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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

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