ML20055G680
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| ML20055G680 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/31/1990 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20055G679 | List: |
| References | |
| NUDOCS 9007240065 | |
| Download: ML20055G680 (39) | |
Similar Documents at Yankee Rowe | |
|---|---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20216C4581998-02-27027 February 1998
[Table view]Some use of "" in your query was not closed by a matching "".Response to NRC Demand for Info (NRC OI Rept 1-95-050) ML20203L1931998-02-25025 February 1998 Duke Energy Corp,Duke Engineering & Svcs,Inc,Yankee Atomic Small Break LOCA Technical Review Rept ML20203L2451998-02-23023 February 1998 Assessment Rept of Engineering & Technical Work Process Utilized at De&S Bolton Ofc ML20203L1621998-02-18018 February 1998 Rept of Root Cause Assessment Review ML20203L2691998-02-16016 February 1998 Duke Engineering & Svcs Assessment Process Review Rept ML20056H1741993-06-10010 June 1993 Preliminary Assessment of Potential Human Exposures to Routine Tritium Emissions from Yankee Atomic Electric Co Nuclear Power Facility Located Near Rowe,Ma ML20062H1981990-11-30030 November 1990 Plant Specific Fast Neutron Exposure Evaluations for First 20 Operating Fuel Cycles of Yankee Rowe Reactor ML20055E1591990-07-31031 July 1990 Reactor Pressure Vessel Evaluation Rept ML20055G6801990-07-31031 July 1990 Yankee Plant Small Break LOCA Analysis ML20055J3221990-07-25025 July 1990 Decommissioning Funding Assurance Rept & Certification ML20155G6101988-09-30030 September 1988 App a Rev 1 to Incore Detection Sys Analysis ML20155G6661988-06-0303 June 1988 Reanalysis of 1984 Eddy Current Data for Steam Generators 3 & 4, Supplemental Rept ML20151H9581988-04-30030 April 1988 CASMO-3G Validation ML20151A3711988-03-31031 March 1988 Cask Drop Analysis Yankee Nuclear Power Station Spent Fuel Pool ML20148Q9031988-03-31031 March 1988 Incore Detection Sys Analysis ML20148G5431988-01-15015 January 1988 Nonproprietary Mods to Critical Flow Model in RELAP5YA ML20234F0851987-12-30030 December 1987 Revised Summary Evaluation of Reactor Pressure Vessel/ Neutron Shield Tank Seismic Response & Amplified Response Spectra Generation ML20147B3151987-11-30030 November 1987 Rev to Yankee Atomic Electric Co Reflood Heat Transfer Correlation ML20149L5461987-10-31031 October 1987 Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20235P2761987-10-0101 October 1987 Reg Guide 1.97 Nuclear Instrumentation Analysis ML20239A0921987-09-30030 September 1987 Assessment of Benefits & Potential Impacts of Proposed Change to Expiration Date of Plant Ol ML20206D5711987-03-27027 March 1987 Vapor Container Seismic Evaluation Soil Bearing Capacity Analysis ML20203N5641986-09-30030 September 1986 Rev 0 to Leak-Before-Break Evaluation for 5-Inch Diameter Bypass Lines at Yankee Nuclear Power Station ML20212P8421986-08-22022 August 1986 Auxiliary Power Sys Voltage Study for Yankee Nuclear Power Station ML20137B0181985-09-19019 September 1985 Fire Water Tank Seismic Analysis for Yankee Nuclear Power Station ML20133P8401985-08-0606 August 1985 Refueling Cavity Water Seal Evaluation ML20133B5081985-08-0101 August 1985 Dcrdr Summary Rept for Yankee Nuclear Power Station ML20214E5211985-01-31031 January 1985 Assessment of Structural Seismic Design Adequacy of Yankee Nuclear Power Station ML20138L1881984-09-30030 September 1984 Tornado Cost-Benefit Analysis for Proposed Backfits of Yankee Nuclear Power Station ML20212M8411981-03-31031 March 1981 Analysis of Fast Neutron Flux Levels & End-of-Life Exposure for Yankee Rowe Reactor Pressure Vessel ML20132A8621979-08-21021 August 1979 Assessment of Effect of Increased Fuel Rod Fill Gas Pressure on Core 14 ECCS Performance Analysis ML20148G9291976-09-30030 September 1976 App C,Addl LOCA Analysis W/Revised Upper Hemispherical Head Temp ML20148E9731975-12-11011 December 1975 Energy Absorption by Size 14 Figure 607 Valve Seat & Disk at Yankee Rowe ML20148E9681975-08-13013 August 1975 Disk Velocity at Impact W/Seat for Line Break at Upstream Side of Size 14 Figure 607 Non-Return Valve 1998-02-27 Category:TEXT-SAFETY REPORT Some use of "" in your query was not closed by a matching "". [Table view]Some use of "" in your query was not closed by a matching "". |
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