| Date |
Title |
| 01/19/1989 |
Mark I Containment Performance Improvement Program |
| 01/19/1989 |
Resolution Of Generic Issue 43, "Air Systems Reliability" |
| 01/19/1989 |
Draft Final Rule On Standardization And Licensing Reform, 10 CFR Part 52, "Early Site Permits; Standard Design Certifications; And Combined Licenses For Nuclear Power Plants" |
| 01/19/1989 |
Code Scaling, Applicability, And Uncertainty (CSAU) Methodology For Determination Of Uncertainty Associated With the Use Of Realistic ECCS Evaluation Models |
| 01/19/1989 |
Safety Evaluation Report For The Sodium Advanced Fast Reactor (SAFR) Design |
| 01/23/1989 |
NUREG-1150: Resolution Of ACRS Comments |
| 02/15/1989 |
Proposed Policy Statement On Additional Applications Of Leak-Before-Break Technology (SECY-88-325) |
| 02/15/1989 |
Final Rule On Standardization And Licensing Reform, 10 CFR Part 52 , "Early Site Permits; Standard Design Certifications; And Combined Licenses For Nuclear Power Plants" |
| 02/16/1989 |
Proposed Resolution Of Generic Issues 70, "Power Operated Relief Valve And Block Valve Reliability," And 94, "Additional Low-Temperature Overpressure Protection For LWRs" |
| 02/16/1989 |
Further ACRS Comment On Proposed Resolution Of Generic Issue 99, "Improved Reliability Of RHR Capability In PWRs" |
| 02/16/1989 |
Further ACRS Comments On Implementation Of The Safety Goal Policy |
| 02/17/1989 |
Letter to Honorable J. Danforth Quayle, President of the United States Senate |
| 03/14/1989 |
Review Of The Peach Bottom Atomic Power Station Restart |
| 03/14/1989 |
Additional Applications Of Leak-Before-Break Technology |
| 03/15/1989 |
Proposed Severe Accident Research Program Plan |
| 03/15/1989 |
Containment Design Criteria |
| 04/11/1989 |
Proposed Final Rulemaking Related To Maintenance Of Nuclear Power Plants |
| 04/11/1989 |
Proposed Amendment To 10 CFR 50.60, "Fracture Toughness Requirements For Protection Against Pressurized Thermal Shock Events" |
| 04/11/1989 |
Proposed Resolution Of Generic Issue 82, "Beyond Design Basis Accidents In Spent Fuel Pools" |
| 04/11/1989 |
Proposed Resolution Of Generic Issue 101, "BWR Water Level Redundancy" |
| 04/11/1989 |
Proposed Final Resolution Of Generic Safety Issue 103, "Design For Probable Maximum Precipitation" |
| 04/11/1989 |
Proposed Resolution of Generic Issue 115, "Enhancement Of Reliability Of Westinghouse Solid State Protection Systems" |
| 04/13/1989 |
Letter From James R. Sutton Dated March 23, 1989 Regarding Three Mile Island Warning Siren |
| 04/17/1989 |
Integrated Approach On Regulatory Matters |
| 05/09/1989 |
NUREG-1150, "Severe Accident Risks: An Assessment For Five U.S. Nuclear Power Plants" |
| 05/09/1989 |
NRC's Human Factors Programs And Initiatives |
| 05/09/1989 |
Generic Letter On Safety-Related Motor-Operated Valve Testing And Surveillance |
| 05/09/1989 |
Generic Letter Related To Occupational Radiation Exposure Of Skin From Hot Particles |
| 05/11/1989 |
Operating License Application For Limerick Generating Station, Unit 2 |
| 06/13/1989 |
USI A-17, "Systems Interactions In Nuclear Power Plants" |
| 06/14/1989 |
Reliability And Diversity |
| 06/14/1989 |
Boiling Water Reactor Core Power Stability |
| 06/14/1989 |
Proposed Generic Letter Regarding Service Water System Problems Affecting Safety-Related Equipment |
| 06/14/1989 |
Proposed Resolution Of Generic Issue 128, "Electrical Power Reliability" |
| 06/15/1989 |
Proposed Commission Policy Statement On Education For Senior Operators And Shift Supervisors At Nuclear Power Plants |
| 06/15/1989 |
NRC Thermal-Hydraulic Research Program |
| 07/18/1989 |
Proposed Resolution Of Unresolved Safety Issue A-40 , "Seismic Design Criteria" |
| 07/18/1989 |
Proposed Staff Actions Regarding The Fire Risk Scoping Study (NUREG/CR-5088) |
| 08/15/1989 |
Proposed Resolution Of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown |
| 09/12/1989 |
Proposed Resolution Of Generic Issue A-29, "Nuclear Power Plant Design For Reduction Of Vulnerability To Industrial Sabotage" |
| 09/12/1989 |
Electric Power Research Institute Advanced Light Water Reactor Requirements Document |
| 09/13/1989 |
Emergency Plan For Full-Power Operation Of The Seabrook Station, Unit 1 |
| 10/11/1989 |
ACRS Comments On The Safety Goal Policy And Its Relationship To The Concept Of Adequate Protection |
| 10/11/1989 |
Proposed Resolution Of Generic Issue 135, Steam Generator And Steam Line Overfill Issues |
| 10/12/1989 |
Proposed Revised Policy Statement On The Maintenance Of Nuclear Power Plants |
| 11/20/1989 |
The Relationship Of The Quantitative Safety Goal To The Concept Of Adequate Protection |
| 11/20/1989 |
Draft Supplement No. 2 To Generic Letter 88-20, "Accident Management Strategies For Consideration In The Individual Plant Examination Process |
| 11/20/1989 |
Proposed Resolution Of Generic Issue-87 (GI-87), "HPCI Steam Line Break Without Isolation" |
| 11/20/1989 |
Letter to Honorable Kenneth M. Carr, Chairman of U.S. Nuclear Regulatory Commission |
| 11/24/1989 |
Module 1 Of The Draft Safety Evaluation Report For The Advanced Boiling Water Reactor Design |
| 11/24/1989 |
Coherence In The Regulatory Process |
| 12/19/1989 |
Proposed Rule On Access Authorization At Nuclear Power Plants |
| 12/20/1989 |
Proposed Amendment To 10 CFR Part 55, Operators' Licenses, To Include "Fitness-For-Duty" Penalties |
| 12/21/1989 |
Coherence In The Regulatory Process |
