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Nuclear Power in an Age of Uncertainty

Description: An assessment by the Office of Technology Assessment (OTA) that examines "the future of nuclear power in this country, and how the technology and institutions might be changed to reduce the problems now besetting the nuclear option" (p. iii).
Date: February 1984
Creator: United States. Congress. Office of Technology Assessment.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ABWR: PL-2 Design Report

Description: From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
Date: October 15, 1960
Creator: Combustion Engineering, inc. Nuclear Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactivity Lifetime. Section I. Third Performance. 2797-3797 EFPH. Core I Seed I.

Description: The PWR Plant was operated at approximately 60 MW net electrical output for a total of 1000 EFPH from February 3, 1959 to March 28, 1959. During this period, while performing DL-S-225, there were two planned shutdowns, no safety shutdowns or safety insertions and one flux title. The performance of the plant was satisfactory during the period of the test.
Date: November 23, 1959
Creator: Lawrence, Roger J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey. Section I. EFPH-4182. First Performance. Core I, Seed 1. Test Results DL-S-231 (T-612394)

Description: The purpose of the survey was to determine the radiation levels in the 1 D Boiler Chamber during plant operation. The conclusion of this survey is that the radiation level in the 1 D Boiler Compartment with the 1A, 1B, and 1C Main Coolant loops in service at approximately 100 per cent power ranged from .03 MR/HR to 6.0 MR/HR.
Date: November 3, 1959
Creator: Ritz, William C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey. Section II. 4182-EFPH. Second Performance. Core I, Seed 1. Test Results DL-S-231 (T-612394)

Description: The purpose of the survey was to determine the radiation level in the Turbine Generator Services Building, around the Fuel Handling Canal, in the limited access areas of the reactor plant containers and on the boiler container roofs during plant operation. The test was performed with the plant at approximately 100 per cent power with three loops (1A, 1B, and 1C) in service. The radiation levels of the areas surveyed with a few exceptions were essentially background (.03 MR/HR). These exceptions… more
Date: November 10, 1959
Creator: Ritz, William C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Periodic Intercalibration of Temperature Sensing Elements. Section I. First Performance. Test Results DL-S-243 (T-641306)

Description: The purpose of the test was to determine the direction and magnitude of any drift in the temperature sensing elements and the receiver-indicating units for the primary loop and pressurizer resistance thermometers. To obtain intercalibration data for various temperature sensing elements in the primary coolant system. To obtain data on the difference between the calculated signal generated by the BF-3 counters, considering the known rate of decay of the PO-BE source, and the measured values. Dete… more
Date: November 9, 1959
Creator: Lawrence, Roger J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Periodic Intercalibration of Temperature Sensing Elements. Section I. Second Performance. Test Results DL-S-243 (T-641303)

Description: The purpose of the test was to determine the direction and magnitude of any drift in the temperature sensing elements and the receiver-indicating units for the primary loop and pressurizer resistance thermometers. To obtain intercalibration data for various temperature sensing elements in the primary coolant system. To obtain data on the difference between the calculated signal generated by the BF-3 counters, considering the known rate of decay of the PO-BE source, and the measured values. Of t… more
Date: November 9, 1959
Creator: Lawrence, Roger J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dynamic Response of Reactor Plant to Load Changes. Section I. First Performance. Core I, Seed 1. Test Results DL-S-251 (T-612390)

Description: The purpose of the test was to determine the responses of the plant when subjected to load transients exceeding the design magnitudes, and to determine the maximum load changes, positive or negative, that the plant can sustain. The reactor plant responded satisfactorily to all load transients. The only limits exceed were the pressurizer high and low level alarm points. The magnitude of the transients and the time required for the plant to return to equilibrium was dependent upon the size of the… more
Date: November 6, 1959
Creator: Gentry, George
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Loss of Level in D/P Cell Reference Chambers. Section I. First Performance. Core I, Seed 1. Test Results DL-S-279 (RNI-23)

Description: The purpose of the test is to determine the reason for the decreases in the liquid levels of the reference chambers serving the reactor plant remote liquid level indicators. The remote gages and the local liquid level gages agreed closely for the Reactor Plant Component Cooling Water Expansion Tank and the Coolant Discharge and Vent System flash tank and blow-off tank. There appeared to be no loss of water from the D/P cell reference chambers for these two systems over the period of the test. … more
Date: October 30, 1959
Creator: Gentry, George
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurements of Coefficients of Reactivity. Section I. Seventh Performance. 3032-EFPH. Core I, Seed 1. Test Results DL-S-151 (T-550132)

Description: The purpose of the test was to determine the temperature and pressure coefficients of reactivity at zero power. Data was obtained during this test which indicates a new temperature coefficient and a pressure coefficient corrected to station operating conditions of 500 F and 1785 PSIG.
Date: November 18, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Station Radiation Level Survey. Section II. Fifth Performance. Core I, Seed 1. Test Results DL-S-157

Description: The purpose of the test was to determine the level of the radiation field in the Turbine Plant during a significant power run. The initial power level survey had an average radiation level of 0.02 mr/hr. this survey showed and average radiation level of 0.03, which was considered background level. this radiation level was far below the maximum allowable level of 2 mr/hyr. No Neutrons were detected.
Date: November 18, 1959
Creator: McTish, James M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Control Air Conditions at the Reactor Chamber. Section I. Test Results DL-S-269

Description: The purpose of the test was to determine the ability of the Control Air System to provide the necessary quantity and quality of clean, dry air to keep the rod drive mechanism stator and position indicator housings at about 3 PSIG in order to avoid low stator resistances resulting from condensation during plant cooldown. The Control Air System is capable of providing the quality of air specified in AEC letter SBO:JWF:100 dated November 17, 1958 of less than 44 grains of moisture per lb. of air i… more
Date: November 18, 1959
Creator: Eckenrode, Gerald E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Condensate System. Section II. Fifth Core I, Seed 1. Test Results DL-S-105

Description: The purpose of the test was to fill the condensate storage tank and the Condensate System and obtain satisfactory preliminary operation. The components of the Condensate System performed adequately and satisfactorily with the exception of fill control valve (M9-VI). This valve (M9-VI) is not used in the current operation procedure.
Date: December 8, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey. Section I. EFPH-5465.2. Second Performance. Core I, Seed 1. Test Results DL-S-231, T-612394

Description: The purpose of the test was to determine the radiation levels in a Reactor Plant Boiler Compartment with the respective loop shut down and the remainder of the plant operating at power. The highest radiation levels recorded in the IC Boiler Compartment were located in the vicinity of the reactor coolant loop pipe penetrations of the Compartment. Except for the above mentioned areas, personnel could continuously occupy the IC Boiler Compartment without exceeding the maximum dose rate of 300 mr p… more
Date: December 16, 1959
Creator: McTish, James M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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1A Reactor Inlet Hydraulic Valve Position Detector Temperature. Section I. Core I, Seed 1. Test Results DL-S-258-S, RNI-3

Description: The purpose of the test was to determine the internal temperature of the valve position detector for the 1A reactor inlet hydraulic valve with the plant at normal pressure and temperature and at power. The normal operating temperatures for the valve position detector on the 1A reactor inlet hydraulic valve range from a minimum of 287 F to a maximum of 294.7 F.
Date: November 20, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Leveling of Extraction Tool Crane Rails. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-246, FY-59-323

Description: The purpose of the test was to check the extraction crane rails in the area of the reactor pit for level and parallelism. The west extraction crane rail exceeded the allowed tolerance of 1/32 inch at only one location. The elevation of the north bumper was out of tolerance by 1/64 inch. The east extraction crane rail was consistently lower than the west rail by as much as 8/64 inch. The east rail was parallel with the west rail within allowable tolerances over the length tested except at one lo… more
Date: November 30, 1959
Creator: Pazuchanics, Nicholas
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Possible Failed Blanket Elements Using the FEDAL System. Section I. First Performance. Core I, Seed 1. Test Results DL-S-2810S, RNI-24

Description: The purpose of the test was to determine if failed blanket elements exist in other regions of the core beside F-2. FEDAL sampling ports that have indicted the greatest deviation as determined in a statistical analysis performed on a number of traverses in the FEDAL system will be tested. Data obtained from the start up runs of the FEDAL sample port Nos. 11, 31, 36 and 37 of Monitor 2 and port Nos. 14, 46, 11, 49 and 7 of Monitor 1 gave no indications of a blanket element failure. At each power … more
Date: November 23, 1959
Creator: Pazuchanics, Nicholas & Kearns, Walter
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey. Section III. First Performance. Core I, Seed 1. Test Results DL-S-231, T-612394

Description: The purpose of the test was to determine the radiation levels inside the concrete enclosures but outside the reactor plant containers after shutdown following plant power operation. Radiation levels at the survey points in the 1-AC and 10BD Boiler Chambers Enclosures and in the Reactor Container Enclosure indicated that no significant radiation hazards were present approximately 25 minutes after all rods had been inserted. The radiation levels approximately 4 minutes after shutdown at the surve… more
Date: November 30, 1959
Creator: Shramko, John, Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Examination of Components for Crud and Corrosion. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-155, T-612080

Description: The purpose of the test was to observe the extent and location of corrosion, crud deposits and defects in components of the primary fluid system and its auxiliaries. This observation will allow an estimate to be made of the future behavior of the affected parts. The test also provides for obtaining corrosion products and crud samples for analysis as necessary for planning remedial actions. This test was limited to the 1D Main Coolant Pump which failed November 3, 1958. The pump failed after 223… more
Date: December 7, 1959
Creator: Muldoon, James B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Charging and Discharge of Demineralizer Resins. Section IV. First Performance. Core I, Seed 1. Test Results DL-S-180, T-612085

Description: The purpose of the test was to determine if the 1A Canal Water System Demineralizers can be satisfactorily charged with resin. The 1A Canal Water System Demineralizer was satisfactorily charged with resin and conductivity of the demineralizer effluent was less than 0.1 microbes as specified in the Test Procedure.
Date: December 3, 1959
Creator: Eckenrode, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Determination of Decontamination Factors for Radioisotopes Through Lithium Hydroxide Resin. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-277-S, RNI-22

Description: The purpose of the test was to obtain data on the decontamination factors for Cesium-136, Cesium-137, Strontium-92, one hour gross iodine and Iodine-131. This data will be used to determinate efficiency of lithium hydroxide resin for removing radioactive cations and anions. The denomination factors for a particular demineralizer using lithium hydroxide resign were found to vary for different radioisotopes. This variation was from 2.3 for Cesium136 to 77,000 for gross iodine.
Date: December 3, 1959
Creator: Strauos, Roger O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Instrumentation Operation During Plant Operation. Section I. First Performance. Core I, Seed 1. Test Results DL-S-309, RNI-41

Description: The purpose of the test was to evaluate the operation of the Nuclear Instrumentation Power Range Amplifier during start up. While the station was operating at a gross load of 16.5 megawatts, a variation of 0, 8.5, 2.7 and 4.4 existed between the compensated ion chamber currents (CIC) and the test currents for channels A, B, C and D respectively. The off site modifications to channel C power range amplifier did not cause the ion chamber current and test current to be the same at 16.5 megawatts g… more
Date: December 8, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Main Coolant Pump Performance Test. Section I. First Performance. Core I, Seed 1. Test Results DL-S-290, T-641326

Description: The purpose of the test was to obtain performance data for the main coolant pumps on fast and slow speed at various coolant temperatures. The 1A, 1B and 1C pump performances on both fast and slow speed were approximately as shown in the manufacture's predicted performance curve. The 1D pump performance was below the manufacturer's predicted flow efficiency, line current and hydraulic horsepower on both fast and slow speeds.
Date: December 7, 1959
Creator: Edwards, Gerald E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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