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	Issue date	Site	Title
ML20134L941	13 November 1996	Vermont Yankee	Concludes That Change in Design Basis for Containment Isolation of RHR & CS Sys Cannot Be Made Under 10CFR50.59 & Requires Full Licensing Review
1CAN088906, Withdraws 871204 Application for Amend to License DPR-51, Consisting of Proposed Change 2 to Tech Specs,Modifying Responsibilities of Plant Safety Review Committee	3 August 1989	Arkansas Nuclear	Withdraws 871204 Application for Amend to License DPR-51, Consisting of Proposed Change 2 to Tech Specs,Modifying Responsibilities of Plant Safety Review Committee
2CAN088905, Withdraws 871204 Application for Amend to License NPF-6, Consisting of Proposed Change 2 to Tech Specs,Modifying Responsibilities of Plant Safety Review Committee	3 August 1989	Arkansas Nuclear	Withdraws 871204 Application for Amend to License NPF-6, Consisting of Proposed Change 2 to Tech Specs,Modifying Responsibilities of Plant Safety Review Committee
1CAN078903, Forwards Partial Response to Questions Re Seismically Qualified,Partially Tornado Protected Condensate Storage Tank.Final Response to Be Submitted by 900115	10 July 1989	Arkansas Nuclear	Forwards Partial Response to Questions Re Seismically Qualified,Partially Tornado Protected Condensate Storage Tank.Final Response to Be Submitted by 900115
1CAN068907, Clarifies Independent RCS Level Indications Credited in Response W/Meeting Expeditious Action (4) & Programmed Enhancement (1)(a) of Generic Ltr 88-17	12 June 1989	Arkansas Nuclear	Clarifies Independent RCS Level Indications Credited in Response W/Meeting Expeditious Action (4) & Programmed Enhancement (1)(a) of Generic Ltr 88-17
1CAN048916, Forwards Revised Tech Spec Table 4.1-1 Re Channel Check Surveillance Requirements for Radiation Monitoring Sys	27 April 1989	Arkansas Nuclear	Forwards Revised Tech Spec Table 4.1-1 Re Channel Check Surveillance Requirements for Radiation Monitoring Sys
0CAN038906, Responds to 890223 Request for Addl Info Re Util 881221 Submittal of Results of Latest Fire Barrier Penetration Seal Testing.Response to Request Will Be Submitted by 890424. Delay Due to Workload of Fire Protection Group	8 March 1989	Arkansas Nuclear	Responds to 890223 Request for Addl Info Re Util 881221 Submittal of Results of Latest Fire Barrier Penetration Seal Testing.Response to Request Will Be Submitted by 890424. Delay Due to Workload of Fire Protection Group
0CAN028907, Forwards Summary of SPDS Isolation Device Test Results	28 February 1989	Arkansas Nuclear	Forwards Summary of SPDS Isolation Device Test Results
1CAN098801, Forwards Followup to 870827 Reactor Bldg Temp Justification for Operation Submittal,Per NRC Telcon Request for Addl Info on Error Calculations Used to Access Effects of Elevated Temps on Protection Sys Setpoints	6 September 1988	Arkansas Nuclear	Forwards Followup to 870827 Reactor Bldg Temp Justification for Operation Submittal,Per NRC Telcon Request for Addl Info on Error Calculations Used to Access Effects of Elevated Temps on Protection Sys Setpoints
0CAN068812, Responds to NRC 880523 Request for Addl Info Re Spds.Util Will Evaluate Rochester Instrument Sys Model SC-1302 & Energy,Inc Model 00993-4 Isolators Against 120-volt Ac 20 Amp Guidance.Evaluation of Test Data Expected by 880815	30 June 1988	Arkansas Nuclear	Responds to NRC 880523 Request for Addl Info Re Spds.Util Will Evaluate Rochester Instrument Sys Model SC-1302 & Energy,Inc Model 00993-4 Isolators Against 120-volt Ac 20 Amp Guidance.Evaluation of Test Data Expected by 880815
0CAN068813, Requests Addl 30 Days to Completely Implement Necessary Mods for Majority of Work to Protect Secondary Power Supply.Util Will Still Be in Compliance W/Nrc Implementation Guide	29 June 1988	Arkansas Nuclear	Requests Addl 30 Days to Completely Implement Necessary Mods for Majority of Work to Protect Secondary Power Supply.Util Will Still Be in Compliance W/Nrc Implementation Guide
2CAN068806, Submits Response to Generic Ltr 86-06, Automatic Trip of Reactor Coolant Pumps, Re TMI Action Item II.K.3.5	3 June 1988	Arkansas Nuclear	Submits Response to Generic Ltr 86-06, Automatic Trip of Reactor Coolant Pumps, Re TMI Action Item II.K.3.5

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