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	Issue date	Title	Topic
ML20125D507	14 December 1992	Proposed Tech Specs Re Deletion of AC Sources & Onsite Power Distribution Sys Requirements & Changing Frequency of Radiological Effluent Release Reporting Requirements	Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report
ML20086K098	5 December 1991	Proposed Tech Spec Section 6.5.1 Re Site Review Committee & 6.5.2 Re Independent Review Panel	Offsite Dose Calculation Manual Process Control Program Fire Protection Program
ML20079P398	31 October 1991	Proposed Tech Specs 6.5.1 & 6.5.2 Re Site Review Committee & Independent Review Panel,Respectively	High Radiation Area Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Fire Protection Program
ML20070H619	11 March 1991	Proposed Tech Specs Removing License Condition 14 from License NPF-82
ML20070D492	26 February 1991	Proposed Tech Specs Re Seismic Monitoring Instrumentation Surveillance Requirements,Radiation Monitoring Instrumentation & Administrative Controls
ML20058E305	30 October 1990	Proposed Tech Specs Replacing Pages 3/4 4-1 & 3/4 4-3 of Defueled Tech Specs
ML20059G370	30 August 1990	Revised Tech Specs Re Limiting Conditions for Fuel Handling Operation	High Radiation Area Offsite Dose Calculation Manual Hydrostatic Annual Radiological Environmental Operating Report Process Control Program Earthquake Fire Protection Program
ML20056B508	21 August 1990	Proposed Tech Specs,Deleting Section 6.2.3, Independent Safety Engineering Group (Iseg) & Associated Administrative Controls
ML20058N543	10 August 1990	Proposed Tech Specs Re Defueled SAR	Safe Shutdown Ultimate heat sink Chernobyl
ML20044A801	28 June 1990	Proposed Tech Specs Designating Long Island Power Authority as Plant Licensee Upon or After NRC Amends License to Nonoperating Status	Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Fire Protection Program
ML20006F471	20 February 1990	Proposed Tech Specs Conforming to Guidance of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent Tech Specs in Administrative Controls Section of Tech Specs & Relocation of Procedural....	Shutdown Margin Grab sample Process Control Program Pressure Boundary Leakage Fire Protection Program Fire Watch
ML20005F248	5 January 1990	Proposed Tech Specs Re Defueled Facility OL	High Radiation Area Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Safeguards Contingency Plan Earthquake Offsite Circuit
ML20246N973	13 July 1989	Proposed Tech Specs Removing Inconsistency in Plant Procedural Change Approval Process	Offsite Dose Calculation Manual Post Accident Monitoring Process Control Program Fire Protection Program
ML20246E589	30 April 1989	Technical Specifications for Shoreham Nuclear Power Station, Unit 1.Docket No. 50-322.(Long Island Lighting Company)
SNRC-1509, Proposed Tech Spec Table 1.2, Operational Conditions	19 October 1988	Proposed Tech Spec Table 1.2, Operational Conditions
ML20151D714	15 July 1988	Proposed Tech Specs Re Test Frequency of Emergency Diesel Generators	Offsite Circuit
ML20151D742	11 July 1988	Proposed Tech Specs Clarifying Method of Demonstating Operability of Source Range Monitor Channels	Shutdown Margin
ML20154M632	24 May 1988	Proposed Tech Specs,Changing Alarm/Trip Setpoint and Measurement Range of Main Control Room Vent Radiation Monitors
ML20154H147	19 May 1988	Proposed Tech Spec Pages 3/4 5-6 & 3/4 5-8,providing Clarification to Eliminate Possibility of Misinterpretation
ML20236C466	14 October 1987	Proposed Tech Specs,Correcting Tupos & Tech Spec Internal Inconsistencies Re Radiological Environ Monitoring & Designation of Number of Valves in Table 3.6.3-1
ML20238C447	4 September 1987	Proposed Tech Spec Pages 1-2,3/4 1-1,3/4 1-2,3/4 1-6, 3/4 3-4,3/4 9-3 & 3/4 9-7,changing Definition of & Footnotes Re Core Alteration	Shutdown Margin
ML20206F879	10 April 1987	Proposed Amended Tech Specs Re Surveillance Testing for B-10 Enrichment Level of Standby Liquid Control Sys Tank	Squib
ML20210C779	4 February 1987	Proposed Tech Specs,Implementing Design Change That Will Equip Standby Liquid Control Sys W/Slightly More than Twice Equivalent Control Capacity Required by 10CFR50.62(c)(4)	Squib
ML20212J475	21 January 1987	Proposed Tech Specs,Incorporating License Change Application 6 to Implement Design Change to Lower Reactor Vessel Water Level of MSIVs & Steam Line Drain Valves from Level 2 to Level 1	Reactor Vessel Water Level
ML20207P963	12 January 1987	Proposed Tech Specs Re Location of Meteorological Towers & Composition of Independent Safety Engineering Group
ML20206P274	26 June 1986	Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept & Review of Operations Committee Responsibilities	Offsite Dose Calculation Manual Process Control Program
ML20140A810	20 January 1986	Proposed Tech Spec Correcting Error in Basis for Location of Milk Control Sample & Eliminating Sampling Analysis If No Waste Batch Released During Month	Grab sample
ML20137Z294	9 December 1985	Revised Tech Spec Table 3.3.7.9-1, Fire Detection Instrumentation
ML20136B445	16 November 1985	Proposed Tech Specs Increasing & Relocating Fire Detectors & Modifying Reactor Coolant Leakage Detection Sys Surveillance Requirement	Grab sample Fire Watch
ML20138C879	21 October 1985	Proposed Tech Specs Re Conversion of Reactor Bldg Standby Ventilation Sys low-range Noble Gas Radiation Monitor to Vent Stack low-range Nobel Gas Radiation Monitor	Reactor Vessel Water Level
ML20128M137	31 July 1985	Technical Specifications for Shoreham Nuclear Power Station, Unit No. 1.Docket No. 50-322.(Long Island Lighting Company)	Safe Shutdown Boric Acid Shutdown Margin Reactor Vessel Water Level High Radiation Area Ultimate heat sink Grab sample Offsite Dose Calculation Manual Fire Barrier Anticipated operational occurrence Post Accident Monitoring Hydrostatic Squib Abnormal operational transient Scram Discharge Volume Annual Radiological Environmental Operating Report Process Control Program Excess Flow Check Valve Fast acting solenoid valve Overtravel Earthquake Fuel cladding Pressure Boundary Leakage Offsite Circuit Continuous fire watch Fire Protection Program Fire Watch Hourly Fire Watch Grace period Power change Unidentified leakage Failure to Scram
SNRC-1181, Proposed Tech Spec 3.10.5 Suspending Provisions of Tech Spec 3.6.6.2 During Performance of Startup Test Program Until Reactor Has Operated for 120 EFPD	19 June 1985	Proposed Tech Spec 3.10.5 Suspending Provisions of Tech Spec 3.6.6.2 During Performance of Startup Test Program Until Reactor Has Operated for 120 EFPD

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