ML19256A112
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Initiation
Results Other: 05000280/LER-1980-046, Forwards LER 80-046/03L-0, A01085, Forwards Nonproprietary Response to Questions on Cycle 4 Basic Safety Rept, A01151, Advises of Minor Adjustments to Evaluation Program Re Resolution of Cycle 3 Startup Commitments.Adjustments Are to Optimize Timetable for Critical Path Refueling Activities, B10005, Discusses Small Break LOCA ECCS Performance Results. Primarily Effect Function of Sys Characteristics Such as ECCS Flow Rates,Safety Injection Tank Actuation Pressures & Core Power Level.Supporting Info Encl, B10009, Forwards Reload Safety Analysis, Demonstrating That Cycle 4 Reload Assures Continued Conformance to Design & Safety Limits of Facility, B10015, Forwards Large Break Loca/Eccs Performance Results. Analysis Showed double-ended Cold Leg Guillotine Break at Pump Discharge to Be Limiting Large Break.Review of Results Determined That Applicable Fee Was Submitted 800509, B10028, Forwards Addl Info Re Fuel Design & Physics Calculations Per RA Clark 800620 Request.Response to Question 10 Withheld (Ref 10CFR2.790), B10060, Forwards Addl Info Requested by NRC Re Design Mod to Cycle 4 Fuel Assemblies & QA Program in Effect During Design of Cycle 4 Reload Fuel, B10068, Advises That C-E Owners Group 800215,0630 & 0731 Ltrs Re Asymmetric LOCA Loads Are Applicable to Millstone Unit 2 & Should Be Regarded as Util Response to NRC 780125 Request, B10076, Forwards Nonproprietary & Proprietary Repts, Guide Thimble Inset Design. Withholding Application & Affidavit Encl. Proprietary Version Withheld (Ref 10CFR2.790), B10080, Corrects Typographical Error in Tech Spec Table 3.9-1 of Amend 60 to License DPR-65.Doors 292 & 297,listed as Servicing Solidification Sys Area,Should Be 292 & 207, B10084, Submits Addl Info Re Fuel Misload Analysis Performed in Support of Cycle 4 Reload.Procedures Utilized During Fuel Movement Provide Adequate Assurance That Probability of Fuel Misloading Event Is Sufficiently Low to Preclude Analysis, ML19207B946, ML19210C634, ML19210C638, ML19253B386, ML19257A505, ML19290E339, ML19296B295, ML19296B298, ML19305E096, ML19309B532, ML19309C217, ML19309G003, ML19312E209, ML19312E212, ML19318A345, ML19323C588, ML19323C595, ML19323D864, ML19323H680, ML19330B446, ML19332A343, ML19337A776, ML19338C766, ML19338E936, ML19341C989, ML19344D183, ML20002D299, ML20003D677, ML20024D472, ML20024F023, ML20024F025, ML20028B682, ML20063L534, ML20069H794, ML20072M866, ML20076A987, ML20083Q550, ML20087N088... further results | |
MONTHYEARML19256A1121978-10-27027 October 1978
[Table View]Application for Amend to License DPR-35,changing Tech Specs to Accomodate New Steamline Break Protection Sys Scheduled for Installation in Spring of 1979.Fee Paid Project stage: Request ML20071G1291978-12-14014 December 1978 Forwards Addl Info Re Lic Amend Appl Covering Eval of Low Feedwater Flow Reactor Trip Setpoint Change Project stage: Other ML19263C8021979-02-0505 February 1979 Lists Individual Fee Classes for 781027 Application for Tech Spec Changes.Requests Submittal of Addl $13,500 Fee. Any Overcharges Will Be Refunded Project stage: Other ML19276E2751979-03-0707 March 1979 Forwards Addl Info Requested at 790223 Meeting Re Proposed Steam Break Protection Sys Project stage: Meeting ML19270F9971979-03-12012 March 1979 Summary of 790223 Meeting W/Westinghouse & Duquesne Light Re Steamline Break Protection Sys.W/Supporting Documentation Project stage: Meeting ML20037A2061979-03-21021 March 1979 Forwards Proprietary Info Presented to NRC at 790126 Meeting Re Reload Application.Info Withheld (Ref 10CFR2.790) Project stage: Meeting ML20076A9871979-04-27027 April 1979 Forwards Proposed Revision to Tech Specs to Allow Unlimited Containment Purges.Revisions Deal W/Containment Isolation Valves Project stage: Other ML19241B4191979-07-13013 July 1979 Forwards Tech Spec Change Requests 42 & 47 Re Amend to App a of DPR-72.Change Is Required Prior to Startup After Completion of Planned ECCS Mod,Which Could Be Accomplished as Early as 790722 Project stage: Other ML19241B4271979-07-13013 July 1979 Tech Spec Change Requests 42 & 47 Re Mod to ECCS Project stage: Other ML19274G1021979-07-31031 July 1979 Forwards Request for Addl Info to Util Proposed Steam Break Protection Sys & N-1 Loop Operation Project stage: RAI ML19208B5691979-08-21021 August 1979 Forwards Safety Evaluation Re Electrical,Instrumentation & Control Aspects of Deletion of Reactor Trip on Turbine Trip Below 50% Power Project stage: Approval ML19207B9461979-08-28028 August 1979 Forwards Addl Info Supporting Tech Specs Change 35 Re Proposed New Steamline Break Protection Sys,In Response to 790731 Request Project stage: Other ML20125A7061979-08-31031 August 1979 Proposed Revisions to Tech Specs to Add Leak Rate Surveillance Requirements to ECCS & Containment Sys Project stage: Other ML19253B3861979-10-0909 October 1979 Discusses Method for Mitigating Control Element Assembly Guide Tube Wear in Fuel Supplied by Westinghouse for Cycle 4.Util Will Use Westinghouse Sleeve Design Project stage: Other ML19254D2721979-10-18018 October 1979 Forwards Addl Info Re Proposed Steam Break Protection Sys Per Tech Spec Change Request 35.Proposed Tech Spec Re Maint of Required Shutdown Margin & Revised Reactivity Control Sys Tech Specs Encl Project stage: Other ML19259D6001979-10-18018 October 1979 Summary of 791009 Meeting W/Util Re Proposed Steamline Break Protection Project stage: Meeting ML19210C6341979-11-0909 November 1979 Responds to Re Resolution of Cycle 3 Startup Commitments.Forwards Rept, Evaluation of Neutron Shield Effectiveness Project stage: Other ML19210C6381979-11-30030 November 1979 Evaluation of Neutron Shield Effectiveness Project stage: Other ML19257A5051979-12-31031 December 1979 Responds to NRC 790913 TMI Lessons Learned Task Force short- Term Requirements.All short-term Requirements Will Be Implemented by 800101.Implementation Rept Encl Project stage: Other ML19296B2951980-02-0808 February 1980 Discusses Fuel Cladding Strain & Fuel Assembly Flow Blockage Models for Facility.Analysis Was Performed for Operating Plants W/Ce Fuel.Forwards Analysis Verifying Compliance W/Eccs Acceptance Criteria Project stage: Other ML19344D1831980-02-29029 February 1980 Discusses Slightly Diminished Capacity of Charging Pumps to Inject Concentrated Boric Acid Into RCS Under Test Conditions.Change in Peak Clad Temp Due to Smaller Charging Pump Flow Is Not Significant Enough to Be Reportable Project stage: Other ML19296B2981980-02-29029 February 1980 Verification of Compliance W/Eccs Acceptance Criteria of Code Utilizing Conservative Cladding Rupture Strain & Assembly Flow Blockage Models Project stage: Other ML19290E3391980-03-0606 March 1980 Forwards Basic Safety Rept, in Support of Cycle 4 Reload. Affidavit Encl.Rept Withheld (Ref 10CFR2.790) & Available in Central Files Only Project stage: Other ML19309B5321980-03-26026 March 1980 Forwards Basic Safety Rept. Proprietary Version Withheld (Ref 10CFR2.790).Affidavit Previously Submitted on 800229 & 760727 Project stage: Other ML19309A8581980-03-28028 March 1980 Forwards Documents Re Investigation Into Extended Outages at Facility.Documents Include Trial Staff Statement Before PA Public Util Commission,Consumer Advocate Statement & CN Dunn Testimony Project stage: Request ML19309C2171980-03-31031 March 1980 Outlines Plans for Cycle 4 Reload Outage Steam Generator Insp Per Amend 52 to License DPR-65.Resolution of Cycle 3 Startup Commitments Encl Project stage: Other ML19305E0961980-04-15015 April 1980 Submits Info in Support of Continued Operation W/Sleeved Guide Tubes in Cycle 4.Anticipates That Negligible Guide Tube Sleeve Wear Will Be Measured Project stage: Other ML19309H2151980-04-15015 April 1980 Notification of 800422 Meeting W/Util in Bethesda,Md to Discuss & Review Decay Heat Exchanger Sys Integrity & Operation Project stage: Request ML19309G0031980-04-24024 April 1980 Responds to IE Bulletin 79-13, Cracking in Feedwater Sys Piping. Util Conducted Insp During Aug 1979 Outage.Several Crack Indications in nozzle-to-pipe Welds of Both Steam Generators Were Found.All Repairs Completed Project stage: Other ML19323C5881980-05-0707 May 1980 Forwards Revised Steam Generator Insp. Includes Final Dent Progression Statistics Re Mar 1979 Steam Generator Tube eddy-current Insp.Biases Identified in Testing Procedures Have Been Corrected Project stage: Other IR 05000302/19800181980-05-0707 May 1980 IE Insp Rept 50-302/80-18 on 800331-0411.No Noncompliance Noted.Major Areas Inspected:Previous Insp Findings,Fuel Receipt,Refueling Activities,Maint Activities & IE Bulletin 79-01B Project stage: Request IR 05000334/19800081980-05-0707 May 1980 IE Insp Rept 50-334/80-08 on 800324-28.No Noncompliance Noted.Major Areas Inspected:Qa Program Review,Qa/Qc Administrative Design Change & Mod Control,Measurement & Test & Previous Insp Items Project stage: Request ML19323D8641980-05-13013 May 1980 Submits Info Re Proposal for Permanent Type Repair of Containment Electrical Penetrations.Penetration Modules Which Have Experienced Insulation Resistance Degradation, Will Be Replaced Project stage: Other B10002, Forwards Proprietary Version of Basic Safety Rept Addendum, Nuclear Uncertainties, Supplementing Rept Section 4.0. Describes Power Peaking Factor Uncertainty Analysis Used in Reload Fuel Design.Rept Withheld (Ref 10CFR2.790)1980-05-28028 May 1980 Forwards Proprietary Version of Basic Safety Rept Addendum, Nuclear Uncertainties, Supplementing Rept Section 4.0. Describes Power Peaking Factor Uncertainty Analysis Used in Reload Fuel Design.Rept Withheld (Ref 10CFR2.790) Project stage: Supplement ML19312E2091980-05-30030 May 1980 Forwards Addendum to Basic Safety Rept Re Nuclear Uncertainties,Nonproprietary Version Project stage: Other ML19323C5951980-05-31031 May 1980 Steam Generator Insp Project stage: Other ML19312E2121980-05-31031 May 1980 Addendum to Basic Safety Rept Re Nuclear Uncertainties, Nonproprietary Version Project stage: Other B10005, Discusses Small Break LOCA ECCS Performance Results. Primarily Effect Function of Sys Characteristics Such as ECCS Flow Rates,Safety Injection Tank Actuation Pressures & Core Power Level.Supporting Info Encl1980-06-0202 June 1980 Discusses Small Break LOCA ECCS Performance Results. Primarily Effect Function of Sys Characteristics Such as ECCS Flow Rates,Safety Injection Tank Actuation Pressures & Core Power Level.Supporting Info Encl Project stage: Other B10009, Forwards Reload Safety Analysis, Demonstrating That Cycle 4 Reload Assures Continued Conformance to Design & Safety Limits of Facility1980-06-0303 June 1980 Forwards Reload Safety Analysis, Demonstrating That Cycle 4 Reload Assures Continued Conformance to Design & Safety Limits of Facility Project stage: Other ML19310A4261980-06-0909 June 1980 Responds to & Schedule for Implementation of TMI-2-related Requirements.Discusses Shift Manning,Scope & Criteria for Licensing Exam,Procedures for Feedback of Operating Experience & Control Room Habitability Project stage: Other B10015, Forwards Large Break Loca/Eccs Performance Results. Analysis Showed double-ended Cold Leg Guillotine Break at Pump Discharge to Be Limiting Large Break.Review of Results Determined That Applicable Fee Was Submitted 8005091980-06-11011 June 1980 Forwards Large Break Loca/Eccs Performance Results. Analysis Showed double-ended Cold Leg Guillotine Break at Pump Discharge to Be Limiting Large Break.Review of Results Determined That Applicable Fee Was Submitted 800509 Project stage: Other ML20244B0591980-06-16016 June 1980 Summary of 800604 Meeting W/Util in Bethesda,Md Re Cycle 4 Reload at Facility W/Westinghouse Fuel.List of Attendees & Agenda Encl Project stage: Meeting ML19329G1251980-06-16016 June 1980 Summary of 800604 Meeting W/Util in Bethesda,Md Re Cycle 4 Reload at Facility W/Westinghouse Fuel.List of Attendees & Agenda Encl Project stage: Meeting ML19310A8971980-06-18018 June 1980 Summary of 800318 Meeting W/Util & Westinghouse Re Cycle 4 Reload W/Westinghouse Fuel Project stage: Meeting ML19326D8271980-06-20020 June 1980 Requests Response to Encl Questions Re Fuel Design & Physics Calculations to Complete Review of Basic Safety Rept Supporting Cycle 4 Reload.Requests That Addl Info Be Provided by 800630 to Meet Review Schedule Project stage: Approval ML19323H6801980-06-30030 June 1980 Reload Safety Analysis Project stage: Other ML19318A3451980-06-30030 June 1980 Large Break Loca/Eccs Performance Results Project stage: Other IR 05000412/19800061980-07-0303 July 1980 IE Insp Rept 50-412/80-06 on 800602-06.Noncompliance Noted: Failure to Return Used or Damaged Welding Electrodes to Issue Station & Failure to Provide Adequate Protection for Equipment in Temporary Storage Project stage: Request B10028, Forwards Addl Info Re Fuel Design & Physics Calculations Per RA Clark 800620 Request.Response to Question 10 Withheld (Ref 10CFR2.790)1980-07-0707 July 1980 Forwards Addl Info Re Fuel Design & Physics Calculations Per RA Clark 800620 Request.Response to Question 10 Withheld (Ref 10CFR2.790) Project stage: Other ML19321A6951980-07-21021 July 1980 Forwards Schedule for Commitments to TMI-2 Related Requirements,Per NRC 800507 Request.Affidavit Encl Project stage: Other 1980-03-28 |
| ML19256A112 | |
| Person / Time | |
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| Site: | Beaver Valley |
| Issue date: | 10/27/1978 |
| From: | Dunn C DUQUESNE LIGHT CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| TAC-10386, TAC-11010, TAC-11011, TAC-11012, TAC-45471, NUDOCS 7811030107 | |
| Download: ML19256A112 (423) | |
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