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Advisory Committee on Reactor Safeguards (ACRS) 1991 Letter Reports

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Date Title
01/14/1991 Proposed Resolution Of Generic Safety Issue 29, "Bolting Degradation Or Failure In Nuclear Power Plants"
01/15/1991 Letter to Honorable J. Danforth Quayle, President of the United States Senate
02/12/1991 Standard Review Plan For Reviewing Safety Analysis Reports For Dry Metallic Spent Fuel Storage Casks
02/12/1991 EDO Response To ACRS Report Dated December 12,1990 On The Preliminary Design Approval For The RESAR SP/90
02/12/1991 Proposed Supplement 4 To Generic Letter 88-20, Individual Plant Examination Of External Events (IPEEE) For Severe Accident Vulnerabilities - 10 CFR 50.54 (f)
03/12/1991 Restart Of The Browns Ferry Nuclear Plant, Unit 2
03/12/1991 Full-Term Operating License For The Oyster Creek Nuclear Generating Station
03/12/1991 Proposed Rule On Selection, Training, And Qualification Of Nuclear Power Plant Personnel
04/17/1991 Draft Final Rule On Nuclear Power Plant License Renewal
04/18/1991 Proposed Resolution Of Generic Safety Issue 130, "Essential Service Water System Failures At Multi-Unit Sites"
04/23/1991 Proposed Policy Issues Identified In SECY-91-078, "Chapter 11 Of The Electric Power Research Institute's (EPRI'S) Requirements Document And Additional Evolutionary Light Water Reactor (LWR) Certification Issues"
05/17/1991 Proposed Final Rule Revision 10 CFR Part 55, "Operators' Licenses" To Include Fitness-For-Duty Requirements
05/17/1991 Proposed Final Revision To Appendix J To 10 CFR Part 50 And Related Final Regulatory Guide
05/17/1991 Final Rulemaking To Implement The Emergency Response Data System
05/17/1991 Proposed Criteria To Accommodate Severe Accidents In Containment Design
05/17/1991 Documentation Of Computer Codes
05/17/1991 Proposed Resolution Of Generic Safety Issue 29, "Bolting Degradation Or Failure In Nuclear Power Plants"
05/20/1991 Staff Evaluation And Recommendations On Maintenance Rulemaking
07/18/1991 Schedules For Advanced Reactor Reviews
07/18/1991 Proposed NUMARC/EPRI Fire Vulnerability Evaluation Methodology For Use In The EPEEE
07/18/1991 Concerns Related To The General Electric Advanced Boiling Water Reactor Design
07/19/1991 The Consistent Use Of Probabilistic Risk Assessment
08/13/1991 Additional Comment On Schedules For Advanced Reactor Reviews
08/13/1991 Full-Term Operating License For The San Onofre Nuclear Generating Station, Unit 1
08/13/1991 Evaluation Of Risks During Low Power And Shutdown Operations Of Nuclear Power Plants
08/13/1991 Proposed Resolution Of Generic Issue 130, "Essential Service Water System Failures At Multi-Unit Sites" And Task Action Plan For Generic Issue 153, "Loss Of Essential Service Water In LWR's"
09/10/1991 The Staff's Recommendations On The Regulatory Impact Survey Report
09/10/1991 Inspections, Tests, Analyses, And Acceptance Criteria (ITAAC) For Design Certifications
09/11/1991 Need For ACRS Review Of Recent Staff Papers
10/17/1991 Schedule For ACRS Review Of Recent Staff Papers
10/17/1991 Proposed Resolution Of Generic Issue 113, "Dynamic Qualification And Testing Of Large Bore Hydraulic Snubbers"
10/17/1991 Regulatory Guides Being Developed In Support Of The Revised 10 CFR Part 20
10/17/1991 Proposed Paper On Metrication Policy
10/18/1991 Diablo Canyon Nuclear Power Plant Long Term Seismic Program
11/14/1991 NRC Staff Recommendations For Reviewing, Monitoring, And Approving Vendors' Test Programs To Support The Design Certification Of Passive Light Water Reactors As Described In SECY-91-273
11/15/1991 Steam Generator Tube Repair Limits
12/14/1991 The Consistent Use Of Probabilistic Rick Assessment
12/18/1991 SECY-91-262, "Resolution Of Selected Technical And Severe Accident Issues For Evolutionary Light Water Reactor (LWR) Designs"
12/18/1991 SECY-91-270, "Interim Guidance On Staff Implementation Of The Commission's Safety Goal Policy"
12/18/1991 NRC Staff Approach To The Review Of The Role Of Personnel And Advanced Control Rooms In Future Nuclear Power Plants As Described In SECY-91-272
12/20/1991 Resolution Of Generic Safety Issue B-56, "Diesel Generator Reliability"

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