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Issue date | Title | Topic | |
---|---|---|---|
ML20212D678 | 31 March 1999 | Supplemental Technical Evaluation Report Based on Review of Additional Responses Concerning Individual Plant Examination of External Events at Point Beach Nuclear Plant,Units 1 & 2. Final Rept | Hot Short Safe Shutdown Fire Barrier Safe Shutdown Earthquake Earthquake |
ML20212J260 | 31 March 1998 | Technical Evaluation Rept on 'Submittal Only' Review of IPEEE at Pilgrim Nuclear Power Station, Final Rept | Hot Short Safe Shutdown High winds Ultimate heat sink Mission time Fire Barrier Tornado Missile Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Tornado Generated Missile Seismically rugged Earthquake Fire Protection Program |
ML20212D641 | 31 March 1998 | Technical Evaluation Report on Submittal Only Review of Individual Plant Examination of External Events at Point Beach Nuclear Plant,Units 1 & 2. Final Rept | Hot Short Safe Shutdown High winds Ultimate heat sink Mission time Fire Barrier Tornado Missile Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Operating Basis Earthquake Earthquake Turbine Missile |
ML20134D193 | 31 July 1996 | Review of Plant Implementation of Soultion I-D:Use of LAPUR-5 for Exclusion Region Calculations | |
L-96-017, TER on Third 10-Yr Interval ISI Program Plan:Boston Edison Co,Pilgrim Nuclear Power Station | 30 June 1996 | TER on Third 10-Yr Interval ISI Program Plan:Boston Edison Co,Pilgrim Nuclear Power Station | Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Liquid penetrant Through-Wall Leak Backfit |
ML20128K206 | 31 May 1996 | Technical Evaluation Rept of Pilgrim IPE Back-End Submittal Final Rept | Probabilistic Risk Assessment Hardened vent |
ML20128K213 | 11 April 1996 | Plant Technical Evaluation Rept on IPE Submittal Human Reliability Analysis,Final Rept | Internal Flooding Probabilistic Risk Assessment |
ML20128K187 | 9 April 1996 | Pilgrim,Technical Evaluation Rept on IPE Front End Analysis | Internal Flooding Probabilistic Risk Assessment Hardened vent |
ML20100F086 | 30 November 1995 | TER of Vermont Yankee Ipe,Back End Submittal, Final Rept | Probabilistic Risk Assessment Hardened vent Weak link |
ML20100F061 | 30 November 1995 | TER on Ipe,Front End Analysis | Mission time Internal Flooding Probabilistic Risk Assessment |
ML20100F068 | 20 November 1995 | TER of IPE Submittal,Human Reliability Analysis, Final Rept | Internal Flooding Temporary Modification |
L-95-005, Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan | 30 April 1995 | Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan | Hydrostatic VT-2 Incorporated by reference |
L-94-013, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01, for Plant | 30 November 1994 | Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01, for Plant | Reactor Vessel Water Level Scram Discharge Volume |
ML20078E047 | 4 October 1994 | TER on Front End IPE Submittal, Task 22,dtd 941004 | Boric Acid Mission time Internal Flooding Probabilistic Risk Assessment |
ML20080B092 | 30 September 1994 | Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01, for Plant | |
ML20078E122 | 30 September 1994 | IPE Back-End TER Dtd Sept 1994 | Mission time Internal Flooding Severe Accident Management Guideline |
ML20082A639 | 30 September 1994 | Review of Technical Issues Related to Long Term Solution I-D 'Regional Exclusion w/Flow-Biased APRM Scram.' | |
ML20078E150 | 31 August 1994 | TER of IPE Submittal Human Reliability Analysis, Final Rept, Task 23.Draft Dtd 940131,final Aug 1994 | Internal Flooding Probabilistic Risk Assessment |
ML20141D327 | 31 August 1994 | Dispersion Estimates in Vicinity of Buildings | |
ML20073S648 | 10 June 1994 | Technical Evaluation:Core Thermal Limit Protection Function Setpoint Methodology for Seabrook Station YAEC-1854P for Yankee Atomic Electric Co | Anticipated operational occurrence |
ML20063H271 | 31 January 1994 | Evaluation of Utility Response to Suppl 1 to NRC Bulletin 90-01: Vermont Yankee, Technical Evalution Rept | |
ML20149D729 | 31 August 1993 | Pressurized Thermal Shock Probabilistic Fracture Mechanics Sensitivity Analysis for Yankee Rowe Reactor Pressure Vessel | |
ML20056D271 | 30 June 1993 | TER Pump & Valve Inservice Testing Program Vermont Yankee Nuclear Power Station | Ultimate heat sink Stroke time Scram Discharge Volume Power-Operated Valves |
ML20044E739 | 23 June 1993 | Technical Evaluation Rept Pump & Valve Inservice Testing Program Pilgrim Nuclear Power Station. | High Radiation Area Ultimate heat sink Stroke time Squib Scram Discharge Volume Excess Flow Check Valve Cold shutdown justification Power-Operated Valves Power Operated Valves Scaffolding Grace period |
ML20116J685 | 31 October 1992 | High Pressure Coolant Injection (HPCI) System RISK-BASED Inspection Guide.Pilgrim Nuclear Power Station | Reactor Vessel Water Level Probabilistic Risk Assessment Overtravel |
ML20106B289 | 31 July 1992 | Technical Evaluation Rept of FROSSTEY-2 Fuel Performance Code | |
ML20097A828 | 6 April 1992 | Technical Evaluation Rept Pump & Valve Inservice Testing Program Point Beach Nuclear Power Plant,Units 1 & 2 Wepc, Per 10CFR50.55a(g) | Boric Acid Stroke time Anchor Darling Incorporated by reference Cold shutdown justification Power Operated Valves |
ML20094F055 | 31 January 1992 | Rev 1 to Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Pilgrim Nuclear Power Station | High Radiation Area Ultimate heat sink Stroke time Scram Discharge Volume Fast acting solenoid valve Cold shutdown justification Power-Operated Valves Power Operated Valves |
ML20091H875 | 17 December 1991 | Final Technical Evaluation Rept,Seabrook Station Unit 1 Station Blackout Evaluation | Safe Shutdown Battery sizing |
ML20073E564 | 31 March 1991 | Technical Evaluation Rept Pump & Valve Inservice Testing Program,Pilgrim Nuclear Power Station | High Radiation Area Ultimate heat sink Stroke time Scram Discharge Volume Cold shutdown justification Power-Operated Valves Power Operated Valves |
ML20029A639 | 30 September 1990 | Review of Huxy Code for Determining Radiation View Factors for Vermont Yankee, Technical Evaluation Rept | |
ML20055J411 | 30 July 1990 | 1990 Shift Estimates for Yankee Rowe Vessel | |
ML20072P775 | 30 June 1990 | Conformance to Reg Guide 1.97:Pilgrim | Post Accident Monitoring Squib Fuel cladding |
ML20065C835 | 31 May 1990 | Conformance to Reg Guide 1.97:Vermont Yankee, Technical Evaluation Rept | Post Accident Monitoring Fuel cladding |
ML20006F035 | 30 November 1989 | Technical Evaluation Rept on First 10-yr Interval Inservice Insp Program Plan:Public Svc of New Hampshire,Seabrook Station,Unit 1. | Incorporated by reference Dissimilar Metal Weld |
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 |
ML19327B676 | 3 October 1989 | Technical Evaluation Rept for Boston Edison Co,Pilgrim Station Dcrdr Suppl Summary Rept. | |
ML19327B673 | 3 October 1989 | Technical Evaluation Rept for Dcrdr at Boston Edison Co, Pilgrim Nuclear Power Station. | |
ML20248E219 | 16 August 1989 | Mod 16,reflecting Return of Equipment to Tva,To Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators | |
ML20248E212 | 16 August 1989 | Notification of Contract Execution,Mod 16,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn for Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva | |
ML20244A470 | 31 May 1989 | Rev 1 to Technical Evaluation Rept,Tmi Action--NUREG-0737 (II.D.1),Relief & Safety Valve Testing,Seabrook Nuclear Station - Units 1 & 2 | |
ML20247R394 | 16 May 1989 | Mod 15,extending Period of Performance,Providing Addl Work Re Training for NRC Inspectors & Supervisors,Changing NRC Project Officer & Adding TVA Project Manager & Increasing Contract Ceiling & Funding to Use of TVA Reactor.. | |
ML20247R385 | 16 May 1989 | Notification of Contract Execution,Mod 15,to Use of TVA Reactor Simulator Facilities at Chattanooga,Tn,For Training on Browns Ferry,Sequoyah & Bellefonte Simulators. Contractor:Tva | |
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 | |
ML20245G779 | 12 April 1989 | In-Progress Audit Rept for Boston Edison Co Pilgrim Nuclear Power Station Spds | |
ML20245G760 | 12 April 1989 | In-Progress Audit Rept of Dcrdr at Boston Edison Co Pilgrim Nuclear Power Station | |
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 | |
ML20235H597 | 30 January 1989 | Evaluation of Pilgrim Offsite Dose Calculation Manual Through Rev 2 | Grab sample Offsite Dose Calculation Manual |
ML20245E937 | 31 December 1988 | Rev 1 to EGG-NTA-8030, TMI Action--NUREG-0737 (II.D.1) Point Beach,Units 1 & 2, Technical Evaluation Rept | Loop seal Stroke time Anticipated operational occurrence Earthquake |