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Issue date | Title | Topic | |
---|---|---|---|
ML17284A912 | 13 October 1999 | Proposed Tech Specs 3.3.6.1,Table 3.3. 6.1-1, Primary Containment Isolation Instrumentation. | Reactor Vessel Water Level |
ML17284A876 | 27 August 1999 | Replacement Page 9 of 9 to Attachment 4 of Procedure 13.10.6 | |
ML17284A849 | 29 July 1999 | Proposed Tech Specs,Revising SR 3.5.2.2 Re Condensate Storage Tank Water Level | |
ML17284A842 | 29 July 1999 | Proposed Tech Specs Revising SR of TS 3.8.4, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. | |
ML17284A846 | 29 July 1999 | Proposed Tech Specs,Revising Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & E.A. | |
ML17284A852 | 29 July 1999 | Proposed Tech Specs 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. | Stroke time |
ML17333A002 | 20 April 1999 | Proposed Tech Specs Section 3.4.11,replacing Existing Reactor Pressure Temp Limit Curves by 000630 | Hydrostatic |
ML17292B634 | 7 April 1999 | Proposed Tech Specs Modifying MCPR Safety Limits to Allow Continued Power Operation at Plant Following Restart from R-14 RFO | Reactor Vessel Water Level Anticipated operational occurrence Fuel cladding |
ML17292B573 | 1 March 1999 | ODCM for WNP-2 | Boric Acid Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Power change |
ML17292B488 | 17 December 1998 | Proposed Tech Specs SR 3.8.1.8,allowing Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 | Offsite Circuit |
ML20198A705 | 30 November 1998 | Revs 8 Through 13 to TS Bases & Revs 12 Through 15 of Licensee Controlled Specs | Safe Shutdown Reactor Vessel Water Level Grab sample Post Accident Monitoring Squib Scram Discharge Volume Operability Determination Battery sizing Fuel cladding Offsite Circuit |
ML17284A718 | 5 August 1998 | Proposed Tech Specs SR 3.8.4.7,allowing Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 | |
ML17284A707 | 17 July 1998 | Proposed Tech Specs Modifying SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc,Battery E-B1-2 | |
ML17284A643 | 29 May 1998 | Revised Plant Procedure Sys for Site Wide Procedures, Replacing Pages Located in Manual W/Pages in Package | |
ML17292B283 | 9 March 1998 | Proposed Tech Specs Establishing Interim SLMCPR for Siemens Power Corp ATRIUM-9X Fuel Applicable to Cycle 14 Only | Reactor Vessel Water Level Post Accident Monitoring |
ML17292B259 | 31 January 1998 | Offsite Dose Calculation Manual. | Boric Acid Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Power change |
ML17292B132 | 4 December 1997 | Proposed Tech Specs Modifying Min Critical Power Ratio Safety Limits | Reactor Vessel Water Level Anticipated operational occurrence |
ML17292B028 | 14 August 1997 | Proposed Tech Specs Revising TS 5.5.6 by Adding Note That Would Extend Interval Requirement to Perform Full Stroke Exercise Testing of TIP-V-6 Until 1998 Refueling Outage | |
ML17292A969 | 12 August 1997 | Proposed Tech Specs Supporting Request for Enforcement Discretion for Period of 45 Days from TS Action 3.6.1.3.A Required Actions to Isolate Purge Line & Verify Penetration Flow Path Isolated Every 31 Days | Enforcement Discretion |
ML17292A942 | 16 July 1997 | Proposed Tech Specs Adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 EFPYs | Unanalyzed Condition Hydrostatic |
ML17292A890 | 6 June 1997 | Revised Tech Spec Page 2.0-1 Modified to Indicate That SLMCPR for ATRIUM-9X Fuel Applies Only to Cycle 13 & Corresponding Bases Pages | Reactor Vessel Water Level Fuel cladding |
ML17292A865 | 20 May 1997 | Proposed Tech Specs,Requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 | Reactor Vessel Water Level Anticipated operational occurrence Post Accident Monitoring |
ML17292A830 | 31 March 1997 | Wppss WNP-2 RPV Surveillance Matls Testing & Analysis. | Offsite Dose Calculation Manual Process Control Program |
ML17292A762 | 24 March 1997 | Rev 5 to TS Bases. | Safe Shutdown Unanalyzed Condition Shutdown Margin Reactor Vessel Water Level High Radiation Area Ultimate heat sink Grab sample Stroke time Anticipated operational occurrence Post Accident Monitoring Hydrostatic Squib Qualified Offsite Circuit Emergency Lighting Abnormal operational transient Scram Discharge Volume Feedwater Controller Failure Spiral reload Battery sizing Overtravel Power Operated Valves Fuel cladding Pressure Boundary Leakage Offsite Circuit Power change Unidentified leakage |
ML17292A763 | 24 March 1997 | Rev 7 to Licensee Controlled Specs. | Time of Discovery Reactor Vessel Water Level High Radiation Area Grab sample Post Accident Monitoring Operating Basis Earthquake Scram Discharge Volume Excess Flow Check Valve Battery sizing Earthquake Turbine Missile Operability Assessment |
ML17292A758 | 22 March 1997 | Proposed Tech Specs Modifying Response Time Testing SR for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation | |
ML17292A753 | 20 March 1997 | Proposed Tech Specs Re Response Time Testing Requirements | Shutdown Margin |
ML17292A659 | 14 January 1997 | Proposed Tech Specs Reflecting Compilation of TS Change Requests Submitted to NRC in Ltrs Dtd 951208,960709 & 1212 | Time of Discovery Shutdown Margin Reactor Vessel Water Level High Radiation Area Ultimate heat sink Grab sample Offsite Dose Calculation Manual Anticipated operational occurrence Post Accident Monitoring Hydrostatic Squib Abnormal operational transient Scram Discharge Volume Process Control Program Spiral reload Overtravel Deep Dose Equivalent Power Operated Valves Fuel cladding Offsite Circuit Fire Protection Program Unidentified leakage |
ML17292A634 | 12 December 1996 | Proposed Tech Specs Requesting Conversion Based Upon NUREG-1434,rev 1 | Unanalyzed Condition Shutdown Margin Reactor Vessel Water Level High Radiation Area Ultimate heat sink Grab sample Offsite Dose Calculation Manual Stroke time Anticipated operational occurrence Post Accident Monitoring Hydrostatic Abnormal operational transient Scram Discharge Volume Process Control Program Feedwater Controller Failure Deep Dose Equivalent Fuel cladding Pressure Boundary Leakage Offsite Circuit |
ML17292A616 | 19 November 1996 | Rev 1 to WNP-2 IST Program Plan (Pumps & Valves) 2nd Interval (941213-041212). | Safe Shutdown High Radiation Area Ultimate heat sink Stroke time Squib Incorporated by reference Cold shutdown justification Power Operated Valves |
ML17292A551 | 15 October 1996 | Proposed Tech Specs Re Secondary Containment & SGTS to Reflect Revised Secondary Containment Drawdown & post- Accident Analyses Results | Hot Short Stroke time Squib |
ML17292A541 | 10 October 1996 | Proposed Tech Specs Requesting Addition of Section 2B(6) Re Storage of Byproduct,Source & Special Nuclear Materials | |
ML17292A450 | 6 September 1996 | Proposed Tech Specs,Containing Corrections to Factual Statements & Proposed Info to Clarify Evaluations | Time of Discovery Shutdown Margin Reactor Vessel Water Level High Radiation Area Ultimate heat sink Grab sample Offsite Dose Calculation Manual Stroke time Post Accident Monitoring Hydrostatic Probabilistic Risk Assessment Squib Missed surveillance Scram Discharge Volume Annual Radiological Environmental Operating Report Process Control Program Excess Flow Check Valve Overtravel Turbine Missile Fuel cladding Pressure Boundary Leakage Offsite Circuit Grace period Unidentified leakage Power Uprate |
ML17292A411 | 9 August 1996 | Proposed Tech Specs,Revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 | |
ML17292A356 | 9 July 1996 | Proposed Tech Specs,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of NSHC or Environ Assessment Provided Rev a | Safe Shutdown Shutdown Margin Reactor Vessel Water Level High Radiation Area Grab sample Offsite Dose Calculation Manual Stroke time Anticipated operational occurrence Post Accident Monitoring Hydrostatic Squib Pressure and Temperature Limits Report Process Control Program Excess Flow Check Valve Battery sizing Overtravel Fuel cladding Pressure Boundary Leakage Offsite Circuit Grace period Unidentified leakage Power Uprate |
ML17292A724 | 31 May 1996 | Offsite Dose Calculation Manual. | Boric Acid Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Power change |
ML17292A274 | 25 April 1996 | Rev 0 to UT-WNP2-208V0, Exam Summary Sheet. | |
ML20107M339 | 24 April 1996 | Proposed Tech Specs,Modifying TS to Support Cycle 12, Scheduled to Begin Subsequent to Spring 1996 Outage | |
ML17292A151 | 22 April 1996 | Proposed Tech Specs,Supplementing TS That Describes Administrative & Editorial Changes to Section 6.0, Administrative Controls. | High Radiation Area Offsite Dose Calculation Manual Process Control Program Fire Protection Program |
ML17291B280 | 19 March 1996 | Proposed Tech Specs Re Containment Leakage Testing | |
ML17291B249 | 26 February 1996 | Proposed Tech Specs,Submitting Revised Copy of TS Bases Which Include Minor Changes & Clarifications Made Per Requirements of 10CFR50.59 | Safe Shutdown Shutdown Margin Reactor Vessel Water Level High Radiation Area Anticipated operational occurrence Hydrostatic Abnormal operational transient Scram Discharge Volume Feedwater Controller Failure Fast acting solenoid valve Overtravel Fuel cladding Grace period Failure to Scram |
ML17333A020 | 19 January 1996 | Proposed Tech Specs Re Primary Containment Leakage Testing | High Radiation Area Squib |
ML17291B175 | 31 December 1995 | Reactor Power Uprate Startup Test Rept, for WNP-2. W/951215 Ltr | Shutdown Margin |
ML17291B094 | 26 October 1995 | Proposed Tech Specs,Replacing Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys | Coast down |
ML17291A991 | 16 August 1995 | Proposed Tech Specs Page 3/4 4-4,incorporating Surveillance Notes in Front of Surveillances 4.4.1.2.1 & 4.4.1.2.2 for Jet Pump Operability to Clarify That Notes Apply to Each Surveillance | |
ML17291A959 | 28 July 1995 | Operations Instructions OI-23,Rev a to, Human Performance Improvement Program. | |
ML20087E283 | 26 July 1995 | Performance Enhancement Strategy 1995 | Safe Shutdown Fire Barrier Job Performance Measure Foreign Material Exclusion Maintenance Rule Program |
ML17291A840 | 6 June 1995 | Proposed Tech Specs Index,Deleting Ref to Bases Pages | Shutdown Margin |
ML17291A837 | 6 June 1995 | Proposed Tech Specs Section 6.9.3.2,adding Ref to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications | |
ML17291A844 | 6 June 1995 | Proposed Tech Specs Section 6.0, Administrative Controls. | High Radiation Area Offsite Dose Calculation Manual Process Control Program Fire Protection Program |