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NUREG 0933
Displaying 51 - 75 of 458
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 objective of this task is to assure that the lessons learned from TMI are applied to other NRC programs. ITEM IV.C.1: EXTEND LESSONS LEARNED FROM TMI TO OTHER NRC PROGRAMS DESCRIPTION This TMI Action Plan Item [1] required that lessons learned from …
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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 objective of this task is to enhance public safety through the reduction of disincentives to safety resulting from financial pressures on the utility at the construction, operation, and decommissioning stages. ITEM IV.F 1: INCREASED OIE SCRUTINY OF …
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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 …
1
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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DISCUSSION On May 7, 1975, the NRC was informed by VEPCO that an asymmetric loading on the reactor vessel supports resulting from a postulated reactor coolant pipe rupture at a specific location (e.g., the vessel nozzle) had not been considered by W or …
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DESCRIPTION Prior to 1978, operating experience with PWR steam generators was characterized by extensive corrosion and mechanically-induced degradation of the steam generator tubes, frequent plant shutdowns to repair primary-to- secondary leaks, and two …
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DESCRIPTION This item was originally identified in NUREG-0371 [1] and was later declared a USI in NUREG-0510. [2] (See Item A-3 for further details.) CONCLUSION This item was RESOLVED and requirements were established. (See Item A-3 for further details.) …
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DESCRIPTION This item was originally identified in NUREG-0371 [1] and was later declared a USI in NUREG-0510. [2] (See Item A-3 for further details.) CONCLUSION This item was RESOLVED and requirements were established. (See Item A-3 for further details.) …
1
DESCRIPTION During the conduct of a large scale testing program for an advanced design BWR pressure suppression containment system (MARK III), new suppression pool hydrodynamic loads associated with a postulated LOCA were identified which had not been …
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DESCRIPTION During testing for an advanced BWR containment system design (MARK III), suppression pool hydrodynamic loads were identified which had not been considered in the original design of the MARK I containment system. To address this issue, a MARK I …
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DESCRIPTION As a result of the GE testing program for the MARK III pressure-suppression containment program, new containment loads associated with a postulated LOCA were identified in 1975 which had not been explicitly included in the original design of …
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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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Page Last Reviewed/Updated 3/1/2026
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