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Joseph Pollock
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Joseph Pollock# QUERY3dc96ad6cbe16148409705e36838bb27
Joseph Pollock OR Joseph Pollock
Joseph Pollock# QUERY660fb74e694b8c504a2e32134341aed5
Joseph Pollock# QUERYb38962560e56aa69b390e93c9c4a249b
Joseph Pollock# QUERY01f5e817c8d5dd308a6b29a30bba0185
Joseph Pollock# QUERY4c1169eae9e4198ceca914d1c0b5c78b
Joseph Pollock# QUERY92e8610e8c04ffa9b32f071f8f00eaaa
False
Joseph Pollock# QUERY600bb62cdec9e3bca7c4ea81d1f9984f
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Joseph Pollock# QUERYea8d93abe6e4c24534553889ca4241ff
Nuclear Energy Institute
Joseph Pollock# QUERYbccd8c030dd7760504b4ee22b2a90b26
Joseph Pollock# ERR1dd423a8697e32d6813ecd1a7aae482c
CP-201600329, Summary of Compliance with EA-12-049, NRC Order Modifying Licenses with Regard to Requirements for Mitigating Strategies for Beyond Design-Basis External Events
NLS2017100, Anchor Darling Double Disc Gate Valve Information and Status
L-17-351, Anchor Darling Double Disc Gate Valve Information and Status
L-17-352, No Active Safety Function Anchor Darling Double Disc Gate Valves
L-17-353, No Active Safety Function Anchor Darling Double Disc Gate Valves
NL-11-131, Response to Request for Additional Information Regarding Response to NRC Bulletin 2011-01, Mitigating Strategies
NL-11-076, Day Response to NRC Bulletin 2011-01, Mitigating Strategies
NL-11-066, 30-Day Response to NRC Bulletin 2011-01, Mitigating Strategies
NL-11-029, Response to Request for Additional Information Regarding the Review of the Spent Fuel Management Program and the Preliminary Decommissioning Cost Estimate
NL-10-064, License Amendment Withdrawal and Request - Cyber Security Plan
NL-10-030, Indian Point, Unit 2, Revised Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule, Appendix H
NL-10-010, Letter NC-10-010 Dated 01/11/10, Indian Point, Unit 3 - Proposed License Amendment Regarding One Time Extension of the Auxiliary Boiler Feedwater Pump Allowed Outage Time
NL-10-025, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Per 10 CFR 50, Appendix H
NL-10-016, Supplement to Proposed License Amendment to Change Technical Specifications Regarding Surveillance Requirements for AC and DC Sources
NL-10-009, Exemption Request from Physical Security Requirements
NL-10-001, Supplement to Proposed Exigent License Amendment Regarding One Time Extension of the Auxiliary Boiler Feedwater Pump Allowed Outage Time
NL-09-147, Proposed License Amendment Regarding Cyber Security Plan
NL-09-013, Indian Point, Unit 2, Proposed Changes to Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Over Pressure Requirements
L-MT-16-056, Response to an Apparent Violation Regarding NRC Inspection Report 05000263/2016010 (EA-16-175)
NL-11-110, Amendment Update to the Final Safety Analysis Report (Fsar), Revision 04
NL-11-130, Response to Request for Additional Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request (TAC Nos. ME1671, ME1672, and L24299)
NL-11-127, CFR 50.75(f)(1) 2011 Decommissioning Funding Status Report, Response to Request for Additional Information
NL-11-119, Proposed Change to the Technical Specification Requirement for Containment Sump Level Indication
NL-11-087, Proposed License Amendment Regarding Travelers - TSTF-479-A and TSTF-497-A
NL-11-052, Response to Request for Additional Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request (TAC Nos. ME1671, ME1672, and L24299)
NL-11-079, Resubmittal to Clarify the IPEC Cyber Security Plan
NL-11-064, Submittal of Revision 12 to Physical Security, Training and Qualification, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program
NL-11-061, Emergency Response Data System (ERDS) Changes
NL-11-060, Revised Table from Entergy Letter NL-11-014 Regarding Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions
NL-11-059, Revised Tables from Entergy Letter NL-11-013 Regarding Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions
NL-11-017, Application for Preemption Authority Pursuant to Section 161A of the Atomic Energy Act
NL-11-0033, Response to Request for Additional Information and Revisions to IPEC Cyber Security Plan
NL-11-015, Response to Request for Additional Information Regarding IPEC Cyber Security Plan
NL-11-013, Revised Tables from Responses to Requests for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions
NL-11-0141, Revised Tables from Responses to Requests for Additional Information Regarding Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions
NL-11-007, Response to December 16, 2010 Request for Additional Information Regarding Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions
NL-11-006, Response to December 16, 2010 Request for Additional Information Regarding Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions
NL-10-107, (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22
NL-11-065, Indian Point, Units 2 & 3, NEI 99-01, Revision 5, Methodology for Development of Emergency Action Levels, February 2008.
NL-10-123, Program for Maintenance of Irradiated Fuel and Preliminary Decommissioning Cost Analysis in Accordance with 10 CFR 50.54 (Bb) and 10 CFR 50.75(f)(3)
NL-10-100, Response to August 11, 2010 Request for Additional Information Regarding Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2
NL-10-101, Response to August 11, 2010 Request for Additional Information Regarding Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual
NL-10-072, Proposed Technical Specification Change Regarding RWST Surveillance Requirement
NL-10-093, Response to Request for Additional Information Re Inter-Unit Spent Fuel Transfer License Amendment Request
NL-10-096, Notification Letter Designating Balance of Plant Systems within the Cyber Security Rule Scope
NL-10-074, Response to Request for Additional Information Regarding Generic Letter 2004-02
NL-10-075, Submittal of Revision 10 to Physical Security, Training and Qualification, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program
NL-10-049, Submittal of Revision 9 to Physical Security, Training and Qualification, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program
NL-10-043, Response to January 20, 2010 Request for Additional Information Regarding Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions for Indian Point Unit 3
NL-10-042, Response to January 20, 2010 Request for Additional Information Re Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions
NL-09-168, Request for Delay to Answers NRC Orders EA-09-204 and EA-09-205 Imposing Increased Controls and Fingerprinting and Criminal History Records Check Requirements on Power Reactor Licensees Undergoing Decommissioning
NL-09-170, Response to Request for Additional Information Regarding Amendment Application for Battery Capacity Surveillance Requirement
NL-09-132, Submittal of Revision 8 to Physical Security, Training and Qualification, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program
NL-09-144, Proposed Technical Specification Change Regarding Ventilation Filter Testing Program
NL-09-138, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
NL-09-142, Request for Additional Information Regarding Response to Generic Letter 2008-001
NL-09-141, Submittal of Response to Request for Supplemental Information Regarding the Spent Fuel Transfer License Amendment
NL-09-100, Response to Request for Supplemental Information Regarding the Spent Fuel Transfer License Amendment Request
NL-09-116, Revision to Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions
NL-09-117, Revision to Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions
NL-08-144, Program for Maintenance of Irradiated Fuel and Preliminary Decommissioning Cost Analysis in Accordance with 10 CFR 50.54 (Bb) and 10 CFR 50.75(f)(3)
NL-09-099, Request for Extension of Completion Dates for Indian Point, Units 2 and 3 Corrective Actions Required by Generic Letter 2004-02, 'Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-W
NL-09-062, Proposed Technical Specification Change Regarding RWST Surveillance Requirement
NL-09-068, Reply to Request for Additional Information Regarding Decommissioning Cost Estimate and Irradiated Fuel Management Program
NL-09-082, Withdrawal of Request for License Amendment for Submittal of ISI Information and Analyses Regarding Extension of In-Service Inspection Interval for the Reactor Vessel Weld Examination
NL-09-075, Generic Letter 2008-001, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Nine Month Supplemental (Post Outage) Response
NL-09-070, Response to Request for Additional Information Regarding Amendment Application for Revised Reactor Vessel Heatup and Cooldown Curves
NL-09-059, Proposed License Amendment Request to the Allowable Completion Time for Offsite AC Sources
NL-09-054, Foreign Obligations Regarding Replacement Reactor Vessel Closure Heads
NL-09-0464, Supplement to the Proposed License Amendment Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Over Pressure Requirements (ME0788)
NL-08-173, Letter to U.S. NRC Document Control Desk, from: J.E. Pollock, Site Vice President, Indian Point Energy Center, Notification of Unit 1 Transfer of 160 Spent Fuel Assemblies from the Spent Fuel Pool to the Indian Point ISFSI
NL-09-038, Submittal of Revision 7 to Physical Security, Training and Qualification, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Cover Letter
NL-09-001, Proposed Change to Technical Specifications Regarding Battery Capacity Surveillance Requirement
NL-09-004, License Amendment Request Regarding Surveillance Requirements for ECCS Valves Required to Be in Position with Power to the Valve Operator Removed
NL-09-031, Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions
NL-09-032, Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions
NL-09-010, Reply to Request for Additional Information Regarding Proposed Changes to Technical Specifications on Diesel Generator Endurance Test Surveillance
NL-09-021, Response to Request for Additional Information Regarding Generic Letter 2004-02
NL-09-009, Response to Request for Additional Information on License Amendment to Allowable Completion Time for Offsite AC Sources
NL-08-171, Planned Replacement of Internal Recirculation Pump Bearings in Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
NL-08-163, (IP2) - Transmittal of Amendment Update to the Final Safety Analysis Report (Fsar), Revision 21
NL-08-153, Request for Extension of Completion Dates for Indian Point Units 2 and 3 Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wat
NL-08-136, Nine Month Response to NRC Generic Letter 2008-001, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
NL-08-157, Supplement to Reply to Request for Additional Information Regarding Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance
NL-08-147, Notification of Delay of Submittal of Program for Maintenance of Irradiated Fuel and Preliminary Decommissioning Cost Analysis in Accordance with 10 CFR 50.54 (Bb) and 10 CFR 50.75 (f)(3)
NL-08-1453, Registration of Unit 1, Spent Fuel Cask Use
NL-08-123, License Amendment Request Application for Licensee Name Changes to Equagen Nuclear LLC and Enexus Nuclear Indian Point 2, LLC
NL-08-124, License Amendment Request Application for License Name Changes to Equagen Nuclear LLC and Enexus Nuclear Indian Point 2, LLC
NL-08-139, Reply to Request for Additional Information, Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance
NL-08-137, Reply to Request for Additional Information Regarding Amendment Application on Control Room Envelope Habitability
NL-08-133, Registration of Spent Fuel Cask Use
NL-08-115, Reply to Request for Additional Information Regarding Bulletin 2007-01, Security Officer Attentiveness.
NL-08-094, Exigent License Amendment Request to the Allowable Completion Time for Offsite AC Sources
NL-08-106, Reply to Request for Additional Information Regarding Surveillance Requirements for ECCS Valves Required to Be in Position with Power to the Valve Operator Removed
NL-08-101, Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance
NL-08-096, Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License Amendment for Submittal of ISI Information and Analyses
NL-08-0522, License Amendment Request Regarding Removal of Spent Fuel from Unit I and Drain Down of the Spent Fuel Pool (LAR for Amendment 54)
NL-08-093, Proposed Directors Decision Under 10 CFR 2.206 on the Friends United for Sustainable Energy Petition
NL-08-080, Letter Supplemental Information Associated with the Assessment of Safety Culture (Indian Point Units 2 and 3)
NL-08-058, Letter Assessment of NRC Safety Culture (Indian Point Units 2 and 3)
NL-08-082, Revised Action Plan to Address the Procedure Adequacy Substantive Cross-Cutting Issue for Indian Point Units 2 & 3
NL-08-079, Remediation and Long Term Monitoring of Site Groundwater
NL-08-065, Three Month Response to NRC Generic Letter 2008-001, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems
NL-08-054, Request for Extension of Completion Dates for Indian Point, Units 2 & 3, Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wat
NL-07-129, Proposed Changes to the Technical Specifications Regarding Replacement of the Sodium Hydroxide Buffer with Sodium Tetraborate Decahydrate
NL-08-025, Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
NL-08-035, Reply to Request for Additional Information (RAI) Regarding Indian Point 1 License Amendment Request (LAR) for Handling Building Crane
NL-08-029, Transmittal of Indian Point, Unit 1, 2 and 3, Response to NRC Bulletin 2007-01, Security Officer Attentiveness.
NL-08-027, Registration of Spent Fuel Cask Use
NL-08-030, Response to Request for Additional Information Regarding the 2007 Steam Generator Tube Inspections
NL-08-001, Notification of Commencement of Dry Cask Storage Campaign
NL-11-114, Response to RAI on Application for Preemption Authority Pursuant to Section 161A of the Atomic Energy Act
05000247/LER-2011-003, Regarding Technical Specification (TS) Violation for Entry Into TS 3.0.3 for 3 Inoperable Fan Cooler Unit Trains and Failure to Correct within 1 Hour and Actions Taken for Plant Shutdown
05000247/LER-2011-002, Regarding Technical Specification (TS) Prohibited Condition Caused by an Inoperable 21 Service Water Pump for Greater than TS AOT Due to a Faulty Inertia Latch in the Supply Breaker
05000286/LER-2011-005, Indain Point, Unit 3 Regarding Automatic Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps Due to Undervoltage on 480 Vac Vital Buses Due to a Loss of Offsite Power During a Severe Storm
05000286/LER-2011-004, Ctr Technical Specification Prohibited Condition Caused by Two Main Steam Safety Valves Outside Their As-Found Lift Setpoint Test Acceptance Criteria
05000247/LER-2011-001, Regarding Automatic Actuations of Emergency Diesel Generators Due to Undervoltage on 480 Vac Vital Buses 5A and 6A Caused by a Loss of Offsite Power During Switchyard Troubleshooting
05000286/LER-2011-002, Regarding Technical Specification Prohibited Condition Caused by an Inoperable 31 Battery Charger Due to Low Voltage Caused by a Degreased Gate Driver Board
05000286/LER-2011-003, For Indian Point Unit 3, Regarding Technical Specification Required Shutdown and a Safety System Functional Failure for a Leaking Service Water Piper Causing Flooding in the SW Valve Pit Preventing Access for Accident Mitigatio
05000286/LER-2011-001, Regarding Technical Specification Prohibited Condition Caused by an Inoperable 32 Containment Spray Pump Due to High Contact Resistance in the Supply Breaker Closing Circuit
05000247/LER-2010-009, Regarding Automatic Reactor Trip Due to a Turbine-Generator Trip Caused by a Fault of the 21 Main Transformer Phase B High Voltage Bushing
05000247/LER-2010-008, For Indian Point Unit 2, Regarding Safety System Functional Failure Due to Inoperable Refueling Water Storage Tank Low-Low Level Alarms
05000286/LER-2010-002, Regarding Manual Reactor Trip Due to a Cooling Water Leak in the Main Generator Exciter Air Cooler
05000247/LER-2010-007, Regarding Automatic Reactor Trip Due to a Turbine Trip as a Result of a High Steam Generator Level Trip After Transition to Single Feedwater Pump Operation
05000247/LER-2010-006, For Indian Point 2, Regarding Safety System Functional Failure Due to Inoperable Reactor Coolant Loop 21 and 22 Wide Range Hot Leg Temperature Indicators Credited for Remote Shutdown Per Technical Specification 3.3.4
05000247/LER-2010-005, For Indian Point, Unit 2, Regarding Technical Specification Prohibited Condition Due to an Inoperable Control Room Ventilation System Caused by a Closed Normally Open Damper
05000247/LER-2010-004, Regarding Plant Operation Outside Technical Specifications Due to a Leak in the Reactor Coolant Pressure Boundary
05000247/LER-2010-003, Regarding Inoperable Emergency Diesel Generators During Refueling Shutdown Due to Inadvertent Isolation of Service Water Cooling Caused by Failure to Properly Verify the In-Service Cooling Header
05000286/LER-2010-001, Regarding SSFF and TS Violation for an Inoperable RCS Wide Range Temperature Cold Leg Instrument TE-413B Credited for TS 3.3.4 Remote Shutdown
05000247/LER-2010-002, For Indian Point 2, Regarding Technical Specification Prohibited Condition Caused by Two Main Steam Safety Valves Outside As-Found Lift Setpoint Test Acceptance Criteria
05000247/LER-2010-001, Regarding Automatic Reactor Trip as a Result of a Turbine-Generator Trip Due to a Loss of Generator Field Excitation Caused by a Failed Exciter Rectifier
05000247/LER-2009-005, Automatic Reactor Trip Due to a Turbine-Generator Exciter Protective Trip Caused by a Loss of the Generrex Power Supply Monitored Voltage Due to a High Resistance Ground Connection
05000286/LER-2009-009, Regarding Loss of Single Train Neutron Flux Detector N-38 Required for Plant Shutdown Remote from the Control Room Due to a Power Supply Failure
05000286/LER-2009-008, Technical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for an Inoperable Over Power Delta Temperature (Opdt) Bistable
05000286/LER-2008-006, Automatic Actuation of an Emergency Diesel Generator and Two Auxiliary Feedwater Pumps During Surveillance Testing Due to Inadvertent De-Energization of the Normal Supply Breaker to 480 Volt Safeguards Bus 6A
05000286/LER-2009-007, Regarding Automatic Reactor Trip Due to a Turbine as a Result of Turbine Autostop Oil Actuation Caused by a Failed Autostop Oil Fitting
05000286/LER-2009-006, Re Automatic Trip Due to a Turbine-Generator Trip Caused by Actuation of the Generator Protection System Lockout Relay During a Severe Storm with Heavy Lightning
05000286/LER-2009-005, Regarding Technical Specification Prohibited Condition Due to Exceeding Allowed Completion Time for an Inoperable 480 Volt Undervoltage/Degraded Grid Relay Caused by Personal Error
05000247/LER-2009-004, For Indian Point 2, Regarding Loss of Single Train 23 Charging Pump Required for Remote Plant Shutdown from the Control Room Due to a Failure of a Pump Internal Check Valve
05000247/LER-2009-003, Regarding Loss of Single Train 21 Pressurizer Backup Heater Required for Remote Plant Shutdown from the Control Room Due to an Inoperable Breaker
05000286/LER-2009-003, Regarding Manual Reactor Trip Due to Steam Generator 33 High Water Level Caused by a Failed 33 Main Feedwater Regulating Valve
05000247/LER-2009-002, Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by a Loss of Main Feedwater Pump 21 and Failure of the Main Turbine to Automatically Runback
05000286/LER-2009-002, Regarding Technical Specification Prohibited Condition Caused by Two Main Steam Safety Valves Outside Their As-Found Lift Setpoint Test Acceptance Criteria
05000247/LER-2009-001, Re Technical Specification Prohibited Condition Due to a Surveillance Requirement Never Performed for the Atmospheric Steam Dump Valve Local Nitrogen Controls
05000286/LER-2009-001, Regarding Automatic Actuation of an Emergency Diesel Generator & Two Auxiliary Feedwater Pumps During Surveillance Testing Due to Inadvertent De-Energization of Normal Supply Breaker to 480 Volt Safeguards Bus 6A
05000286/LER-2008-005, Regarding Technical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for an Out of Position Valve Caused by Personnel Error
05000286/LER-2008-004, Automatic Actuation of the Motor Driven Auxiliary Feedwater Pumps During Surveillance Testing Caused by Incorrect Test Jumper Connection Due to Personnel Error
NL-08-160, Proposed Exigent License Amendment to Revise Technical Specification Surveillance Requirement 3.8.1.10 Frequency Regarding Diesel Generator Endurance Test
05000003/LER-2008-001, Attempted Introduction of Contraband Into the Plant Protected Area Due to Personnel Error
05000247/LER-2008-003, Re Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by a Main Turbine Runback Due to a Failed Runback Circuit Bistable with a Control Switch Mis-Positioned to Armed
05000247/LER-2008-002, Re. Technical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for an Inoperable Engineered Safety Feature Actuation System Automatic Actuation Logic & Actuation Relay Caused
05000247/LER-2008-001, Regarding Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by Loss of Feedwater Flow as a Result of Feedwater Pump Speed Control Malfunction
05000286/LER-2008-003, Regarding Automatic Actuation of Emergency Diesel Generator 33 During Surveillance Testing Caused by Inadvertent Actuation of the Undervoltage Sensing Circuit on 488 Volt AC Safeguards Bus 5A
05000286/LER-2008-002, Regarding Loss of Single Train 31 Pressurizer Backup Heater Bank Required to Function to Shutdown and Maintain the Reactor in a Safe Condition Remote from Control Room
05000286/LER-2008-001, Regarding Technical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for an Inoperable Safety Injection Pump Caused by a Failed Motor Supply Breaker
05000286/LER-2007-003, Re Technical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for an Inoperable Recirculation Pump Caused by a Potential Strong Pump-Weak Pump Interaction During a Small Break LOCA
05000247/LER-2007-005, Re Technical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for an Inoperable Recirculation Pump Caused by a Potential Strong Pump-Weak Pump Interaction During a Small Break LOCA
NL-08-176, Submittal of Revision 6 of Indian Point Units 1, 2, & 3, Physical Security, Training and Qualification Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program
05000318/LER-2007-001, Re Channel C Linear Range Nuclear Instrument Inoperable During Startup
05000318/LER-2006-001, Regarding Reactor Trip During Performance of Maintenance Clearance Order
05000317/LER-2006-005, Re Startup Rate Trip Bypass Enabling Function Below Setpoint
05000317/LER-2006-004, Re Reactor Trip Due to Loose Wire During Maintenance on Turbine Control System
05000317/LER-2007-001, Regarding Reactor Coolant System Pressure Boundary Leakage in Pump Cover Heat Exchanger
05000317/LER-2006-003, Re Impact on Safety-Related Equipment Not Considered When High Energy Line Break Barrier Removed
05000317/LER-2006-002, Regarding Control Element Assembly Determined to Be Untrippable
05000317/LER-2006-001, Re 1A Diesel Generator Feeder Breaker Tripped Due to Low Design Setpoint
05000317/LER-2005-003, Overpower Condition Resulting from Non-Conservative Flow Correction Factors
05000315/LER-2003-003, From Cook, Unit 1 Regarding Dual Unit Manual Trip Due to Failure of Intake Traveling Screens & Failure to Comply with TS 3.8.1.1
05000316/LER-2003-004, From Cook, Unit 2, Regarding Weight of Ice Basket Below Minimum Allowed in TS 3.6.5.1
05000316/LER-2003-003, Technical Specification 3.7.1.2 Limiting Condition for Operation Exceeded for Auxiliary Feedwater System
05000316/LER-2003-002, Re Reactor Trip to Instrument Rack 24 Vdc Power Supply Failure
05000315/LER-2003-002, Technical Specification 3.3.3.1 Required Special Report for Inoperable Radiation Monitor 1-MRA-1701
05000316/LER-2003-001, Shutdown in Accordance with Technical Specification 3.8.1.1, A.C. Sources, Action B
05000316/LER-2002-007, Re Technical Specification 3.8.1.1 Allowed Outage Time Exceeded
05000316/LER-2002-006, Regarding Reactor Trip Due to Low Condenser Vacuum
05000315/LER-2002-007, Technical Specification 3.3.3 1 Required Special Report for Inoperable Radiation Monitors
05000315/LER-2002-006, Switchyard Fire Results in Violation of Technical Specification 3.0.5
05000316/LER-2002-005, On May 12,2002 Unit 2 Tripped Due to Instrument Rack 24-Volt DC Power Supply Failure
05000316/LER-2002-003, Re Battery Inoperable for Longer than Allowed by Plants Technical Specification
05000315/LER-2002-002, Pressurizer Power Operated Relief Valves Inoperable Due to Control Switch Position
05000316/LER-2002-002, Technical Specification 3.9.4.c Was Violated During Core Alteration
05000315/LER-2002-001, Re Failure to Perform Ice Condenser Door Testing in Accordance with Technical Specifications
05000316/LER-2002-004, Re Unanticipated Start of the Turbine Drive Auxiliary Feedwater Pump
05000315/LER-1999-012-01, Re Auxiliary Building ESF Ventilation System May Not Be Capable of Maintaining ESF Room Temperature Post-Accident
05000316/LER-2002-001, Containment Isolation Valve Alignment Error During Local Leak Rate Testing
05000316/LER-2001-003-01, Degraded ESW Flow Renders Both Unit 2 Emergency Diesel Generators Inoperable
05000315/LER-2001-005-01, Rcca Tool Over Spent Fuel Pool Racks Technical Specification Violation
NL-11-036, Submittal of Revision 11 to Physical Security, Training and Qualification, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation, Security Program