation method, qualified by hardware operating experience, will give utilities a means of quantifying nuclear components and piping.the safe remaining life of billions of dollars worth of ag 8-1
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SMALL BUSINESS INNOVATION RESEARCH (SBIR) PROGRAM PROPOSALS l
g gy,J k FOR FY 1986
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A/S.
SBIR NAME OF APPLICA T TYPE OF CONTROL NO.
AND ADDRESS BUSINESS SUBJECT TOPIC - SUBTOPIC 86-01 Quest,Co.
Small Theoretical and Experimental Development 9.2 A
15-F Woodland Ave.
of a Hign Efficiency Walking Robotic Bloomfield, CT 06002 Vehicle (WRV) 86-02 Structural Analysis Tech.,Inc Small Improvement of Safety of Piping Systems 9.2 C
10440 South De Anza Blvd., D7 Using Nonlinear Analysis Methods Cupertino, CA 95014 86-03 Interpacific Technology Inc.
Small A Feasibility Study for a Cost Effective 9.5 B&D 1624 Franklin Stree,t, Suite 1022 Design for Large Diameter Hole Casing Oakland. CA 94612 86-04 R.D. Averette & Co., Inc.
Small Fluo Dynamic Chromatograph 9
6 77 Underwoodstreet, N.W.
Washington, DC 20012 86-05 AA Research Company Small Expert System Safety Yardstick 9.4 C.1 3388 W. Cougar Avenue Las Vegas, NV 89118 86-06 Vesta, Inc.
Small Development of an Hierarchical Approach 9.2 B
2545 Spring Arbor Road to Equipment Qualification Jackson, Michigan 49203 86-07 PDI Technology, Div. of Small Aerosol Source Term Reduction Systems 9.2 E
Plastics Design, Inc.
246 Viking Avenue Brea, CA 92621 86-08 REM Technologies, Inc.
Small Test Method for Ident'ifying Shaft Cracks 9.2 A
1913 Central Avenue
/g,Q /64 gg Albany New York 12205
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- EARCH (SBIR) PROGRAM PROPOSALS FOR FY 1986 SBIR NAME OF APPLICA T TYPE OF CONTROL NO.
AND ADDRESS BUSINESS SUBJECT TOPIC - SUBTOPIC 86-09 ENIG Associates, Inc.
Small Prediction of Flow Capacity and Dynamic 9.3 13230 Ingleside Drive Response of Safety and Pressure Relief Beltsville, MD 20705 Valves86-010 Miller Consulting Engineers Small Improved Design Criteria for Containment 9.5 0
5308 South 12th Street of Fine Grained Mill Tailings Sheboygan, WI 53081 86-011 Peter O'Driscoll, Inc.
Small A Comprehensive Check on the Structural 9.2 B
1120 San Antonio Road Reliability of Mechanical Equipment in Palo Alto, CA 94303 a Nuclear Power Plant 86-012 Quintus Computer Systems, Inc.
Small Control Integration System for Nuclear 9.2 2345 Yale Street Reactors Palo Alto, CA 94306 86-013 Innovative Sciences, Inc.
Small An Improved Approach to Underground 9.5 0
400 Hester Street Wast'e Storage Site Assessment San Leandro, CA '94577 86-014 KLM Technologies,,Inc.
Small Use of a Novel Biopolymer in Radwaster 9.5 0
2700 Ygnacio ' Valley Road Decontamination and Treatment Suite 160 Walnut Creek, CA 94598-3454 86-015 ICF-Clement Small Estimation of Radon-222-induced Respira-9.6 1515 Wilson Blvd.
tory Cancer Risk in the Presence and Arl ington,. V.A 22209 Absence of Cigarette Smoking 86-016 Keyline Science & Engineerinc Small Development and*Use of a Seismic Root 9.4 D
Inc.
Cause Analysis Approach 45-560 Apapane Street Kaneohe, Hawaii 96744
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SMALL BUSINESS INNOVATIO
- EARCH (SBIR) PROGRAM ' PROPOSALS'-
FOR FY 1986 2
i -
1 SBIR NAME OF APPLICANT-TYPE OF.
i CONTROL NO.
AND ADDRESS BUSINESS SUBJECT TOPIC - SUBTOPIC i
86,-017 Research Dynamics Inc.
Small Development of a Method for. Preventing.
9.5-
~ D.
L 637 Redna Terrace, Unit #1 Radiation Migration From LLW Sites i
Cincinnati, Ohio 45215 i
86-018 Leading Edge Enterprises, Inc.
Small Development of. Cost Effective Liquid.
9.2
.E-l P.O. Box 18383 1
Waste Treatment Technique Philadelphia, PA 19120 l-__-___
I 86-019 Innovative Technology Labs Small Environmental Control of Nuclear Facility 9.2 EL i
2339 Davison Ave.
Enclosures by Fluidic Vortex Amplifier-Richland, WA 99352 96-020 Sirius, Incorporated Small Knowledge Fusion and AIl Formatting of _
9.3 E
P.O. Box 8988 Fuel Behavior Information Virginia Beach, VA 23452 l
l 86-021 Future Resource Associates, Small Extending a HCLPF-Based Seismic Margin 9.2 8
i Inc.
Review to Analyze Plant Damage States 2000 Center Street, Suite 418 and the Role of Human Factors and Non-l Berkeley, CA 94704 Seismic Failures-j 86-022 Electromechan'ical ' Engineering Small Insitu Inspection of Reactor-Coolant.
9.2 A
i Associates, Inc.
Pump Motors 1717 Penn Ave., Suite 425 Pittsburgh, PA 15221
~
i 86-023 Quality Service Associates, Small Welding History Data ' Management for Nuclea r..
i Inc. - 2007 Redway Lane Power Plants i
Clear Lake, TX 77062 4
86-024 g g p g ion Small Engineering Technology for Nuclear Power 9.2' D
i Chicago, IL 60680 Plants Electrical Equipment Qualification (Including Fire Protection) u 4
/
c SMALL BUSINESS INNOVATIO
- EARCH (SBIR) PROGRAM PROPOSALS FOR FY 1986
~
SBIR NAME OF APPLICA T TYPE OF CONTROL NO.
AND ADDRESS BUSINESS SUBJECT TOPIC - SUBTOPIC 86-025 Relational Integration, Inc.
Small Building Expert' System for Performing 9.2 B
%F.L. (Bill) Cho; Mechanical Equipment Qualification 5855 N. Sheridan Rd., Suite 9E, Chicago, IL 60660 86-026 Viking Energy Systems Small Failure Prediction of Components and 9.2 A
121 N. Highland Avenue Strtctures in a Nuclear Power Environment Suite 203 Pittsburgh, PA 15206 86-027 INET Corporation Small Feasibility Study of Code Conversion for 9.3 C
8450 Central Avenue RELAP5/M002 Code Newark, CA 94560 -
86-028 Scientech, Inc.
Small Gathering Plant-Specific Data 9.3 B
P.O. Box 1406 Idaho Falls, ID 83403-1406 86-029 Intermountain Technologies Small Gathering Plant-Specific Data 9.3 8
1400 Benton, P.O. Box 1604 Idaho Falls, Idaho 83403-16C 4 86-030 Geoscience Ltd Small A Proposal for a Radfoactive Waste 9.5 0
410 South Cedros Avenue Accountability Syster Based on Heat Solana Beach, CA 92075 Release Monitoring: A Demonstration Prcgram 86-031 Sach Sinah and Associates Small Optimizing Maintenance Pl'an for a Nuclear 9.2 A
P.O. Box 11205 Power System Burbank, CA 91510-1205 86-032 Waste Management Group, Inc.
Small Evaluation of Uncertainties in Irradiated 9.5 P.O. Box 579 Hardware Characterization Crompond, NY 10517
.o p.
m SMALL BUSINESS INNOVATIO
,EARCH (SBIR) PROGRAM PROPOSALS FOR-FY 1986
~
SBIR NAME OF APPLICANT TYPE OF CONTROL NO.
AND ADDRESS BUSINESS SUBJECT TOPIC - SUBTOPIC 86-033 PDI Technology, Div. of Small Nuclear Power Plant Life Extension 9.2 A
Plastics Design, Inc.
246 Viking Avenue Brea, CA 92621 86-034 DULY Consultants Small Primary Nuclear Component Fatique 9.2 C
1912 MacArthur Street Evaluation due to Pressurized Thermal Rancho Palos Verdes, CA 907: 2 Shock 86-035 Morning International, Inc.
Small Effects of Non-vertically Propagating 9.2 C
4085 Merganser Drive Seismic Waves on Buried Pipes in-Fremont, CA 94536-Saturated Soils and in Dry Soils86-036 Master Bond, Inc.
Small Development of Ambient Temperature Curing 9.2 C
154 Hobart Street Radiation and Heat Resistant Structural Hackensack, NJ 07601 Adhesive System for Field Repair and Installation of Piping, Valves and Other Process Equipment in Nuclear Power Plants86-037 Bajada Research, Inc.
Small Development of Sigma Phase Binding Energy 9.5 C
2955 Hyder, SE Calculations Albuquerque, NM 87106 86-038 Sonora Timeshare Corp.
Small Radiation Protection and Health Effects 9
6 P.O. Box 126 Soulsbyville, CA 95372 86-039 GRP Consulting, (a Div. of Small Conversion of TRAC-PFl/ MODI FORTRAN 9.3 SWUCO, Inc.
Best Estimate Code for IBM /370 Series 12655 S.W. Center Street Mainframes.
Suite #380 i
Beaverton, OR 97005
/
n, SMALL BUSINESS INNOVATIO
.EARCH (SBIR) PROGRAM PROPOSALS FOR FY 1986 SBIR NAMEOFAPPLICAkT' TYPE OF CONTROL NO.
AND ADDRESS BUSINESS SUBJECT TOPIC - SUBTOPIC 86-040 Intermountain Technologies, Small-Code Conversion for the Best Estimate Code 9.3.
C Inc.
P.O. Box 1604 Idaho Falls, Idaho 83403-1600 86-041 Quintus Computer Systems, Inc Small Expert Knowledge Based System for the 9.3 E
2345 Yale Street Utilization of Nuclear Reactor Fuel Palo Alto, CA 94306 Behavior Information 86-042 Quintus Computer Systems, Inc.
Small Expert Automation for Detection and 9.4 8
2345 Yale Street Resolution of Logic Loops Palo Alto, CA 94306 86-043 Pickard, Lowe and Garrick, In:
Small Display and Presentation of Risk Results 9.4 C.2 2260 University Drive Newport Beach, CA 92660 86-044 Pickard, Lowe and Garrick, In:.
Small Ca. librating Methods for Expert Opinion 9.4 C.4 2260 University Drive Use in Risk Studies Newport Beach, CA 92660 9.4 D
86-045 EQE Incorporated Small Development of Seismic Root' Cause 3300 Irvine Avenue, Suite 345 Analysis Approach Newport Beach, CA 92660 86-046 Kominek & Associates Small Expert Systems for Fuel Behavior 9.3 E
519 Linden Avenue Wilmette, IL 60091 86-047 Terra Tek, Inc.
Small Factors Affecting Hole Stability in 9.5 B
400 Wakara Way Horizontal. Drilling -
Salt Lake City, Utah 84108 6
SMALL BUSINESS INNOVATION ArSEARCH (SBIR) PROGRAM PROPOSALS FOR
.986 SBIR NAME OF APPLICANT j
TYPE OF CONTROL NO.
AND ADDRESS BUSINESS SUBJECT TOPIC - SUBTOPIC 86-048 Lexeme Corporation Small Automated Translation Of NRC Software 9.3 C
Suite 250 to IBM Systems Commerce Court, Four Station Square Pittsburgh, PA 15219-1119 86-049 Bondico, Inc.
Small Stability Testing of New Hic Technology 9.5 D
2410 Silver Street for Disposal of Low Level Radioactive
-Jacksonville, FL 32206 Waste 86-050 American Research Corp. of VA Small Remote Field Eddy Current Technique for 9.2 A
P.O. Box 3406 In-service Inspection in Nuclear Power Radford, VA 24143 Plants86-051 Corporate Development Associates Small Development of Non-Destructive Quality 9.5 A
1126 S. Country Club Drive Control Measurements of the Moisture Schenectady, NY 12309 Content of Low Level Waste Storage Disks86-052 Environmental Protection Small Radioactive Waste Management Concept 9.5 D
Polymers, Inc.
13414 Prairie Avenue Hawthorne, CA. 90250 05-053
.Tnatoch International Corp.
Small Code Conversion for TDAC-PFl/! 0D1 0.3 C
3344 B. Torrey Pines Ct.,#320' La Jolla, CA 92037 86-054 Pentek, Inc.
Small Development of Testing and Analysis 9.2 A
1026 Fourth Avenue Methodology to Determine Functional Coraopolis, PA 15108 Condition of Solenoid-Operated Valves Used in Nuclear Power Plant Safety Applications86-055 Pentek, Inc.
Small Design and Improvement of Prototype 9.2 A
1026 Fourth Avenue Electrical Circuit Cl}aracterization and rnrannn14e pa
SMALL BUSINESS INNOVATIO
,EARCH (SBIR) PROGRAM PROPOSALS FOR FY 1986 -
SBIR NAME OF APPLICANT TYPE OF CONTROL NO.
~AND ADDRESS BUSINESS SUBJECT TOPIC - SUBTOPIC' 1
86-056 Energy Incorporated Small The Integrated Consultant for Nuclear 9.2
.A P.O. Box 736 Plant Aging Idaho Falls, ID 83402 86-057 ALV International Corporatior Small Consideration of Ir. elastic Behavior in 9.2 B
1485 G Enea Court, Suite 133C Nuclear ' Power Plant Piping Support Design Concord, CA 94520 and Evaluation 86-058 Grove Engineering, Inc.
Small Fuel Behavior Evaluation System 9.3 E
P.O. Box 720 Washington Grove, MD 20880 i
86-059 Frontier Research Small Application of the Finite Element Method 9.2 C
P.O. Box 1261 to the Pressurized Thermal Shock Problem Huntsville, AL 35807 86-060 Risk Management Associates Small Computational Module to Estimate 9.2 E
2309 Dietz Farm Rd., NW.
Thermocemstry Effects on Source Terms Albuquerque, NM.87107 86-061 ENSA, Inc.
Small Conversion of TRAC-PFl/M001 to IBM System 9.3 C.
P.O. Box 5537 Rockville, MD 20'855 86-062 Innovative Sciences Inc.
Small Defect Characterization of Nuclear
.9.2 A
400 Hester Street Reactor Piping Welds Using EMATs San Leandro, CA 94577 86-063
' Analysis and Measurement Small Degradation of Nuclear Plant Temperature 9.2 A
Services Corporation Sensors 4706 Papemill Road
' Knoxville, TN 37909
S
/
,.m SMALL BUSINESS INNOVATIO EARCH (SBIR) PROGRAM PROPOSALS FOR FY 1986 SBIR NAMEOFAPPLICA5T TYPE OF CONTROL NO.
AND ADDRESS BUSINESS SUBJECT TOPIC - SUBTOPIC 86-064 Aptech Engineering Services, Small Field Useable Extraction Replication of 9.2 A
Inc.
Duplex Stainless Steels for Monitoring 795 San Antonio Road Service Induced Material Degradation Palo Al to, CA 94303 86-065 TTI Small Research on Controls Reliability and 200 Garden City Plaza Susceptability Improvement Suite 500 Garden City, NY 11530 86-066 UFA, Inc.
Small Reactor System Fuel Behavior: Database 9.3 E
710 Commonwealth Avenue Assistant Newton, MA 02159 86-067 Energy Incorporated Small TRAC-PFl/M001 Conversion to IBM Computers 9.3 C
P.O. Box 736 Idaho Falls, ID 83402 A
86-068 Troglodyte Society, Inc.
Small Derivation of a Method for Representing 1400 Post Lane Damping in Inelastic Range Bowie, MD 20716 86-069 Applied Decision Analysis, Inc. Small Research on the Use of Comparative Risk 9.4 C.2 3000 Sand Hill Road, Information as an Aid to Communicating Suite 4-255 Risk and Related Information to Decision Menlo Park, CA 94025 Makers86-070 NUCLEAR STRUCTURES, Inc.
Small Nuclear Criticality Safety Evaluation of 9.3 D
6025 Atlantic Blvd., Suite C LWR Accidents with Severe Fuel Norcross, GA 30071-1304 86-071 Keyline Science & Engineering Small Evaluation of Scismic Safety Margins to 9.2 B
45-560 Apapane Street Realistically Define the Probabilities of Kaneohe, Hawaii 96744 Radioactive Release due to Earthquakes
SMALL BUSINESS INNOVATIOP 2 ARCH (SBIR) PROGRAM PROPOSALS FOR FY 1986 SBIR NAME OF APPLICANT TYPE OF CONTROL NO.
AND ADDRESS BUSINESS SUBJECT TOPIC - SUBTOPIC 86-072 sPectraSOFT, Inc.
Samil Fuel Behavior Knowledge Data Base Manager 9.3 E
P.O. Box 10167 State College, PA 16003 86-073 American Autogard Corporation Small
. Torque Limiter Over-Ride 6201 Material Avenue Rockford, IL 61111 86-074 PDI Technology, div. of Small Aging Processes in Nuclear Reactors 9.2 A
Plastics Design, Inc.
246 Viking Ave.
Brea, CA 92621 86-075 Cambridge Collaborative, Inc.
Small Leak Localization in Heat Exchangers Using 9.2 A
689 Concord Avenue Acoustical Signal Processing Cambridge, MA 02138-1002 86-076 Technology for Energy Corp.
Small A Systematic Approach for Developing an 9.3 C
One Energy Center IBM Version of the TRAC Program Lexington Drive Knoxville, TN 37922 86-077 Erdmann & Associat.es, Inc.
Small Code Conversion for the Best Estimate Code 9.3 C
6 Lilly Lane San Carlos, CA 94070 86-078 Quantex Corporation Small Integrating Fiber Optic Radiation Dosimeter 9.6 2 Research Court Rockville, MD 20850 86-079 International Education Small A Sharp Approach to the Solution of 9.3 B(2)
Research & Development Eng.
Reactor Thermal-Hydraulics Equations and Consulting LOCA Analysis via Weighted Residual Vanikoy Cad., 59 Criteria (With Application to TMI Accidenu)
Cengelkoy, Istanbul, Turkey
~
SMALL BUSINESS INNOVATI ' *ESEARCH (SBIR) PROGRAM PROPOSALS F0n
( 1986 SBIR NAME OF APPLICANT TYPE OF CONTROL NO.
AND ADDRESS BUSINESS SUBJECT TOPIC - SUBTOPIC 86-080 Atom Sciences, Inc.
Small Bioassay of Radionuclides Using Resonance 9.6 114 Ridgeway Center Ionization Spectroscopy Oak Ridge, TN 37830 86-081 0.K. Litho / Buddy Bert Shirt Small Design and Completion of - Improv 71' P.O. Box 54 (Air Force) SR-71 Cortland, Ohio 86-082 Daniel & Associates, Inc.
Small Development of Standardized Method for 9.6 850 Sligo Avenue Recording and Calculating Skin Contamina-501 Union Trust Bldg.
tion Doses Silver Spring, MD 29910 86-083 tiichael Fox, PH.D.
Small Transgranular Stress Corrosion Cracking 9.2 E
Route 2, Box 252 in BWRs Athens, AL 35611 86-084 titchael Fox, PH.D.
Small Organic Chemical and Resin Detector 9.2 E
Route 2, Box 252 Athens, AL 35611' 4
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