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Recasha Mitchell
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NRC Headquarters
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CY-16-027, Comment (2) of Robert Mitchell on Behalf of Connecticut Yankee Atomic Power Company Regarding Draft Standard Review Plan on Foreign Ownership, Control, or Domination, Revision 1
CY-16-014, Comment (094) of Robert Mitchell on Behalf of Connecticut Yankee Atomic Power Co on ANPR-26, 50, 52, 73, and 140 - Regulatory Improvements for Decommissioning Power Reactors
CY-16-006, ISFSI - Annual Notification of Foreign Ownership, Control, or Influence (FOCI) Status
CY-16-002, ISFSI - Revision 5 of the Post-Shutdown Decommissioning Activities Report
CY-15-043, ISFSI - Revision 13 to the Emergency Plan
NRC-2013-0195, Comment (6) of Robert M. Mitchell, on Behalf of Yankee Atomic Electric Co., on Proposed Rulemaking and Guidance, Amendments to Material Control and Accounting Regulations
NRC-2013-0004, Comment (12) of Robert M. Mitchell, of the Yankee Atomic Electric Company, on Retrievability, Cladding Integrity and Safe Handling of Spent Fuel at an Independent Spent Fuel Storage Installation and During Transportation
05000029/LER-1977-035-03, /03L-0:on 770627,discovered That Four of Eight Thermocouple Locations on Boron Injection Flow Path Were Less than 150 F.Caused by Leakage from Purification Sys Through Three Valves to SI Tank.Valves Repaired
05000029/LER-1977-033-03, /03L-0:on 770620,discovered That Five of Eight Thermocouple Locations on Boron Injection Flow Path Were Less than 150 F.Caused by Leakage from Purification Sys Through Three Valves to SI Tank.Valves Repaired
05000029/LER-1977-055-03, /03L-0:on 771217,during 12-h Shutdown for Operator Training,Dose Equivalent I-131 Concentration of Primary Coolant Sys Exceeded Tech Spec.Cause Assumed to Be Cladding Defect in Single Fuel Rod
05000029/LER-1977-043-03, /03L-0:on 770810,during Refueling,Pressurized Wide Range Level Scram Setpoint Discovered Out of Tolerance. Caused by Instrument Drift.Setpoints Were Readjusted
05000029/LER-1977-031-03, /03L-0:on 770609,loop Seal Radiation Monitor Pegged at Low End of Scale.Caused by RM-40 Power Supply High Voltage Tripping.Voltage Adjusted
05000029/LER-1977-029-03, /03L-0:on 770603,during Mode 1,primary Vent Stack Radiation Detection Sys Particulate Channel Failed.Caused by Control Setpoint Being Set Too Close Together.Control Setpoint Readjusted
05000029/LER-1977-028-03, /03L-0:on 770530,noble Gas Monitor of Primary Vent Stack Radiation Detection Sys Failed.Cause Could Not Be Ascertained as Trouble Could Not Be Repeated After Alarm Reset
05000029/LER-1977-023-03, /03L-0:on 770425,net Decrease in Sys Vol Found. Sys Check Performed & Leaking Diaphragm Valve Discovered.Caused by Petroleum Based Substance on Valve. Diaphragm Replaced
05000029/LER-1977-027-03, /03L-0:on 770524,biannual Recalibr Performed on Two LPIS Accumulator Channels.Instruments Below Tech Specs Limit.Recalibr Adjustments Made to Bring Channels within Tech Specs Limit
05000029/LER-1977-025-03, /03L-0:on 770503,when Component Cooling Radiation Monitor Channel Drawer Removed,Cables Dropped Into Uncovered High Voltage Power Supply Used for Loop Seal Discharge Monitor Causing Short Circuit & Failure of Monitor
05000029/LER-1977-019-03, /03L-0:on 770402,radioactive Gaseous Waste Monitor Loop Seal Discharge Monitor Alarm Failed to Operate.Caused by Alarm Setpoint & Meter Pointer Contacts Being Corroded. Contacts Cleaned,Mylar Film & Protective Tape Replaced
05000029/LER-1977-017-03, /03L-0:on 770324,following Plant Trip,Chlorides in Steam Generator 4 Exceeded Tech Specs Limits.Caused by Impurities Released in Bulk Water
05000029/LER-1977-021-03, /03L-0:on 770420,air Mass Calculation Performed on 770419 Indicated That Significant Leak in Primary Containment Might Exist.Data Point Indicated That VC Air Pressure Had Fallen.No Leak Found,Reactor Cooled Down
05000029/LER-1977-015-03, /03L-0:on 770311,reading of built-in Source Check of Main Coolant Leak Detection Vapor Container Air Particulate Monitor Found Indicating Low & Declared Inoperative.Caused by High Voltage & Control Drift