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NUREG 0933
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Displaying 26 - 50 of 330
TASK III.A.1: IMPROVE LICENSEE EMERGENCY PREPAREDNESS - SHORT-TERM The objectives of this task were to improve and upgrade licensee emergency preparedness by requiring improvements in facilities, plans, procedures, offsite support, technical assistance, …
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The objective of this task was to upgrade the emergency preparedness of nuclear power plants. Specific criteria to meet this objective were delineated in NUREG-0654. [1] ITEM III.A.2.1: AMEND 10 CFR 50 AND 10 CFR 50, APPENDIX E The four parts of this item …
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The objective of this task is to enable NRC, in the event of a nuclear accident at a licensed reactor facility, to: (1) monitor and evaluate the situation and potential hazards, (2) advise the licensee's operating staff as needed, and (3) in an extreme …
1
The objective of this task is to upgrade the state of emergency preparedness of State and local governments affected by nuclear facilities. The Federal Emergency Management Agency was given the lead on this effort by the President on December 7, 1979. …
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The objectives of this task are: (1) to have information available for the news media and the public describing how nuclear plants operate, radiation and its health effects, and protective actions against radiation; and (2) to provide training for members …
1
TASK III.D.1: RADIATION SOURCE CONTROL The objective of this task is to perform evaluations to establish additional design features that should be included in the rulemaking proceeding of Item II.B.8. The purpose of these evaluations is to identify design …
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The objective of this task was to improve public radiation protection in the event of a nuclear power plant accident by improving (1) radioactive effluent monitoring, (2) the dose analysis for accidental releases of radioiodine, tritium, and carbon-14, …
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The objective of this task is to improve nuclear power plant worker radiation protection to allow workers to take effective action to control the course and consequences of an accident, as well as to keep exposures as low as reasonably achievable (ALARA) …
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The objective of this task is to substantially improve licensee awareness of and attitude toward safety by vigorous enforcement of NRC rules. The two major aspects of this objective are as follows: (1) assess substantial penalties for licensee failure to …
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The objective of this task is to develop a more efficient and effective management method for issuing information and requirements to licensees to elimination the duplication of staff effort for NRC and licensees. Provide an NRC-wide system for tracking …
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The objectives of this task are: (1) to improve and expand the NRC training program for the technical staff and resident inspectors, including, where appropriate, hands-on training; and (2) to establish a program to provide technically qualified …
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The objective of this task is to develop plans for an integrated program of safety decision-making. These plans include: (1) an expanded program of regulatory research covering methodologies for making safety decisions and safety-cost tradeoffs, with …
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The objectives of this task are to improve NRC rulemaking procedures to provide a greater opportunity for public participation, to assure a periodic and systematic reevaluation of NRC rules, and to include appropriate provision for backfitting in all new …
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The objective of this task is to respond to the President's request for NRC participation in the Radiation Policy Council. ITEM IV.H.1: NRC PARTICIPATION IN THE RADIATION POLICY COUNCIL DESCRIPTION The Radiation Policy Council, a policy coordinating body …
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The objective of this task was the further delineation of substantive safety policy by the NRC. ITEM V.A.1: DEVELOP NRC POLICY STATEMENT ON SAFETY DESCRIPTION This NUREG-0660, [1] Rev. 1 item called for the Commission to develop more explicit articulation …
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The objective of this task was the elimination of nonsafety responsibilities from NRC jurisdiction, if appropriate. ITEM V.B.1: STUDY AND RECOMMEND, AS APPROPRIATE, ELIMINATION OF NON-SAFETY RESPONSIBILITIES DESCRIPTION This NUREG-0660, [1] Rev. 1 item …
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The objective of this task was to strengthen the role of advisory committees in Commission activities. ITEM V.C.1: STRENGTHEN THE ROLE OF ADVISORY COMMITTEE ON REACTOR SAFEGUARDS DESCRIPTION This NUREG-0660, [1] Rev. 1 item called for the Commission to …
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The objective of this task was to enhance public participation in, and make needed reforms to, the nuclear licensing process. ITEM V.D.1: IMPROVE PUBLIC AND INTERVENOR PARTICIPATION IN THE HEARING PROCESS DESCRIPTION This NUREG-0660, [1] Rev. 1 item …
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The objective of this task was to evaluate legislative needs evidenced by and from TMI. ITEM V.E.1: STUDY THE NEED FOR TMI-RELATED LEGISLATION DESCRIPTION This NUREG-0660, [1] Rev. 1 item called for the Commission to study the need for legislation with …
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The objective of this task was to improve Commission organization and management. ITEM V.F.1: STUDY NRC TOP MANAGEMENT STRUCTURE AND PROCESS DESCRIPTION This NUREG-0660, [1] Rev. 1 item called for the Commission to hire an independent management …
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The objective of this task was to achieve a single location for the NRC's headquarters office. ITEM V.G.1: ACHIEVE SINGLE LOCATION, LONG-TERM DESCRIPTION This NUREG-0660, [1] Rev. 1 item called for the Commission to break the impasse hindering the …
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DESCRIPTION The issue was raised after the occurrence of various incidents of water hammer that involved steam generator feedrings and piping, emergency core cooling systems, RHR systems, containment spray, service water, feedwater, and steam lines. The …
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DESCRIPTION The technical report on ATWS for water-cooled reactors (WASH-1270) [1] discussed the probability of an ATWS event as well as an appropriate safety objective for the event. After several years of discussions with vendors and evaluations of …
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DESCRIPTION Inspections of operating BWRs conducted up to April 1978 revealed cracks in the feedwater nozzles of 20 reactor vessels. Most of these BWRs contained 4 nozzles with diameters ranging from 10 in. to 12 in. Although most cracks ranged from 1/2 …
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DESCRIPTION Because of the remote possibility of failure of nuclear reactor pressure vessels designed to the ASME Boiler and Pressure Vessel Code, the design of nuclear facilities does not provide protection against reactor vessel failure. Prevention of …
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