1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) | 8 June 2023 | Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) | Probabilistic Risk Assessment Power change |
0CAN042301, Radioactive Effluent Release Report for 2022 | 14 April 2023 | Radioactive Effluent Release Report for 2022 | Time of Discovery Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Annual Radiological Effluent Release Report Tritium |
1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure | 30 March 2023 | License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure | Boric Acid Anticipated operational occurrence Safe Shutdown Earthquake Hydrostatic Operating Basis Earthquake Maintenance Rule Program |
2CAN122103, Relief Request ANO2-RR-21-002, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Submittal of Analyses - Affidavits and Calculation Summary Sheet | 19 November 2021 | Relief Request ANO2-RR-21-002, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Submittal of Analyses - Affidavits and Calculation Summary Sheet | Boric Acid Non-Destructive Examination Hydrostatic |
ML14309A187 | 31 October 2014 | Structural Integrity Associates, Inc. Calculation 1401289.301, ANO Leaking Flaw Evaluation, Revision 0 | Through-Wall Leak Dissimilar Metal Weld |
ML14309A190 | 31 October 2014 | Attachment 2, Calculation 1401289.301, Revision 0, ANO Leaking Flaw Evaluation. | Through-Wall Leak Dissimilar Metal Weld |
ML14307A911 | 30 April 2014 | Calculation 32-9207374-000, Arkansas Nuclear One Flooding Hazard Re-Evaluation - Probable Maximum Precipitaion, Rev 18 | |
0CAN041104, Annual Radioactive Effluent Release Report for 2010 | 29 April 2011 | Annual Radioactive Effluent Release Report for 2010 | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Annual Radiological Effluent Release Report |
1CAN041105, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05 Relief Request ANO1-R&R-016 | 20 April 2011 | Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05 Relief Request ANO1-R&R-016 | Non-Destructive Examination Weld Overlay Nondestructive Examination Liquid penetrant Through-Wall Leak |
ML100630091 | 25 February 2010 | Offsite Dose Calculation Manual | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Annual Radiological Effluent Release Report |
ML090641023 | 26 February 2009 | Attachment 2 to 0CAN020901, Offsite Dose Calculation Manual, Revision 16 | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Annual Radiological Effluent Release Report |
ML060110063 | 3 January 2006 | Supplement to Amendment Request, Revision of the Allowable Value for Emergency Feedwater Initiation and Control Function (Efic), Enclosure 1, Calculation, EFIC System Loop Error and Setpoint Analysis | |
1CAN010603, Supplement to Amendment Request, Revision of the Allowable Value for Emergency Feedwater Initiation and Control Function (Efic), Enclosure 1, Calculation, Efic System Loop Error and Setpoint Analysis | 3 January 2006 | Supplement to Amendment Request, Revision of the Allowable Value for Emergency Feedwater Initiation and Control Function (Efic), Enclosure 1, Calculation, Efic System Loop Error and Setpoint Analysis | |
ML050660191 | 15 December 2004 | Offsite Dose Calculation Manual (014-03-0) | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program |
ML060610166 | 15 December 2004 | Offsite Dose Calculation Manual Arkansas Nuclear One, Revision 014-03-0 | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program |
ML040630154 | 31 December 2003 | Offsite Dose Calculation Manual, Attachment 2 to 0CAN020405 | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report |
CNRO-2002-00058, Proposed Alternative to ASME Examination Requirements for Repairs Performed on Reactor Vessel Head Penetrations | 16 December 2002 | Proposed Alternative to ASME Examination Requirements for Repairs Performed on Reactor Vessel Head Penetrations | Non-Destructive Examination Finite Element Analysis |
ML040440473 | 4 November 2002 | to 86-E-0074-160, Weld Anomaly Considerations in the B&W CRDM Id Temper Weld Repair. | |
ML040440457 | 30 October 2002 | to 86-E-0074-164, Evaluation of Potential for Loose Parts in the RCS from the CRDM Idtb Repair. | |
ML040680538 | 19 September 2002 | Fax to Pruett from Walker Icwclgiso Worksheets & Revised P7AMANREC | |
ML040640736 | 14 March 2002 | Calculation Cover Sheet, Calculation 02-E-0004-02, Rev. 0, Zone 98-J PSA Analysis for Operator Action SDP | Hot Short Fire Barrier Significance Determination Process |
ML040640734 | 1 March 2002 | Calculation 02-E-0004-01, Rev. 0, Zone 99-M PSA Analysis for Operator Action SDP | Significance Determination Process |
ML040680541 | 15 February 2002 | Calculation Submittal Sheet, Calculation 02-E-0004-01, Rev. 1, Zone 99-M PSA Analysis for Operator Action SDP | Fire Barrier Significance Determination Process |