TAC:63425
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Request for: Approved, Closed | |
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MONTHYEARML18018B1161985-09-30030 September 1985
[table view]Nine Mile Point Unit 2 - Detailed Control Room Design Review Final Summary Report Program Implementation Volume 2 ML20136D1721985-12-31031 December 1985 Forwards S&W Proprietary Calculations Re Design of Containment Downcomers Discussed During 851220 Meeting. S&W Affidavit Encl.Calculations Withheld (Ref 10CFR2.790) IR 05000220/19850141985-12-31031 December 1985 Exam Rept 50-220/85-14 on 850910-12.Exam Results:All Candidates Passed.Util 851004 Comments & Recommendations to NRC Re Reactor & Senior Reactor Operator Exams on 850910 Encl IR 05000220/19850231986-01-0808 January 1986 Insp Repts 50-220/85-23 & 50-410/85-40 on 851125-27.No Violation or Deviation Noted.Major Areas Inspected:Nuclear Matl Control & Accounting,Organization & Operation,Shipping & Receiving,Inventory & Mgt of Matls Control Sys ML20137M3941986-01-22022 January 1986 Forwards Safety Evaluation Re Power Ascension Program Proposed Test Mods Submitted by 850821,0920,23 & 30 Ltrs. Review of Listed Test Mods Completed.Amend to FSAR for Acceptable Test Mods Requested ML17055B1431986-01-23023 January 1986 Forwards Proprietary S&W Calculations Re Design of Facility Containment Downcomers & Response to NRC Concerns Discussed in .Calculations Supersede Calculations Submitted on 851231.Encls Withheld (Ref 10CFR2.790) IR 05000410/19850481986-01-24024 January 1986 Preoperational Security Program Insp Rept 50-410/85-48 on 851216-19.No Violation Noted.Major Areas Inspected:Review of Implementing Procedures for Receipt of Snm.Info Partially Withheld (Ref 10CFR2.790) ML17055B2251986-01-31031 January 1986 Advises That Based on Review of Recent Applicant Submittals, Unbraced Downcomer Design Marginal.Although Licensing Criteria for Upset & Emergency Conditions Met,Design Adequacy for Faulted Condition Inadequately Demonstrated ML20140G0761986-01-31031 January 1986 Summary of 860124 Meeting W/Consultants to Discuss Adequacy of Downcomer Design in Context of Reanalysis Performed by Util.Design Marginal.Recommends Granting OL W/Listed Condition.List of Attendees Encl ML20141N5311986-02-10010 February 1986 Comments on Review of Structural Adequacy of BWR Mark II Downcomers for Nine Mile Point 2 Nuclear Power Station. Allowable Moments Are Less than Calculated Applied Moment of 4914 in-kips ML17055B2811986-02-12012 February 1986 Forwards Bd Liaw 860131 Memo to RM Bernero,Summarizing 860124 Meeting W/Consultants Re Downcomers ML20141N5321986-02-14014 February 1986 Summarizes 860124 Meeting W/Nrc & EC Rodabaugh Re Structural Integrity of Facility Downcomer Design.Design Meets Licensing Requirements for Upset & Emergency Conditions ML17058A5221986-03-18018 March 1986 Forwards Draft SER & NRC Consultants Repts on Downcomer Design Issue.Nrc Reviewing 860218 Exemption Request ML17055B4471986-04-0101 April 1986 Notification of 860402 Meeting W/Util in Bethesda,Md Re Loads on Downcomers ML17055B5571986-04-23023 April 1986 Summary of 860402 Meeting W/Util & S&W Re Structural Adequacy of Downcomers.Handout & List of Attendees Encl ML17055B9351986-06-26026 June 1986 Forwards Draft Section 6 of Sser 3 Containing Util Request for Exemption on Downcomers ML17055C1551986-07-31031 July 1986 Staff Requirements Memo Re Commission 860723 Briefing in Washington,Dc on Status of near-term OL Plants ML17055C6661986-11-26026 November 1986 Requests Info to Assess Util Progress in Completing Actions Required to Meet GDC 2 & to Schedule NRC Review of Downcomer Issue,No Later than 10 Working Days Before Commission Briefing.Info Should Include Progress Since 860218 ML20236U2261987-11-23023 November 1987 Notification of 871207 Meeting W/S&W & Util in Bethesda,Md to Discuss Downcomers for Facility ML17055D4541987-12-16016 December 1987 Summary of 871207 Meeting W/Util & S&W Re Downcomers for Facility.Handout & List of Meeting Attendees Encl NUREG-0808, Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations1988-06-29029 June 1988 Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations 1986-02-12 | |
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