H.6-28a-29
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H.6(a)
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05000251/LER-2001-001
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ONS-2017-006, Emergency Plan Revision 2016-003
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NRC-17-0019, Submittal of Revision 47 to the Fermi 2 Radiological Emergency Response Preparedness (RERP) Plan
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ONS-2017-030, Emergency Plan Revision 2017-002. Part 2 of 2
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LIC-17-0041, Independent Spent Fuel Storage Installation - Revision to Emergency Plan Update
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ONS-2017-071, Emergency Plan Revision 2017-003, Figure P1
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LIC-17-0076, EP-FC-1001 Revision 3, Post-Shutdown Radiological Emergency Response Plan for Fort Calhoun Station
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JAFP-13-0074, Emergency Plan and Implementing Procedures
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CNS-17-056, Emergency Plan, Revision 17-2, Section P, Responsibility for the Planning Effort
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NLS2105025, 10 CFR 50.55a Requests for Fifth Ten-Year Inservice Inspection Interval
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L-PI-14-071, July 21, 2014 ML14204A052
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NRC-14-0006, Submittal of Revision 43 to the Fermi 2 Radiological Emergency Response Preparedness (RERP) Plan
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RBG-47362, Request for Alternative in Accordance with 10 CFR 50.55a(a)(3)(i) Use of Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
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L-12-457, Emergency Plan and Implementing Procedures
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BVY 11-024, Deviation from BWRVIP-25 Inspection Requirements
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RBG-47827, Request for Alternative in Accordance with 10 CFR 50.55a(z)(1) Use of Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements (RR- RBS-ISI-019)
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ONS-2017-030, Oconee Nuclear Station Emergency Plan Revision 2017-002. Part 1 of 2
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NL-15-0820, Farley, Units 1 and 2 - Emergency Plan, Revision 64, Part 1 of 3
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NL-13-0053, Joseph M. Farley, Units 1 and 2, Emergency Plan, Rev. 58. Cover Through Page J-11
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RA-09-039, Biennial 10 CFR 50.59 and 10 CFR 72.48 Summary Reports for Period 1/1/2007 Through 12/31/2008
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1CAN030906, Deviation from EPRI Guideline Steam Generator Chemistry Specification
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1CAN010904, Deviation from EPRI Guideline - Steam Generator Chemistry Specification
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ONS-2016-085, Submittal of Emergency Plan Revision 2016-002
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RS-07-134, Co. and Amergen Energy Co., LLC, Response to Request for Additional Information Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
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NL-18-1480, Response to NRC Request for Additional Information on Alternative Request (HNP-ISI-ALT-05-04)
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RA-19-0190, Attachments 1, 2 & 3 - Emergency Plan 10CFR 50.54(q) Evaluation and Screen, Plan Update Instructions and Emergency Plan Revision 19-03
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RNP-RA/01-0027, Transmittal of Emergency Procedure Revisions
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DCL-19-093, Independent Spent Fuel Storage Installation - Emergency Plan Facilities and Equipment Update, Section 7
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NRC-20-0005, Submittal of Revision 49 to the Fermi 2 Radiological Emergency Response Preparedness Plan
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BSEP-96-0432, Submits Results of Core Shroud re-insp Completed During Refueling Outage 10 (B111R1).Cracking Is Typical IGSCC in Heat Affected Zone of Welds.Forwards Rev 0 to ESR 96-00160, ...Evaluation,B111R1 Core Shroud Insp
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DCL-21-012, Spent Fuel Storage Installation, Emergency Plan Update
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3F0798-06, Forwards Summary of Scope & Objectives for 1998 Annual Radiological Emergency Response Plant Exercise to Be Held on 981014 at Crystal River,Unit 3
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A05027, Forwards Addl Info Re 850102 Draft 2 to Rev 0 of Emergency Plan,Per 850520 & 0701 Requests.Responses to Items Identified in NRC 850722-26 Emergency Preparedness Appraisal Also Encl.Rev 0 of Plan to Be Submitted by 850913
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NOC-AE-00013, Forwards Onsite & Offsite Objectives & Exercise Participation Guidelines (Extent of Play) for Graded Er Exercise on 980805 for Review.Scenario Will Be Forwarded 60 Days Prior to Exercise IAW NRC IP 82302
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IR 05000346/1986019
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BSEP-95-0192, Forwards Revised Insp Scope & Associated Technical Basis for Core Shroud Welds H6a & H6b
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0CAN128305, Documents Results of Activities Conducted During 831031-1104 IE Insp to Review Open Items Re Emergency Planning. Commitment Status to Resolve Items Provided.Expeditious Actions by NRC to Remove Items Requested
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LIC-90-0664, Forwards Objectives for 1990 Emergency Preparedness Exercise
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LER-1984-010-02, :on 840901,reactor Control Rods from More than One Bank Withdrawn at Same Time.Caused by Procedural Deficiency.Main Reactor Trip Breakers Opened.Procedures Revised to Guard Against Similar Occurrences
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IR 05000029/1981020
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LIC-93-0094, Forwards Scope & Objectives for Plant 1993 EP Exercise on 930629.Informs That Complete Scenario Package Will Be Submitted to NRC & FEMA by 930430
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LER-1993-004-01, :on 930316,broken Fuel rod,11-12 Inches in Length,Protruded Out of Fuel Assembly F67 at Core Position FH-6.Caused by Grid to Rod Fretting Failures.Util Evaluating Fluid Elastic Instability
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TXX-3389, Forwards Response to NRC Re Discrepancies in Emergency Plan.Info Will Be Incorporated Into Plan Revision
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ML20100R196
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1989-003:on 891030,31 & 1107,tendon Grease Deficiencies Noted During Combined Tendon Surveillances.No Corrosion or Cracks Found.Tensile Test Results for Strand Samples Expected by End of Dec 1989
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label: ELV-01105, Special Rept 50-424/1989-003:on 891030,31 & 1107,tendon Grease Deficiencies Noted During Combined Tendon Surveillances.No Corrosion or Cracks Found.Tensile Test Results for Strand Samples Expected by End of Dec 1989
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NRC-23-0077, Submittal of Revision 50 to the Fermi 2 Radiological Emergency Response Preparedness Plan
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NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station
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JAFP-23-0064, Emergency Plan Document Revision
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NMP1L3486, Radiological Emergency Plan Document Revision
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ML18041A297
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Demand Indication.Caused by Temp Variation in Indications Inherent to Sys design.In-core Flux Maps Performed & Indications Adjusted
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label: 05000251/LER-1992-001-01, :on 920202,discovered That Rod Cluster Control Indicators Not in Agreement W/Demand Indication.Caused by Temp Variation in Indications Inherent to Sys design.In-core Flux Maps Performed & Indications Adjusted
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IR 05000387/1995022
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LIC-17-0063, EP-FC-1001, Rev. 2, Post-Shutdown Radiological Emergency Response Plan
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05000327/LER-1916-009-01, Regarding Manual Reactor Trip During Startup Due to a Control Rod Misalignment
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ML17059B542
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HNP-15-009, 3 to Emergency Plan Procedure PLP-201, Emergency Plan
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RNP-RA/04-0011, To EPJIC-06, Joint Information Center Generic Information, and Revision 15 to EPPRO-01, Program Responsibilities
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NRC-24-0020, Submittal of Revision 51 to the Fermi 2 Radiological Emergency Response Preparedness Plan
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ML093370764
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ST-HL-AE-1643, Forwards Response to Gw Knighton Transmitting Comments on Emergency Plan.Encl Rev 2 to Emergency Plan Includes Draft Tables Which Will Be Revised by 860501.NRC Response Expected by 860523
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IR 05000498/1986006
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ML20136A542
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IR 05000219/1990005
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IR 05000313/1981022
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Cross cutting aspect
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