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Issue date | Title | Topic | |
---|---|---|---|
ML17229B067 | 16 March 1999 | Technical 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 |
ML20203H882 | 30 September 1998 | Technical Evaluation Rept on Second 10-year ISI Program Plan:Entergy Operations,Waterford-3 Steam Electric Station | VT-2 Incorporated by reference |
ML17355A280 | 30 September 1998 | Rev 1,Ltr Rept, Technical Evaluation of Florida Power & Light Fire Barrier Ampacity Derating Assessment for St.Lucie & Turkey Point. | Fire Barrier Coatings |
ML17229B001 | 31 January 1998 | Technical 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 |
ML17229A415 | 27 May 1997 | Technical Evaluation Rept of IPE Submittal & RAI Responses for St Lucie Nuclear Plant. | Boric Acid Ultimate heat sink Mission time Internal Flooding Probabilistic Risk Assessment |
ML20135E584 | 26 February 1997 | Revised, TER of IPE Submittal & RAI Responses for Waterford-3 Steam Electric Station | Safe Shutdown Boric Acid Ultimate heat sink Mission time Internal Flooding |
ML20147A710 | 31 December 1996 | Technical Ltr Rept, Pacific Northwest Natl Lab Review of Main Yankee In-Situ Pressure Test Assessment, Rev 2 | Safe Shutdown Earthquake Finite Element Analysis Flow Induced Vibration |
ML20148C644 | 30 June 1996 | Review of Operating Experience for Maine Yankee from Jan 1993 - Mar 1996 | Unanalyzed Condition Fire Barrier Temporary Modification Fire Watch |
ML17228B126 | 31 March 1995 | Technical Evaluation Rept on Second 10-Year Interval Insp Program Plan. | Hydrostatic Nondestructive Examination Incorporated by reference Dissimilar Metal Weld Scaffolding |
ML17309A747 | 30 September 1994 | Technical Evaluation Rept;Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-001:St.Lucie-1/-2. | |
ML17228A885 | 30 September 1994 | Errata 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 | |
ML20138E148 | 22 June 1993 | Pump & Valve Inservice Testing Program St Lucie Unit 2 FPL, Technical Evaluation Rept | Boric Acid Stroke time Incorporated by reference Power Operated Valves Backfit |
ML20105D087 | 31 August 1992 | Auxiliary Feedwater System RISK-BASED Inspection Guide for the St. Lucie Unit 1 Nuclear Power Generation Station | Probabilistic Risk Assessment |
ML17309A665 | 30 November 1991 | Technical Evaluation Rept Pump & Valve Inservice Testing Program,St Lucie-Unit 1. | Boric Acid Shutdown Margin Stroke time Power-Operated Valves Power Operated Valves |
ML20082S937 | 30 September 1991 | Trip Rept:Onsite Analysis of Human Factors of Event at Waterford 3 on 910624 (Manual Reactor Trip W/Excess Steam Demand) | Boric Acid Stroke time |
ML17223B323 | 31 August 1991 | TER 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 |
ML20082N092 | 18 June 1991 | Draft Assessment of Intersystem LOCA Risks - Methodology & Application:C-E Plant | |
ML17308A504 | 17 August 1990 | Final Technical Evaluation Rept St Lucie Unit 1 Station Blackout Evaluation. | Safe Shutdown Boric Acid |
ML20058K870 | 9 July 1990 | Rev 2 to Technical Evaluation Rept,Maine Yankee Atomic Power Station,Station Blackout Evaluation | |
ML19332B614 | 31 October 1989 | Conformance to Generic Ltr 83-28,Item 2.2.1--Equipment Classification for All Other Safety-Related Components:Quad Cities 1 & 2, Final Technical Evaluation Rept | Safe Shutdown |
ML17308A482 | 31 May 1989 | Conformance to Generic Ltr 83-28,Item 2.2.1,Equipment Classification for All Other Safety-Related Components,St Lucie 1/2, Technical Evaluation Rept | |
ML20246N697 | 2 May 1989 | Summary of Environ Data from Plant for 1988 | |
ML20246B815 | 30 April 1989 | Rev 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 | |
ML20246B973 | 31 March 1989 | Conformance to Reg Guide 1.97:Byron 1/2 & Braidwood 1/2, Technical Evaluation Rept | Boric Acid |
ML20236B805 | 13 March 1989 | Monthly Progress Rept for Contract NRC-02-87-004 for Period 890204-890303.Financial Data Available in Central Files | |
ML17222A741 | 31 January 1989 | Technical 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 |
ML20070Q767 | 31 December 1988 | Nuclear Power Plant Sys Sourcebook,Waterford 3 | Safe Shutdown Boric Acid Ultimate heat sink Emergency Lighting B.5.b Mitigating Strategies |
ML17223A129 | 31 December 1988 | Technical 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 |
ML17223A132 | 31 December 1988 | Technical 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 |
ML20244C293 | 30 November 1988 | Review of Florida Power & Light Co Safety Evaluations for Extending St Lucie Plant,Unit 2,ESFAS Subgroup Relay Test Interval, Technical Evaluation Rept | |
ML20235C472 | 31 October 1988 | Pump & Valve Inservice Testing Program,Waterford Steam Electric Station,Unit 3 | Boric Acid Stroke time Power-Operated Valves Power Operated Valves |
ML20205N943 | 31 October 1988 | Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-1 | |
ML20207J439 | 30 June 1988 | Conformance to Reg Guide 1.97:Maine Yankee, Technical Evaluation Rept | Boric Acid Fuel cladding |
ML17308A446 | 31 March 1988 | Technical Evaluation Rept for Natural Circulation,Boron Mixing & Cooldown at St Lucie Unit 2. | Tornado Missile |
ML20148M069 | 31 March 1988 | Technical Evaluation Rept for Natural Circulation,Boron Mixing & Cooldown at Waterford Unit 3 | |
ML20196G292 | 29 February 1988 | Technical Evaluation Rept,Evaluation of High Density Spent Fuel Rack Structural Analysis for St Lucie Plant - Unit 1 | Safe Shutdown Earthquake Earthquake |
ML20196C164 | 4 February 1988 | Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 | |
ML20205N953 | 31 January 1988 | Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Millstone-3 | Safe Shutdown |
ML20205N948 | 31 January 1988 | Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components - Millstone-2 | Safe Shutdown |
ML20195G556 | 30 September 1987 | TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing,Maine Yankee Docket, Technical Evaluation Rept | Loop seal Anticipated operational occurrence Anchor Darling |
ML20195G545 | 30 September 1987 | TMI Action-NUREG-0737 (II.D.1) Relief & Safety Valve Testing Waterford Steam Electric Station,Unit 3, Technical Evaluation Rept | Loop seal Anticipated operational occurrence |
ML20236F793 | 30 September 1987 | Structural Adequacy of Waterford 3 Basemat, Technical Evaluation Rept | |
ML18040B189 | 31 August 1987 | Selected Operating Reactors Issues:Stability Calculations for Grand Gulf 1 & Susquehanna 2 Bwrs. | |
ML20235M359 | 31 August 1987 | Preliminary Conformance to Reg Guide 1.97:Byron Units 1 & 2 & Braidwood Units 1 & 2, Technical Evaluation Rept | Boric Acid |
ML20235V152 | 31 August 1987 | Technical 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 | |
ML20237J062 | 19 August 1987 | Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds | Backfit |
ML20237J141 | 17 August 1987 | Facility Sys Analysis Support, Progress Rept 23 for 870713 -0807 | |
ML20236P640 | 31 July 1987 | Review of Recirculation Pump Trip Design for Brunswick Steam Electric Plants, Informal Rept | |
ML20236D918 | 31 July 1987 | Methodology and Application of Surrogate Plant PRA Analysis to the Rancho Seco Power Plant.Task 1 - Analysis of ANO-1 and Oconee PRAs | Probabilistic Risk Assessment Earthquake |
ML17347A593 | 31 July 1987 | Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept |