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Issue date | Title | Topic | |
---|---|---|---|
ML20210H290 | 30 July 1999 | Proposed Tech Specs Pages,Extending Operation of RBS from Current Licensed Power Level of 2894 Mwt to Uprated Power Level 3039 Mwt | Reactor Vessel Water Level Hydrostatic Abnormal operational transient Overtravel Fuel cladding |
ML20205P870 | 15 April 1999 | Proposed Tech Specs,Implementing Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long-term Solution | Anticipated operational occurrence |
ML20205L732 | 8 April 1999 | Proposed Tech Specs,Removing Notes That Refer to Specific Cycles,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits | Reactor Vessel Water Level |
ML20206R935 | 12 January 1999 | Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions | |
ML20199C188 | 8 January 1999 | Revised Page 7 to Rev 13 of RBS Security Training & Qualification Plan | |
ML20198E809 | 16 December 1998 | Proposed Tech Specs Pages Re Change to TS Safety Limit 2.1.1.2,changing Two Recirculation Loop MCPR Limit from 1.13 to 1.12 & Single Recirculation Loop MCPR Limit from 1.14 to 1.13 | Reactor Vessel Water Level |
ML20196A140 | 20 November 1998 | Proposed Tech Specs Adding 3.10.9, Control Rod Pattern - Cycle 8, to Support Startup from Outage Planned for Early Dec 1998 | |
ML20154H369 | 8 October 1998 | Proposed Tech Specs Implementing BWROG Enhanced Option I-A Reactor Stability Long Term Solution as Documented in NEDO-32339,Rev 1, Reactor Stability Long-Term Solution, Enhanced Option I-A | Anticipated operational occurrence Abnormal operational transient Annual Radiological Environmental Operating Report Process Control Program Fuel cladding |
ML20153H031 | 23 September 1998 | Proposed Tech Specs Changing Specific Gravity Acceptance Criteria for Div III Battery | |
ML20153E811 | 22 September 1998 | Proposed Tech Specs Deleting License Conditions Associated with Transamerica Delaval,Inc EDGs | Ultimate heat sink |
ML20217J095 | 21 April 1998 | Proposed Tech Specs Bases Update Package for Revs Implemented Since Last Submittal Through Refuel Outage 7 | Safe Shutdown Shutdown Margin High Radiation Area Ultimate heat sink Stroke time Anticipated operational occurrence Post Accident Monitoring Hydrostatic Abnormal operational transient Scram Discharge Volume Fuel cladding Offsite Circuit |
ML20216F194 | 9 April 1998 | Proposed Tech Specs License Condition 2.C(13) Re Partial Feedwater Heating & Final Feedwater Temp Reduction | |
RBG-44355, Cycle 8 Startup Physics Test Summary | 19 January 1998 | Cycle 8 Startup Physics Test Summary | Shutdown Margin Stroke time |
ML20202F036 | 26 November 1997 | Rev 0 to IST Plan for Pumps & Valves Second Ten-Yr Interval | Safe Shutdown Ultimate heat sink Stroke time Hydrostatic Scram Discharge Volume Cold shutdown justification Power-Operated Valves Power Operated Valves Scaffolding |
ML20216E486 | 5 September 1997 | Proposed Tech Specs Re APRM Setpoints,Reactivity Anomalies & RPS Instrumentation | Annual Radiological Environmental Operating Report Process Control Program |
ML20210K213 | 15 August 1997 | Proposed Administrative Changes to TS 2.1.1.2 W/Note to Indicate Operating Cycle for Which SLMCPR Value Has Been Approved & TS 5.6.5 W/Note Providing Link to Specific GE Documents Used in Approving SLMCPR Changes for Given Cycle | Reactor Vessel Water Level |
ML20217J048 | 5 August 1997 | Proposed Tech Specs 2.1.1.2, Reactor Core (Safety Limits), Increasing Two Recirculation Loop MCPR Limit to 1.13 & Single Recirculation Loop MCPR Limit to 1.14 | Reactor Vessel Water Level |
ML20151L604 | 31 July 1997 | Proposed Tech Specs,Requesting Approval of Change to TS 3.6.1.8, Penetration Valve Leakage Control Sys, for Upcoming Outage | |
ML20196J774 | 30 July 1997 | Proposed Tech Specs Clarifying Surveillance Requirements 3.6.4.2.1 & 3.6.4.2.2 to Match Corresponding Changes to NUREG-1434 | |
ML20134A702 | 20 January 1997 | Proposed Tech Specs to License NPF-47,enhancing Operation of Plant to Allow Operation at 100% Power W/Lower Core Flows & Use of Flow Control Spectral Shift Strategies to Increase Cycle Energy | Abnormal operational transient |
ML20133M045 | 10 January 1997 | Proposed Tech Specs 3.4.11 Re RCS Pressure & Temp Limits | |
ML20140F015 | 26 December 1996 | Rev 6 to RSP-0008, ODCM Procedure | Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report |
ML20134M227 | 15 November 1996 | Proposed Tech Specs,Changing TS SL 2.1.1.2, Reactor Core (Sl), Which Increases Two Recirculation Loop MCPR Limit from 1.07 to 1.10 & Single Recirculation Loop MCPR from 1.08 to 1.12 | Reactor Vessel Water Level |
ML20134M015 | 15 November 1996 | Proposed Tech Specs 3.8.1 Re AC Sources Operating | |
ML20134M206 | 6 November 1996 | Proposed Tech Specs,Permitting Increase in Allowable Leak Rate for MSIVs & Deleting Penetration Valve Leakage Control Sys & Ms Positive Leakage Control Sys Requirements | |
ML20129J423 | 24 October 1996 | Proposed Tech Specs 3.8.1 Re A.C. Sources - Operating | Offsite Circuit |
ML20117K107 | 29 August 1996 | Proposed Tech Specs Re Reactor Vessel Matl Surveillance Program Capsule Withdrawal Schedule | |
ML20117G740 | 29 August 1996 | Proposed Tech Specs 3.1 Re Reactivity Control Systems | Shutdown Margin Anticipated operational occurrence Fuel cladding |
ML20116P134 | 8 August 1996 | Technical Requirements Manual | Safe Shutdown Time of Discovery Reactor Vessel Water Level High Radiation Area Ultimate heat sink Grab sample Offsite Dose Calculation Manual Fire Barrier Hydrostatic Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Earthquake Pressure Boundary Leakage Fire Protection Program Fire Watch Early Warning Fire Detection Power change Unidentified leakage |
ML20116J315 | 7 August 1996 | Proposed Tech Specs,Submitting TS Bases Pages for Revs Performed Since 951001 Approval of TS Bases | Safe Shutdown Reactor Vessel Water Level High Radiation Area Stroke time Anticipated operational occurrence Post Accident Monitoring Squib Scram Discharge Volume Battery sizing Overtravel Fuel cladding Recently irradiated fuel |
ML20116L632 | 1 August 1996 | Proposed Tech Specs Re Primary Containment/Drywell Hydrogen Mixing Sys & Drywell Isolation Valves | High Radiation Area |
ML20113F227 | 12 June 1996 | Rev 0 to Calculation PI-0103-00203.002-101, Ampacity Derating Evaluation | Fire Barrier |
ML20117L258 | 4 June 1996 | Proposed Tech Specs Re Replacement Page for Ltr | Spiral reload |
RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks | 31 May 1996 | Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks | |
ML20112E783 | 30 May 1996 | Proposed Tech Spec 3.8.3 Re Incorporation of 5-start Air Pressure Design Criterion for Div III DG | |
ML20117H327 | 20 May 1996 | Proposed Tech Specs Re Change in Co Name from Gulf States Utils Co to Entergy Gulf States,Inc | |
B130180, Surveillance Specimen Program Evaluation for River Bend Station | 30 April 1996 | Surveillance Specimen Program Evaluation for River Bend Station | |
ML20107E468 | 18 April 1996 | Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells | Spiral reload |
ML20094N774 | 22 November 1995 | Proposed Tech Specs,Clarifying Info Contained in License Amend Request (LAR) 95-21 | Biofouling |
ML20094M800 | 20 November 1995 | Proposed Tech Specs Re Drywell Leak Rate Testing Requirements | High Radiation Area Stroke time |
ML20094N009 | 20 November 1995 | Proposed Tech Specs Eliminating Selected Response Time Testing Requirements | |
ML20094B000 | 26 October 1995 | Proposed Tech Specs,Consisting of Change Request 95-10, Deleting TS 5.5.12, Biofouling Prevention & Detection, & Various Editorial Corrections | High Radiation Area Post Accident Monitoring Biofouling |
ML20093L736 | 24 October 1995 | Proposed Tech Specs 3.6.1.1 Through 3.6.1.3 Re Containment Sys | Biofouling |
ML20108B594 | 1 October 1995 | Rev 5A to River Bend Station Offsite Dose Calculation Manual Procedure | Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report |
ML20087J545 | 17 August 1995 | Proposed Tech Specs Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions | |
ML20084L500 | 30 May 1995 | Proposed Tech Specs,Allowing TS 3/4.6.2.2, Drywell Bypass Leakage, Tests to Be Performed at Intervals as Long as Five Yrs Based on Demonstrated Performance of Drywell Structure | |
ML20084L454 | 30 May 1995 | Proposed Tech Specs Re Request for Exemption from App J, Primary Reactor Containment Leakage Testing for Water- Cooled Power Reactors | |
ML20078M117 | 8 February 1995 | Proposed Tech Specs Page Re Secondary Containment Automatic Isolation Dampers | |
ML20077S440 | 18 January 1995 | Revised Pages of Proposed Tech Specs Re Conversion to TS Based on NUREG-1434, Improved TS Rev 0 | |
ML20078H088 | 10 November 1994 | Proposed Tech Specs Reflecting Clarifications to LAR 91-11 |