Revitalizing Nuclear Safety Research (1986)

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Appendix B Planned FY 1986 Safety Research Program of the Nuclear Regulatory Commission 91

92 A. REACTOR ENGINEERING DECISION UNIT 1. TITLE: LOAD COMBINATIONS FY 85 FY 86 FY 87 CONTRACTOR: Lawrence Livermore BUDGET: 115 225 0 National Laboratory OBJECTIVE: General Design Criterion 4 has resulted in the installation of protective devices (e.g., pipe whip restraints and jet impingement barriers) to mitigate events which are now regarded as extremely unlikely for PWR reactor coolant loops. These protective devices impede inservice inspection and maintenance, reduce safety if improperly installed, and increase worker radiation exposures. It is now generally believed that the number of protective devices can be reduced because pipe degradation will be detected through leakage monitoring before breaking occurs. The objective of this program is to provide the licensing staff with the technical basis for applying the leak-before-break concept to reactor coolant loop piping. 2. TITLE: SEISMIC MARGINS STUDIES FY 85 FY 86 FY 87 CONTRACTOR: Lawrence Livermore BUDGET 591 600 500 National Lab OBJECTIVE: Nuclear power plants are designed to resist large earthquakes. However, as new seismological data are obtained throughout the U.S., the appropriateness of current plant design earthquake levels has been questioned. There is concern over the ability of current light water reactor plant designs to accommodate earthquakes larger than the design basis and to adequately protect the public health and safety. The objective of this program is to provide the licensing staff with a procedure to evaluate the seismic design margin of light-water-reactor plants with potentially increased design basis earthquakes. This will serve as the basis or regulatory decision on the acceptability of licensee submittals regarding the continued operation of their facilities. 3. SEISMIC RISK METHOD. TECH TRANSFER FY 85 FY 86 FY 87 CONTRACTOR: Lawrence Livermore BUDGET 100 100 0 National Lab OBJECTIVE: Nuclear power plants are designed to resist large earthquakes. However, as new seismological data are obtained throughout the U.S., the appropriateness of plant design earthquake levels have been questioned. There is concern over the ability of current light water reactor plant designs to accommodate earthquakes larger than the design basis and to adequately protect the public health and safety. The objective of this program is to transfer computer codes and data developed under the SSMRP to national laboratories and other entities engaged in seismic studies, with the intent that these facilities could assist the NRC staff in evaluating seismic design criteria. In addition, the seismic information developed as part of this research program will be used to help establish international technical exchange agreements from which NRC can obtain information from other countries.

93 4. TITLE: ASSESS & IMP OF SPECTRUM- FY 85 FY 86 FY 87 BROADENING PROC USED IN PIPING BUDGET 50 75 0 DESIGN CONTRACTOR; Lawrence Livermore National Lab OBJECTIVE: NRC dynamic load design criteria have led to the placement of large numbers of snubbers and rigid supports on nuclear plant piping. The installation of too many restraints has potentially detrimental effects. Because of the stiffening they provide, the restraints which are installed to resist earthquake and other dynamic loads have increased the thermal forces on the piping systems during normal operating conditions. In addition, the snubber have proven to be unreliable devices that require extensive inservice inspection and maintenance, resulting in increased levels of worker radiation exposure. The objective of this program is to provide the NRC staff with the information necessary to evaluate licensee subroittals to reduce the conservations associated with defining in-plant response spectra for seismic loads on piping systems, and thereby use fewer restraints. 5. TITLE: VALIDATION, PLANNING & COORD FY 85 FY 86 FY 87 CONTRACTOR: Argonne National Lab BUDGET 365 625 900 OBJECTIVE; Nuclear power plants are designed to resist large earthquakes. However, as new data are obtained on earthquake activity throughout the U.S., plant design earthquake levels have increased. There is concern over the ability of current light water reactor plant designs to accommodate these larger earthquakes and to adequately protect the public health and safety. Thus, there is a high priority need to establish seismic design margins of these plants. The objective of this program is to provide, through domestic and international cooperative efforts, information and experimental data which can be used to validate and improve predictions of the behavior of nuclear power plants (including soil-structure interaction and the nonlinear behavior of buildings and piping system) subjected to earthquakes larger than design basis. The predictive methods to be validated are used both in probabilistic and deterministic calculations and in particular may be used as part of Seismic Probabilistic Risk Assessments (PRAs) for nuclear power plants.

94 6. TITLE: BENCHMARKING COMPUTER CODES FY 85 FY 86 FY 87 FOR STRUG ENGR. BUDGET 300 200 208 CONTRACTOR: Brookhaven National Laboratory OBJECTIVE: Nuclear power plants are designed to resist large earthquakes. However, as new data are obtained on earthquake activity throughout the U.S., plant design earthquake levels have increased. There is concern over the ability of current light water reactor plant designs to accommodate these larger earthquakes and to adequately protect the public health and safety. The objective of this program is to establish problems with experimentally known solutions (benchmarks) for use by the licensing staff to validate major parts of licensee methods used to calculate the transmittance of earthquake loads through the soil to safety-related buildings, systems and components. 7. TITLE: SEISMIC COORD 7 SSMRP TECH FY 85 FY 86 FY 87 TRANSFER BUDGET 234 100 1000 CONTRACTOR: Brookhaven National Laboratory OBJECTIVE: Nuclear power plants are designed to resist large earthquakes. However, as new data are obtained on earthquake activity throughout the U.S., plant design earthquake levels have increased. There is concern over the ability of current light water reactor plant designs to accommodate these larger earthquakes and to adequately protect the public health and safety. The objective of this program is to validate, through domestic and international cooperative efforts, those computer codes used to predict the nonlinear behavior of piping systems and buildings subjected to earthquakes larger than the design basis. These validated computer codes can then be used by the licensing staff as a basis for evaluating licensee submittals. 8. TITLE: COMP FRAGILITY DATA FY 85 FY 86 FY 87 ACQUISITION & EVAL BUDGET 240 875 100B CONTRACTOR: Brookhaven National Laboratory OBJECTIVE: Nuclear power plants are designed to resist large earthquakes. However, as new data are obtained on earthquake activity throughout the U.S., plant design earthquake levels have increased. There is concern over the ability of current light water reactor plant designs to accommodate these larger earthquakes and to adequately protect the public health and safety. Although large uncertainties exist in predicting the earthquake level at which critical components fail to perform their safety function (because qualification data cannot be extrapolated to accurately predict failure level),' it is now believed

95 components have greater resistance to earthquake loads than previously estimated. The objective of this program is to establish an experimental data base on component fragility through domestic and foreign cooperative efforts. This data base will provide the licensing staff with a basis for assessing the earthquake levels at which individual components and generic classes of components fail to perform their safety functions. 9. TITLE: REL ANALYSIS OF NON- FY 85 FY 86 FY 87 LINEAR BEHAVIOR OF CONCRETE BUDGET 0 200 200 STRUCTURES CONTRACTOR: Brookhaven National Laboratory OBJECTIVE: Develop a reliability analysis method and a stochastic nonlinear analysis method for concrete containments and shear walls subjected to multiple static and dynamic loads that produce nonlinear behavior. Extend RAS code to include nonlinear behavior. Define when appropriate to use this nonlinear method or the simplified (linear SSMRP) method. Verify the approximate nonlinear limit states from A-3802. I0. TITLE: DAMPING STUDIES FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 230 200 0 Engineering Laboratory OBJECTIVE: NRC dynamic load design criteria have led to the placement of large numbers of snubbers and rigid supports on nuclear plant piping. The installation of too many restraints has potentially detrimental effects. Because of the stiffening they provide, the restraints which are installed to resist earthquake and other dynamic loads have increased the thermal forces on the piping systems during normal operating conditions. In addition, the snubbers have proven to be unreliable devices that require extensive inservice inspection and maintenance, resulting in increased levels of worker radiation exposure. The objective of this program is to provide the NRC staff with information with which to evaluate licensee submittals to increase the level of damping for plant piping systems and thereby reduce the number of snubbers without reducing the level of plant safety.

96 11. TITLE: SEISMIC CATEGORY I FY 85 FY 86 FY 87 STRUCTURES PGM BUDGET 820 1200 15BB CONTRACTOR: Los Alamos National Laboratory OBJECTIVE: Nuclear power plants are designed to resist large earthquakes. However, as new data are obtained on earthquake activity throughout the U.S., plant design earthquake levels have increased. There is concern over the ability of current light water reactor plant designs to accommodate these larger earthquakes and to adequately protect the public health and safety. The objective of this program is to validate existing methods and, as necessary, to develop new methods to reduce uncertainties that exist in the methods used by the NRC staff to predict the transfer of the increased earthquake loads used by plant buildings to safety systems and components needed to operate and shutdown the plant, and to provide a basis for regulatory decisions regarding continued operation of these facilities. 12. TITLE: PIPE-TO-PIPE IMPACT FY 85 FY 86 FY 87 CONTRACTOR: Pacific Northwest BUDGET 25 25 0 OBJECTIVE: Nuclear power plants are designed for many types of postulated accidents, including pipe breaks. Certain types of pipe breaks may cause the broken pipe to whip freely and impact nearby components and other piping. It is important that such impacts not cause safety equipment to malfunction and prevent plant shutdown. The objective of this program is to determine whether existing licensing criteria on pipe-to-pipe impact are acceptable, and to develop new criteria where necessary. 13. TITLE: SEISMIC FRAGILITY DEMONSTRATION FY 85 FY 86 FY 87 PIPING TEST BUDGET 92 100 0 CONTRACTOR: Energy Tech Engr. Corp. OBJECTIVE: NRC dynamic load design criteria have lead to the placement of large numbers of snubbers and rigid supports on nuclear plant piping. The installation of too many restraints has potentially detrimental effects. Because of the stiffening they provide, the restraints which are installed to resist earthquake and other dynamic loads have increased the thermal forces on the piping systems during normal operating conditions. In addition, the snubbers have proven to be unreliable devices that require extensive inservice inspection and maintenance, resulting in increased levels of worker radiation exposure. The primary objective of this program is to provide the NRC staff with information to evaluate whether the ASME Code failure mode criterion for dynamic loads is overly conservative. Modifications to the Code criterion would permit the use of fewer restraints without reducing the overall level of plant safety. A secondary objective of this program is to validate current assumptions on piping fragility (i.e., failure levels) that influence the results of seismic probabilistic risk assessment studies.

97 14. TITLE: PIPE CAPACITY/FAILURE MODES FY 85 FY 86 FY 87 CONTRACTOR: Anco BUDGET 108 700 700 OBJECTIVE: NRC dynamic load design criteria have led to the placement of large numbers of snubbers and rigid supports on nuclear plant piping. The installation of too many restraints has potentially detrimental effects. Because of the stiffening they provide, the restraints which are installed to resist earthquake and other dynamic loads have increased the thermal forces on the piping systems during normal operating conditions. In addition, the snubbers have proven to be unreliable devices that require extensive inservice inspection and maintenance, resulting in increased levels of workers radiation exposure. The objectives of this program are to clearly and systematically demonstrate the failure modes of piping due to dynamic invertial loads, and to provide the basis for changing ASME code rules regarding seismic piping stress criteria. 15. TITLE: DESIGN CRITERIA FOR SHIPPING FY 85 FY 86 FY 87 CONTAINERS BUDGET 250 300 300 CONTRACTOR: Lawrence Livermore National Lab OBJECTIVE: Shipping containers are used to store and transport spent radioactive fuel. There is concern over the ability of these containers to properly protect the public health and safety during postulated storage and transportation conditions. The objective of this program is to develop licensing criteria for the design and fabrication of spent fuel shipping containers, and to develop simplified thermal stress analysis procedures for use by the licensing staff in evaluating similar analyses by licensees. 16. TITLE: MECHANICAL EQ QUAL PROGRAM FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET ll86 2000 1800 Engineering Laboratory OBJECTIVE: The NRC requires that nuclear power plant equipment important to safety be qualified to assure operability during design basis accident conditions. Because qualification procedures are in many cases inadequately defined there are many areas where the procedures are inconsistent or incorrect. These areas include the proper mounting of equipment to be qualified; the proper definition of qualification loads; and the generic application of qualification test results. The objective of this program is to provide the licensing staff with the technical basis for evaluating equipment operability testing and to provide the technical basis for developing the criteria and methodologies to improve national standards and regulatory documents used to qualify specific mechanical equipment.

98 17. TITLE: ASME XI SUPPORT - TECHNICAL FY 85 FY 86 FY 87 ASSISTANCE - RES BUDGET 60 200 300 CONTRACTOR: Idaho National Engineering Lab OBJECTIVE: Assist the NRC staff in a thorough evaluation of proposed revisions and/or additions to the ASME Boiler and Pressure Vessel Code (ASME Code) rules which are used to detect nuclear power plant component degradation (including that of primary system piping) as they age in operating reactors, so that corrective action can be taken before safety is compromised. These rules, which are contained in Section XI, "Rules for Inservice Inspection of Nuclear power Plant Components" of the ASME Code, are incorporated by reference, as appropriate, into the NRC regulations following the NRC staff evaluation of each new Section XI edition and addenda. 18. TITLE: ASME SECTION III FY 85 FY 86 FY 87 CONTRACTOR: Oak Ridge BUDGET 104 150 200 National Laboratory OBJECTIVE: Assist the NRC staff in a thorough evaluation of proposed revision and/or additions to the ASME Boiler and Pressure Vessel Code (ASME Code), which provides rules for the design and construction of nuclear power plant components, to ensure that the quality of new components is adequate to protect the public health and safety. These rules, which are contained in Section III, "Rules for Construction of Nuclear Power Plant Components" of the ASME Code, are incorporated by reference, as appropriate, into the NRC regulations following the NRC staff evaluation of each new Section III edition and addenda. 19. TITLE: VALVE PERFORMANCE TESTING FY 85 FY 86 FY 87 CONTRACTOR: Energy Tech BUDGET 370 200 200 Engineering Corp. OBJECTIVE: Primary system isolation valves are used to separate and protect low pressure reactor systems from the high pressure of the primary system. The integrity of these isolation valves is presently verified by periodic inservice leak testing. The ability of these leak tests to adequately detect valve degradation is uncertain. Experiments are needed to reduce this uncertainty by developing a correlation between inservice leak tests and valve degradation. The objective of this program is to validate and improve existing technical specification (license condition) allowable leak rates and ASME Code (Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components") methodology for inservice testing of primary system isolation valves, to assure these valves crucial to safety will operate when called upon; and to evaluate advanced techniques for detecting valve degradation.

99 20. TITLE: EXPERIMENTS ON CONTAINMENT FY 85 FY 86 FY 87 MODELS BUDGET 2060 2000 2400 CONTRACTOR: Sandia National Laboratory OBJECTIVE: Severe accidents exceeding the original design basis that lead to core melt have been postulated. The containment building provides the last barrier to the release of radioactivity resulting from such an accident. There are large uncertainties in predicting the leak integrity of containment buildings under severe accident pressures and temperatures. The objective of this program is to implement tests on scale containment models to support development and validation of methods for assessing the capabilities of containment buildings under conditions exceeding their design basis to permit licensing staff evaluation of licensee estimates of containment performance and to support Commission policy on severe accidents. 21. TITLE: CONTAINMENT PENETRATIONS FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 900 900 600 Laboratory OBJECTIVE: Severe accidents exceeding the original design basis that lead to core melt have been postulated. The containment building provides the last barrier to the release of radioactivity resulting from such an accident. There are large uncertainties in predicting the leak integrity of containment buildings under severe accident pressures and temperatures. The objective of this program is to develop an experimental data base for assessing the leak integrity of containment penetrations under severe accident conditions and for validating existing methods used to assess these penetrations, in order to provide a basis for regulatory decisions regarding continued operation of existing facilities, and for identifying containment penetration features, which if improved, would significantly increase containment capacity. 22. TITLE: CONT INTEGRITY UNDER EXTREME FY 85 FY 86 FY 87 LOAD BUDGET 740 600 700 CONTRACTOR: Sandia National Laboratory OBJECTIVE: Severe accidents exceeding the original design basis that lead to core melt have been postulated. The containment building provides the last barrier to the release of radioactivity resulting from such an accident. There are large uncertanties in predicting the leak integrity of containment buildings under severe accident pressures and temperatures. The objective of this program is to provide a basis for the reliable estimation of containment performance during severe accidents.

100 23. TITLE: FISSION PRODUCT CONTROL ESF FY 85 FY 86 FY 87 EFFECTIVENESS BUDGET 400 195 686 CONTRACTOR: Pacific Northwest Labs OBJECTIVE: In evaluating potential releases of radioactivity from containment atmospheres to the environment as a result of severe light water reactor accidents, the effectiveness of certain Engineered Safety Features for removal of radioactive participates is an important factor. This project will develop and validate codes and models to estimate particulate removal effectiveness of ice condensers and suppression pools. 24. TITLE: ICEDF CODE VERIF/VALID TESTS FY 85 FY 86 FY 87 CONTRACTOR: Pacific Northwest Labs BUDGET 179 450 0 OBJECTIVE: In evaluating potential releases of radioactivity from containment atmospheres to the environment as a result of severe light water reactor accidents, the effectiveness of certain Engineered Safety Features for removal of radioactive particulates is an important factor. This project will support experimental studies to be used in validation of a developed model and code for ice condenser effectiveness. 25. TITLE: ADDITIONAL REQUIREMENTS FOR FY 85 FY 86 FY 87 MATERIALS BUDGET 75 150 200 CONTRACTOR: Oak Ridge National Lab OBJECTIVE: Provide technical expertise and assistance to Research in the review of national codes and standards that may be referenced in NRC regulations or guides related to nuclear reactor components. Provide comments, proposed modifications and reviews as appropriate in the areas of design, materials, fabrication and inspection. When necessary, specific information (or data) will be developed and/or analyzed to support recommendations related to proposed regulations, guides, or referenced codes and standards. 26. TITLE: HEAVY SECTION STEEL TECH PROG FY 85 FY 86 FY 87 CONTRACTOR: Oak Ridge National Lab BUDGET 5520 5200 510B OBJECTIVE: To provide a thorough, quantitative assessment of heavy-section reactor vessel fracture characteristics including a realistic evaluation of fracture potential and development of fracture prevention criteria, flaw growth mechanisms, crack propagation and crack arrest, including the effects of irradiation are considered. The development and evaluation of materials characterization methods, fracture mechanics analysis methods, the development of material data bases, and the validation of structural integrity analytical methods using thick-section structural tests are major activities in this program.

101 27. TITLE: PRESSURE VESSEL SIMULATION FY 85 FY 86 FY 87 CONTRACTOR: Oak Ridge National Lab BUDGET 280 360 100 OBJECTIVES: Validate in well-defined reproducible benchmark experiments, methodologies and data bases which are used to predict radiation damage in reactor pressure vessels. Considerable attention is given to the quality of data generated. A key element in this program is the need to set and achieve realistic uncertainties for neutron dosimetry and to ensure that these uncertainties are fairly propagated in the assessment of irradiated material performance. Rigorous variables are characterized and quantified in terms of their mean values and their associated uncertanties. 28. TITLE: RESIDENT ENGINEER - FRG FY 85 FY 86 FY 87 CONTRACTOR: Oak Ridge National Lab BUDGET 120 130 130 OBJECTIVES: Act as a resident engineer in Stuttgart, Germany, for the Division of Engineering Technology, Materials Engineering Branch, for liason to the materials, structural and safety programs underway at MPA and elsewhere. To provide information on European regulatory activities for comparision to or adoption into NRC regulations. 29. TITLE: SURVEILLANCE DOSIMETRY FY 85 FY 86 FY 87 CONTRACTOR: Hanford Engr Dev Lab BUDGET 450 660 420 OBJECTIVE: Preparation of updated and improved dosimetry, damage correlation, and the associated reactor analysis ASTM standards for LWR pressure vessel (PV) irradiation surveillance programs to assure conformance with 10CFR Part 50, Appendix G requirements. Perform supporting "Benchmark Fields," reactor "Test Regions," and operate power reactor "Surveillance Positions" validation and calibration testing of the recommended ASTM procedures, measurements, and analysis techniques.

102 30. TITLE: DOSIMETRY MEAS DATA BASE FY 85 FY 86 FY 87 CONTRACTOR: National Bureau of BUDGET 210 200 111 Standards OBJECTIVES: Provide calibration of LWR-PV related surveillance dosimetry traceable to NBS standard neutron fields including distribution of neutron fluence standards. Such dosimetry is needed to accurately assess radiation damage in reactor pressure vessels and to assure conformance with 10CFR Part 50, Appendix G. Maintain a compendium of reference data for LWR-PV related benchmark neutron fields. Participate in the preparation of ASTM standards for routine LWR-PV dosimetry and in establishing consensus methods of data interpretation. Provide experimental assistance for LWR-PV dosimetry benchmark measurement programs. 31. TITLE: ELASTIC PLASTIC FRACTURE FY 85 FY 86 FY 87 MECHANICS EVALUATION OF LWR ALLOYS BUDGET 185 300 301 CONTRACTOR: Naval Ship R&D Center OBJECTIVE: Through small and moderate scale experiments determine the critical parameters affecting ductile fracture toughness of nuclear grade steels and weldments, evaluate new test methods for possible standardization, and verify the applicability of new data analysis methods to existing specimen types. 32. TITLE: STRUCTURAL INTEGRITY OF H20 FY 85 FY 86 FY 87 REACTOR BOUNDRY COMP II BUDGET 1880 2150 2101 CONTRACTOR: Naval Ship R&D Center CONTRACTOR: Materials Engr. Assoc., Inc. OBJECTIVES: To provide to the NRC analytical and experimental methods and data that are necessary for compliance with 10CFR50 Appendix A, GDC-14, 30 and 31, to ensure the structural safety and reliability of pressure boundary components in light water reactor components of U.S. commercial nuclear power systems. Specific objectives are: a) Development of criteria for establishing elastic plastic fracture toughness. b) An experimentally validated mechanism model for irradiation damage effect of reactor pressure vessel steels. c) Modification of Code fatigue curves to recognize environmental effects. d) An experimentally validated mechanism model for corrosion assisted fatigue crack growth. e) A comprehensive computerized fracture mechanics data base for all steels and weldments in U.S. nuclear commercial power plant piping.

103 33. TITLE: GUNDREMMINGEN FY 85 FY 86 FY 87 CONTRACTOR: Noell, GG BUDGET 0 100 • OBJECTIVE: Evaluation of irradiated pressure vessel material removed from a decommissioned reactor to determine effect of long-time irradiation at service temperature and low flux rate, for comparison to regulatory trends for rate of irradiation versus fluence from irradiations at a faster rate, to assure compliance with 10CFR50 Appendix A, GDC 14, 30 and 31. To measure fracture toughness values through the vessel thickness to validate the regulatory position on fluence and embrittlement gradients, to determine annealing recovery from in-situ irradiated vessel steel, and through parallel irradiation in test reactors, to measure the dose rate effect. 34. TITLE: HYDROGEN CONTROL FY 85 FY 86 FY 87 CONTRACTOR: Sandia National Lab BUDGET 780 400 0 OBJECTIVE: An igniter system is employed in a reactor containment to control the combustion of hydrogen that may result from certain possible accidents. Data are needed to reduce the uncertainties associated with the capability of an igniter system to perform its function, i.e., controlled burning of hydrogen without detonation, in the presence of water sprays provided to reduce the temperature of the containment atmosphere. Too much water on the igniter element would prevent the hydrogen-air mixture from reaching its ignition temperature. This project will provide the NEC licensing staff the information to evaluate the igniter systems and operational schemes proposed by reactor licensees. 35. TITLE: ENVIRONMENTALLY ASSISTED FY 85 FY 86 FY 87 CRACKING IN LWR PIPING SYSTEMS BUDGET 1715 1820 1800 CONTRACTOR: Argonne National Laboratory OBJECTIVE: To determine if the "fixes" proposed by industry for mitigation of intergranular stress corrosion cracks including induction heating stress improvement, hydrogen water chemistry, repair by weld clad overlay, or replacement material 316 NG (nuclear grade) will actually perform the crack mitigation and provide assurance of crack-free future service, to provide assurance that repaired cracks will not continue to grow and thus threaten catastrophic failure of the pipe system especially when it is known that the weld clad overlay precludes effective ultrasonic inspection to monitor any further growth.

104 36. TITLE: CAST STAINLESS STEEL FY 85 FY 86 FY 87 CONTRACTOR: Argonne National Lab BUDGET 75 300 300 OBJECTIVE: To evaluate if the loss in toughness suffered by cast stainless steel during normal operating service, is sufficient to render the steel so brittle that it will not stand up to operating or accident loads, and thus could fracture, leading to a loss of coolant accident, possible meltdown and exposure of the public to radiation. This program will measure the fracture toughness of such aged steels to determine whether the code requirements and NRC regulations are adequate for Leak Before Break and for the safety of the public against failure of the reactor primary system. 37. TITLE: AGING STUDIES ON MATERIALS FY 85 FY 86 FY 87 FROM THE SHIPPINGPORT REACTOR BUDGET 10 750 125i CONTRACTOR: Argonne National Laboratory OBJECTIVE: To measure the properties of materials comprising the pressure vessel, thermal shield, piping, pumps and valves of the Shippingport reactor plant to determine how much change there has been due to service, and to help validate models of aging degradation due to time, temperature, pressure and radiation in reactor service. 38. TITLE: STRESS CORROSION CRACKING OF PWR FY 85 FY 86 FY 87 STEAM GENERATOR TUBING BUDGET 30 30 0 CONTRACTOR: Brookhaven National Laboratory OBJECTIVE: Develop data and models to be used by the regulatory staff to predict the stress corrosion cracking (SCO service life if Inconel 600 steam generator tubing under normal and upset conditions and establish criteria for safe operation of such steam generators. Factors related to service and material conditions which influence SCC such as temperature, stress, strain and strain rate, metallurgical structure and processing and ingredients of the primary and secondary coolant are included as variables in the testing program and appropriate results and factors incorporated in the predictive models for SCC service life. 39. TITLE: STEAM GENERATOR INTEGRITY-GROUP FY 85 FY 86 FY 87 PROJECT BUDGET 1250 1350 1250 CONTRACTOR: Pacific Northwest Laboratory OBJECTIVE: To reduce the uncertainty of possible multiple and massive failures of steam generator tubing that have become dented, cracked or dangerously thinned down by wastage or intergranular attack during service in light water reactor steam generators, and to fully characterize the massive breaking up of structural and supporting components of the

105 generators, the broken parts of which can hammer at the tubing to cause additional breaks, all of which results in loss of coolant accidents which could lead to core meltdown and serious exposure of the public to radiation. To improve the reliability of the non-destructive examination procedures which are the only means available for early warning of imminent tube failure which could lead to the loss of coolant and potential exposure of the public to radiation. Because of broad international concern about these problems this is an international program whose participants (France, Italy, Japan, EPRI) are contributing funds. 40. TITLE: WELDED & WELD-REPAIRED STAINLESS FY 85 FY 86 FY 87 STEEL BUDGET 335 350 500 CONTRACTOR: Pacific Northwest Laboratory OBJECTIVE: To evaluate whether or not the welding or repair welding of a pipe will cause sensitization that will likely develop into a stress corrosion crack during service which could break under an accident loading thus leading to a loss of coolant, possible core meltdown and significant exposure of the public to radiation. This program will develop a model for prediction of the degree of sensitization and the susceptibility to intergranular stress corrosion cracking of welded and repair welded stainless steel piping in LWR service so that licensing reviewers and IE and regional inspectors can perform independent evaluations of weld and weld repair procedures by applicant. 41. TITLE: DEGRADED PIPING PHASE II FY 85 FY 86 FY 87 CONTRACTOR: Battelle Columbus Lab BUDGET 1800 1250 1200 OBJECTIVE: Experimentally determine the capacity of cracked ductile piping to withstand normal, transient and accident loading conditions to assure compliance with 10CFR50 Appendix A, GDC 14, 30 and 31. Develop and validate ducticle fracture mechanics analyses for predicting the loading capacity and failure mode of cracked pipes. 42. TITLE: INTL PIPING INTEG RESEARCH FY 85 FY 86 FY 87 GP (IPIRG) BUDGET 0 650 500 CONTRACTOR: Battelle Columbus Labs OBJECTIVE: To develop, improve and verify engineering methods for assessing the integrity of nuclear power plant piping containing defects, and to develop the technology to justify plant life extension and simplifications in nuclear plant piping design criteria.

106 43. TITLE: LEAK DETECTION FY 85 FY 86 FY 87 CONTRACTOR: Argonne National Lab BUDGET 450 550 600 OBJECTIVE: To validate that acoustic emission technology can be used for leak detection to provide additional confidence that the Leak Before Break regulatory principle can be maintained. 44. TITLE: IMP EDDY CURRENT INSERVICE FY 85 FY 86 FY 87 INSP FOR STEAM GEN TUBING BUDGET 100 150 200 CONTRACTOR: Oak Ridge National Laboratory OBJECTIVE: To verify and upgrade inspections required by ASNE code, and assure validity of tube plugging and inspection plan criteria set forth in Reg Guides 1.83 and 1.121. To demonstrate significantly improved capability for detection and sizing of all kinds of flaws and degradation in steam generator tubing, so that the reliability of such inspections will be greatly increased (and the uncertainty about the reliability of in-service inspection results will be greatly reduced) thus greatly lessening the possibility of unexpected and massive tube failures resulting in loss of coolant and exposure of the public to radiation. The unrealiability of present methods, and the need for such improved methods, is demonstrated by the round robin inspection trials of the Steam Generator Group Project using the retired Surry steam generator. 45. TITLE: ACOUSTIC EMMISSION MATERIAL STUDY FY 85 FY 86 FY 87 CONTRACTOR: Pacific Northwest Lab BUDGET 600 200 200 OBJECTIVE: To validate that acoustic emmission technology can be used as a continuous monitor to provide assurance that cracks, have neither initialized nor are growing and thus that the pressure boundary is not endangered and remains in compliance with 10CFR50, Appendix A, General Design Criteria 30, 31 and 32. The technology is a key method of assuring Leak Before Break in piping systems and thus preclude violation of that new regulatory basis.

107 46. TITLE: INTEGRATION OF NDE RELIABILITY AND FY 85 FY 86 FY 87 FRACTURE MECHANICS BUDGET 1200 1200 1200 CONTRACTOR: Pacific Northwest Laboratories OBJECTIVE: To establish the effectiveness and adequacy of inservice inspections to reliably find and accurately size flaws in reactor pressure vessels and piping systems using current and advanced nondestructive examination techniques. To determine the impact of inservice inspection reliability on system integrity and to reduce the uncertainty in safety evaluations through quantitative knowledge of the inspection reliability. To recommend ASME Boiler and Pressure vessel Code and NRC regulatory changes to inspection criteria (sampling plan, frequency of inspections) based on material properties, service conditions and inspection uncertainties and develop the requirements for demonstration of qualification inspection personnel, procedures and equipment to assure that flaws can be reliably found and evaluated as plants age to avoid unexpected failures. 47. TITLE: REAL TIME SAFT-UT FY 85 FY 86 FY 87 CONTRACTOR: Pacific Northwest Labs BUDGET 600 300 300 OBJECTIVE: To reduce the uncertainty in safety evaluations by improving the detection reliability and sizing accuracy of flaws in light water reactor nuclear components, to assure that component failures and corresponding loss of coolant accidents cannot occur because a severe flaw was missed during inspection or because a large flaw was allowed to remain in service since it was improperly thought to be of much smaller size. This program is completing field validation of a new untrasonic test inspection method, SAF-UT, that will provide this greatly enhanced detection and sizing capability that can be used by the NRR staff for third party checks on questionable inspection results from the field. To incorporate the method into the ASME Boiler and Pressure Vessel Code and or NRC Regulatory requirements to provide improved results from commercial inservice inspection of nuclear reactor components. 48. TITLE: POSTMORTEM EXAMS OF EQUIP - PLANT FY 85 FY 86 FY 87 AGING BUDGET 575 650 1250 CONTRACTOR: Brock haver, National Laboratory OBJECTIVE: To identify and characterize aging and sevice wear effects associated with selected safety system equipment. Also, determine how aging and service wear affects the capability of selected equipment to perform its function during or after seismic events and what methods might be practical and cost effective in detecting significant aging and service wear deterioration that may compromise its seismic performance.

108 49. TITLE: SURVEY OF AGED POWER PLANT PLANT FY 85 FY 86 FY 87 FACILITIES BUDGET 351 1050 1500 CONTRACTOR: Idaho National Engineering Laboratory OBJECTIVE: The major objectives of this research element are to identify, at plant level, LWR systems and components which might develop aging concerns and impact safety as plant operations continue; to perform a structured aging assessment study on a selected fluid-mechanical and electrical system and to develop a plan for residual life evaluation of vital safety system mechanical components. 50. TITLE: DECONTAMINATION METHODS - EFF FY 85 FY 86 FY 87 AND SAFETY BUDGET 100 0 400 CONTRACTOR: Idaho National Engineering Laboratory OBJECTIVE: The increased utilization of in situ decontamination of primary coolant systems and associated equipment has raised questions within the Nuclear Regulatory Commission as to the effectiveness of the decontaminations in reducing occupational exposure. This program is to obtain information, by collecting actual operating experience, on decontamination methods in reducing occupational exposures, waste forms generated, and potential problem areas. 51. TITLE: DEGRADATION MONITORING NPP SAFETY FY 85 FY 86 FY 87 EQUIPMENT BUDGET 905 1300 1500 CONTRACTOR: Oak Ridge National Laboratory OBJECTIVE: Evaluate and identify practical and cost effective methods for detecting, monitoring and assessing the severity of time dependent degradation (aging) of electrical and mechanical components and structures in nuclear power plants. Emphasis will be on methods for detection of the onset of incipient defects prior to failures and on assessment of periodic maintenance and surveillance schedules for vital components in plant safety systems.

109 52. TITLE: LWR AGING STUDIES; SHIPPIN PWR FY 85 FY 86 FY 87 AGING EVALUATION BUDGET 475 700 1000 CONTRACTOR: Pacific Northwest Laboratory OBJECTIVE: A. Evaluate the relevancy of components and materials at Shippingport - PWR as a source of plant aging information, perform in-situ assessments of aged components and obtain equipment for post service examinations and tests. B. Evaluate and assess the system performance of hydraulic and mechanical snubbers. Establish failure mechanisms and causes and provide recommendations for practical and cost effective application, operation, and maintenance. C. Make recommendations and generate guidelines for inspection, surveillance conditions monitoring methods and maintenance for room coolers and emergency diesel generators associated with plant safety systems. 53. TITLE: FACILITIES UNDERGOING DECOMMISS- FY 85 FY 86 FY 87 ZONING BUDGET 475 700 1000 CONTRACTOR: United Nuclear Corp. OBJECTIVE: Provide the NRC licensing staff data which will allow an assessment of radiation exposure during decommissioning and the implementation of ALARA techniques. Provide information to determine the proper amount of funds which must be available to ensure timely and safe decommissioning operations. This information is being used by NRR for evaluation of reactor decommissioning plans and will be used by RES in the development of the final decommissioning rule and in the proposed residual contamination rule. 54. TITLE: FIRE PROTECTION RESEARCH FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 800 650 500 Laboratory OBJECTIVE: Probabilistic risk assessments (PRA) have indicated that fires may contribute a significant fraction of the risk from nuclear plants, but there are large uncertainties in estimating the risk because of lack of data quantifying heat and corrosive materials generated by fires, their transport through the plant, the effects on safety equipment, and the relative effectiveness of fire protection measures to suppress fires and prevent damage to safety equipment. The objective for FIN A-1010 is therefore to develop test data for use in (a) evaluation of residual risk from fires in nuclear power plants in order to determine whether the licensing requirements for fire protection need to be modified, and (b) assessment of proposals by licensees for implementation of current regulations.

110 55. TITLE: QUAL TESTING EVALUATION FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 1600 1355 1600 Laboratory OBJECTIVE: Evaluate the procedures and methods used to qualify safety related electrical equipment to assure that they survive and function during and following an accident taking into account the effects of aging prior to the accident. 56. TITLE: EQUIPMENT SURVIVABILITY FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 78 300 208 Laboratory OBJECTIVE: 1. Analyses and equipment thermal response tests to provide data for licensing decision on equipment survival in large dry PWR containment. 2. Develop criteria for assessing Hydrogen Control Owners Group (HCOG) experiments on equipment survival in a BWR MK III containment with standing flames. 57. TITLE: ELECTRIC PENETRATION ASSEMBLIES FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 187 250 100 Laboratory OBJECTIVE: 1. Evaluate the containment integrity, leakage and potential failure mechanisms with electrical penetration assemblies (EPA) used in the three principal reactor containments (PWR, MI I BWR and MK III BWR) when exposed to a severe accident environment. 2. Determine the electric functional behavior of the EPAs under these same accident conditions. 58. TITLE: TESTING EQUIPMENT - SEVERE FY 85 FY 86 FY 87 ACCIDENT SEQUENCES BUDGET 50 150 400 CONTRACTOR: Sandia National Laboratory OBJECTIVE: Confirm the adequacy of data obtained from plant instrumentation and the availability of electrical equipment under severe accident states which provide the basis for operational and emergency preparedness actions; provide more accurate data for deterministic and probabilistic calculations as they pertain to severe accident states.

Ill 59. TITLE: FIRE PROTECTION RESEARCH FY 85 FY 86 FY 87 CONTRACTOR: Brookhaven National BUDGET 200 350 200 Laboratory OBJECTIVE: Probabilistic risk assessments (PRA) have indicated that fires may contribute a significant fraction of the risk from nuclear plants, but there are large uncertainties in estimating the risk because of lack of data quantifying heat and corrosive materials generated by fires, their transport through the plant, the effects on safety equipment, and the relative effectiveness of fire protection measures to suppress fires and prevent damage to safety equipment. The objective for FIN A-3252 at Brookhaven National Laboratory is to develop a computational capability for use in (a) evaluation of residual risk from fires in nuclear power plants, and (b) assessment of proposals by licensees for implementation of current regulations. 60. TITLE: OPER AVAIL OF INSTRUMENTS FOR FY 85 FY 86 FY 87 SEVERE ACCIDENTS BUDGET 300 150 300 CONTRACTOR: Idaho National Engineering Lab OBJECTIVE: Confirm the adequacy of data obtained from plant instrumentation and the availability of electrical equipment under severe accident states which provide the basis for operational and emergency preparedness actions; provide more accurate data for deterministic and probabilistic calculations as they pertain to severe accident states. B. THERMAL HYDRAULICS DECISION UNIT 61. TITLE: MIST INSTRUMENT FACILITY SUPT FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 465 300 300 Engineering Laboratory OBJECTIVE: Provide advanced instrumentation, analysis and consulting support for MIST test program, which has as its objective to provide experimental data unique to the NRC safety analysis code verification. 62. TITLE: MIST & OTIS ANALYSIS FY 85 FY 86 FY 87 CONTRACTOR: Los Alamos National BUDGET 405 400 400 Laboratory OBJECTIVE: To provide code analysis and consulting support for MIST program, which has as its objective to provide experimental data unique to the B&W reactor system geometry for NRC safety analysis code verification.

112 63. TITLE: MIST/OTIS LOOP FACILITY FY 85 FY 86 FY 87 CONTRACTOR: Babcock & Wilcox BUDGET 4500 2425 3500 OBJECTIVE: To provide the only full pressure integral system experimental data unique to the B&W system design for addressing safety and licensing issues and code assessment requirements for transients involving SBLOCA (small break loss-of-coollant accidents), reestablishment of natural circulation and steam generator tube rupture (SGTR). This will provide data needed by NRR and B&W Owners to resolve uncertainties raised by the Three-Mile Island Accident in 1979 with respect to the ability of emergency cooling or different operating procedures to prevent fuel damage and radionuclide release. 64. TITLE: 3D INSTRU SUPPORT FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 750 500 451 Engineering Laboratory OBJECTIVE: To provide technical support and instrumentation services for several facilities of the 2D/3D program in Germany and Japan. 65. TITLE: TRAC APPLICATIONS TO 2D/3D FY 85 FY 86 FY 87 CONTRACTOR: Los Alamos National BUDGET 2621 1900 2350 Laboratory OBJECTIVE: To calculate with TRAC multidimensional processes during the refill and reflood stages of a PWR LOCA in order to plan and coordinate multidimensional experiments providing data to assess NRC best-estimate licensing codes under large break (LOCA) conditions. To perform post-test predictions and analyses for the refill/reflood tests being performed in Japan and Germany. To resolve uncertainties in the three dimensional (cross) flows of steam and liquid along with fall back of liquid from the upper plenum into the reactor core. The above objectives support the ultimate objective of developing more realistic thermal hydraulic codes to predict plant performance under accident conditions. 66. TITLE: ADV INSTRUMENTATION FOR PWR FY 85 FY 86 FY 87 REFLOOD STUDIES BUDGET 570 300 251 CONTRACTOR: Oak Ridge National Laboratory OBJECTIVE: To provide two-phase flow instrumentation for large scale reflood studies.

113 67. TITLE: LOCA/ECCS SUPPORT STUDIES FY 85 FY 86 FY 87 CONTRACTOR: WPR Associates BUDGET 695 350 350 OBJECTIVE: 1. To provide technical support for revising 10 CFR 50 Appendix K rules. 2. To provide technical support for analyzing data for improved understanding of the loss-of-coolant accident (LOCA) phenomena and computer code TRAC assessment. 68. TITLE: ROSE 4 TECH SUPPORT FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 680 550 500 Engineering Laboratory OBJECTIVE: To obtain thermal-hydraulic experimental data from a facility of sufficiently large scale to verify existing small scale data. Scaling uncertainties become important in some accidents that are affected by the higher surface to volume ration of small test facilities. For instance, ROSA-IV will help resolve uncertanties in an accident discovered in the Semiscale facility in which larger than expected water level depression in the core was experienced with accompanying fuel heat up as a result of liquid hold-up in other parts of the primary system. 69. TITLE: TECHNICAL SUPPORT TO JAERI FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 220 0 400 Engineering Laboratory OBJECTIVE: To obtain data from large scale integral thermal hydraulic test facilities. The data are to be used to evaluate safety analysis codes which are being used by the NRC licensing staff to audit licensees. The data are to be obtained as economically as possible from foreign facilities through exchange of instrumentation and computer codes. Scaling uncertainties become important in some accidents that are affected by the higher surface to volume ratio of small facilities. Specifically, the data obtained is to help resolve uncertainties in an accident discovered in the Semiscale facility in which larger than expected water level depression in the core was experienced with accompanying fuel heat up as a result of liquid hold-up in other parts of the primary system. 70. TITLE: ROSA IV DATA ANALYSIS FY 85 FY 86 FY 87 CONTRACTOR: Los Alamos National BUDGET 220 650 700 Laboratory OBJECTIVE: To confirm the ability of NRC's safety analysis codes to predict safety system performance during transients and accidents by validating the code against data from large scale integral test facilities.

114 71. TITLE: COOP PROGRAMS SUPPORT FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 500 300 5i0 Engineering Laboratory OBJECTIVE: To provide support, advice and transfer of national laboratory technology to industry cooperative programs to ensure that these programs meet their regulatory objectives (see discussion under B3014, RWR FIST, and B8252, MB-2). Audit cooperative programs to address potential conflict-of-interest questions since the reactor vendors are parties to the cooperative ventures. 72. TITLE: SEMISCALE PROGRAM FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 4581 3146 5M Engineering Laboratory OBJECTIVE: As needed to resolve NRC concerns with plant safety and with licensing concerns in Westinghouse and Combusion Engineering plant designs, perform integral systems transient and loss of coolant accident tests and evaluate the data generated from these tests. Provide data for validation of computer codes used for reactor licensing safety evaluations by NRC staff. Uncertainties in the ability of best-estimate codes to predict response to these transients and accidents must be quantified as a basis for assessing the adequacy of conservatisms used in licensing-type codes. In this way the NRC staff can independently assess vendor and utility approaches to plant design and operations to assure safe response of the reactors to these events. During its lifetime, Semiscale has provided data for uncertainty assessment on essentially every loss of coolant accident and transient type of interest to the NRC staff. 73. TITLE: NRC/DAE DATA BANK FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 75 400 401 Engineering Laboratory OBJECTIVE: The regulatory purpose is to preserve the results of safety tests performed in experimental facilities and reactors. These safety tests were performed for regulatory purposes in the U.S.A. and worldwide. The test results could become inacessible after an experiment is dismantled. Hence, the Experimental Data Bank preserves and provides rapid access in a common easy to use format for all the safety tests. The safety tests data are needed to test and verify computer codes used for licensing analyses. 74. TITLE: SG TUBE RUPTURE FY 85 FY 86 FY 87 CONTRACTOR: Oak Ridge National BUDGET 155 200 190 Laboratory OBJECTIVE: To experimentally determine the partition of iodine between liquid and steam in an environment which simulates steam generator tube rupture.

115 75. TITLE: MIXING IN STRATIFIED FLOWS FY 85 FY 86 FY 87 CONTRACTOR: UC-SB BUDGET 05 254 200 OBJECTIVE: (1) Develop simplified accurate methods to analyze thermal mixing in reactors and perform analyses in support of the Pressurized Thermal Shock (PTS) rule. (2) Obtain boron mixing data needed for boron transport model development. 76. TITLE: MODELING OF TWO-PHASE FLOW FY 85 FY 86 FY 87 CONTRACTOR: Argonne National Lab BUDGET 310 240 300 OBJECTIVE: To develop two-phase flow models and correlations to support accurate LWR safety analyses and to assess scaling compromises in experimental facilities. 77. TITLE: CRIT DISCHARGE THRU PIPE CRACK FY 85 FY 86 FY 87 CONTRACTOR: Lawrence Berkeley Lab BUDGET 80 75 0 OBJECTIVE: To remove uncertainties in determining: a. critical discharge through pipe cracks, and b. critical flow through small-breaks in horizontal pipes with stratified upstream conditions by providing test data and validated models. 78. TITLE: NONEQUIL HEAT TRANSFER FY 85 FY 86 FY 87 CONTRACTOR: Lehigh University BUDGET 85 100 0 OBJECTIVE: To develop an experimentally and phenomenologically based model for thermal non equilibrium post Critical Heat Flux (CHF) heat transfer model applicable to both high and low flow rates in rod bundles. 79. TITLE: GEOMETRIC ANAL OF ENSEMBLE OF FY 85 FY 86 FY 87 SOL - 2 PHASE FLOWS BUDGET 50 80 0 CONTRACTOR: Brown University OBJECTIVE: a. To complete the resolution of the choking flow problem by conducting a geometric analysis of two-phase flow solutions. b. To establish a choked flow criterion and validate it against available experimental data.

116 80. TITLE: DATA ANALYSIS & TESTS OF CORK FY 85 FY 86 FY 87 CONTRACTOR: Undes Laboratory BUDGET 0 50 fl OBJECTIVE: To explore the feasibility of synthesizing and generalizing experimental data and code calculation results via appropriate similarity groups and/or similarity functions. To date, experiments and/or code calculations are performed by varying one parameter at a time, for example, by varying break size or power or emergency core cooling (ECC) water, etc. Similarly, for each run the results are presented as plots of single variables versus time, for example, pressure or break flow or T clad are plotted versus time. As a result, a large number of test runs and/or of code calculations and required in order to assess the effects of the various parameters of interest. If this program demonstrates that syntheses of experimental data and/or of calculated results are feasible, then this program will yield methods for achieving considerable savings in funds by reducing the number of required experimental tests and/or of code calculations. 81. TITLE: CODE ASSESSMENT & APPL (A1205) FY 85 FY 86 FY 87 CONTRACTOR: Sandia National Lab BUDGET 525 425 300 OBJECTIVE: As part of the TRAC-PWR assessment effort. 82. TITLE: CODE ASSESSMENT & APPL FY 85 FY 86 FY 87 CONTRACTOR: Brookhaven National Lab BUDGET 225 200 150 OBJECTIVE: The objectives are 1) to assess thermal & hydraulic system transient codes TRAC-BWR and RAMONA III B using domestic test data to assure the accuracy of the codes and to quantify the uncertainties of code predictions. The regulatory goal is to provide NRR with assessed computer codes so that vendor submittals of reactor transient analyses and operator guidelines can be audited. 83. TITLE: CODE ASSESSMENT & APPL FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 435 0 300 Engineering Laboratory OBJECTIVE: The objectives are 1) to assess thermal & hydraulic system transient codes (TRAC-PFl/MODl, TRAC-BDl/MODl and TRAC-BFl) using domestic test data to assure the accuracy of the codes, 2) to quantify the uncertanties of code predictions and 3) to perform transient analyses to resolve licensing issues. The regulatory goal is to provide NRR with assessed computer codes so that vendor submittals on reactor transient analyses and operator guidelines can be independently audited.

117 84. TITLE: USER ASSISTANCE FOR CODE FY 85 FY 86 FY 87 EXCHANGE BUDGET 350 1200 850 CONTRACTOR: Idaho National Engineering Laboratory OBJECTIVE: The objectives are 1) to assess thermal & hydraulic system transient codes RELAPS/MOD2, TRAC-BWR using foreign results and domestic data to 1) assure the accuracy of the codes: 2) quantify the uncertainty of code predictions and 3) perform plant transient analyses. The regulatory goal is to provide NRR with assessed computer codes so that licensee submittals on reactor transient analyses and operator guidelines can be audited and reviewed, and operating transients can be reviewed and assessed. 85. TITLE: USER ASSISTANCE FOR CODE FY 85 FY 86 FY 87 EXCHANGE BUDGET 350 685 450 CONTRACTOR: Los Alamos National Laboratory OBJECTIVE: The objectives are 1) to assess thermal & hydraulic system transient code TRAC-PFl/MODl using foreign results and domestic data to: 1) assure the accuracy of the codes; 2) quantify the uncertainty of code predictions; and 3) perform plant transient analyses. The regulatory goal is to provide NRR with assessed computer codes so that license submittals on reactor transient analyses and operator guidelines can be reviewed and audited and operating transients can be reviewed and assessed. Resolves uncertanties associated with noding sensitivities in B&W reactor thermal hydraulic behavior predictions with TRAC-PFl/MODl. 86. TITLE: THERMAL REACTOR SAFETY CODE FY 85 FY 86 FY 87 DEVELOPMENT BUDGET 50 50 100 CONTRACTOR: Brookhaven National Laboratory OBJECTIVE: The objective is to provide NRR with a system transient Boiling Water Reactor thermal & hydraulic analysis code (RAMONA III B) with three dimensional neutron kinetics capability so that vendor submittals on reactor transient analyses and operator guidelines can be audited. 87. TITLE: DEVELOPMENT OF PLANT ANALYZER FY 85 FY 86 FY 87 CONTRACTOR: Brookhaven National BUDGET 150 150 200 Laboratory OBJECTIVE: The objective is to provide NRR with a fast running system transient (not including LOCA) Boiling Water Reactor thermal & hydraulic analysis code (HIPA) on a stand-alone parallel processing computer so that vendor submittals on reactor transient analyses and operator guidelines can be audited quickly.

118 88. TITLE: CODE DEVELOPMENT & IMPROVEMENT FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 656 885 500 Engineering Laboratory OBJECTIVE: To provide NRR the capability to accurately analyze a wide variety of PWR transients for use in auditing vendor calculations of ECCS behavior under Loss-of-Coolant Accident conditions defined 10 CFR 50.46 Appendix K, and reviewing operator procedures. Develop a code to be used to perform sensitivity study on paramters (such as decay heat, break flow, etc.,) which affect fuel peak clad temperature. 89. TITLE: RELAP 5 FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 150 0 200 Engineering Laboratory OBJECTIVE: To provide NRR the capability to accurately calculate a wide variety to PWR transients for use in auditing vendor calculations of ECCS behavior under Loss-of-Coolant-Accident conditions defined 10 CFR 50.46 Appendix K, and reviewing operator procedures. Develop a code to be used to perform sensitivity study on parameters (such as decay heat, break flow, etc.,) which affect fuel peak clad temperature. 90. TITLE: PLANT ANALYZER FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 533 575 700 Engineering Laboratory OBJECTIVE: The objective is to assist NRR in auditing licensee application and performance. The regulatory goal is to make swift decisions on the safe operation of a plant where an operational transient has occurred (and similar plants). This requires speed up of the computer program used for analysis, making input to the programs easier and making program output more quickly comprehensible by translating thousands of numerical values into pictures. 91. TITLE: TRAC CODE DEVELOPMENT FY 85 FY 86 FY 87 CONTRACTOR: Los Alamos National BUDGET 500 500 500 Laboratory OBJECTIVE: To maintain the best estimate advanced TRAC-PWR code (thermal-hydraulic code for Pressurized Water Reactors) in order to respond to licensing issues such as: (1) best estimate LOCA calculations to determine the available margins in vendor calculations of plant behavior under LOCA and transient conditions, (2) resolution of issues involving decay heat removed using feed and bleed procedures, and (3) evaluation of operator guidelines. Calculations using TRAC-PWR allow resolution of uncertainties regarding the ability of the reactor safety systems to prevent fuel damage during these transient conditions and accidents. Some of the specific uncertainties are critical heat flux, heat transfer following critical heat flux and coolant flow distribution during reactor blowdown.

119 92. TITLE: PLANT ANALYZER FY 85 FY 86 FY 87 CONTRACTOR: Los Alamos National BUDGET 750 500 700 Laboratory OBJECTIVE: The objective is to assist NRR in auditing licensee applications and performance. The regulatory goal is to make swift decisions on the safe operation of a plant where an operational transient has occurred (and similar plants). This requires speed up of the computer program used for analysis, making input to the programs easier and making program output more quickly comprehensible by translating thousands of numerical values into pictures. 93. TITLE: COBRA MAINTENANCE FY 85 FY 86 FY 87 CONTRACTOR: Pacific Northwest BUDGET 79 15 100 Laboratories OBJECTIVE: To maintain the COBRA-TRAC and COBRA-FS thermal-hydraulic codes for pressurized water reactors with specific ability to calculate two phase flow mechanistically and to handle complex geometries in order to respond to licensing issues. The codes should be able to perform best estimate loss-of-coolant-accident (LOCA) predictions (especially for Westinghouse plants with Upper Head Injection) to determine the available margins in vendor calculation, and to evaluate operator guidelines, and should be able to perform detailed sub-channel behavior calculation for the reactor core. 94. TITLE: NUCLEAR REACTOR PLANT FY 85 FY 86 FY 87 DESCRIPTION DATA BANK BUDGET 30 65 0 CONTRACTOR: Technology Develop Corp. OBJECTIVE: Serve as a computer bank of plant reactor geometric and operating data, sufficient for thermal hydraulic reactor safety analyses. Provide automated tools to permit rapid renodelization and creation of input decks to NRCs safety analysis computer codes. Train potential users to input data and perform input deck creations. Assist with User Acceptance Testing of the software. C. ACCIDENT EVALUATION DECISION UNIT 95. TITLE: SEVERE ACCIDENT SEQUENCE FY 85 FY 86 FY 87 ANALYSIS-PWRS BUDGET 825 600 600 CONTRACTOR: Sandia National Laboratory OBJECTIVE: Apply deterministic analyses to risk dominant accident sequences for specific plants utilizing best estimate values. Improve our understanding on severe accidents by defining operator actions which can reduce core melt likelihood or mitigate its consequences and provide assessment of the adequacy of proposed operational guidelines for coping with transients that challenge plant safety. Provide mechanistic analyses of containment loading from severe accidents and the resulting threats to safety equipment.

120 96. TITLE: BWR SEVERE ACCIDENT ANALYSIS FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 0 240 0 Laboratory OBJECTIVE: Apply deterministic analyses to risk dominant accident sequences for specific plants utilizing best estimate values. Improve our understanding of severe accidents by assuring development of ex-vessel core/concrete interaction models to be fully representative of BWR plants. Provide mechanistic analysis of containment loading from severe accident and the resulting threats to safety equipment. 97. TITLE: SEVERE ACCIDENT SEQUENCE FY 85 FY 86 FY 87 ANALYSIS-PWRS BUDGET 825 800 65» CONTRACTOR: Idaho National Engineering Laboratory OBJECTIVE: Perform realistic analyses for risk dominant accident sequences for specific plants utilizing best-estimate values in deterministic analysis codes. Improve understanding of potential severe reactor accidents by i) defining operator action which can reduce core melt likelihood or mitigate its consequences and ii) providing an assessment of the adequacy of proposed operational guidelines for coping with transients that challenge a plants safety. 98. TITLE: SEVERE ACCIDENT ANALYSIS-BWRS FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 0 150 0 Engineering Laboratory OBJECTIVE: Perform realistic analyses for risk dominant accident sequences for specific plants utilizing best-estimate values in deterministic analysis codes. Improve understanding of potential severe reactor accidents by i) defining operator action which can reduce core melt likelihood or mitigate its consequences and ii) providing an assessment of the adequacy of proposed operational guidelines for coping with transients that challenge a plants safety. 99. TITLE: METH SAFETY ANALYSIS FY 85 FY 86 FY 87 CONTRACTOR: Los Alamos National BUDGET 400 475 0 Laboratory OBJECTIVE: The SIMMER-II computer code was developed to provide a tool to analyse hypothetical core disruptive accidents (HCDA) in liquid metal fast breeder reactors. The code calculates the energetics of HCDS's and their potential threat to the reactor vessel and containment. The objective of ongoing work is to make improvements to the running time of the code to reduce costs and to apply the code to analysis of safety problems. Continued cooperation with KFK of West Germany, CEA of France and PNC of Japan will maintain access to experimental data from foreign fast breeder research programs.

121 100 TITLE: SEVERE ACCIDENT SEQUENCE FY 85 FY 86 FY 87 ANALYSIS-PWRS BUDGET 1004 850 650 CONTRACTOR: Oak Ridge National Laboratory OBJECTIVE: Apply deterministic analyses to risk dominant accident sequences for specific plants utilizing best estimate values. Improve understanding of severe accidents by defining operator actions which can reduce core melt likelihood or mitigate its consequences and provide assessment of the adequacy of proposed operational guidelines for coping with transients that challenge plant safety. Assure that methodology developed primarily for PWR analysis includes adequate modification of BWR plant studies. 101 TITLE: FP TRANSPORT IN BWR SEVERE FY 85 FY 86 FY 87 ACCIDENTS BUDGET 0 180 0 CONTRACTOR: Oak Ridge National Laboratory OBJECTIVE: Apply deterministic analyses to risk dominant accident sequences for specific plants utilizing best estimate values for fission product tracking. Improve understanding of severe accidents by defining operator actions which can reduce the source term to the environment and the offsite consequences. Assure that methodology developed primarily for PWR analysis includes an adequate data base for BWR plant studies. 102 TITLE: ACRR MELT PROG EXPETS FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 975 1000 1400 Laboratory OBJECTIVE: To develop a data base and validated analytical models on the governing processes in the development of severe fuel damage (including the oxidation process and hydrogen generation), core-melt progression (including control-rod effects), and in-vessel fission-product and aerosol release for the range of LWR severe accident conditions by performing small-scale integral experiments in the Annular Core Research Reactor (ACRR). The results are used to assess and improve severe-accident analysis codes, in particular the mechanistic MELPROG melt-progression and SCDAP fuel-damage codes. This program includes four fresh-fuel Debris Formation (DF) experiments, two with control-rods, to be completed in FY 86, and two follow-on Melt Progression and Source Term (MPST) experiments with high burnup fuel up to fuel-melt temperatures for a PWR and a BWR risk-dominant accident sequence that are to be performed in FY 87. This program is part of the joint international Severe Fuel Damage (SFD) and Source Term (ST) research program of the Fuel Systems Research Branch.

122 103 TITLE: MELPROG CODE DEVELOPMENT FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 565 800 600 Laboratory OBJECTIVE: 1. Develop a best-estimate computer code (joint work with FIN A7303) MELPROG, to analyze severe accidents from core melt to reactor vessel failure. 2. Apply the code to predict the timing and the characteristics of the release of core debris and radioactive materials to the containment. 104 TITLE: MELPROG VALIDATION EXPTS FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 0 1200 1300 Laboratory OBJECTIVE: To provide a technical basis for validation of the MELPROG mechanistic in-vessel core-melt progression code by assessing the uncertainties in the governing process and by providing a much stronger validation data base by experiments to reduce the risk-dominant uncertainties. Because of the large scale and complex interactions involved, a large-scale integral validation proof test of MELPROG is not feasible. Key individual elements of the code are to be validated by experiment with integration of the elements of necessity by analysis with some relevant integration data furnished by the TMI-2 core examination. Areas requiring new experimental data include: core-debris relocation, the thermal attack on the core-support structure and the reactor vessel, the node of vessel failure, the effects of control rod materials, and the effects of multi-dimensional natural convection and heat transfer. These are to be addressed by a program of separate-effect experiments, out-of-pile in the laboratory and in existing test facilities, and in-pile in ACRR. 105 TITLE: TMI FUEL EXAM FY 85 FY 86 FY 87 CONTRACTOR: Argonne National BUDGET 200 300 300 Laboratory OBJECTIVE: By examination of the TMI-2 core debris, to provide benchmark data for the assessment of severe accident codes and for augmentation of results of the Severe Fuel Damage and Source Term research program. 106 TITLE: COMMIX CALCULATIONS FY 85 FY 86 FY 87 CONTRACTOR: Argonne National BUDGET 150 100 0 Laboratory OBJECTIVE: To predict multi-dimensional flow patterns and temperature distributions in the reactor coolant system of a pressurized water reactor (PWR) during high-pressure transients.

123 107 TITLE: MELCOR BENCHMARKING FY 85 FY 86 FY 87 CONTRACTOR: Brookhaven National BUDGET 200 500 600 Engineering Laboratory OBJECTIVE: To ensure that models developed for MELCOR are adequate for source term analysis, and to perform benchmark analyses and code verification for the complete MELCOR code. 108 TITLE: PBF STANDBY OPERATIONS FY 85 FY 86 FY 87 (POST FY 85) BUDGET 6530 500 0 CONTRACTOR: Idaho National Engineering Laboratory OBJECTIVE: In FY 86 to provide for minimum cost standby operation of Power Burst Facility until FY 87. When funds for deactivation will become available. 109 TITLE: RESIDENT SCIENTIST AT FY 85 FY 86 FY 87 KFK, FRG BUDGET 100 60 200 CONTRACTOR: Idaho National Engineering Laboratory OBJECTIVE: To facilitate the exchange of nuclear safety-related information between the U.S. and Germany. Germany provides in-kind research as its contribution under the Severe Fuel Damage International Agreement. ll0 TITLE: SEVERE FUEL DAMAGE MODEL DEV FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 780 770 650 Engineering Laboratory OBJECTIVE: 1. Develop and validate a best-estimate computer code (SCDAP) to analyze recovered or mitigated severe accidents from initial core damage to accident recovery. 2. Apply this (SCDAP) code to predict the timing and magnitude of radioactive material and hydrogen release to the containment or to other areas outside the reactor coolant system during recovered severe accidents.

124 ll1 TITLE: TRAC/MELPROG INTEGRATION FY 85 FY 86 FY 87 CONTRACTOR: Los Alamos National BUDGET 320 300 351 Laboratory OBJECTIVE: 1. Develop the best-estimate computer code (joint work with FIN A1342) MELPROG, to analyze severe accidents from core melt to reactor vessel failure. 2. Apply the code to predict the timing and the characteristics of the release of core debris and radioactive materials to the containment. ll2 TITLE: SEVERE CORE DAMAGE MATERIALS FY 85 FY 86 FY 87 PROP TEST BUDGET 290 300 200 CONTRACTOR: Pacific Northwest Laboratories OBJECTIVE: To obtain high temperature data on core material behavior for use in severe core damage fuel behavior irradiation tests, for safety analysis codes, and for analysis of the severe fuel damage research program results. Uncertainties in reactor core materials properties under severe accident conditions affect fission product release analyses in two ways. The chemical interactions calculations, which require accurate material properties input, yield radionuclide chemical states. These are needed for health effects determinations. The second effect of accurate materials properties data is on fuel mitigative actions to cool a damaged core. 113 TITLE: MOLTEN CORE-COOLANT FY 85 FY 86 FY 87 INTERACTIONS BUDGET ll00 585 0 CONTRACTOR: Sandia National Laboratory OBJECTIVE: To study the interaction of molten core material with water in order to develop a fundamental understanding of the governing phenomena and to measure the mechanical energy released from a corium-coolant interaction during a severe accident in a light water reactor. Provide analytical methods and computer codes to predict the mechanical energy produced, hydrogen generation rate, coarse mixing, and debris characteristics resulting from corium-coolant interactions. ll4 TITLE: CONTAINMENT ANALYSIS FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 1050 800 1200 Laboratory OBJECTIVE: To develop and implement a computer program (CONTAIN) to model power-reactor containment systems and to predict the thermal, physical, and chemical loads imposed by accident conditions.

125 ll5 TITLE: CORE MELT TECHNOLOGY FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 2000 1450 1500 Laboratory OBJECTIVE: In severe reactor accidents in which molten core material escapes the reactor pressure vessel and falls into the reactor cavity, thermal and chemical interactions between the high-temperature core debris and structure concrete are expected to ensure. The purpose of this project is to design and conduct experiments to study the thermal and chemical phenomena expected to characterize these core-concrete interactions. 116 TITLE: HYDROGEN BEHAVIOR PROGRAM FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 1318 1200 200 Laboratory OBJECTIVE: To provide the NRC with the basis to quantify the threat to nuclear power plants containment structure, safety equipment and the primary system posed by hydrogen combusion. 117 TITLE: DIRECT CONTAINMENT HEATING FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 0 650 700 Laboratory OBJECTIVE: The objective of this program is to investigate consequences of high pressure melt ejection. In certain accident scenarios, the reactor vessel may remain pressurized when the molten core materials breaches the bottom of the reactor vessel. When the melt is ejected under pressure into the containment, it is likely to be dispersed as fine particles and heat the containment atmosphere by thermal and chemical interactions producing high static and dynamic loading on the containment. A large amount of aerosols, including refractory radioactive fission products, could be generated so that is the containment should fail from the DCH loading, massive release of fission products could result. Results of this experimental program will provide data basis for quantitative assessment of the consequences of this potentially high risk event. 118 TITLE: QUANT UNCERTAIN OF FY 85 FY 86 FY 87 CONTAINMENT LOADING BUDGET 0 200 0 CONTRACTOR: Sandia National Laboratory OBJECTIVE: Evaluate uncertainties in quantitative predications of loading on reactor containments for selected severe accident sequences at specific plants.

126 ll9 TITLE: ICE CONDENSER MSLB ANALYSIS FY 85 FY 86 FY 87 MTHDS (MAIN STEAM LINE BREAK) BUDGET 0 150 0 CONTRACTOR: Argonne National Laboratory OBJECTIVE: Develop and implement the necessary models in the COMMIX code to investigate the mixing phenomena and temperature behavior in the lower compartment of an Ice Condenser PWR during a postulated main steam line break accident using a three dimensional simulation. 120 TITLE: CORIUM-COOLANT MIXING FY 85 FY 86 FY 87 CONTRACTOR: Argonne National BUDGET 0 865 0 Laboratory OBJECTIVE: To study the mixing of corium with water in order to develop a fundamental understanding of the governing phenomena during a severe accident in a light water reactor. Provide analyses of the mechanical energy produced, hydrogen generation rate, amount of breakup and mixing, depth of mixing, quench rate, and debris characteristics resulting from corium-coolant interactions. 121 TITLE: THERMAL HYDRAULIC EXP FY 85 FY 86 FY 87 CONTRACTOR: Brookhaven National BUDGET 750 450 800 Laboratory OBJECTIVE: Perform experiments, together with corresponding model development, to improve understanding of thermal-hydraulic phenomena involved in severe accident high-temperature core debris behavior. 122 TITLE: THERMAL HYDRAULICS-CORE/ FY 85 FY 86 FY 87 CONCRETE INTERACTIONS BUDGET 0 290 0 CONTRACTOR: Brookhaven National Laboratory OBJECTIVE: Conduct experiments together with analysis and model development on the thermo-dynamic phenomena that govern the interactions between reactor core debris and concrete as well as evolution of aerosols and fission products from debris pool. 123 TITLE: HYDROGEN MIGRATION & MIXING FY 85 FY 86 FY 87 STUDIES BUDGET 250 175 100 CONTRACTOR: Los Alamos National Laboratory OBJECTIVE: To develop a three-dimensional code for the analysis of hydrogen distribution and combustion under severe accident conditions. The code will provide the capability to analyze hydrogen diffusion flames, sepcifically to assess the impact of the flames on safety related equipment.

127 124 TITLE: AEROSOL RELEASE & TRANSPORT FY 85 FY 86 FY 87 CONTRACTOR: Oak Ridge National BUDGET 1300 1000 1000 Laboratory OBJECTIVE: Perform designed experiments to investigate phenomena affecting the behavior of aerosols within containment over a range of light water reactor severe accident conditions. Develop a data base for the assessment of existing analytical models and codes that will accurately predict the behavior of aerosols within LWR containments. 125 TITLE: COBRA APPLICATIONS (b2391) FY 85 FY 86 FY 87 CONTRACTOR: Pacific Northwest BUDGET 250 55 400 Laboratory OBJECTIVEt The objective of this program is to develop a finite-difference, advanced containment analysis code that can benchmark simpler lump-parameter codes and analyze problems which these lump-parameter codes are unable to deal with. Examples of such problems are: o Design basis accident - subcompartment differential pressure, reactor cavity pressurization, ice condenser drain water mixing, etc. o Severe accident - combustible gas mixing and transport, aerosol transport inside containment. Typically, the analysis of these problems require the capability to calculate the motion and conditions of different species and/or phases of the fluid mixture. This cannot be accomodated by the lump-parameter code with a well mixed assumption. 126 TITLE: HIGH TEMP FISSION PROD CHEK FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 450 400 400 Laboratory OBJECTIVE: To provide data for development of fission product transport models to enable best-estimate consequence calculations for the retention of fission products in the reactor coolant system in a severe accident. Specifically, to investigate, following release from the fuel, the high temperature chemistry of fission products in the vapor phase and the chemical interaction of fission products with structural surface materials and airborne aerosols.

128 127 TITLE: ACER SOURCE TERM EXPTS FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 800 1500 1800 Laboratory OBJECTIVE: To develop a data base on the in-vessel fission-product and aerosol release rates from reactor fuel and on fission product and aerosol chemical form for core-uncovery-accident conditions including temperatures up to fuel melt, a range of pressure, and a range of conditions of fuel liquifaction and thermo-chemical environment. A series of seven separate-effects Source Term (ST) experiments will be performed in the Annular Core Research Reactor (ACRR) test reactor in precisely controlled in-core environments to provide these data. This research is part of the integrated Severe Fuel Damage and Source Term research program of the NRC and its foreign program partners, who have furnished the majority of the program funding. 128 TITLE: FUEL FP REL FASTGRASS CODE FY 85 FY 86 FY 87 CONTRACTOR: Argonne National BUDGET 800 250 150 Laboratories OBJECTIVE: To develop a mechanistic fission product release model (the FASTGRASS code) for best-estimate source term calculations for the NRC licensing staff. The code should describe fission product release from LWR fuels during thermal transients and severe reactor accidents and should be developed based on experimental results obtained from other NRC sponsored programs on the area of fission product release. 129 TITLE: POST TEST FUEL EXAM FY 85 FY 86 FY 87 CONTRACTOR: Argonne National BUDGET 150 150 0 Laboratories OBJECTIVE: To provide information on fission product release mechanisms for use in developing detailed models of fission product release from fuel in severe core melt accidents by conducting post-test examinations of the commercially irradiated fuel rods specimens subjected to high temperature fission product release testing at ORNL. 130 TITLE: UNCERTAINTY ANALYSIS OF FY 85 FY 86 FY 87 SOURCE TERM BUDGET 83 800 600 CONTRACTOR: Brookhaven National Laboratory OBJECTIVE: (1) Perform a systematic evaluation of the input parameters on phenomenological models in the Source Term Code Package (STCP) to define reasonable, technically defensible ranges and assumptions for use in the STCP). (2) Determine the uncertainty in the source term to the containment for selected sequences at two of the five reference plants studied by the NRC's Assitent Source Term Program Office (ATPO) in order to evaluate conformance to NRC severe accident policy.

129 131 TITLE: PBF EXPT PGM FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 2923 1950 2000 Engineering Laboratory OBJECTIVE: To provide a data base for mechanistic models on the development of severe fuel damage, under the core-uncovery conditions of severe accidents in Light-Water Reactors (LWRs), by performing integral multi-rod fuel-bundle tests in the Power Bust Facility test reactor, analysis of the test results, and by model development and assessment. Fission-product release and transport, hydrogen generation and temperature distributions during the test transients are measured, with post-test characterization of test fuel debris, including core-melt progression, made by neutron radiography and tomography and by Post-Irradiation Examination (PIE). This program is part of the integrated Severe Fuel Damage and Source Term research program of the NRC and its foreign program partners. 132 TITLE: PBF FISSION PRODUCT FY 85 FY 86 FY 87 STUDIES BUDGET 1884 950 1000 CONTRACTOR: Idaho National Engineering Laboratory OBJECTIVE: 1. To investigate fission product release, transport and behavior under proto-typic accident conditions. 2. To collect, analyze, and report fission product release and transport data from the Severe Fuel Damage (SFD) tests. 3. To measure magnitude, timing, release tales, chemical forms, transport and deposition of fission products released in in-pile Tests. 133 TITLE: FP RELEASE AT SEVERE FY 85 FY 86 FY 87 ACCIDENT CONDITIONS BUDGET 1460 1300 850 CONTRACTOR: Oak Ridge National Laboratory OBJECTIVE: To provide an experimental data base for developing fission product release models to enable best-estimate source term calculations in the fission product release area in severe accidents. Specifically, to investigate experimentally uncertainties in the magnitude and physiochemical form of fission products released and control rod failure behavior under the elevated temperature and environmental conditions characteristic of severe fuel damage and core melt accidents. 134 TITLE: POST ACCIDENT FISS PROD FY 85 FY 86 FY 87 CHEN BUDGET 300 300 200 CONTRACTOR: Oak Ridge National Laboratory OBJECTIVE: To determine the aqueous and vapor phase chemistry of fission products in the containment under representative reactor accident conditions and to model the findings in mathematical formulations to facilitate best-estimate source term calculations.

130 135 TITLE: TRAP-MELT VERIFICATION PGM FY 85 FY 86 FY 87 CONTRACTOR: Oak Ridge National BUDGET 300 300 300 Laboratory OBJECTIVE: To provide data for the assessment of the TRAP-MELT primary system transport and deposition code which enables the NRC regulatory staff to have best-estimate consequence calculations done to determine the retention of fission products and aerosols in the reactor coolant system in a severe accident. Specifically, to conduct small scale aerosol transport tests and resuspension tests. The former will provide data to be compared to TRAP-MELT calculations, with the final aim of assessing the code's aerosol transport models. The latter will provide data for the development of an aerosol resuspension model that can be incorporated in TRAP-MELT and other aerosol transport codes. 136 TITLE: MARVIKEN ATT SUPPORT FY 85 FY 86 FY 87 CONTRACTOR: Oak Ridge National BUDGET 135 25 0 Laboratory OBJECTIVE: Provide technical support for the large fission product and aerosol tests in the MARVIKEN facility (Sweden) as needed to identify uncertainties in the quantities and form in which fission product aerosols might be released to the public. 137 TITLE: NRU COOLANT BOILAWAY & FY 85 FY 86 FY 87 DAMAGE PROGRESSION TESTS BUDGET 1992 2800 2700 CONTRACTOR: Pacific Northwest Laboratories OBJECTIVE: To obtain data for full-length coolant boildown tests in NRU on in-reactor fission product release and transport, hydrogen release, and fuel relocation for computer code verification, for implementation of the NRC Severe Accident Policy Statement, for emergency planning, and for establishing siting policy. 138 TITLE: SUPPORT SERVICES FOR SEVERE FY 85 FY 86 FY 87 ACCIDENT ANALYSIS BUDGET 1902 ll40 0 CONTRACTOR: Battelle Columbus Laboratories OBJECTIVE: Provide a source of expertise and analysis capability which can be called upon by RES to perform research and evaluation of severe accident phenomena. Assist NRC in expeditiously developing a revised source term and severe accident policy statement. Provide integrating assistance to NRC with regard to the severe accident research program.

131 D. REACTOR OPERATIONS AND RISK 139 TITLE: EFFICIENT PROB COMPUTATIONS FY 85 FY 86 FY 87 & METHODS/PRA BUDGET 225 90 0 CONTRACTOR: Lawrence Livermore National Lab OBJECTIVE: Existing PRA methods and procedures lack internal consistency, are incomplete in terms of their treatment of common-cause failures (e.g., external events, human reliability) and, as a result, produce results with large uncertainties. These inadequacies have severely limited the usefulness of PRAs in guiding and supporting a broad range of Commission decisions and actions, e.g., in the areas of safety issue isolation, backfitting, implementation of safety goal and severe accident policies. The objective of this project is to assess and develop a quantification technique that will be used for calculating system reliability characteristics when the rare event approximation does not hold, to investigate extensions of the fault graph method, and to investigate and refine cut set generation algorithms. 141 TITLE: INTEGRATED DEPENDENT FAILURE FY 85 FY 86 FY 87 METHODOLOGY BUDGET 275 285 250 CONTRACTOR: Sandia National Laboratory OBJECTIVE: Existing PRA methods and procedures lack internal consistency, are incomplete in terms of their treatment of common-cause failures (e.g., external events, human reliability) and, as a result, produce results with large uncertainties. These inadequacies have severely limited the usefulness of PRAs in guiding and supporting a broad range of Commission decisions and actions, e.g., in the areas of safety issue isolation, backfitting, implementation of safety goal and severe accident policies. The objective of this project is to develop an integrated methodology for the identification, quantification, and assessment of the impact of dependent failures upon system failures and accident sequence occurrences. The methods will address location-dependent common causes that can link events in system models by location and susceptibility to generic environments as well as common causes that transcend locations such as maintenance and operator actions.

132 141 TITLE: RISK METHODOLOGY INTEGRATION FY 85 FY 86 FY 87 & EVAL PGM (RMIEP) BUDGET 900 545 425 CONTRACTOR: Sandia National Laboratory OBJECTIVE: To provide RNN information needed in areas of external events, human factors, plant analysis and containment analysis, RMIEP will: o Integrate internal, external, and dependent failure risk methods to achieve greater efficiency, consistency, and completeness in risk assessments; o Evaluate Probabilistic Risk Analysis (PRA) technology developments and lay the basis for improved PRA procedures; o Identify, evaluate, and effectively display the uncertainties in PRA risk predictions which stem from limitations in plant modeling, PRA methods, or data; o Conduct a PRA on Boiling Water Reactor (BWR 5). Mark II nuclear plant (La Salle Unit 2), ascertain the plant's dominant sequences, and formulate the results to make it possible to easily update the PRA and to allow testing of future improvements in methodology, data, and the treatment of phenomena. 142 TITLE: FIRE RISK ANALYSIS APPLICATION FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 218 50 51 Laboratory OBJECTIVE: The objective of this program is to perform a probabilistic analysis of the occurrance frequency and severity of fire accident scenarios for the Risk Methodology Integration and Evaluation Program (RMIEP) , using the state-of-the-art fire risk analysis modelling techniques. Existing analytic techniques have large uncertainties, lack internal consistency, and are incomplete in treatment of major failure mechanisms. These inadequacies severely limit the application of PRA to safety goal decisions, plant-specific examination of generic safety issues, and the synergistic considerations necessary for prudent regulation. The objective of this program is to provide for these problems a set of solutions which are complete, integrated, and tested. 143 TITLE: INTEGRATED PRA SOFTWARE DEV FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 200 200 I0B Engineering Laboratory OBJECTIVE: The objective of the program is to provide computer tools for systematically performing reliability and risk studies and assessing the uncertainties in them. This will help provide a more uniform and consistent treatment of uncertainties in regulatory and reliability analyses.

133 Design the software system including development of analytical techniques, evaluate and integrate existing techniques to meet the needs identified in the PKA software plan, identify techniques and existing software, and develop software where needed. In addition this program will develop integrated software which includes capabilities to treat dependent failures and external events in a consistent manner. 144 TITLE: SYSTEM ANAL & RISK ASSESS FY 85 FY 86 FY 87 SYSTEM (SARA) BUDGET 250 250 200 CONTRACTOR: Idaho National Engineering Lab OBJECTIVE: Develop a capability for computation and analysis of information on NPP risk characteristics, using state-of-the-art, user-friendly and modularized computer software and existing NPP risk information developed under current programs. The purpose is primarily to assist the CRGR in tracking the progress that required/proposed plan modifications did/will make toward improved safety levels. In addition, the SARA system is to be designed as a flexible tool to support different levels of users requiring risk and reliability information for decisionmaking and regulatory analysis. 145 TITLE: BRA RESULTS UTILIZATION FOR FY 85 FY 86 FY 87 DSI/GSI RESOLUTION BUDGET 330 205 250 CONTRACTOR: Brookhaven National Lab OBJECTIVE: Existing probabilistic risk assessment (PRA) methods and procedures lack internal consistency, are incomplete in terms of their treatment of common cause failure (e.g., external events, human reliability) and, as a result, produce results with large uncertainties. These inadequacies have severely limited the usefulness of PRAs in guiding and supporting a broad range of Commission decisions and actions, e.g., in the areas of safety issue isolation, backfitting, implementation of safety goals and severe accident policies. The objective of this research is to develop and field evaluate/validate methods and techniques for systematically using human reliability analysis (BRA) data from PRAs and other human reliability or human factors sources, for supporting resolution of unresolved and Generic Safety Issues, and for identifying immediate and long-term human reliability and human factors research requirements consistant with NRC safety goals.

134 146 TITLE: HUMAN RELIABILITY ANAL FOR FY 85 FY 86 FY 87 RMIPP BUDGET 0 330 175 CONTRACTOR: Idaho National Engineering Laboratory OBJECTIVE: Begin with the Generic Objective, a) Identify, evaluate, and apply selected human reliability analysis inputs for probabilistic risk assessments, in support of the RMIEP program, b) Analyze selected accident sequences using more qualified human reliability analysis methods in order to predict the nature, frequency, duration and probability of significant human error contributions to the LaSalle PRA. c) Provide recommendations for future utilization of human reliability analysis methods in PRAs as an integrated element in the RMIEP program. 147 TITLE: HUMAN RELIABILITY DATA BOOK FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 0 250 200 Engineering Laboratory OBJECTIVE: Existing probabilistic risk assessment (PRA) methods and procedures lack internal consistency, are incomplete in terms of their treatment of common cause failure (e.g., external events, human reliability) and, as a result, produce results with large uncertainties. These inadequacies have severely limited the usefulness of PRAs in guiding and supporting a broad range of Commission decisions and actions, e.g., in the areas of safety issue isolation, backfitting, implementation of safety goals and severe accident policies. The objective of this research is to computerize and bring on-line a real-time human reliability data bank based on the technical specification presented in NUREG/CR-4010. This technical specification was the final milestone of an earlier NRC research program directed toward a data bank configuration capable of accepting human performance data from a wide variety of sources and collating and processing those data for use in reliability evaluations. 148 TITLE: COGNITIVE MODELING-NUC POWER FY 85 FY 86 FY 87 STATIONS BUDGET 152 250 275 CONTRACTOR: Westinghouse OBJECTIVE: Existing probabilistic risk assessment (PRA) methods and procedures lack internal consistency, are incomplete in terms of their treatment of commoncause failure (e.g., external events, human reliability) and, as a result, produce results with large uncertainties. These inadequacies have severely limited the usefulness of PRAs in guiding and supporting a broad range of Commission decisions and actions, e.g., in the areas of safety issue isolation, backfitting, implementation of safety goals and severe accident policies. The objective of this research is to develop and test improved methods and techniques for modeling the cognitive performance of selected NPP personnel, for use in reliability evaluation studies and programs, safety issue, resolution and related risk reduction initiatives of the NRC.

135 149 TITLE: REL EVAL BASE STUDY WITH EPRI FY 85 FY 86 FY 87 CONTRACTOR: Undes Laboratory BUDGET 0 50 0 OBJECTIVE: Existing probabilistic risk assessment (PRA) methods and procedures lack internal consistency, are incomplete in terms of their treatment of common cause failure (e.g., external events, human reliability) and, as a result, produce results with large uncertainties. These inadequacies have severely limited the usefulness of PRAs in guiding and supporting a broad range of Commission decisions and actions, e.g., in the areas of safety issue isolation, backfitting, implementation of safety goals and severe accident policies. The objectives of this research is to conduct a field evaluation within the context of an Italian Joint Research Center Benchmark program, of selected human reliability analytic tools and procedures recently developed by the NRC and Electric Power Research Institute (EPRI). Utilizing a case study approach, this project will allow the NRC and EPRI to acquire comparative data on selected NRC and EPRI analytic tools/procedures and tools/procedures developed by other nations participating in the program. 150 TITLE: HUMAN FACTORS NEEDS IN RES FY 85 FY 86 FY 87 CONTRACTOR: NAS BUDGET 0 131 0 OBJECTIVE: With the termination of the NRC human factors research program at the end of FY 1985, except for participation in the international Halden Project, and consideration of the changing human factors function of NRR, NRC staff (RES and NRR), ACRS (May 13, 1985 letter to Commission), and the Commission (September 13, 1985 meeting), have determined that it would be highly beneficial to obtain an independent, unbiased, nonevaluative assessment of U.S. commercial nuclear power human factors research and applications accomplishments both inside and outside the NRC since the TMI-2 accident, and to identify broad areas where additional human factors research may be needed in the future to enhance plant safety. The objective of this project is to benchmark, make broad recommendations for future research. 151 TITLE: PRA UNCERTAINTIES FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 50 700 700 Laboratory OBJECTIVE: 1. To perform an integrated uncertainty analysis (including the likelihood and consequences) of the ATWS class of accidents for the Peach Bottom plant. 2. Develop guidelines for incorporating accident likelihood uncertainties and physical process uncertainties into an overall risk uncertainty estimate, and for determining the principal contributors to this uncertainty. Perform core, containment, and consequence analyses for LaSalle being investigated in the RMIE (Risk Methods Integration and Evaluation) program using the MELCOR code system, in order to evaluate the central estimate consequences of accident sequences in that plant, the associated uncertainty, and the principal contributors to that uncertainty.

136 152 TITLE: ROOT CAUSE FAILURE ANALYSIS FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 150 185 0 Engineering Laboratory OBJECTIVE: Develop methodologies and provide demonstrations for utilization and interpretation of root causes of component failure information for plant aging, reliability assurance, inspection, and other regulatory applications. 153 TITLE: INTEGRATED RISK ANALYSIS DATA FY 85 FY 86 FY 87 ACQUISITION PROGRAM BUDGET 200 250 0 CONTRACTOR: Idaho National Engineering Lab OBJECTIVE: A uniform, comprehensive and consistent set of data on failure rates for components and plant safety systems does not presently exist. Furthermore, the absence of data on the root causes of such failures severely limits the use of PRA in supporting regulatory decisions as well as in the development and implementation of inspection and reliability assurance programs applicable to NRC licensees. The objective of this project is to integrate existing data prograns to obtain a coherent data base for use in risk assessments and collect and analyze additional data, as required. 154 TITLE: ANALYSIS OF RELIABILITY DATA FY 85 FY 86 FY 87 FROM NPPS (IPRDS) BUDGET 500 300 0 CONTRACTOR: Oak Ridge National Laboratory OBJECTIVE: Provide uniform, consistent nuclear component reliability data for use in NUREG ll50 and probabilistic risk assessments in general. Existing PRA data sources do not provide sufficient statistics for reliability and risk estimates with small uncertainties that are reasonably achievable. The lack of coordination and consistency among the various sources of data injects added uncertainty and variability in PRA results. Important data are lacking, such as fractions of root causes contributing to important component failure modes. Such data are vital to plant reliability programs and to use of PRA in the NRC inspection program. The objectives of these programs (A6831, A6393, B9445, A72225, and A1393) are to provide for identification of regulatory risk assessment data needs, identify the proper sources for various data, and to put in place the mechanisms for coordinated collection of consistent sets of data. 155 TITLE: PROCEDURE FOR EVALUATING TECH FY 85 FY 86 FY 87 SPECS (PETS) BUDGET 500 800 700 CONTRACTOR: Brookhaven National Laboratory OBJECTIVE: Develop and demonstrate methodologies to utilize reliability and risk techniques in evaluating the scope, detailed requirements, and safety impact of plant technical specifications. The procedures developed are to provide a quantitative basis for making engineering judgements in revising the specifications and in responding to licensee submittal«.

137 156 TITLE: OPERATIONAL SAFETY RELIABILITY FY 85 FY 86 FY 87 RESEARCH BUDGET 407 800 1000 CONTRACTOR: Brookhaven National Laboratory OBJECTIVE: This project is part of the planned resolution of Generic Issue II C 4, Reliability Engineering. This generic issue arises from the concern that during a plant's operating lifetime, the reliability of systems and activities important to safety might degrade from the designed-in reliability that was considered in the licensing process. This research is evaluating the effectiveness of a reliability program to prevent safety degradation during a plant's operating lifetime. 157 TITLE: INSPECTION GUIDANCE FY 85 FY 86 FY 87 CONTRACTOR: Oak Ridge National BUDGET 533 200 1330 Laboratory OBJECTIVE: This program will review & evaluate existing PRA results, methods & data with the specific objective of developing information which will assist NRR licensing project managers resident inspectors, regional t headquarters staff to prioritize specific inspection activities on the basis of risk relevance, taking into account, wherever possible, the real-time status of the nuclear power plant. 158 TITLE: TRANSPORTATION MODAL STUDY FY 85 FY 86 FY 87 CONTRACTOR: Lawrence Livermore BUDGET 260 220 0 National Laboratory OBJECTIVE: Document the basis of protection provided by spent fuel casks designed to existing regulatory standards if these casks are subjected to severe transportation accident conditions. 159 TITLE: ACCIDENT SEQUENCE EVALUATION FY 85 FY 86 FY 87 (PREV B6742) BUDGET 1670 1200 700 CONTRACTOR: Sandia National Laboratory OBJECTIVE: Provide updated LWR accident sequence information for the NRC reference plants and extend the information for all operating and near-term operating plants to support NRC/IDCOR interface on severe accident technical issues, preparation of NUREG ll50, implementation of Severe Accident Policy Statement, NRC source term reassessment, and other safety and regulatory issues. Specifically, ASEP is to: 1) develop accident sequence likelihood information and insights for the reference plants; 2) extend the reference plant accident likelihood information to other LWRS including systems modeling, accident sequence likelihood characteristics and insights on major contributors; 3) catalog the dominant accident sequence information from existing PRAs into a single reference document.

138 160 TITLE: ACCIDENT SEQUENCE EVALUATION FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 570 540 700 Engineering Laboratory OBJECTIVE: Provides updated LWR accident sequence information for the NRC reference plan and extend the information for all operating and near-term operating plants to support NRC/IDCOR interface on severe accident technical issues, preparation of NUREG ll50, implementation of Severe Accident Policy Statement, NRC source term reassessment, and other safety and regulatory issues. Specifically, ASEP is to: 1) develop accident sequence likelihood information for the reference plants; 2) extend the reference plant accident likelihood information to other LWRS including systems modeling, accident sequence likelihood characteristics, and insights of major contributors; and 3) catalog the dominant accident sequence information from existing PRAs into a single reference document. 161 TITLE: REACTOR VITAL EQUIP FY 85 FY 86 FY 87 DETERMINATION TECHNIQUES BUDGET 250 450 0 CONTRACTOR: Los Alamos National Laboratory OBJECTIVE: To provide increased assurance that the reactor vital equipment assumptions and procedures used the NRC as a technical basis for safeguards reactor licensing decisions reflect current knowledge in the area of reactor safety and sabotage vulnerability. This project will also provide guidelines for implementation of the Vital Area Committee recommendations. 162 TITLE: STAT METHODS FOR NUCLEAR MC&A FY 85 FY 86 FY 87 CONTRACTOR: Pacific Northwest BUDGET 8193 50 0 Laboratories OBJECTIVE: To provide the NRC with a reference handbook needed to update and revise the regulatory guidance and the statistical methods for nuclear material control and accounting. 163 TITLE: REGULALTORY SUPPORT FY 85 FY 86 FY 87 CONTRACTOR: Pacific Northwest BUDGET 25 1100 2200 Laboratories OBJECTIVE: Support initiatives designed to improve regulations and to ensure that NRC regulatory decisions are based on adequate information. To accomplish these goals, efforts will be undertaken to develop, document, demonstrate, and implement new tools and methods for performing regulatory analyses. In addition, efforts will be directed toward the review and evaluation on a continuing basis of the existing regulatory requirements to determine their risk effectiveness; toward review of existing regulatory guides for possible revision or withdrawal; and in general exercising centralized control of ongoing rulemaking/standards activities.

139 164 TITLE: SYSTEMS RELIABILITY SERVICE FY 85 FY 86 FY 87 STUDIES BUDGET 85 85 85 CONTRACTOR: United Kingdom AEA OBJECTIVE: The objective of this agreement is to provide for collaboration between the parties in regard to the review and evaluation of USNRC program plans, methods, guidelines and standards relating to system analysis, risk assessment methodology and reliability data development. The UKAEA/SRS performs specific review and assessment tasks for the SIMRC relating to various topics including; probability and statistics for reliability analysis, accident sequence analysis, systems reliability analysis, reliability engineering and reliability assurance, and numberical risk criteria development. 165 TITLE: PROTECTIVE ACTION DECISIOMAKING FY 85 FY 86 FY 87 CONTRACTOR: Brookhaven National BUDGET 250 350 100 Laboratorty OBJECTIVE: To develop a revised protective action strategy for accidents at nuclear power plants based on results of new source term research. 166 TITLE: EVALUATION OF PROT ACTION RISKS FY 85 FY 86 FY 87 CONTRACTOR: Pennst BUDGET 120 50 200 OBJECTIVE: The purpose of this contract is, under radiological accident conditions, to determine how the non-radiological risks of evacuation compare with the radiological risks if no protective actions are taken. 167 TITLE: STATISTICAL TECHNIQUES FOR FY 85 FY 86 FY 87 RISK ANAL BUDGET 440 250 300 CONTRACTOR: Los Alamos National Laboratory OBJECTIVE: This program will provide a data base and improved methods for estimating component failure characteristics and consequently reducing the uncertainty in core melt frequency estimates. This program will also develop a data base for the Accident Sequence Evaluation Program, develop methods for quantifying common cause failures and continue direct support to RMIEP in the development of improved methods for PRA. 168 TITLE: ACCIDENT SEQUENCE PRECURSORS FY 85 FY 86 FY 87 (PREV B6745) BUDGET 435 325 0 CONTRACTOR: Oak Ridge National Laboratory OBJECTIVE: Produce and validate a method to aid in systematically evaluating the significance of NPP operational experience LER data by estimating the likelihood of severe core damage, and show which precursor incidents or accidents contribute the most to this frequency estimate.

140 169 TITLE: CONSEQUENCE MODELING-NUC REAC FY 85 ft 86 FY 87 ACCIDENTS BUDGET 300 650 650 CONTRACTOR: Sandia National Laboratory OBJECTIVE: The objective of this work is to update the accident consequence models originally developed for the Reactor Safety Study in 1973, to account for new environmental transport, radiation dosimetry, health effect and economic models and data bases developed during the past decade, or more. Further, the code structure is being designed for ease of the user and to be readily amenable for uncertainty analyses. The latter is a major objective of the MELCOR program, which this FIN supports, in part. 170 TITLE: MELCORE FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 1250 1450 500 Laboratory OBJECTIVE: NRC is faced in the near term with determining how considerations of severe reactor accidents should be incorporated into the regulatory process and, further, on determining how the results of source term research should influence current regulatory requirements. Specific conversion decisions will be required in the areas of emergency planning, siting, and the implementation of a quantitative safety goal. The objective of this project is to develop, verify, and maintain a second generation accident simulation code for use in uncertainty analysis for probabilistic risk analysis. 171 TITLE: SEV. ACCIDENT RISK REBASELING FY 85 FY 86 FY 87 AND REDUCTION PROGRAM (SARRP) BUDGET 800 900 0 CONTRACTOR: Sandia National Laboratory OBJECTIVE: Provide risk profiles with associated uncertainties and assessments of the costs and risk reduction effectiveness of methods to prevent or mitigate the consequences of severe reactor accidents in six reference plants representing different containment types. 172 TITLE: 2ION REBASELING FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 0 250 0 Laboratory OBJECTIVE: The objective is to provide a risk profile and an assessment of the values and impacts of the various prevention and mitigation features, for use in the staff report, NUREG-ll50. Sandia National Laboratories (SNL) is performing the evaluation for five plants, and Zion, the sixth plant, will be done by BNL. SNL, however, will provide the "frontend" evaluation (the list of sequences) and containment event tree to BNL. Battelle Columbus Laboratories (BCD will provide the source term calculations using the Source Term Code Package (STCP).

141 173 TITLE: ANALYSIS OF VENTING OPTION FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 387 450 0 Engineering Laboratory OBJECTIVE: Perform a systematic evaluation of venting a BWR, Mark I Containment, as a means of mitigating consequences of loss of containment so as to identify operator actions, procedures, or hardware which individually or collectively reduce risk. 174 TITLE: RISK METHODOLOGY-OTHER MEDIA FY 85 FY 86 FY 87 CONTRACTOR: Sandia National BUDGET 490 425 425 Laboratory OBJECTIVE: The risk methodology developed for NRC's quantitative assessment of isolation of HLW in bedded salt (under FIN A1192) needs to be extended to assist analysis of HLW isolation in basalt, tuff, domed salt, and granite. The objective of this project is to modify the risk methodology developed for the assessment of isolation of HLW bedded salt (under FIN All92) so that the methodology will be applicable to analyzing HLW isolation in basalt, tuff, domed salt, and granite. 175 TITLE: COMPUTER CALCULATIONS IN SUPPORT FY 85 FY 86 FY 87 OF THE BYDROCOIN STUDY BUDGET 75 100 100 CONTRACTOR: Sandia National Laboratory OBJECTIVE: To provide technical support for NRC participation in HYDROCOIN (an international cooperative investigation) will provide an international cross comparison of predictive models and codes which will provide insight into the appropriate use of such codes for NRC licensing evaluations. This research will enhance the confidence in the applicability of hydrologic programs for safety related calculations associated with geologic disposal of HLW and increase the NRC's awareness of the strength and limitations of various programs and modeling strategies that can or will be used to evaluate HLW geologic repository performance. 176 TITLE: PITTING CORROSION FY 85 FY 86 FY 87 CONTRACTOR: Brookhaven National BUDGET 150 150 200 Laboratory OBJECTIVE: To determine the degree of confidence in extrapolation of short-term laboratory tests of pitting corrosion rates to predictions over long times.

142 177 TITLE: VALENCE EFFECTS ON ADSORPTION FY 85 FY 86 FY 87 CONTRACTOR: Oak Ridge National BUDGET 150 150 150 Laboratory OBJECTIVE: Several of the most hazardous radionuclides in high-level waste can exist in multiple valence (a.k.a. oxidation) states. The valence state of the nuclide* in ground-water, and hence controls the mobility and sorption of the nuclide in a repository setting. The factors which control the valence state of nuclides in the earth are not well understood. This project has three primary objectives: 1) to identify and understand the factors which control radionuclide valence states under repository conditions; 2) to measure the solubility, speciation, and sorption properties of individual valence states of technetium (Tc), neptunium (Np), and uranium (U) under projected repository conditions; and 3) to assess laboratory methods of valence state control needed to replicate repository conditions in the laboratory. These data are needed to model the migration of radionuclides released from a repository, and to independently assess DOE calculations. 178 TITLE: SITE GEOCHEMISTRYN ADSORPTION FY 85 FY 86 FY 87 CONTRACTOR: Lawrence Berkeley BUDGET 687 500 600 Laboratory OBJECTIVE: This research will identify and gauge the relative importance of individaul hydrochemical processes controlling radionuclide behavior within and close to a geologic repository and form a basis for evaluating the chemical evolution of groundwater and transport of radionuclides. 179 TITLE: COUPLED INTERACTIONS- GEOTHERMAL FY 85 FY 86 FY 87 & HYDROTHERMAL SYSTEMS BUDGET 368 200 225 CONTRACTOR: Lawrence Berkeley Lab OBJECTIVE: The objective of this project is to identify, describe, and quantify coupled interactions which may be important to high-level waste isolation, by analogy with similar natural systems. Emplacement of high-level waste in a geologic repository will induce thermal, hydrologic, mechanical, and chemical changes in the geologic environment. Many such changes are coupled, i.e., the combined effects of the changes are different from the sum of the separate parts. Such coupled interactions are difficult to study in the laboratory because the geologic environment is very complex; because the effects often are very large-scale and cannot be scaled down to laboratory size; and because some effects operate over very long time periods. Natural analogues of high-level waste repositories, such as geothermal systems and hydrothermal ore deposits, can be used to observe the response of the geologic environment to coupled thermal, hydrologic, mechanical, and chemical changes at the scales of interest for repository licensing.

143 180 TITLE: LONG-TERM PERF OF HLW PACKAGING FY 85 FY 86 FY 87 MATLS BUDGET 1000 500 500 CONTRACTOR: Battelle Columbus Laboratories OBJECTIVE: NRC must assess the validity of DOE's demonstration that waste packages will meet the containment and controlled release requirements of 10 CFR Part 60. This project will identify the conditions and mechanisms of HLW package failure to be expected under repository conditions. The results will be used to support its claims of compliance with Part 60 requirements. This research will reduce the uncertainties associated with long term predictions of waste package corrosion rates and waste form dissolution under respository conditions. 181 TITLE: CONTAINER MANUFACTURING PARAMETERS FY 85 FY 86 FY 87 CONTRACTOR: Manufacturing BUDGET 90 100 0 Sciences Corp. OBJECTIVE: To assess the effect of manufacturing techniques and variabilities in these techniques on overpack performance. 182 TITLE: UNSAT FLOW t TRANS THRU FACT ROCK FY 85 FY 86 FY 87 PHASE II BUDGET 220 0 200 CONTRACTOR: University of Arizona OBJECTIVE: Assessment of techniques for modeling and data gathering and for describing unsaturated flow and transport in fractured rock. This study will provide the NRC licensing staff with an understanding and technical information for evaluating DOE's site characterization plans and studies on long-term predication of water (liquid/vapor movement) and contaminant transport through unsaturated fractured rock formations. The study will help to provide the NRC with a technical basis for developing regulations and licensing review procedures for assessing DOE submittals for HLW geologic repositories situated in the unsaturated zone. This research will reduce the uncertainties associated with estimation of parameters, such as recharge rate, used to model ground-water flow and transport in unsaturated fractured rock. 183 TITLE: THERMAL EFFECTS ON REPOSITORY ROCKS FY 85 FY 86 FY 87 CONTRACTOR: University of Delaware BUDGET 100 100 100 OBJECTIVE: The objective of this project is to use scale model laboratory tests to evaluate current conceptual and mathematical models of heat transfer from individual HLW packages and from the aggregate of emplaced HLW which can not be tested over long times. 184 TITLE: PITTING STATISTICS FY 85 FY 86 FY 87 CONTRACTOR: National Bureau of BUDGET 210 150 200 Standards OBJECTIVE: To assess the ranges of repository environmental condition that control initiation and rates of pitting corrosion in overpack materials.

144 185 TITLE: GROUNDWATER & TRANSPORT OF FY 85 FY 86 FY 87 CONTAMINANTS BUDGET 227 155 425 CONTRACTOR: ISI OBJECTIVE: The objective of this project is to provide NRC with an independent technical base to judge whether DOE'S models and measurement methods for describing the hydrology of a repository site in low permeability saturated fractured rock are appropriate to such media. 186 TITLE: PROP OF DECON WASTES FY 85 FY 86 FY 87 CONTRACTOR: Brookhaven National BUDGET 100 150 150 Laboratory OBJECTIVE: To determine the leaching characteristics of solidified decontamination waste in expected disposal environments. 187 TITLE: LLW SOURCE TERM FY 85 FY 86 FY 87 CONTRACTOR: Brookhaven National BUDGET 200 400 500 Laboratory OBJECTIVE: In order to assess compliance with Part 61 requirements for modeling performance of LLW disposal the NRC needs a comprehensive set of "source terms". This research will develop a set of "source terms" related to the amount of radionuclides in waste packages and the rate at which they are released from the packages and enter the soils at the disposal site. These will be used for radionuclide transport modeling of LLW disposal sites during licensing reviews. This research will reduce the uncertainties associated with the chemical form and quantity of radionuclides released from shallow land burial facilities, such as C-14, Co-60, and Cs-137. 188 TITLE: CHAR OF LL RAD DECON WASTE FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET 100 100 100 Engineering Laboratory OBJECTIVE: The characteristics of LLW waste from the decontamination of reactor systems must be known in order to establish site performance by modeling the migration of radionuclides for LLW disposal sites. This project will provide reachability data by studying actual wastes from LWR decontamination. The results will be used in establishing the LLW source term for decontamination wastes for use in NRC licensing evaluations. This research will reduce the uncertainties in calculations of the species, quantities, and mobilities of radionuclides from decontamination wastes, such as Ni-63 and Co-60, important to safety of LLW disposal. 189 TITLE: SFTY ASSESSMENT OF ALT TO FY 85 FY 86 FY 87 SHALLOW LAND BURIAL BUDGET 130 150 0 CONTRACTOR: Idaho National Engineering Lab OBJECTIVE: This project will help identify safety issues for engineered enhancements or alternatives to shallow land burial for disposal of low level waste.

145 19» TITLE: CHEMICAL SPECIES OF MIGRATING FY 85 FY 86 FY 87 RADIONUCLIDES BUDGET 150 100 0 CONTRACTOR: Pacific Northwest Laboratories OBJECTIVE: 10 CFR Part 61 requires a performance assessment of LLW disposal. This research is a beginning assessment of the effectiveness and practicability of existing models, codes, and data gathering techniques which may be used in predicting LLW site performance. 191 TITLE: SOIL-BIOTICH-HYDRO PROCESSESG FY 85 FY 86 FY 87 CONTRACTOR: Pacific Northwest Lab BUDGET 95 100 0 OBJECTIVE: Chemicals from plant roots have been observed to affect the mobility of radionuclides in soils. This work will produce an integrated understanding of soil-plant-hydrologic processes governing the mobility and biological availability of radionuclides from LLW disposal facilities. 192 TITLE: LLW/SLB MODEL FIELD VALIDATION FY 85 FY 86 FY 87 CONTRACTOR: Pacific Northwest Lab BUDGET 92 172 400 OBJECTIVE: Geostatistical methods for describing hydrologic processes and parameters in unsaturated heterogeneous soils have not been field validated. This research will test the validity and applicability of such techniques to HLH and LLW disposal performance assessments. The results will assist the licensing staff to identify and quantify the uncertainties using statistical methods for the prediction of radionuclide transport form HLW repositories and LLW disposal facilities. Uncertainties associated with spatial variability in moisture content, hydraulic conductivity, and dispersivity will be quantified. 193 TITLE: STOCHASTIC HYDROGEOLOGIC FY 85 FY 86 FY 87 ANALYSIS BUDGET 120 50 0 CONTRACTOR: Mass Institute of Technology OBJECTIVE: Before the techniques of stochastic hydrology can be used in reviewing license applications for LLW disposal, the applicability of these techniques for this purpose needs to be assessed. This research will provide a theoretical base for evaluating LLW site characterization plans using statistical methods of predicting ground-water flow and solute transport in unsaturated heterogenous earth materials. This research will reduce the present level of uncertainty in modeling movement of radionuclides in heterogeneous unconsolidated soils. 194 TITLE: ASSESSMENT OF CLOSURE METHODS FY 85 FY 86 FY 87 CONTRACTOR: UCA-Lab Bio Envir BUDGET 175 175 200 Science OBJECTIVE: Experience with shallow land burial of LLW at sites in humid areas indicates that water infiltration through trench caps is a problem. This research will assess the effectiveness of a number of methods under consideration by the States and industry to control water entry through LLW site covers in humid areas.

146 195 TITLE: INSTRUMENTATION FOR KENTUCKY FY 85 FY 86 FY 87 NETWORK BUDGET 20 7 0 CONTRACTOR: Univ. Of Kentucky OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is part of a program to obtain such data. This project is providing basic seismological data recorded on Kentucky. This data includes earthquake locations, magnitudes, source parameter, phase arrival time,etc. 196 TITLE: GILES COUNTY SEISMIC PROFILING FY 85 FY 86 FY 87 CONTRACTOR: Virginia Polytech BUDGET 25 25 8 Institute OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is part of a program to obtain such data. This project is providing basic seismological reflection data generated near the Giles County Seismic Zone. Both P-wave and S-wave reflection profiles are being acquired to define subsurvace structure. The data also include earthquake locations, magnitudes, source parameter, phase arrival time, etc. A comparison of the two sets of data is expected to provide insights into the causes of the seismicity in Giles County. 197 TITLE: DOWNHOLE STRONG MOTION STUDIES FY 85 FY 86 FY 87 CONTRACTOR: University of BUDGET 78 103 75 California OBJECTIVE: There is presently no acceptable method for determining the attenuation of seismic shear and body waves in soil. This experiment is designed to measure this attenuation by the use of down-hole seismometers and surface seismometers in a seismically active area of California. 198 TITLE: GEO & SEISMO SITING STUDIES FY 85 FY 86 FY 87 CONTRACTOR: U.S. Geological BUDGET 298 1000 870 Survey OBJECTIVE: The objective of this work is to provide NRR with the data and analytical techniques necessary to maintain an independent technical basis for the review of applications. A. Lack of basic seismological data from any other source for the Charleston region. B. The interpretation of high acceleration ground motion at short distances. C. The interpretation of the propagation of strong ground motion with distance. D. The implications of the numerous theories on the cause of eastern earthquakes.

147 199 TITLE: SOUTHERN NEW MADRID NETWORK FY 85 FY 86 FY 87 CONTRACTOR: Memphis State BUDGET 100 93 120 Unversity OBJECTIVE: The tectonic cause of seisraicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is part of a program to obtain such data. This project is providing basic seismological data recorded near the southern end of the New Madrid Seismic Zone. This data includes earthquake locations, magnitudes, sources parameter, phase arrival time, etc. 200 TITLE: SOIL SETTLEMENT FY 85 FY 86 FY 87 CONTRACTOR: Corp of Engineers/ BUDGET 0 100 250 Waterways Experimental Station OBJECTIVE: The latest position of the United States Geological Survey (USGS) on the 1886 Charleston earthquake could result in the postulation of ground motions higher than the Safe Shutdown Earthquake (SSE) at many nuclear power plant sites in the Eastern United States. Since many of these plants are founded on soil, the stability of nuclear power plant structures, systems and components subject to possible foundation soil liquefaction and dynamic settlement becomes a matter of concern. The objective of this research is the validation of dynamic analyses models capable of predicting settlements resulting from soil liquefaction. 201 TITLE: NEW MADRID RESEARCH PROGRAM FY 85 FY 86 FY 87 CONTRACTOR: St. Louis University BUDGET ll3 120 120 OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is part of a program to obtain such data. This project is providing basic seismological data recorded near the southern end of the New Madrid Seismic Zone. This data includes earthquake locations, magnitudes, source parameter, phase arrival time, etc. 292 TITLE: OHIO/INDIANA SEISMIC NETWORK FY 85 FY 86 FY 87 CONTRACTOR: Univ. of Michigan BUDGET ll3 120 120 OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is part of a program to obtain such data. This project is providing basic seismological data recorded in Ohio and Indiana. This data includes earthquake locations, magnitudes, source parameter, phase arrival time, etc.

148 203 TITLE: NEOTECTONIC INVESTIGATIONS FY 85 FY 86 FY 87 CONTRACTOR: Univ. of South BUDGET 108 100 100 Carolina OBJECTIVE: The tectonic cause of seismieity in the Southeastern United States is not well understood. The seismic history there includes the large 1886 Charleston earthquake. The combination of that event and the unknown tectonics results in a high uncertainty in seismic hazard assessments. Under this project, and evaluation of several hypotheses on the cause of seisraicity in the Southeastern uncertainty in seismic hazard assessment of NPP's. 204 TITLE: CHARLESTON EARTHQUAKE PROJ FY 85 FY 86 FY 87 CONTRACTOR: Law Engineering BUDGET 317 250 200 OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is part of a program to obtain such data. This project is providing geophysical and geological data from the vicinity of Charleston, South Carolina, which will better define the possible mechanism and structures associated with the Charleston earthquake. The geophysical data, including seismic reflection profiles, will define the subsurface at the depths of earthquake hypocenters. The results of this work will narrow down the range of theories that can explain the Charleston earthquake and serve to better define the seismicity of the eastern seaboard. 205 TITLE: IN SITU STRESS MEASUREMENTS FY 85 FY 86 FY 87 CONTRACTOR: Engrs. International BUDGET 128 150 0 OBJECTIVE: The cause of seismicity in the Northeastern United States is not well understood. The objectives of this project are to determine the in situ stresses and the direction of the faulting occurring in the seismic zones. The seismic networks in the New England States, the Southeastern States, the New Madrid area and the Namaha Ridge area have identified active seismic zones; however, they have not fully identified the direction of faulting. This information is needed for testing hypotheses on the causes of seismicity. Better understanding of the causes of seismicity will result in reduced uncertainty in the relationship between seismic hazards, seismicity and active geologic structures.

149 296 TITLE: EQUAKE RESISTANT DESIGN CRITERIA FY 85 FY 86 FY 87 CONTRACTOR: Struct & Ertbqk Engr Con BUDGET 150 48 150 OBJECTIVE: There is paucity of recorded strong ground motion data for the Eastern United States. Currently, records from other geographic areas must be used. If records were available, it would be possible to significantly reduce the uncertainty associated with defining the design response spectrum. The objective of this research is to develop analytical techniques that could be used to generate useable design response spectra for nuclear power plant sites for which a comprehensive suite of strong motion records are not available. The results will be used by NRR in the review of plant license applications and amendments. 2B7 TITLE: TECH BASIS SEISMIC STANDARDS FY 85 FY 86 FY 87 CONTRACTOR: Request for Proposal BUDGET 0 50 100 OBJECTIVE: Objective is to provide prompt basic earth science information for use in NRC investigations prompted by current significant seismic events or geologic discoveries; e.g., the January 9, 1982, New Brunswick earthquake and its aftershocks, and the recently identified Meers fault in Oklahoma. 208 TITLE: CANADIAN SEISMIC COOP AGREEMENT FY 85 FY 86 FY 87 CONTRACTOR: Canadian Comm Corp. BUDGET 305 165 165 OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is part of a program to obtain such data. This project is providing basic seismological data recorded in the vicinity of the US/Canada border. This data includes earthquake locations, magnitudes, source parameter, phase arrival time. 289 TITLE: NE US SEISMOGRAPHIC NETWORKS FY 85 FY 86 FY 87 CONTRACTOR: Columbia University BUDGET 250 330 270 OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is part of a program to obtain such data. This project is providing basic seismological data recorded in New York State. This data includes earthquake locations, magnitudes, source parameter, phase arrival time, etc.

150 210 TITLE: REMOTE SENSING OBS OF NE FY 85 FY 86 FY 87 NEOTECTONICS BUDGET 173 120 100 CONTRACTOR: PENNST OBJECTIVE: The tectonic cause of seismicity in the Northeastern United States is not well understood because this is a structurally complex region where geologic structures are obscured by vegetation, where there are few deep boreholes to give subsurface information, and where damaging earthquakes occur at infrequent intervals. Therefore, there is great uncertainty in estimating seismic hazards for the region. This project will test hypotheses on the causes of seismicity in areas within the Northeastern U.S. where there is localized seismic activity. This will be done through the use of remote sensing coupled with ground investigations to assess the cause of seismicity. Better understanding of the cause of seismicity will reduce uncertainty in the relationship between seismic hazard and seismically active geologic structures. 2ll TITLE: BROAD-BAND INSTRUMENTATION FY 85 FY 86 FY 87 CONTRACTOR: RONDOUT, Associates BUDGET 51 0 50 OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is providing wide dynamic-range, broad-band data on seismic events in the Northeast and on the propagation characteristic there. This data include earthquake locations, mangitudes, source parameters, phase arrival times, etc. 212 TITLE: PIEDMONT SEISMIC REFLECTION FY 85 FY 86 FY 87 CONTRACTOR: Virginia Polytech BUDGET 230 250 200 Institute OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is part of a program to obtain such data. This project is providing seismic reflection data generated in the Southeast. Data may include magnetic and gravity maps and other geological and geophysical data providing information on crustal structure at the depths of earthquake hypocenters. 213 TITLE: REGIONAL SEISMOGRAPHIC FY 85 FY 86 FY 87 NETWORK BUDGET 120 160 130 CONTRACTOR: Memphis State University OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project seismological data recorded in Tennessee and North Carolina. This data includes earthquake locations, magnitudes, source parameter, phase arrival time, etc.

151 214 TITLE: VA-REGIONAL SEISMOGRAPHIC FY 85 FY 86 FY 87 NETWORK BUDGET 160 200 150 CONTRACTOR: Virginia Polytech Institute OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the HRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is part of a program to obtain such data. This project is providing basic seismological data recorded in Tennessee and West Virginia. This data includes earthquake locations, magnitudes, source parameter, phase arrival time, etc. 215 TITLE: GA-AL-REGIONAL SEISHOGRAPHIC FY 85 FY 86 FY 87 NETWORK BUDGET l00 l20 100 CONTRACTOR: Georgia Institute of Tech OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is part of a program to obtain such data. This project is providing basic seismological data recorded in Georgia and Alabama. This data includes earthquake locations, magnitudes, source parameter, phase arrival time, etc. 216 TITLE: NEW ENGLAND SEISMOGRAPHIC FY 85 FY 86 FY 87 NETWORK BUDGET 309 300 270 CONTRACTOR: Boston College OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is pact of a program to obtain such data. This project is providing basic seismological data recorded in New England. This data includes earthquake locations, magnitudes, source parameter, phase arrival time, etc. 217 TITLE: MASS./NEW HAMPSHIRE FY 85 Ft 86 FY 87 SEISMOGRAPHIC NETWORK BUDGET 135 120 130 CONTRACTOR: Mass Institute of Technology OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is part of a program to obtain such data. This project is providing basic seismological data recorded in Massachusetts and New Hampshire. This data includes earthquake locations, magnitudes, source parameter, phase arrival time, etc.

152 218 TITLE: PENNSYLVANIA FY 85 FY 86 FY 87 SEISMOGRAPHIC NETWORK BUDGET ll0 95 110 CONTRACTOR: PENNST OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is part of a program to obtain such data. This project is providing basic seismological data recorded in Pennsylvania and Maryland. This data includes earthquake locations, magnitudes, source parameter, phase arrival time, etc. 219 TITLE: LONG ISLAND SEISMIC ARRAY FY 85 FY 86 FY 87 CONTRACTOR: SUNY BUDGET 81 45 50 OBJECTIVE: The tectonic cause of seismicity in the Eastern United States is not well understood. Additional data is needed to assist the NRC in conducting regulatory reviews and establishing appropriate regulations and policies. This project is part of a program to obtain such data. This project is providing basic seismological data recorded on Long Island. This data includes earthquake locations, magnitudes, source parameter, phase arrival time, etc. 220 TITLE: COMMITTEE ON SEISMOLOGY FY 85 FY 86 FY 87 CONTRACTOR: NAS BUDGET 20 20 20 OBJECTIVE: The Committee on Seismology is a standing committee of the National Academy of Science composed of leading seismologists from industry, academia and government. The results of their efforts are advise the federal government in the area of seismology. The results of this work of the committee will be used to help determine if the NRC policies, guidance and research programs concerning seismic hazard are properly directed. This is a grant to the National Academy of Sciences to partially offset the cost of gathering these expert panels together and for the publication of their findings in special reports. 221 TITLE: WORKSHOP ON STRONG GROUND MOTION FY 85 FY 86 FY 87 CONTRACTOR: Earthquake Engr BUDGET 0 20 0 Research Institute OBJECTIVE: There are gaps in the understanding of the generation and propagation of strong ground motion resulting from seismic events in the Eastern U.S. The Earthquake Engineering Research Institute (EERI) is sponsoring the Third National Conference on Earthquake Engineering to bring together earthquake engineers and scientists to exchange ideas and theories. This conference will include a workshop that is intended to help reduce the uncertainty in seismic hazard assessment that results from these gaps. This workshop will help to reduce the uncertainties in the NRC's independent evaluations of licensee submittals.

153 222 TITLE: CRUSTAL SUBSIDENCE MAINE FY 85 FY 86 FY 87 CONTRACTOR: Main Geological BUDGET 75 75 0 Survey OBJECTIVE: The cause of seismicity in Eastern United States is not well understood. Along coastal Maine there is an area that for the last 500-1000 years has been experiencing very rapid crustal subsidence. That is associated with seismicity. This investigation is directed at determining the cause of the subsidence and the seismicity associated with it. Better understanding of the cause of the seismicity will help reduce uncertainty in seismic hazard assessment for NPP's located in the Eastern U.S. 223 TITLE: GEOLOGICAL SCIENCES BOARD FY 85 FY 86 FY 87 CONTRACTOR: NAS BUDGET 10 10 10 OBJECTIVE: The Geological Sciences Board is a standing Board of the National Academy of Sciences composed of leading geoscientists from industry, academia, and government. The purpose of their efforts is to advise the Federal government in the area of the geological sciences. The results of the board will be used to help determine if the NRC policies, guidance, and research programs concerning geological hazards are properly directed. This grant to the National Academy of Sciences is to partially offset the cost of gathering these expert panels together and of publishing their findings in special reports. 224 TITLE: ACUTE MORBIDITY & MORTALITY FY 85 FY 86 FY 87 IN ANIMALS BUDGET 260 250 0 CONTRACTOR; Inhalation Toxicology OBJECTIVE: To develop information that will improve the estimates of potential early health effects of postulated accidents and sabotage in nuclear power plants, fuel cycle facilities, and transportation. The specific objective is to provide experimental data necessary to verify the early mortality model and to develop models for morbidity and mortality expected to occur within 18 months after exposure to radionuclides. 225 TITLE: METABOLIC STUDIES OF INHALED FY 85 FY 86 FY 87 YELLOHCAKE IN ANIMALS BUDGET 140 100 200 CONTRACTOR; Inhalation Toxicology OBJECTIVE: The results will be used to determine lung deposition and organ transfer factors, and to examine kidney toxicity of yellowcake inhalation.

154 226 TITLE: METABOLISM STUDY OF THORIUM WORKERS FY 85 FY 86 FY 87 CONTRACTOR; Argonne National BUDGET 150 130 200 Laboratory OBJECTIVE: The objective of this research is to enhance the human data base on the behavior and health effects of thorium and other alpha emiting radionuclides. 227 TITLE: GASTROINTESTINAL ABSORPTION OF PU FY 85 FY 86 FY 87 AND ACTINIDES BUDGET 91 105 250 CONTRACTOR: Argonne National Laboratory OBJECTIVE: The current objectives are (1) to determine the gastrointestinal absorption of actinides in a nonhuman primate species, the baboon, to provide a more reliable basis for the extrapolation of GI absorption data in experimental animals to humans, and (2) to determine the steady-state amount of uranium in human bone for a population of persons with prolonged ( 25 y) and known daily intakes of uranium in drinking water. 228 TITLE: QUALITY FACTORS OF LOW DOSE NEUTRONS FY 85 FY 86 FY 87 CONTRACTOR: Argonne National BUDGET 0 259 0 Laboratory OBJECTIVE: To determine the relative biological effectiveness of fission neutrons at occupational exposure levels. 229 TITLE: LUNG CANCER IN WOMEN - RADON FY 85 FY 86 FY 87 CONTRACTOR: Argonne National BUDGET 0 16 0 Laboratory OBJECTIVE: Determine whether the Lung Cancer risk observed in exposed women is, after adjustment for smoking habits of the study population, consistent with lung cancer risks observed in radon exposed miner populations. Present risk estimates for radon are based entirely on miner populations. Thus, the results of this study are valuable in assessing the generality of these estimates. 230 TTTLE: REFERENCE MAN-UPDATE FY 85 FY 86 FY 87 CONTRACTOR: Oak Ridge National BUDGET 25 30 50 Laboratory OBJECTIVE: This research will update anatomical and physiological information for adult males and extend the data base to adult females and children of both sexes.

155 231 TITLE: EARLY EFFECTS OF INHALED FY 85 FY 86 FY 87 EADIONUCLIDES IN ANIMALS BUDGET 280 200 0 CONTRACTOR: Pacific Northwest Laboratories OBJECTIVE: To develop information that will improve the estimates of potential early health effects of postulated accidents and sabotage in nuclear power plants, fuel cycle facilities and transportation. The specific objective is to provide experimental data necessary to verify the early mortality model and to develop models for morbidity and •ortality expected to occur within 18 months after exposure to radionuclides. 232 TITLE: METABOLISM OF SR PU AND AM IN FY 85 FY 86 FY 87 MONKEYS BUDGET 130 140 0 CONTRACTOR: Lawrence Berkeley Lab OBJECTIVE: The results will be used to determine organ uptake and retention factors following injection of strontium, plutonium, and aaericium. 233 TITLE: SUPPORT FOR NAS COMMITTEE BEIR IV FY 85 FY 86 FY 87 CONTRACTOR: Environmental BUDGET 130 150 200 Protection Agency OBJECTIVE: To develop state-of-the-art methods for quantitative assessment of risk to humans from internally deposited alpha-emitting radionuclides and their decay products (IDAER). 234 TITLE: RADIATION PROTECTION/MEASUREMENT STUDY FY 85 FY 86 FY 87 CONTRACTOR: National Council BUDGET 75 200 0 Rad. Prot. R Meas. OBJECTIVE: NCRP is an organization of scientists and physicians expert in radiation related sciences and medicine, which by Congressional Charter provides the nation advice on radiation protection. The results of their efforts are published and serve as a base for Federal, State, and local agencies to develop sound protection practices, including the use of radiation in the healing arts. 235 TITLE: DEVELOP RAD PROT. STANDARDS FY 85 FY 86 FY 87 CONTRACTOR: Int'1 Comm. BUDGET 10 18 25 Radiation Protection. OBJECTIVE: ICRP is an international organization of scientists expert in radiation physics, biology, and medicine that provides recommendations on radiation protection practices. All international standards are based on these recommendations.

156 236 TITLE: SURVEILLANCE; IND/DOE RES & FY 85 FY 86 FY 87 NPP ALARA PGMS BUDGET 120 245 0 CONTRACTOR: Brookhaven National Laboratory OBJECTIVE: Objective is to establish affective surveillance of industry R & D projects on dose reduction aid ALARA engineering by developing work relationship's with national & international government & industry groups, maintaining comprehensive data base on information obtained, analyze projects for effectiveness and developing methods fojr informing government and industry management of important new dose reduction efforts. 237 TITLE: INTERNAL DOSE CALCULATIONS FY 85 FY 86 FY 87 ASSISTANCE BUDGET 15 20 8 CONTRACTOR: Oak Ridge National Lab. OBJECTIVE: The problem is that frequent requests are made of NRC staff to provide approved methods of estimating intakes and internal doses from bioassay data. The goal of this project is to provide NRC staff access to state-of-the-art techniques for calculating worker internal dose, body burdens, and excretion rates. Oak Ridge National Lab (ORNL) monitors major research and development projects being performed by DOE, NIH, and others, and extracts important findings for inclusion into the highly advanced ORNL data banks and computer programs. This technical support is then available to ORPB/RES staff to assit them in reviewing regulatory requirements, such as the proposed Part 20 revisions, in developing licensee guidance on bioassay and respiratory protection, and in providing up-to-date technical information to other NRC offices, other governmental agencies, licensees and groups such as INFO, EPRI, and EEI. 238 TITLE: RAD EXP INFO RPT SYS FY 85 FY 86 FY 87 CONTRACTOR: Oak Ridge National BUDGET 202 205 208 Lab. OBJECTIVE: To provide computer, programming and processing support for the operation of REIRS.

157 239 TITLE: TESTING EXTREMITY DOSIMETRY STANDARDS FY 85 FY 86 FY 87 CONTRACTOR: Pacific Northwest BUDGET 0 100 0 Laboratories OBJECTIVE: NRC inspectors regularly observe inadequate dosimetry for monitoring the heads and extremities of workers who perform tasks in non-uniform radiation fields. In order to improve this situation the NRC staff plans to recommend that licensees be required to use only extremity dosimeters and processors that have passed performance tests as defined in an ANSI standard being developed by the Health Physics Society. The contractor is to determine if the draft standard (P/N13.32, 'Standard for the Performance Testing of Extremity Dosimeter*) is appropriate for testing the performance of extremity dosimeter processors, or to make recommendations to the HPS regarding changes necessary to ensure that the standard is neither too straight nor too lenient.