Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
ML17229B06716 March 1999Technical Evaluation Rept, Florida Power & Light Co, Unit 1 Third Ten-Year Interval Pump & Valve Inservice Testing Program,Unit 2 Second Ten-Year Interval Pump & Valve Inservice Testing Program.Boric Acid
Shutdown Margin
Stroke time
Incorporated by reference
Cold shutdown justification
ML20203H88230 September 1998Technical Evaluation Rept on Second 10-year ISI Program Plan:Entergy Operations,Waterford-3 Steam Electric StationVT-2
Incorporated by reference
ML17355A28030 September 1998Rev 1,Ltr Rept, Technical Evaluation of Florida Power & Light Fire Barrier Ampacity Derating Assessment for St.Lucie & Turkey Point.Fire Barrier
Coatings
ML17229B00131 January 1998Technical Evaluation Rept on 'Submittal-Only' Review of IPEEE at St Lucie Nuclear Plant,Units 1 & 2.Hot Short
Safe Shutdown
Boric Acid
High winds
Ultimate heat sink
Fire Barrier
Tornado Missile
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
Coatings
Tornado Generated Missile
Design basis earthquake
Earthquake
Fire Protection Program
Fire Watch
ML17229A41527 May 1997Technical Evaluation Rept of IPE Submittal & RAI Responses for St Lucie Nuclear Plant.Boric Acid
Ultimate heat sink
Mission time
Internal Flooding
Probabilistic Risk Assessment
ML20135E58426 February 1997Revised, TER of IPE Submittal & RAI Responses for Waterford-3 Steam Electric StationSafe Shutdown
Boric Acid
Ultimate heat sink
Mission time
Internal Flooding
ML20147A71031 December 1996Technical Ltr Rept, Pacific Northwest Natl Lab Review of Main Yankee In-Situ Pressure Test Assessment, Rev 2Safe Shutdown Earthquake
Finite Element Analysis
Flow Induced Vibration
ML20148C64430 June 1996Review of Operating Experience for Maine Yankee from Jan 1993 - Mar 1996Unanalyzed Condition
Fire Barrier
Temporary Modification
Fire Watch
ML17228B12631 March 1995Technical Evaluation Rept on Second 10-Year Interval Insp Program Plan.Hydrostatic
Nondestructive Examination
Incorporated by reference
Dissimilar Metal Weld
Scaffolding
ML17309A74730 September 1994Technical Evaluation Rept;Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001:St.Lucie-1/-2.
ML17228A88530 September 1994Errata to TER, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001,St Lucie 1 & 2, Replacing Every Other Missing Page in Original Rept
ML20138E14822 June 1993Pump & Valve Inservice Testing Program St Lucie Unit 2 FPL, Technical Evaluation ReptBoric Acid
Stroke time
Incorporated by reference
Power Operated Valves
Backfit
ML20105D08731 August 1992Auxiliary Feedwater System RISK-BASED Inspection Guide for the St. Lucie Unit 1 Nuclear Power Generation StationProbabilistic Risk Assessment
ML17309A66530 November 1991Technical Evaluation Rept Pump & Valve Inservice Testing Program,St Lucie-Unit 1.Boric Acid
Shutdown Margin
Stroke time
Power-Operated Valves
Power Operated Valves
ML20082S93730 September 1991Trip Rept:Onsite Analysis of Human Factors of Event at Waterford 3 on 910624 (Manual Reactor Trip W/Excess Steam Demand)Boric Acid
Stroke time
ML17223B32331 August 1991TER of Topical Rept CEN-396-P (Verification of Acceptability of a 1-PIN Burnup Limit of 60 Mwd/Kg for St Lucie Unit 2).Anticipated operational occurrence
Safe Shutdown Earthquake
Earthquake
Fuel cladding
ML20082N09218 June 1991Draft Assessment of Intersystem LOCA Risks - Methodology & Application:C-E Plant
ML17308A50417 August 1990Final Technical Evaluation Rept St Lucie Unit 1 Station Blackout Evaluation.Safe Shutdown
Boric Acid
ML20058K8709 July 1990Rev 2 to Technical Evaluation Rept,Maine Yankee Atomic Power Station,Station Blackout Evaluation
ML19332B61431 October 1989Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation ReptSafe Shutdown
ML17308A48231 May 1989Conformance to Generic Ltr 83-28,Item 2.2.1,Equipment Classification for All Other Safety-Related Components,St Lucie 1/2, Technical Evaluation Rept
ML20246N6972 May 1989Summary of Environ Data from Plant for 1988
ML20246B81530 April 1989Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Duane Arnold,Enrico Fermi-2,Hope Creek,Lasalle County 1 & 2, Limerick 1 & 2,Millstone 1,Monticello,Nine Mile Point 1 & 2 & Oyster Creek, Technical Evaluation Rept
ML20246B97331 March 1989Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation ReptBoric Acid
ML20236B80513 March 1989Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files
ML17222A74131 January 1989Technical Evaluation Rept on Second Ten-Year Interval Inservice Insp Program Plan:Florida Power & Light Co,St Lucie Plant,Unit 1.Hydrostatic
Incorporated by reference
Liquid penetrant
ML20070Q76731 December 1988Nuclear Power Plant Sys Sourcebook,Waterford 3Safe Shutdown
Boric Acid
Ultimate heat sink
Emergency Lighting
B.5.b Mitigating Strategies
ML17223A12931 December 1988Technical Evaluation Rept TMI Action NUREG-0737 (II.D.1) Relief & Safety Valve Testing,St Lucie,Unit 1.Loop seal
Anticipated operational occurrence
Operating Basis Earthquake
Design basis earthquake
ML17223A13231 December 1988Technical Evaluation Rept TMI Action NUREG-0737 (II.D.1) Relief & Safety Valve Testing,St Lucie,Unit 2.Loop seal
Anticipated operational occurrence
Operating Basis Earthquake
Design basis earthquake
ML20244C29330 November 1988Review of Florida Power & Light Co Safety Evaluations for Extending St Lucie Plant,Unit 2,ESFAS Subgroup Relay Test Interval, Technical Evaluation Rept
ML20235C47231 October 1988Pump & Valve Inservice Testing Program,Waterford Steam Electric Station,Unit 3Boric Acid
Stroke time
Power-Operated Valves
Power Operated Valves
ML20205N94331 October 1988Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1
ML20207J43930 June 1988Conformance to Reg Guide 1.97:Maine Yankee, Technical Evaluation ReptBoric Acid
Fuel cladding
ML17308A44631 March 1988Technical Evaluation Rept for Natural Circulation,Boron Mixing & Cooldown at St Lucie Unit 2.Tornado Missile
ML20148M06931 March 1988Technical Evaluation Rept for Natural Circulation,Boron Mixing & Cooldown at Waterford Unit 3
ML20196G29229 February 1988Technical Evaluation Rept,Evaluation of High Density Spent Fuel Rack Structural Analysis for St Lucie Plant - Unit 1Safe Shutdown Earthquake
Earthquake
ML20196C1644 February 1988Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131
ML20205N95331 January 1988Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3Safe Shutdown
ML20205N94831 January 1988Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2Safe Shutdown
ML20195G55630 September 1987TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing,Maine Yankee Docket, Technical Evaluation ReptLoop seal
Anticipated operational occurrence
Anchor Darling
ML20195G54530 September 1987TMI Action-NUREG-0737 (II.D.1) Relief & Safety Valve Testing Waterford Steam Electric Station,Unit 3, Technical Evaluation ReptLoop seal
Anticipated operational occurrence
ML20236F79330 September 1987Structural Adequacy of Waterford 3 Basemat, Technical Evaluation Rept
ML18040B18931 August 1987Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs.
ML20235M35931 August 1987Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation ReptBoric Acid
ML20235V15231 August 1987Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Peach Bottom 2 & 3,Perry 1 & 2,Pilgrim 1,Quad Cities 1 & 2,River Bend 1, Shoreham,Susquehanna 1 & 2,Vermont Yankee & WNP-2
ML20237J06219 August 1987Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations SpdsBackfit
ML20237J14117 August 1987Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807
ML20236P64031 July 1987Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept
ML20236D91831 July 1987Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAsProbabilistic Risk Assessment
Earthquake
ML17347A59331 July 1987Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept