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 Issue dateFromTitleProject stage
ML20137R72222 November 1985Thompson H
Office of Nuclear Reactor Regulation
Requests Presentation,Within 60 Days of Ltr Date,Of Plans for Assuring That Plant Designed Per FSAR Commitments & NRC Regulations.Plans Needed to Facilitate Decision Re Whether or Not Integrated Design Insp Will Be ConductedOther
ML20137J01817 January 1986Duquesne Light Company
Carey J
Submits Design Verification Activities Per 841122 Request. Actions Taken in Past & Activities in Process or Scheduled Identified for Providing Assurance That Facility Designed in Accordance W/Fsar CommitmentsOther
ML20153H10518 February 1986Tam P
Office of Nuclear Reactor Regulation
Notification of 860228 Meeting W/Util in Bethesda,Md to Discuss Engineering Assurance Program & NRC Participation in ProgramMeeting
ML20154M57010 March 1986Tam P
Office of Nuclear Reactor Regulation
Summary of 860228 Meeting W/Util Re Engineering Assurance Program & Independent Design Verification.Engineering Assurance Program Will Be Performed W/Nrc Participation to Assure Plant Built Per Util Commitments.W/O Encl AuditsMeeting
ML20155K34321 May 1986Duquesne Light Company
Carey J
Forwards Evidence Documenting That Continuing S&W Detailed Design Reviews Provide Addl Assurance Sought by NRC That Design Process Used for Constructing Plant in Full Compliance W/Fsar & NRC RegulationsOther
ML20199L7427 July 1986Mcdonald D
Office of Nuclear Reactor Regulation
Notifies of Review of Util Re Proposed Program for Completion of Engineering Assurance In-Depth Technical Audit. Proposed Engineering Assurance Program Acceptable for Integrated Design Insp or IdvpApproval
ML20214Q93326 August 1986Duquesne Light Company
Carey J
Forwards S&W Assurance Technical Audit Rept 52. Rept Provides Results of Phase I of Program for Completion of Engineering Assurance in-depth Technical Audits for Facility.W/O EnclOther
ML20211A2177 October 1986STONE & WEBSTER ENGINEERING CORP.
Garfinkel P
Part 21 Rept Re Outside Containment Flooding Analysis Calculation.Initially Reported on 860407.Calculation Revised to Evaluate Lines Previously Exempted from Analysis & Flood Barriers Constructed Around Listed AreasOther
ML20207J88419 December 1986Novak T
Office of Nuclear Reactor Regulation
Responds to 861114 Request to Address Issue of Whether Use of Stress Intensification Factor (SIF) of 1.0 for Branch Connections Technically Justified.Approach Similar to That Used at Shoreham Will Provide Technically Sound ResolutionApproval
ML20207N2018 January 1987Tam P
Office of Nuclear Reactor Regulation
Notification of 870123 Meeting W/Util in Bethesda,Md to Discuss Issues Re Stress Intensification Factor Used in Piping Stress AnalysisMeeting
ML20155H99923 February 1987Duquesne Light Company
Carey J
Forwards S&W 870212 Engineering Assurance Corrective Action Status Rept Providing Status of Corrective Action Items Resulting from Engineering Assurance Audit 52Other
ML20214D73215 May 1987Duquesne Light Company
Carey J
Lists Efforts Towards Completion of S&W Confirmation Programs Prior to Fuel Loading,Per LS Rubenstein 870408 Commitment.Efforts Re Equipment Qualification Will Be Addressed in Separate SubmittalsOther
ML20214K32720 May 1987Duquesne Light Company
Carey J
Forwards S&W Engineering Assurance Corrective Action Status Rept,In-Depth Technical Audits. Rept Indicates That All of Action Items Resulting from Audit 52 Closed Based on Verification of Util Corrective & Preventive ActionsOther