ML20045F335
| ML20045F335 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 06/30/1993 |
| From: | NORTHEAST UTILITIES SERVICE CO. |
| To: | |
| Shared Package | |
| ML20045F319 | List: |
| References | |
| NUDOCS 9307070192 | |
| Download: ML20045F335 (250) | |
Similar Documents at Haddam Neck | |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20199L5891997-12-24024 December 1997
[Table view]Independent Analysis & Evaluation of AM-241 & Transuranics & Subsequent Dose to Two Male Workers at Connecticut Yankee Atomic Power Plant ML20210P8721997-08-31031 August 1997 Post Decommissioning Activities Rept, for Aug 1997 ML20141A0041997-05-31031 May 1997 Independent Assessment of Radiological Controls Program at Cyap Haddam Neck Plant Final Rept May 1997 ML20137H3031997-03-31031 March 1997 Rev 2 to Nuclear Training Loit/Lout Audit Reviews ML20137C6281997-03-14014 March 1997 Redacted Version of Rev 1 to Nuclear Training Loit/Lout Audit Reviews ML20135E3221997-02-13013 February 1997 Independent Review Team Rept 1996 MP -1 Lout NRC Exam Failures ML20134L2751997-02-0303 February 1997 Draft Rev to GPRI-30, Spent Fuel Storage Facility Licensing Basis/Design Basis ML20134L2911997-01-0808 January 1997 Rev 0 to UFSAR Rev Grpi ML20204B6811996-12-31031 December 1996 Nuclear Lemons Assessment of America Worst Commerical Nuclear Power Plants. 5th Edition ML20237E0751996-12-31031 December 1996 Decommissioning Cost Study for Connecticut Yankee Nuclear Power Plant ML20134L2591996-12-31031 December 1996 Rev 0 to Sys Reclassification ML20134L2721996-12-31031 December 1996 Commitment Mgt Grpi ML20134L2481996-12-30030 December 1996 Rev 0 to Sys Needed for Decommissioning Sys Evaluation Process ML20135E2711996-12-26026 December 1996 Evaluation of Intakes by Two Workers at CT Yankee Atomic Power Co ML20134L2841996-12-23023 December 1996 Rev 0 to Spent Fuel Pool Island Studies ML20134L2871996-12-19019 December 1996 Rev 0 to Grpi for Defueled Condition Fire Protection Technical Requirements ML20134L2381996-12-19019 December 1996 Rev 0 to Accident Analysis ML20058G3481993-10-31031 October 1993 Nonproprietary VIPRE/WRB-1 DNBR Thermal Limit for Westinghouse Fuel Types, for Oct 1993 ML20058G6771993-09-29029 September 1993 Rev 0 to Project Assignment 91-006, Connecticut Yankee Event V Mods ML20058L7411993-07-15015 July 1993 QA Svcs Dept Surveillance Rept SS-169, Assessment of Fitness for Duty Program ML20045F3351993-06-30030 June 1993 IPE for Severe Accident Vulnerabilities RA-93-022, Cy Containment Isolation Failure Probability1993-05-18018 May 1993 Cy Containment Isolation Failure Probability ML20127J5391992-11-30030 November 1992 Connecticut Yankee Structural Reevaluation of Plant Structures to Address SEP Topic III-7.B Load Combinations Code Changes ML20125E5661992-03-31031 March 1992 Nonproprietary PWR SG Tube Repair Limits:Technical Support Document for Expansion Zone PWSCC in Roll Transitions Final Rept A08995, Rev 1 to Auxiliary Initiation Event Analysis1990-09-14014 September 1990 Rev 1 to Auxiliary Initiation Event Analysis ML20062G4951990-07-31031 July 1990 Rev 3 to Northeast Utils USNRC Read & Sign ML20055G4951990-07-31031 July 1990 Decommissioning Financial Assurance Certification Rept ML20044A8481990-07-0202 July 1990 Vol 1 to Connecticut Yankee Simulator Certification Submittal:Connecticut Yankee Simulator Design Info & Certification Program Overview ML20055D8931990-06-30030 June 1990 Fracture Mechanics Evaluation:Haddam Neck Pressurizer ML20043A4831990-04-30030 April 1990 Rev 1 to Technical Rept Supporting Cycle 16 Operation ML20012A2281990-03-0101 March 1990 Vol 6 to Probabilistic Safety Study B13388, Zircaloy Clad Fuel Mechanical Design Rept1989-11-30030 November 1989 Zircaloy Clad Fuel Mechanical Design Rept ML20246N9421989-08-31031 August 1989 Tornado Missile Risk Analysis of Bleed & Feed & Auxiliary Feedwater Safe Shutdown Sys at Connecticut Yankee Atomic Power Station ML20044G5131989-07-31031 July 1989 Rev 1 to Final Rept J5439-89-001R1, Fluidelastic Instability Analysis of U-Bend Region of Westinghouse Model 27 Sg ML20206J9991988-10-31031 October 1988 Crdr Summary Rept, Per Suppl 1 to NUREG-0737 ML20153G4081988-06-0303 June 1988 Rev 0 to Conneticut Yankee Replace Nuclear Instrumentation Sys, Neo Project Description ML20153G4031988-03-0808 March 1988 Rev 0 to, Connecticut Yankee Modernize Reactor Protection Sys - Phase 2, Conceptual Project Description ML20235B5911987-09-24024 September 1987 Undated Technical Evaluation:Haddam Neck Plant Reanalysis of Non-LOCA DBAs & Tech Spec Change Requests in Support of Reload Cycle 15 B12619, Bimonthly Progress Rept 5:New Switchgear Bldg Const1987-07-31031 July 1987 Bimonthly Progress Rept 5:New Switchgear Bldg Const ML20214R6371987-06-30030 June 1987 Technical Rept Supporting Cycle 15 Operation ML20205Q7011987-04-30030 April 1987 Bimonthly Progress Rept 3:New Switchgear Bldg Const B12480, Const Design Info Submittal:New Switchgear Bldg Const. W/38 Oversize Encl1987-04-30030 April 1987 Const Design Info Submittal:New Switchgear Bldg Const. W/38 Oversize Encl ML20238C3751986-12-31031 December 1986 Connecticut Yankee 1986 Core XIII - Xiv Refueling Outage ALARA Rept ML20238C3821986-12-31031 December 1986 Connecticut Yankee 1986 Steam Generator Repair Outage ALARA Rept ML20209C7161986-12-31031 December 1986 Vols 1 & 2 to Isap,Haddam Neck Plant,Final Rept ML20206J8871986-06-30030 June 1986 Isap Public Safety Impact Model Project Analyses Summaries ML20202D5071986-06-30030 June 1986 Non-LOCA Transient Analysis ML20205T1201986-05-19019 May 1986 Steam Generator Tube Insp Rept for 1986 Refueling Outage ML20205T1231986-05-0808 May 1986 Steam Generator Tube W/55% Through Wall Defect Safety Evaluation for Structural Integrity CY-86-031, Rev 1 to 4.10.1(D) Inservice Insp of Steam Generator Tubes (Acceptance Criteria)1986-05-0808 May 1986 Rev 1 to 4.10.1(D) Inservice Insp of Steam Generator Tubes (Acceptance Criteria) 1997-08-31 Category:INDIVIDUAL PLANT EXAM (OF EXTERNAL EVENTS) MONTHYEARB14801, Provides Response to NRC Request for Addl Info Re Individual Plant Exam,Per GL 88-20.Rev 0 to CY-PRA-93-022 Rept Encl1994-04-18018 April 1994
[Table view]Provides Response to NRC Request for Addl Info Re Individual Plant Exam,Per GL 88-20.Rev 0 to CY-PRA-93-022 Rept Encl ML20045F3351993-06-30030 June 1993 IPE for Severe Accident Vulnerabilities 1994-04-18 Category:TEXT-SAFETY REPORT MONTHYEARML20217K3301999-10-19019 October 1999
[Table view]Safety Evaluation Supporting Amend 195 to License DPR-61 ML20206C8761999-04-28028 April 1999 Safety Evaluation Supporting Amend 194 to License DPR-61 CY-99-047, Ro:On 981217,identified Unsuccessful Dewatering of Cnsi HIC, Model PL8-120R,containing Resins.Caused by Apparent Failure of Dewatering Tree.Other HICs Have Been Procured,Recertified & Returned to Plant for Use1999-03-23023 March 1999 Ro:On 981217,identified Unsuccessful Dewatering of Cnsi HIC, Model PL8-120R,containing Resins.Caused by Apparent Failure of Dewatering Tree.Other HICs Have Been Procured,Recertified & Returned to Plant for Use 05000213/LER-1999-001, :on 990105,main Stack RM R-14A Pressure Compensating Signal Was Not Calibrated.Caused by Personnel Error.Revised Calibration Procedure.With1999-02-0101 February 1999
1999-04-28 |