TABLE IV: LISTING OF AEOD REPORTS AND RELATED GENERIC ISSUES

This listing shows all AEOD reports that have been addressed either as completely new safety issues or as part of existing safety issues. It should be noted that, in some cases, more than one AEOD report has

been generated on a single topic. However, all AEOD reports related to the identified safety issues are listed alphanumerically including those that have been superseded by other AEOD reports. The following is a description of the types of AEOD reports:

C - Reactor Case Study

E - Reactor Engineering Evaluation

S - Special Study Report

T - Technical Review Report

 

AEOD REPORT NO. AEOD REPORT TITLE RELATED ISSUE NO. RELATED AEOD REPORT
C001 Report on the Browns Ferry 3 Partial Failure to Scram Event on June 28, 1980 41 -
C003 Report on Loss of Offsite Power Event at Arkansas Nuclear One, Units 1 and 2 47 -
C004 AEOD Actions Concerning the Crystal River 3 Loss of Non-Nuclear Instrumentation and Integrated Control System Power on February 26, 1980 33 E122
C005 AEOD Observations and Recommendations Concerning the Problem of Steam Generator Overfill and Combined Primary and Secondary Side Blowdown 37, 42 -
C101 Report on the Saint Lucie 1 Natural Circulation Cooldown on June 11, 1980 31 -
C102 H. B. Robinson Reactor Coolant System Leak on January 29, 1981 34 -
C103 AEOD Safety Concerns Associated with Pipe Breaks in the BWR Scram System 40 -
C104 Millstone Unit 2 Loss of 125 V DC Bus Event on January 2, 1981 46 -
C105 Report on the Calvert Cliffs Unit 1 Loss of Service Water on May 20, 1980 36 -
C201 Safety Concern Associated with Reactor Vessel Level Instrumentation in Boiling Water Reactors 50, 101 -
C202 Report on Service Water System Flow Blockages by Bivalve Mollusks at Arkansas Nuclear One and Brunswick 32 E016
C203 Survey of Valve Operator-Related Events Occurring During 1978, 1979, and 1980 54 E305

 

 

AEOD REPORT NO. AEOD REPORT TITLE RELATED ISSUE NO. RELATED AEOD REPORT
C204 San Onofre Unit 1 Loss of Salt Water Cooling Event of March 10, 1980 44 -
C205 Abnormal Transient Operating Guidelines (ATOG) as Applied to the April 1981 Overfill Event at Arkansas Nuclear One, Unit 1 56 -
C301 Failures of Class 1E Safety-Related Switchgear Circuit Breakers to Close on Demand 55 -
C401 Low Temperature Overpressure Events at Turkey Point Unit 4 94 E426
C403 Edwin I. Hatch Unit No. 2 Plant Systems Interaction Event on August 25, 1982 85 E322
C404 Steam Binding of Auxiliary Feedwater Pumps 93 E325
C501 Safety Implications Associated with In-Plant Pressurized Gas Storage and Distribution Systems in Nuclear Power Plants 106 E902
C503 Decay Heat Removal Problems at U.S. Pressurized Water Reactors 99 -
C701 Air Systems Reliability 43 E123
E002 BWR Jet Pump Integrity 12 -
E005 Operational Restrictions for Class 1E 120 VAC Vital Instrument Buses 48 -
E007 Potential for Unacceptable Interaction Between the Control Rod Drive System and Non-Essential Control Air System at the Browns Ferry Plant 39 -
E010 Tie Breaker Between Redundant Class 1E Buses - Point Beach Nuclear Plant, Units 1 and 2 49 -
E011 Concerns Relating to the Integrity of a Polymer Coating for Surfaces Inside Containment 38 -
E016 Flow Blockage in Essential Equipment at ANO Caused by Corbicula sp. (Asiatic Clams) 32 C202
E101 Degradation of Internal Appurtenances in LWR Piping 35 -
E112 Inoperability of Instrumentation Due to Extreme Cold Weather 45 E226
E122 AEOD Concern Regarding Inadvertent Opening of Atmospheric Dump Valves on B&W Plants During Loss of ICS/NNI Power 33 C004

 

 

AEOD REPORT NO. AEOD REPORT TITLE RELATED ISSUE NO. RELATED AEOD REPORT
E123 Common Cause Failure Potential at Rancho Seco - Desiccant Contamination of Air Lines 43 C701
E204 Effects of Fire Protection System Actuation on Safety-Related Equipment 57 -
E209 Generator Rotor Retaining Ring as a Potential Missile (Incident at Barseback 1 on 4/13/79) 30 -
E215 Engineering Evaluation of the Salt Service Water System Flow Blockage at the Pilgrim Nuclear Power Station by Blue Mussels 52 -
E226 Inoperability of Instrumentation Due to Extreme Cold Weather 45 E112
E304 Investigation of Backflow Protection in Common Equipment and Floor Drain Systems to Prevent Flooding of Vital Equipment in Safety-Related Compartments 77 -
E305 Inoperable Motor-Operational Valve Assemblies Due to Premature Degradation of Motors and/or Improper Limit Switch/Torque Switch Adjustment 54 C203
E322 Damage to Vacuum Breaker Valves as a Result of Relief Valve Lifting 85 C403
E325 Vapor Binding of Auxiliary Feedwater Pumps at Robinson 2 93 C404
E414 Stuck Open Isolation Check Valve on the Residual Heat Removal System at Hatch Unit 2 105 -
E417 Loosening of Flange Bolts on RHR Heat Exchanger Leading to Primary to Secondary Side Leakage C-9 -
E426 Single Failure Vulnerability of Power Operated Relief Valve (PORV) Actuation Circuitry for Low Temperature Overpressure Protection (LTOP) 94 C401
E609 Inadvertent Draining of Reactor Vessel During Shutdown Cooling Operation 129 -
E804 Reliability of Non-Safety-Related Field Breakers During ATWS Events 151 -
E807 Pump Damage Due to Low Flow Cavitation 159 -
S401 Human Error in Events Involving Wrong Unit or Wrong Train 102 -
S92-02 Safety and Safety/Relief Valve Reliability 165 -

 

 

AEOD REPORT NO. AEOD REPORT TITLE RELATED ISSUE NO. RELATED AEOD REPORT
T302 Postulated Loss of Auxiliary Feedwater System Resulting from a Turbine Driven Auxiliary Feedwater Pump Steam Supply Line Rupture 68 -
T305 Flow Blockage in Essential Raw Cooling Water System Due to Asiatic Clam Intrusion at Sequoyah 1 51 -
T420 Failure of an Isolation Valve of the Reactor Core Isolation Cooling System to Open Against Operating Reactor Pressure 87 -

[1]


 

 


[1] NUREG-0371, "Task Action Plans for Generic Activities (Category A)," U.S. Nuclear Regulatory Commission, November 1978.

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Page Last Reviewed/Updated 11/18/2025