ML20203L162
From kanterella
ML20203L162 | |
Person / Time | |
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Site: | Yankee Rowe |
Issue date: | 02/18/1998 |
From: | DUKE ENGINEERING & SERVICES |
To: | |
Shared Package | |
ML20203L159 | List: |
References | |
NUDOCS 9803050381 | |
Download: ML20203L162 (32) | |
Similar Documents at Yankee Rowe | |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20216C4581998-02-27027 February 1998
[Table view]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 ML20148Q9031988-03-31031 March 1988 Incore Detection Sys Analysis ML20151A3711988-03-31031 March 1988 Cask Drop Analysis Yankee Nuclear Power Station Spent Fuel Pool 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 MONTHYEARML20217C1311999-10-0808 October 1999
[Table view]Safety Evaluation Supporting Amend 153 to License DPR-3 ML20211J5111999-08-31031 August 1999 Rev 29 to Yankee Decommissioning QA Program ML20211J3361999-08-27027 August 1999 Safety Evaluation Supporting Amend 152 to License DPR-3 ML20209D5391999-06-22022 June 1999 Rev 29 to Yaec Decommissioning QA Program ML20207F9491999-03-0505 March 1999 Safety Evaluation Supporting Amend 151 to License DPR-3 ML20202H5871999-02-0303 February 1999 Safety Evaluation Supporting Amend 150 to License DPR-3 ML20154P9691998-10-16016 October 1998 Rev 28 to Yankee Atomic Electric Co Decommissioning QA Program ML20249A7901998-06-17017 June 1998 Safety Evaluation Supporting Amend 149 to License DPR-3 ML20216C4581998-02-27027 February 1998 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 ML20199B4601998-01-20020 January 1998 Special Rept:On 980105,meteorological Monnitoring Instrumentation for Air Temp Delta T Inoperable for More than 7 Days.Caused by Breakdown in Wiring Between Junction Box at 199 Foot Level.Wiring Replaced ML20203J3001997-12-31031 December 1997 Ynps 1997 Annual Rept ML20217N0981997-08-21021 August 1997 LER 97-S02-00:on 970725,discovered Uncontrolled Safeguards Documents.Caused by Personnel Error.Matls Retrieved & Stored in Safeguards Repositories ML20210H0991997-08-0707 August 1997 LER 97-S01-00:on 970709,potential Compromise of Safeguards Info Occurred.Caused by Human error.Stand-alone Personal Computer & Printer Not Connected to Network,Have Been Located within Text Graphics Svc Dept ML20149K7781997-07-24024 July 1997 Special Rept:On 970520 & 0714,air Temp Delta T Channel Indicated Temp Difference Between Top & Bottom of Meteorological Tower.Caused by Reversed Input Wiring to Channel.Restored Air Temp Delta T Channel Operability ML20141E4671997-05-30030 May 1997 Rev 28 to Operational QA Program ML20135C8461996-12-31031 December 1996 Yankee Nuclear Power Station 1996 Annual Rept ML20132G6771996-12-20020 December 1996 Rev 27 to YOQAP-I-A, Operational QA Program ML20058N4771993-12-20020 December 1993 Rev 0.0 to Yankee Nuclear Power Station Decommissioning Plan ML20059K8491993-12-15015 December 1993 Clarifications to Pages 2,41,43 & 44 of 44 in Section I, Organization of YOQAP-I-A,Rev 24, Operational QA Program ML20059C5011993-10-29029 October 1993 Special Rept:On 931019,meteorological Instrumentation Channel for Delta T Declared Inoperable.Caused by Ceased Aspirator Motor Located at Top of Tower.Motor Replaced 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 ML20237F1671993-02-19019 February 1993 Safety Evaluation Supporting Amend 147 to License DPR-3 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20198D2481992-05-13013 May 1992 Yankee Nuclear Power Station Certified Fuel Handler Initial Certification Program ML20198D2541992-05-13013 May 1992 Yankee Nuclear Power Station Certified Fuel Handler Recertification Program ML20062H1981990-11-30030 November 1990 Plant Specific Fast Neutron Exposure Evaluations for First 20 Operating Fuel Cycles of Yankee Rowe Reactor ML20058H2841990-11-0303 November 1990 Special Rept:On 901101,control Rod 24 Found Disconnected from Drive Shaft.Drive Shaft Latching Will Be Initiated ML20058F2201990-11-0202 November 1990 Safety Evaluation Accepting Util Response to Generic Ltr 83-28 Re post-trip Review - Data & Info Capability ML20062E8331990-10-31031 October 1990 Monthly Operating Rept for Oct 1990 for Yankee Atomic Power Station ML20058G1471990-10-31031 October 1990 Vol 2 to Star Methodology Application for PWRs Control Rod Ejection Main Steam Line Break ML20058C4061990-10-22022 October 1990 Safety Evaluation Supporting Amend 137 to License DPR-3 ML20062B6751990-09-30030 September 1990 Monthly Operating Rept for Yankee Atomic Power Station for Sept 1990 ML20059G2411990-09-0606 September 1990 Safety Evaluation Supporting Amend 135 to License DPR-3 ML20059E3071990-08-31031 August 1990 Safety Assessment of Yaec 1735, Reactor Pressure Vessel Evaluation Rept for Yankee Nuclear Power Station. Detailed Plan of Action W/Listed Elements Requested within 60 Days After Restart to Demonstrate Ability to Operate Longer ML20059E8001990-08-31031 August 1990 Monthly Operating Rept for Aug 1990 for Yankee Atomic Power Station ML20058P7841990-08-14014 August 1990 Part 21 Rept Re Misapplication of Fluorolube FS-5 Oil in Main Steam Line Pressure Gauges.All Four Indicators Replaced W/Spare Gauges Which Utilize High Temp Silicone Oil ML20058N6581990-08-13013 August 1990 Special Rept Re Diesel Fire Pump & Tank Inoperable for Greater than Seven Days for Draining,Cleaning & Insp.During Period Redundant Pumping Capacity Available Via Two Remaining Electric Driven Fire Pumps ML20058L6651990-08-0202 August 1990 Safety Evaluation Supporting Amend 134 to License DPR-3 ML20058L0321990-08-0202 August 1990 Safety Evaluation Supporting Amend 133 to License DPR-3 ML20056A1961990-08-0101 August 1990 Special Rept:Two Fire Pumps Inoperable at Same Time.Caused by Necessity to Accomplish Surveillance to Verify Capability to Start Pump on Emergency Diesel Generator 3 & Planned 18-month Insp of Diesel Per Tech Specs ML20055G6801990-07-31031 July 1990 Yankee Plant Small Break LOCA Analysis ML20055E1591990-07-31031 July 1990 Reactor Pressure Vessel Evaluation Rept ML20055G7011990-07-31031 July 1990 Yankee Nuclear Power Station Core 21 Performance Analysis ML20055J3221990-07-25025 July 1990 Decommissioning Funding Assurance Rept & Certification ML20055G7051990-07-19019 July 1990 Rev 0 to Yankee Cycle 21 Core Operating Limits Rept ML20055F6751990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Yankee Atomic Power Station 1999-08-31 |
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