Semantic search
Jump to navigation
Jump to search
Issue date | Title | Topic | |
---|---|---|---|
ML17059C791 | 30 September 1999 | Proposed Tech Specs Re Rev B to Conversion of Unit 2 Current TS to ITS | |
ML20211P593 | 10 September 1999 | Marked-up Tech Specs Pages Reflecting Conforming Administrative License Amend Associated with Proposed Transfer of Facilities to Amergen Energy Co,Llc | Safe Shutdown Fitness for Duty Shutdown Margin Pressure Boundary Leakage Fire Protection Program |
ML20211H223 | 26 August 1999 | Proposed Tech Specs,Supporting Implementation of Noble Metal Chemical by Raising Reactor Water Conductivity Limit in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b | |
ML18041A073 | 27 July 1999 | Rev 1 to NMP2-ISI-006, Second Ten Year Interval Inservice Insp Program Plan for Nine Mile Point Nuclear Power Station Unit 2. | Safe Shutdown Weld Overlay Hydrostatic Nondestructive Examination VT-2 Liquid penetrant Dissimilar Metal Weld Scaffolding Backfit |
ML20206P266 | 30 December 1998 | Proposed Tech Specs Making Application of Emergency Condenser Vent Ng Activity Monitor Channel Operability Requirement & Daily Sensor Check SR Consistent with Conditions Stated in LCO 3.1.3.a Re Emergency Cooling Sys | Offsite Dose Calculation Manual Anticipated operational occurrence Hydrostatic |
ML20197K104 | 4 December 1998 | Revised Proposed TS Bases Reflecting Previous Removal of Condenser Low Vacuum Scram Function from TS as Well as Plant Design & Changes to EDG Ratings,Design Basis Load Limits & Loading Profiles | Safe Shutdown Scram Discharge Volume |
ML20196H067 | 30 November 1998 | Proposed Tech Specs,Correcting LCO & Associated Bases for TS Section 3.1.2, Liquid Poison Sys, That Had Been Incorporated Into TS as Part of NMP Unit 1 TS Amend 101 | Squib |
ML20196D208 | 24 November 1998 | Proposed Tech Specs B 2.1.1, Fuel Cladding - Safety Limit, B 3.2.5 & 4.2.5, Reactor Coolant Sys Leakage Rate | Fuel cladding Unidentified leakage |
ML20154R110 | 16 October 1998 | Proposed Ts,Revising LCO 3.7.1.1 & Associated Actions & SRs to Provide Assurance That Four SW Pumps Are Operable & Are Operating within Acceptable Sys Parameters,With Divisional Cross Connect Valves Open | Safe Shutdown Reactor Vessel Water Level Ultimate heat sink Hydrostatic |
ML20217N791 | 24 April 1998 | Revised Pages 2-1,3/4 4-1 & B2-1 to Replace Previously Submitted Pages Contained within Attachment a of 971215 Proposed Change to TS to License NPF-49 | Reactor Vessel Water Level Fuel cladding |
ML20202G375 | 5 February 1998 | Proposed Tech Specs Pages,Reflecting References to 10CFR50.55a(f) & (G) as Well as Terminology Used in Second Ten Year Isi/Ist,Beginning on 980405 | Shutdown Margin Hydrostatic |
ML20197H337 | 15 December 1997 | Proposed Tech Specs Revising SLMCPR from 1.07 to 1.09 for Two Recirculation Loop Operation & from 1.08 to 1.10 for Single Loop Operation | Reactor Vessel Water Level Anticipated operational occurrence Minimum Critical Power Ratio Fuel cladding |
ML20211M523 | 7 October 1997 | Proposed Tech Specs Section 4.9.6,reflecting New Setpoints Due to Difference in Weights of Two Existing Triangular Refueling Platform Masts | Safe Shutdown Earthquake Earthquake |
ML20217G901 | 31 July 1997 | Proposed Tech Specs Changing Wording in Action 36 of TS Table 3.3.3-1, Emergency Core Cooling Sys Actuation Instrumentation | Enforcement Discretion |
ML20148A775 | 30 April 1997 | Proposed Change to Tech Specs,Removing Section 3.3.7.3 & Associated Surveillance Section 4.3.7.3,associated Tables 3.3.7.3-1 & 4.3.7.3-1,Bases Section 3.4.3.7.3 & Revising Section 0.0 (Index) Pages VII & Xvii | Safe Shutdown Reactor Vessel Water Level Earthquake |
ML17059B291 | 4 September 1996 | NMP Nine Mile Point Nuclear Station Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan. | |
ML20116D812 | 26 July 1996 | Proposed Tech Specs Re Option B of App J to 10CFR50 | |
ML20115H152 | 12 July 1996 | Proposed Tech Specs Section 6.2.2.i Re App a | Safe Shutdown |
ML20117F950 | 15 May 1996 | Proposed Tech Specs Section 3/4.3.2 Re Isolation Actuation Instrumentation | Reactor Vessel Water Level |
ML20101F428 | 20 March 1996 | Proposed TS 3/4.3.1 Re RPS Instrumentation,Deleting Operability Requirements for APRM Neutron flux-upscale, Setdown & Inoperative Functions in Operational Conditions (Oc) 3 & 4 & Modifying Operability Requirements in Oc 5 | Shutdown Margin Reactor Vessel Water Level Fuel cladding Power change |
ML20101D755 | 15 March 1996 | Proposed Tech Specs Section 4.6.2 Re Depressurization Sys - Suppression Pool | |
ML20097D239 | 7 February 1996 | Proposed Tech Specs Re Administrative Controls | |
ML20100C102 | 25 January 1996 | Proposed Tech Specs Table 3.3.3-1 Re Emergency Core Cooling Sys Actuation Instrumentation | Safe Shutdown Reactor Vessel Water Level |
ML20096G840 | 17 January 1996 | Proposed Tech Specs,Representing Revs to Specs 3/4.3.1, 3/4.3.2,3/4.3.3,3/4.3.4.2 & Associated Bases to Relocate Response Time Limit Tables from TSs to Plant USAR | Fuel cladding |
ML20094B542 | 25 October 1995 | Proposed Tech Specs Re Position Title Changes & Reassignments of Responsibilities at Upper Mgt Level | Offsite Dose Calculation Manual Process Control Program Fire Protection Program |
ML20091Q957 | 28 August 1995 | Proposed TS 3.6.1.7,increasing Time 12-inch & 14-inch Containment Purge Sys Supply & Exhaust Valves May Be Open in Operational Condition 1,2 & 3 from 90 H Per 365 Days to 135 H Per 365 Days & Deleting Expired Footnotes for Clarity | Probabilistic Risk Assessment |
ML20081E249 | 9 March 1995 | Proposed Tech Specs,Revising SR 4.6.1.2.a,allowing Second Primary Containment ILRT (Type a) to Be Performed at Refueling Outage 5 or 72 Months After First Type a Test | Exemption Request |
ML17059B022 | 15 February 1995 | Rev 0 to UT-NMP-311V0, Procedure for Manual Ultrasonic Exam of Nozzles Inner Radius & Bore. | Nondestructive Examination |
ML17059B021 | 10 February 1995 | Rev 0 to UT-NMP-309V0, Procedure for Manual Ultrasonic Exam of Planar Flaw Sizing for Nozzle Inner Radius & Bore Regions. | |
ML17059B020 | 10 February 1995 | Rev 0 to UT-NMP-703V0, Procedure for Geris 2000 Ultrasonic Exam of RPV Nozzle Inner Radius & Bore Regions. | Non-Destructive Examination Nondestructive Examination |
ML17059A888 | 18 January 1995 | Rev 0 to Field Disposition Instruction 0245-90800, Shroud. | |
ML20077N159 | 6 January 1995 | Proposed Tech Specs Re Min Gallons of Fuel Oil Required in Day Tanks & Storage Tanks | Safe Shutdown Emergency Lighting Offsite Circuit |
ML20077N207 | 6 January 1995 | Proposed Tech Specs Re Deletion of Certain Instruments Not Classified as Category 1 | Safe Shutdown Reactor Vessel Water Level |
ML20078Q924 | 13 December 1994 | Proposed Tech Specs Re Change to Table 3.6.1.2-1 That Will Allow Maximum Leakage of 24.0 Scfh for Each of Eight MSIVs | |
ML20077E156 | 2 December 1994 | Proposed TS Page 3/4 1-20,reflecting Rev of SLCS Relief Valve Setpoint to Show Influence of Back Pressure & Rev of Bases Page B3/4 5-2 to Show That Hpsc Sys Designed to Supply 517 Gpm Flow Rate at 1,200 (Instead of 1,175) Psid | |
ML20078J378 | 14 November 1994 | Proposed Tech Specs Reducing Leak Rate Test Pressure for Safety Related ADS Nitrogen Receiving Tanks from 385 Psig to 365 Psig | Safe Shutdown Fuel cladding |
ML17059A566 | 9 November 1994 | Rev 2 to Emergency Plan Maint Procedure EPMP-EPP-08, Maint, Testing & Operation of Oswego County Prompt Notification Sys. | Health Physics Network |
ML20078E033 | 28 October 1994 | Proposed Tech Specs 1.0, Definitions, 3/4.3.2, Isolation Actuation Instrumentation & 3/4.9.3, Control Rod Position | Shutdown Margin Spiral reload |
ML20078B984 | 21 October 1994 | Proposed Tech Specs SR 4.8.1.1.2.e.8,reflecting Addition of Footnote Re 24 H Functional Test of DGs | Safe Shutdown |
ML20073L878 | 5 October 1994 | Proposed TS Table 3.3.7.1-1 Re Radiation Monitoring Instrumentation | |
ML20072U349 | 2 September 1994 | Proposed Tech Specs Re 18 Month Operability Test of Svc Water Pumps Sys & Resistance Test of Intake Deicing Heater Sys | Enforcement Discretion |
ML17059A447 | 1 September 1994 | Proposed Tech Specs Section 3.2.2, Minimum Reactor Vessel Temperature for Pressurization, & Associated Bases | Hydrostatic |
ML20072P621 | 26 August 1994 | Proposed TS 3/4.6.1.3, Primary Containment Air Locks, Allowing Continued Plant Operation If Interlock Becomes Inoperable as Long as Operable Door Locked Shut & Periodically Checked as Being Locked Shut | |
ML17059A424 | 6 July 1994 | Rev 14 to Nine Mile Point Nuclear Station Unit 1 Odcm. | Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report |
ML20071G277 | 1 July 1994 | Proposed Tech Specs Surveillance Requirements 4.6.5.1.c.1 & 4.6.5.1.c.2 | |
ML20029D400 | 27 April 1994 | Proposed Tech Specs Re Drawdown Time Testing & Inleakage Testing for Secondary Containment Integrity | Fire Barrier |
ML18040A294 | 17 December 1993 | Rev 13 to Nine Mile Point Nuclear Station Unit 1 Odcm. | Grab sample Offsite Dose Calculation Manual |
ML20058N349 | 14 December 1993 | Proposed Tech Specs 3/4.8.2, DC Sources, 3/4.8.4, Electrical Equipment Protective Devices & Bases for 3/4.6.3, Primary Containment Isolation Valves | Safe Shutdown Stroke time Emergency Lighting Battery sizing |
ML17059A097 | 25 October 1993 | Rev 4 to NMP2-IST-001,NMP,Nine Mile Point Nuclear Station, Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan. | Stroke time Hydrostatic Squib Cold shutdown justification |
ML20056G939 | 2 September 1993 | Proposed Tech Specs Section 3/4.1.3.5, CR Scram Accumulators | Shutdown Margin Fuel cladding |