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Advisory Committee on Reactor Safeguards (ACRS) 1990 Letter Reports

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Date Title
01/18/1990Resolution Of The Interfacing Systems LOCA Issue
02/15/1990Proposed Power Level Increase For Indian Point Nuclear Generating Station Unit 2
02/15/1990ACRS Review And Evaluation Of Nuclear Power Plant Operating Experience
02/15/1990Coherence In the Regulatory Process
02/15/1990Letter to Honorable J. Danforth Quayle, President of the United States Senate
03/13/1990Containment Performance Improvement Program - Proposed Recommendations For Mark II, Mark III, Ice Condenser, And Dry Containments
04/11/1990Proposed Rule On Nuclear Power Plant License Renewal
04/11/1990NRC Safety Research Program Budget
04/24/1990Severe Accident Research Program
04/26/1990Evolutionary Light Water Reactor Certification Issues And Their Relationship To Current Regulatory Requirements
06/12/1990Proposed Rule To Implement An Emergency Response Data System
06/12/1990Generic Issue-84, Combustion Engineering Plants Without Power Operated Relief Valves
06/12/1990Modified Enforcement Policy For Hot Particle Exposures Incorporating The Recommendations Of NCRP Report No.106
06/13/1990Draft Study On Source Term Update And Decoupling Siting From Design
08/14/1990Proposed Resolution Of Generic Safety Issue B-56, "Diesel Generator Reliability"
08/14/1990Level of Detail Required For Design Certification Under Part 52
08/16/1990NRC Research On Organizational Factors
09/11/1990Implementation Of The Safety Goal Policy
09/11/1990Proposed Priority Rankings Of Generic Issues: Sixth Group
09/12/1990Reevaluation Of The SALP Program
09/12/1990Yankee Rowe Reactor Pressure Vessel Integrity
10/11/1990Draft Implementation Documents For The Proposed License Renewal Rule
10/11/1990NRC Computer Codes And Their Documentation
10/12/1990Letter to Honorable Kenneth M. Carr, Chairman of U.S. Nuclear Regulatory Commission
11/14/1990SECY-90-353, Licensing Review Basis Document For the Combustion Engineering, INC. System 80+ Evolutionary Light Water Reactor
11/15/1990Review Of NUREG-1150, "Severe Accident Risks: An Assessment For Five U.S. Nuclear Power Plants"
12/10/1990SECY-90-377, "Requirements For Design Certification Under 10 CFR Part 52"
12/11/1990Full-Term Operating License For The Dresden Nuclear Power Station, Unit 2
12/11/1990Full-Term Operating License For The Palisades Nuclear Plant
12/12/1990Westinghouse's Application For Preliminary Design Approval For The RESAR SP/90 Design

Page Last Reviewed/Updated Thursday, August 27, 2026

Page Last Reviewed/Updated Thursday, August 27, 2026