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Issue date | Title | Topic | |
---|---|---|---|
ML20057A279 | 12 August 1993 | Safety Evaluation Accepting Licensee Reasons Given for Delay in Completing short-term Actions Requested in Ieb 93-003, Resolution of Issues Re to Rv Water Level Instrumentation in Bwrs | Reactor Vessel Water Level |
ML20057A699 | 3 September 1993 | Safety Evaluation of IST Program Relief Requests for Pumps & Valves for Third 10-yr Insp Interval | Stroke time Incorporated by reference |
ML20127D899 | 6 May 1985 | Safety Evaluation Re 840925 & 1002 Responses to Generic Ltr 83-28,Item 1.1 Concerning post-trip Review Program & Procedures.Program & Procedures Acceptable | |
ML20128N353 | 11 October 1996 | Safety Evaluation Accepting Licensee Flaw Evaluation of Indication Found During Reactor Pressure Vessel Insp at Plant | |
ML20129G361 | 2 October 1996 | Safety Evaluation Accepting Proposed Repair for Plant Core Shroud | Safe Shutdown Non-Destructive Examination Safe Shutdown Earthquake Earthquake |
ML20132D897 | 22 July 1985 | Safety Evaluation Supporting Use of Pvrc Damping Values (ASME Code Case N-411) for Response Spectrum Seismic Piping Analyses | Earthquake |
ML20134F963 | 5 November 1996 | Safety Evaluation Re Power/Flow Exclusion Region Calculation Method Using LAPUR5 Computer Code & Implementation of Solomon Stability Monitor for Licensee Facility | |
ML20134K735 | 19 August 1985 | Safety Evaluation Accepting 831107 Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing | |
ML20134N827 | 20 November 1996 | Safety Evaluation Accepting Licensee Scope & Insp Methods Proposed for Insp of Core Spray Internal Piping During Fall 1996 Refueling Outage at Plant | Safe Shutdown Earthquake Operating Basis Earthquake EVT-1 Flow Induced Vibration |
ML20135C892 | 10 September 1985 | Safety Evaluation Supporting 840824 Commitment to Convert Air Containment Atmosphere Dilution Sys to Nitrogen Sys,In Response to Generic Ltr 84-09 | |
ML20135C912 | 10 September 1985 | Safety Evaluation Supporting Conclusion That Diversification of Scram Discharge Vol Level Instrumentation Not Necessary & Tech Specs,As Modified in Amend 76,resolve Staff Concerns Re Need for Instrumentation Diversity | |
ML20135E540 | 3 March 1997 | Safety Assessment Accepting Mod of RHR & CS Sys Containment Isolation Function Configuration | |
ML20136F124 | 18 November 1985 | Safety Evaluation Re IE Bulletin 80-11, Masonry Wall Design. Issues Re Arching Action Theory Resolved | |
ML20136G361 | 12 August 1985 | Safety Evaluation Accepting Seismic Design Criteria Utilized for Evaluation of Modified Recirculation Sys | Safe Shutdown Earthquake Operating Basis Earthquake Earthquake |
ML20137S733 | 27 September 1985 | Safety Evaluation Approving Use of Fuel Thermal Performance Code,Frosstey,For Analysis of LOCA Conditions at Low & Moderate Burnups | |
ML20138E420 | 2 December 1985 | Safety Evaluation Supporting Util 831107 & 840320 Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 Re post-maint Testing & Reactor Trip Sys Reliability | |
ML20140H988 | 25 March 1986 | Safety Evaluation Re Util 851008 Request to Install Carpet Over Vinyl Asbestos Tiled Control Room Floor Covering. Installation of Carpet Will Not Decrease Level of Fire Safety in Control Room & Deviation Acceptable | Fire Protection Program |
ML20141A415 | 18 June 1997 | Revised SE Accepting Proposed Onsite Disposal of Slightly Contaminated Silt Removed from Vermont Yankee Cooling Towers | Offsite Dose Calculation Manual Annual Radiological Effluent Release Report |
ML20154B695 | 1 October 1998 | SER Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Vermont Yankee Nuclear Power Station | Power-Operated Valves Backfit |
ML20155B647 | 26 October 1998 | Safety Evaluation Accepting Jet Pump Riser Insp Results & Flaw Evaluation,Conducted During 1998 Refueling Outage | Safe Shutdown Earthquake Flow Induced Vibration |
ML20155B835 | 31 March 1986 | Safety Evaluation Supporting Revised Procedure OP-3140, Providing Technically Acceptable Actions During Degraded Grid Voltage Conditions W/O LOCA to Assure Protection of Class 1E Electrical Sys & Equipment | |
ML20195C416 | 9 November 1998 | SER Accepting Request That NRC Approve ASME Code Case N-560, Alternative Exam Requirement for Class 1,Category B-J Piping Welds | Internal Flooding Probabilistic Risk Assessment Large early release frequency Dissimilar Metal Weld |
ML20198P994 | 15 January 1998 | SE Authorizing Relief Requests for Third Interval Pump & Valve Inservice Testing Program | |
ML20199K699 | 20 January 1999 | Safety Evaluation Concluding That Request to Use YAEC-1339, Yankee Atomic Electric Co Application of FIBWR2 Core Hydraulics Code to BWR Reload Analysis, at Vermont Yankee Acceptable | |
ML20199K715 | 21 January 1999 | Corrected Safety Evaluation Supporting Amend 163 Issued to FOL DPR-28.Pages 2 & 3 Required Correction & Clarification | |
ML20199L595 | 14 January 1999 | Safety Evaluation Accepting Licensee Proposed Alternative to Code Requirement,Described in Rev 2 to Pump Relief Request RR-P10 Pursuant to 10CFR50.55a(a)(3)(i) | Incorporated by reference |
ML20202J421 | 31 March 1986 | Safety Evaluation Accepting Util Design Mods & Tech Spec Changes Re Degraded Grid Voltage Protection for Class 1E Sys.Lll Technical Evaluation Rept Encl | Safe Shutdown |
ML20203H988 | 18 February 1999 | SER Accepting Alternative to 10CFR50.55a(g)(6)(ii)(A) Augmented Reactor Vessel Exam at Vermont Yankee Nuclear Power Station.Technical Ltr Rept Encl | Incorporated by reference |
ML20204F727 | 14 October 1988 | Safety Evaluation Supporting Proposed Expansion of Spent Fuel Pool at Facility | High Radiation Area Ultimate heat sink Incorporated by reference Earthquake Control of Heavy Loads |
ML20205K758 | 7 April 1999 | Safety Evaluation Supporting Alternative Proposal for Reexamination of Circumferential Welds with Detected Flaw Indications in Plant RPV | Incorporated by reference |
ML20205T418 | 14 October 1988 | Errata to Safety Evaluation Concluding Util Submittal Re Spent Fuel Pool Expansion | |
ML20206E874 | 29 April 1999 | SER Determined That Flaw Evaluation Meets Rules of ASME Code & Assumed Crack Growth Rate Adequate for Application | Safe Shutdown Earthquake Flow Induced Vibration |
ML20206F068 | 13 June 1986 | Safety Evaluation Supporting 850514,0710,860327,0411 & 0513 Requests for Approval to Use Pvrc Damping Values (ASME Code Case N-411) for Piping Sys Reanalysis | |
ML20206F365 | 16 June 1986 | Safety Evaluation Re Proposed Repair of Core Spray safe- Ends,During Current Refueling Outage.Plant Can Be Safely Returned to Power Operation After Satisfactory Completion of Core Spray safe-end Repairs | Weld Overlay Liquid penetrant |
ML20207S780 | 12 March 1987 | Safety Evaluation Granting Relief from Tech Spec 4.7.A.3 on one-time Basis to Perform RHR Pump Wear Ring Replacement | Enforcement Discretion |
ML20212C255 | 17 September 1999 | Safety Evaluation Supporting Amend 175 to License DPR-28 | Shutdown Margin |
ML20212H152 | 6 March 1998 | Correction to Page 7 of SE Re Relief Request for Third 10-yr Interval Pump & Valve IST Program for Plant | |
ML20214T492 | 24 November 1986 | Safety Evaluation Accepting Licensee 830511 & 860117 Responses to Generic Ltr 83-08 Re Mod of Vaccum Breakers on Mark I Containments | |
ML20214T989 | 28 May 1987 | Safety Evaluation Re Util 870112 Proposed Plans to Inspect Two Overlay Repaired Core Spray safe-ends in Lieu of Replacement During Upcoming 1987 Refueling Outage.Plans Acceptable,Providing That Insp Results Satisfactory | Weld Overlay Liquid penetrant |
ML20215M587 | 24 October 1986 | Preliminary Evaluation of Containment Study Transmitted w/860902 Ltr.Licensee Estimates Appear Optimistic Considering Uncertainties Inherent in Failure Rate Data | Ultimate heat sink |
ML20216F100 | 15 April 1998 | Safety Evaluation Accepting 980331 Licensee Proposal to Perform Alternative Testing for Containment Pressurization Test for Vynp | Incorporated by reference Liquid penetrant |
ML20217F342 | 25 March 1998 | SER Accepting Plans for 1998 & 1999 Refueling Outages Re Reactor Vessel Internals for Plant | |
ML20217G204 | 13 October 1999 | Safety Evaluation Supporting Amend 179 to License DPR-28 | Time of Discovery Missed surveillance |
ML20217L883 | 21 October 1999 | Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18 | Incorporated by reference |
ML20217N491 | 27 February 1998 | SER Pertaining to Cracking of EDG Lube Oil Piping at Vermont Yankee | Hydrostatic Design basis earthquake Earthquake Liquid penetrant Weak link |
ML20236N646 | 7 August 1987 | Safety Evaluation Re Permanent Elimination of Liquid Penetrant Exam of Feedwater Nozzles at Facility.Due to Lack of Reasonable Assurance That Ultrasonic Exam Can Totally Replace Penetrant Exam,Request Unacceptable | Liquid penetrant |
ML20239A136 | 2 September 1998 | SER Re License Request for NRC Review & Concurrence W/Changes to NRC-approved Fire Protection Program | Safe Shutdown Fire Barrier Fire Protection Program |
ML20244D031 | 7 June 1989 | Safety Evaluation Accepting Util Second 10-yr Interval Inservice Insp Program Plan | Incorporated by reference |
ML20246D773 | 21 August 1989 | Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Item 2.2.1, Required Actions Based on Generic Implications of Salem ATWS Events. Equipment Classification Program for safety-related Components Acceptable |