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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20059J283 | 10 September 1990 | Forwards Updated Operator Licensing Exam Schedule for FY91, FY92,FY93 & FY94,per Generic Ltrs 90-07 & 89-12 | |
| ML20059G041 | 7 September 1990 | Lists Util Organizational Changes.Ac Kadak Named President & CEO & Jk Thayer Named vice-president,effective 901001 | |
| ML20059J668 | 7 September 1990 | Forwards Operator Licensing Natl Exam Schedule Through FY94, Per Generic Ltr 90-07 | |
| ML20059H179 | 7 September 1990 | Forwards Addl Info Re Control Element Assembly Failure at Facility | |
| ML20059G035 | 6 September 1990 | Advises That Util Intends to Modify Tech Specs Re Emergency Diesel Generator Surveillance Testing.Util Will Continue to Follow Testing Prescribed by Plant Tech Specs Until Such Time as Approval Received | |
| ML20059E108 | 28 August 1990 | Forwards Revised Diesel Generator Test Plan,Which Includes Addl Commitments Made During 900822 Discussions | |
| ML20059D983 | 28 August 1990 | Forwards fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71.NRC Review of Data Will Provide Realization That Positive Testing Rate Extremely Low & Limited to pre-access Testing Population | Fitness for Duty |
| BVY-90-087, Forwards Addl Info on Use of RELAP5YA Program for LOCA Analyses.Proprietary Encl Withheld | 28 August 1990 | Forwards Addl Info on Use of RELAP5YA Program for LOCA Analyses.Proprietary Encl Withheld | |
| ML20059B812 | 24 August 1990 | Provides fitness-for-duty Program Performance Data for Period Ending 900630 | |
| BVY-90-086, Responds to NRC Re Violations Noted in Insp Rept 50-271/90-06.Corrective Actions:Incident Rept Initiated & All Required Locking Devices in Place by 900706 | 24 August 1990 | Responds to NRC Re Violations Noted in Insp Rept 50-271/90-06.Corrective Actions:Incident Rept Initiated & All Required Locking Devices in Place by 900706 | |
| ML20059F286 | 23 August 1990 | Responds to NRC Re Violations Noted in Insp Rept 50-309/90-10 Re RCS Inventory.Corrective Actions:Root Cause Evaluation Initiated & RCS Stabilized by Increasing Water Inventory & Venting | |
| ML20059F668 | 22 August 1990 | Comments on Review of Amend 115 to License DPR-28,including Safety Evaluation.Requests Explanation of Statement in NRC Re How NRC Considers Comments & What Resolution Could Be for Each Util Comment in | |
| ML20059E934 | 22 August 1990 | Responds to Violations Noted in Insp Rept 50-309/90-11. Corrective Actions:Work Planning Meeting Held Weekly & Radiological Controls Supervision Utilizing Plan of Wk to Assign Radiological Controls Technicians to Specific Jobs | |
| ML20056B356 | 20 August 1990 | Forwards fitness-for-duty Program Performance Data for Jan- June 1990 | |
| ML20059B394 | 17 August 1990 | Advises That Util Performed Automated Ultrasonic Insp of Pressurizer Vessel Cladding Interface at Plant During 1990 Refueling Outage.Results of Insp Continue to Indicate No Evidence of Any Cladding Indication | |
| BVY-90-085, Informs That Sys Testing & Operator Training Successfully Completed & SPDS Declared Operable on 900813.Util Intends to Operate SPDS in Parallel W/Original Honeywell Gepac Plant Computer Until mid-Nov 1990 | 15 August 1990 | Informs That Sys Testing & Operator Training Successfully Completed & SPDS Declared Operable on 900813.Util Intends to Operate SPDS in Parallel W/Original Honeywell Gepac Plant Computer Until mid-Nov 1990 | |
| ML20059A811 | 10 August 1990 | Responds to Emergency Preparedness Exercise & Routine Insp Repts 50-309/88-09 & 90-14,respectively.Corrective Actions: Remedial Training Will Be Given to Available Emergency Coordinators in Use of Procedures for Developing PARs | |
| ML20058N081 | 9 August 1990 | Request Relief from ASME Section XI Requirements for Low Pressure Surge Tank Cooling Pumps,Per Generic Ltr 89-04 as Result of Review of Facility Inservice Testing Program | |
| ML20058P374 | 9 August 1990 | Forwards Monthly Operating Rept for Jul 1990 for Maine Yankee Atomic Power Station & Revised Rept for June 1990 | |
| ML20058L224 | 3 August 1990 | Forwards Peer Review of 900705 Reactor Pressure Vessel Evaluation,Prepared by Le Steele.Review Indicates Agreement W/Methodology in Chapter 5 of Evaluation | |
| ML20058L221 | 2 August 1990 | Forwards Results of PTS Sensitivity Study for Mean Values of Ref Temps for Four Matls in Beltline Region | |
| ML20055J201 | 27 July 1990 | Provides Steam Generator Insp Results & Advises of Nine Defective Tubes Discovered During Jul 1990 Insp.Complete Results Will Follow within 12 Months,Per Tech Spec 4.4.10.5.b | |
| ML20055H670 | 25 July 1990 | Forwards Decommissioning Funding Assurance Rept & Certification, Per 10CFR50.75.Rept Includes Certification That Reasonable Assurance Will Be Provided That Funds Will Be Available for Decommissioning | |
| BVY-90-082, Informs That Effective 900723 Facility Implemented Rev 4 of Procedure Generating Package & Corresponding Revs to Eops. Revs Developed Per Rev 4 of BWR Owners Group Emergency Procedure Guidelines | 24 July 1990 | Informs That Effective 900723 Facility Implemented Rev 4 of Procedure Generating Package & Corresponding Revs to Eops. Revs Developed Per Rev 4 of BWR Owners Group Emergency Procedure Guidelines | |
| BVY-90-084, Notifies NRC of Intentions to Install Test Fuel Assemblies & Test Control Blades During Cycle 15 Refueling Outage in Sept 1990 | 24 July 1990 | Notifies NRC of Intentions to Install Test Fuel Assemblies & Test Control Blades During Cycle 15 Refueling Outage in Sept 1990 | Shutdown Margin |
| ML20055G665 | 20 July 1990 | Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Model 1153 Series D Transmitters Not Currently in Use at Plant | |
| BVY-90-071, Forwards Rev 2 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21) | 20 July 1990 | Forwards Rev 2 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21) | |
| ML20055G696 | 20 July 1990 | Forwards YAEC-1731, Yankee Nuclear Power Station Core 21 Performance Analysis. Results of Analysis Demonstrate That Plant Performance Well within Acceptable Limits | |
| ML20055G678 | 19 July 1990 | Forwards, Yankee Plant Small Break LOCA Analysis | |
| ML20055G703 | 19 July 1990 | Forwards Rev 0 to Yankee Cycle 21 Core Operating Limits Rept. Cycle Scheduled for Startup on 900811 | |
| ML20055G688 | 19 July 1990 | Submits Results of Analysis of Component Cooling Heat Balance to Support Operation at 2,700 Mwt.Prior Administrative Controls Overly Conservative & No Longer Required | |
| BVY-90-078, Forwards List of Refs for Proposed Change 161 to Facility OL & Tech Specs | 17 July 1990 | Forwards List of Refs for Proposed Change 161 to Facility OL & Tech Specs | |
| ML20055H829 | 16 July 1990 | Forwards Response to Request for Addl Info Re YAEC-1710, Yankee Nuclear Power Station Pilot Evaluation Rept for Plant License Renewal, & YAEC-1727P, Methodology for Identifying Potential Fluid Component Age-Related.. | License Renewal |
| ML20055H002 | 16 July 1990 | Forwards Rev 24 to Security Plan.Rev Withheld | |
| ML20055E153 | 5 July 1990 | Forwards Reactor Pressure Vessel Evaluation Rept, in Response to NRC 900501,07 & 15 Requests for Addl Info. Specific Chapters Re Requests Listed | |
| ML20055E064 | 3 July 1990 | Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Outstanding Procurement Actions for Rosemount Pressure & Differential Pressure Transmitters Modified to Specify Mfg After 890711 | |
| ML20055D037 | 2 July 1990 | Responds to 900319 Commitment to Provide Scope & Schedule for Confirmatory Analysis for Steam Generator Overfill Protection by 900702.Scope of Analysis Will Include Identification of Potential Overfill Scenarios | |
| ML20055E050 | 2 July 1990 | Responds to Info Notice 88-085 & NRC Bulletin 89-002 Re Two Anchor/Darling Swing Check Valves.Neither Valve Found to Have Any Svc Induced Cracking of Bolting.Existing Bolting Replaced W/Type 17-4PH Matl (Specification A564-630-1100) | |
| ML20058K360 | 28 June 1990 | Forwards Addl Info to Support Proposed Change 234,modifying Tech Specs to Incorporate Wording Consistent w/NUREG-0452, STS for Westinghouse PWRs Re Min Discharge Pressure | |
| ML20058K302 | 27 June 1990 | Provides Addl Info for Proposed Change 227 to License DPR-3. One Addl LPSI Pump Must Be Capable of Being Placed in Operable Status When Utilizing Spec 3.10.6 | |
| BVY-90-072, Forwards Supplemental Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters 1989,Including Annual Radiological Impact on Man for 1989 | 27 June 1990 | Forwards Supplemental Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters 1989,Including Annual Radiological Impact on Man for 1989 | |
| ML20055D461 | 25 June 1990 | Responds to NRC Re Violations Noted in Insp Rept 50-309/89-82.Corrective Actions:Testing Program Developed & Implemented for Testing of Molded Case Circuit Breakers & Procedure Modified to Address Revised Dedication Process | |
| ML20043G435 | 15 June 1990 | Requests Temporary Waiver of Compliance from Tech Spec Requirements for Limiting Conditions for Operation for Certain post-accident Monitoring Instrumentation Listed in Tech Spec Table 3.2.6.Parameters Listed | |
| ML20043E401 | 8 June 1990 | Responds to Second Request for Addl Info on Use of RELAP5YA. Explanation Re Why More Accurate View Factor Calculation Not Included in Huxy Code Addressed | |
| ML20043C599 | 1 June 1990 | Forwards Accepted Version of YAEC-1683-A, MICBURN-3/ CASMO-3/TABLES-3/SIMULATE-3 Benchmarking of Vermont Yankee Cycles 9 Through 13. | |
| ML20043C613 | 1 June 1990 | Forwards YAEC-1659-A, Simulate-3 Validation & Verification. | |
| ML20043C482 | 30 May 1990 | Informs of Three Organizational Changes That Will Become Effective on 900601.WP Murphy,Jp Pelletier & DA Reid Will Be Senior Vice President of Operations,Newly Created Vice President of Engineering & Plant Manager,Respectively | |
| ML20043B756 | 23 May 1990 | Informs That Util Intends to Utilize Relationship Between Frosstey & FROSSTEY-2 to Support Cycle 15 Calculations.Nrc Approval of FROSSTEY-2 Needed by Aug 1990 for LOCA Analysis Program |