TAC:44877
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Request for: Approved, Closed | |
Questions Answers Results Other: 05000266/LER-1979-010-01, /01T-0 on 790620:plant Safeguards Actuation Circuitry Review Indicated Need for Circuitry Changes.Caused by Changes in IEEE Std Since Plant Design.Mods to Four Applicable Safeguard Circuits Will Be Performed, ML19210C482, ML19242D259, ML19253A712, ML19253B006, ML19257A367, ML19257B511, ML19289C679, ML19310A971, ML19323H481, ML19345H544, ML20010E141, ML20027A527, ML20038C635, ML20039A258, ML20040F029, ML20065R665 | |
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MONTHYEARML20027A5271978-11-28028 November 1978
[table view]Discusses Possible Dangers of LOCA in Containment Purging During Normal Plant Oper.Requests Either Commitment to Limit Purging or Justification for Continuing.W/Encl ANO 7812080207 ML19289C6791979-01-16016 January 1979 Responds to Re Purging During Normal Operation. Need for Purging Has Been Limited,But It Is Essential That Capability of in-containment Activities at Power Be Maintained 05000266/LER-1979-010-01, /01T-0 on 790620:plant Safeguards Actuation Circuitry Review Indicated Need for Circuitry Changes.Caused by Changes in IEEE Std Since Plant Design.Mods to Four Applicable Safeguard Circuits Will Be Performed1979-07-0303 July 1979 /01T-0 on 790620:plant Safeguards Actuation Circuitry Review Indicated Need for Circuitry Changes.Caused by Changes in IEEE Std Since Plant Design.Mods to Four Applicable Safeguard Circuits Will Be Performed ML19253A7121979-08-0808 August 1979 Confirms Action Taken as Result of 790803 Telcon Re Util Request to Leave Containment Purge Values Closed Above Cold Shutdown Condition.Proposal Acceptable on one-time Basis ML19242D2591979-08-10010 August 1979 Appreciates Prompt Approval of Request to Purge Containment. Approval Reduced Personnel Inconvenience & man-rem Exposure. Will Pursue Review of Containment Purge Sys ML19253B0061979-09-0606 September 1979 Discusses Containment Purge Valve Operations.Notifies of Potential Mods to Ensure That Valves Will Close Against Containment Pressure Transients.Consultants Will Conduct Studies & Analyses of Potential Mods ML19323H4811979-09-30030 September 1979 Technical Evaluation of Electrical Instrumentation & Control Design Aspects of Override Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Point Beach Nuclear Power Station,Units 1 & 2 ML19210C4821979-11-0101 November 1979 Responds to Re Guidelines for Operability of Containment Purging & Venting Valves During Normal Operations.Evaluation Will Consider Consultant Studies of Potential Mods to Valves ML19257A3671979-11-19019 November 1979 Forwards Interim Position on Containment Purging & Venting During Normal Operation Pending Resolution of Isolation Valve Operability.Commitment to Comply W/Encl Position Should Be Submitted within 45 Days ML19310A9711979-12-27027 December 1979 Requests Preliminary Evaluation of Licensee Response to NRC 791023 Interim Position for Containment Purge & Vent Valve Operation Pending Resolution of Isolation Valve Operability, Generic Item B-24.Evaluation Form Encl ML19257B5111980-01-0909 January 1980 Provides Commitments Sought in NRC .Forwards to Bechtel Re Purge Valve Capability Verification.Nrc Guidelines Will Be Considered During Evaluation of Mods for Improved Purge Valve Reliability ML19257C8081980-01-11011 January 1980 Forwards Safety Evaluation to Be Substituted for Encl in Ltr Per Agreement Reached at 791213 Meeting Re Containment Purge ML19257C8101980-01-11011 January 1980 Safety Evaluation Approving Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation,Except Radiation Monitors Used to Initiate Containment Purge Isolation ML19323H4781980-05-22022 May 1980 Forwards Safety Evaluation Supporting Design Aspects of Containment Purge Valve Isolation Override & Other Engineered Safety Feature Actuation Signals Except Radiation Monitors Which Initiate Containment Purge Isolation ML19345H5441981-05-0707 May 1981 Documents Basis for Containment Isolation Pressure Setpoint Reported in Item II.E.4.2 of NUREG-0737 Response Per NRC 810414 Telcon.Present 5 Psig Setpoint Considered Realistic & Appropriate ML20008F4471981-07-21021 July 1981 IE Info Notice 81-21, Potential Loss of Direct Access to Ultimate Heat Sink. Provides Addl Info to IE Bulletin 81-03 ML20038C6351981-07-31031 July 1981 Srp,Revision 2 to Section 6.2.4, Containment Isolation Sys ML20010E1411981-08-28028 August 1981 Proposed Tech Spec Revision Pages 15.3.6-2,15.3.6-3, 15.4.4-12,15.4.4-15 & 15.4.4-15a Re Testing of Containment Purge Supply & Exhaust Sys Isolation Valves ML20010E1361981-08-28028 August 1981 Application for Amend to Licenses DPR-24 & DPR-27 Submitted as Tech Spec Change Request 68 to Incorporate Addl Restrictions Re Use & Testing of Containment Purge Supply & Exhaust Sys Isolation Valves,Per NRC Request ML20033C0321981-11-23023 November 1981 Second Discovery Progress Rept for Period Ending 811122,per ASLB 811113 Memorandum Order.Licensee 811027 Responses to Wi Environ Decade 811023 Interrogatories Are Not Fully Responsive.Certificate of Svc Encl.Related Correspondence ML20039B0181981-11-24024 November 1981 Requests That Util Remit Class III Fee for Unit 1 & Class I Fee for Unit 2 to Cover Review of 810828 Application for Tech Spec Changes Re Containment Purge Valve Operability ML20033A9071981-11-24024 November 1981 Advises of Significant Error in 811117 Telcon Transcript ML20039A2581981-12-0707 December 1981 Requests That NRC Reconsider Requirement of Class III Approval Fee During Final Review Re Tech Spec Change Request 68.Changes to Tech Specs Result of NRC Request.No Approval Fee for Amend Review Necessary ML20040F0291982-01-28028 January 1982 Proposed Tech Spec 15.3.6 Re Containment Purge Supply & Exhaust Valves ML20040F0221982-01-28028 January 1982 Application for Amend to Licenses DPR-24 & DPR-27,consisting of Tech Spec Change Request 68 Re Containment Purge Valve Operability ML20065R6651982-10-22022 October 1982 Provides Results of Confirmatory Analysis Demonstrating That Unacceptable Radioactive Release from Containment Would Not Take Place as Result of Small Break LOCA in Which Operator Action Required.Radioactive Release Negligible 1980-01-11 | |
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