| 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" |