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 Issue dateTitleTopic
ML13323A5508 November 2013Attachment 1 to GNRO-2013/00088 JC-Q1P81-90024 Rev. 3 Division III Degraded Bus Voltage Setpoint
ML13323A5544 November 2013Attachment 5 to GNRO-2013/00088, EN-IC-S-022-G Rev. 0 Instrument Performance Monitoring and Drift Trending AnalysisOffsite Dose Calculation Manual
Scram Discharge Volume
ML13323A55329 October 2013Attachment 4 to GNRO-2013/00088, JC-Q1B21-N694-1 Rev. 1 Drywell High Pressure RCIC Isolation Setpoint CalculationGrace period
ML13323A55214 October 2013Attachment 3 to GNRO-2013/00088, JC-Q1B21-N681-1 Rev. 1 Reactor Pressure Vessel Level One Setpoint CalculationFuel cladding
Grace period
ML13323A5518 October 2013Attachment 2 to GNRO-2013/00088, JC-Q1B21-N678-1 Rev. 2 Reactor Steam Dome Pressure Scram SetpointGrace period
ML12157A45023 May 2012Attachment 50 to GNRO-2012/00039 Enercon. 2011 B. Evaluation of Potential Air Emissions from Coal and Natural Gas Fired
ML12157A26323 May 2012Attachment 18 to GNRO-2012100039, Er Reference - Bechtel. 1986. Bechtel, Radial Wells 1, 3, 5 - Reduction of Multiple Well Test Data (Geotech Calc G-035). Approved July 31, 1986
ML09131001728 April 2009Offsite Dose Calculation Manual, Attachment IIHigh Radiation Area
Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Power change
ML07255024527 July 2006GGNS Calculation JC-Q1E51-N635-1, Rev. 1, Instrument Loop Uncertainty and Setpoint Determination for Loops 1E51-N635A&E RCIC Pump Suction Transfer on Low CST Level (TS 3.3.5.2).Stroke time
ML07255024426 July 2006GGNS Calculation JC-Q1E22-N654-1, Rev. 3, Instrument Loop Uncertainty and Setpoint Determination for Loops 1E22-N654C&G HPCS Pump Suction Transfer on Low CST Level (TS 3.3.5.1).
ML07255024727 March 2006GGNS Calculation M6.7.013, Rev. 1, Condensate Storage Tank Reserve Capacity.Stroke time
GNRO-2004/00057, Response to Request for Additional Information for Proposed Upgraded Emergency Action Levels (Eals) Using NEI 99-01 Revision 4 Methodology19 November 2004Response to Request for Additional Information for Proposed Upgraded Emergency Action Levels (Eals) Using NEI 99-01 Revision 4 MethodologySafe Shutdown
High winds
Reactor Vessel Water Level
Ultimate heat sink
Offsite Dose Calculation Manual
Safe Shutdown Earthquake
Internal Flooding
Met Tower
Operating Basis Earthquake
Design basis earthquake
Safeguards Contingency Plan
Earthquake
Fuel cladding
Pressure Boundary Leakage
Unidentified leakage
Failure to Scram
ML09231067426 September 2003Calculation No. 32-5029393-00, Commercial Reactor Reactivity Analysis for Grand Gulf, Unit 1.Fuel cladding