CHAPTER | TITLE | SOURCE OF INFORMATION |
1 | Introduction | NRC Web site for activities in HR, IRO, NMSS, NRR, RES |
2 | Operating Experience Feedback | LERs, NUREG-1187, series |
2.1 | Operating Performance | NUREG-1187, series |
2.1.1 | Reactor Scrams | NUREG-1187, series |
2.1.2 | Engineered Safety Features Actuations | LERs |
2.1.3 | Significant Events | NUREG-1187, series |
2.1.4 | Safety Systems Failures | NUREG-1187, series |
2.1.5 | Forced Outage Rate | NUREG-1187, series |
2.1.6 | Equipment Forced Outages per 1000 Commercial Critical Hours | NUREG-1187, series |
2.1.7 | Collective Radiation Exposure | NUREG-1187, series |
2.1.8 | Cause Codes | NUREG-1187, series |
2.1.9 | Unit Operating Factors | Monthly Operating Reports |
2.1.10 | Statistical Analysis of Some Trends | NUREG-1187, series |
2.1.11 | Nuclear Reactor Safety Performance | NUREG-1187, series NUREG/CR-4674, series |
2.2 | Abnormal Occurrences | NUREG-0090, series |
2.3 | Radiation Exposures From Reactors and Nonreactors | Radiation Exposure Information Reporting System |
2.3.1 | Sources of Radiation Exposure | Radiation Exposure Information Reporting System |
2.3.2 | Exposures for Reactor and Nonreactor | Radiation Exposure Information Reporting System |
2.3.3 | Overexposures for Reactor and Nonreactor Applications | Radiation Exposure Information Reporting System |
2.4 | Allegations at Commercial Nuclear Power Reactors | Allegations Database |
 |
3 | AEOD Reliability and Risk Activities | NUREG/CR-4674, series |
3.1 | Accident Sequence Precursor Program | NUREG/CR-4674, series |
3.1.1 | Results for CY 1995 Events | NUREG/CR-4674, series |
3.1.2 | Results for CY 1982-1983 Events | NUREG/CR-4674, series |
3.1.3 | Results for CY 1996 Events | NUREG/CR-4674, series |
3.2 | System Reliability Studies | NUREG-1272, Vol. 11, No. 1 |
3.2.1 | Reactor Core Isolation Cooling System Reliability | AEOD/S97-02 |
3.3 | Common-Cause Failure Database | NUREG/CR-6268, Vols. 1 to 4 NUREG/CR-5409 |
4 | AEOD Reports | NUREG-1272, Vol. 11, No. 1 |
4.1 | AEOD Activities To Identify and Address Safety Issues | NRC Web site for RES activities |
4.2 | Case Studies | NUREG-1272, Vol. 11, No. 1 |
4.2.1 | Grid Performance Factors | AEOD/C97-01 |
4.3 | Special Studies | NUREG-1272, Vol. 11, No. 1 |
4.3.1 | Oconee Electrical System Design and Operation | AEOD/S97-01 |
4.3.2 | Fire Events - Feedback of U.S.Operating Experience | AEOD/S97-03 |
4.4 | Engineering Evaluations | NUREG-1272, Vol. 11, No. 1 |
4.4.1 | Review of Industry Efforts To Manage Pressurized-Water Reactor Feedwater Nozzle, Piping, and Feedring Cracking and Wall Thinning | AEOD/E97-01 |
4.4.2 | Review of Undetected Failures of Safety System | AEOD/E97-02 |
4.4.3 | Nuclear Power Plant Cold Weather Problems and Protective Measures | AEOD/E97-03 |
4.5 | Technical Reviews | NUREG-1272, Vol. 11, No. 1 |
4.5.1 | Design Errors in Nuclear Power Plants | AEOD/T97-01 |
 |
5 | Operating Experience Data | LERs, Daily events in |
5.1 | Licensee Event Reporting | LERs, Daily events in |
5.2 | U.S. Operational Experience Databases | LERs, Daily events in |
5.3 | Reliability and Availability Data | Section 5.3, NUREG-1272, Vol. 11, No. 1 |
6 | Incident Response | IRO Activities Chapter 6, NUREG-1272, Vol. 11, No. 1 |
6.1 | NRC Operations Center | IRO Activities Section 6.1, NUREG-1272, Vol. 11, No. 1 |
6.2 | Emergency Response | IRO Activities Section 6.2, NUREG-1272, Vol. 11, No. 1 |
6.3 | Operations Center Data for 1997 | IRO Operating Plan, Daily events |
6.4 | Emergency Exercises | IRO Operating Plan, Daily events |
6.5 | State Outreach | IRO Activities |
6.6 | Coordination With Other Federal Agencies | IRO Activities |
7 | Incident Investigation Program | IRO Activities |
7.1 | Incident Investigation Teams | IRO Activities |
7.2 | Augmented Inspection Teams | IRO Activities |
7.2.1 | Zion 1 | IRO Activities Section 7.2.1, NUREG-1272, Vol. 11, No. 1 |
7.2.2 | Oconee 3 | IRO Activities Section 7.2.2, NUREG-1272, Vol. 11, No. 1 |
7.2.3 | Oconee 1 | IRO Activities Section 7.2.3, NUREG-1272, Vol. 11, No. 1 |
7.2.4 | Clinton | IRO Activities Section 7.2.4, NUREG-1272, Vol. 11, No. 1 |
 |
8 | Diagnostic Evaluation Program | IRO Activities NUREG-1272, Vol. 11, No. 1 |
8.1 | Diagnostic Evaluation Teams | Section 8.1, NUREG-1272, Vol. 11, No. 1 |
8.2 | Special Evaluation of Clinton Power Station | IRO Activities Section 8.2, NUREG-1272, Vol. 11, No. 1 |
9 | Committee To Review Generic Requirements | WITS 1997-00390 |
9.1 | CRGR Issues | WITS 1997-00390 |
9.2 | Value Added by the CRGR Review | Section 9.2, NUREG-1272, Vol. 11, No. 1 |
10 | International Exchange of Information | NUREG-1272, Vol. 11, No. 1, NUREG-1145, series |
10.1 | The Incident Reporting System | NRR Activities |
10.2 | International Support Activities | RES and NRR Activities |
10.3 | | Lisbon Initiative Activities (Not applicable) |
10.4 | Limited Participation in the International Nuclear Event Scale | IRO Activities |
 |
Appendix A-1 | Performance Indicator Program Data | NUREG-1187, series |
Appendix A-2 | Other Operational Experience Data | Monthly Operating Reports |
Appendix B | Summary of 1997 Abnormal Occurrences | NUREG-0090, series |
Appendix C | Reports Issued in 1997 | NUREG-1272, Vol. 11, No. 1 |
Appendix D | Reports Issued From CY 1980 Through CY 1996 | NUREG-1272, Vol. 11, No. 1 |
Appendix E | AEOD Technical Reports by Category | NUREG-1272, Vol. 11, No. 1 |
Appendix F | Status of AEOD Recommendations | (All recommendations addressed) |
Appendix G | Status of NRC Staff Actions for Reactor Events Investigations by Incident Investigation Teams | IRO Activities |
Appendix H | Status of Staff Actions Involving Potential Generic Issues Resulting From Diagnostic Evaluation Team Findings | IRO Activities |
Appendix I | Status of Staff Actions Involving Potential Generic Issues Resulting From the NRC/INPO Team Review of the Effects of Hurricane Andrew on Turkey Point Units 3 and 4 | IRO Activities |
Appendix J | Status of NRC Staff Actions Resulting From the Independent Safety Assessment of the Maine Yankee Atomic Power Plant | IRO Activities |