ML20244C261
ML20244C261 | |
Person / Time | |
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Site: | McGuire ![]() |
Issue date: | 04/14/1983 |
From: | Zukor D NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
To: | Seyfrit K NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
Shared Package | |
ML20244C265 | List: |
References | |
AEOD-E306, NUDOCS 8304210569 | |
Download: ML20244C261 (1) | |
Similar Documents at McGuire | |
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Category:INTERNAL OR EXTERNAL MEMORANDUM
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[Table view]Informs That Encl Questions Were Transmitted by Email to PT Vu of Duke Energy Corp,In Preparation for Upcoming Telcon Re 990624 Amend Request ML20216J2171999-09-30030 September 1999 Informs That Encl Questions Were Transmitted by Email on 990930 to M Purser of Duke Energy Corp for Preparation of Upcoming Telcon.Questions Pertain to 990624 Amend Request ML20210L6601999-08-0505 August 1999 Forwards single-page Document Given to G Belisle of Region II by T Clements of Nuclear Control Institute Re Mixed Oxide Fuel ML20196K6231999-07-0101 July 1999 Forwards Draft Safety Evaluation on TR DPC-NE-2009, Duke Power Co Westinghouse Fuel Transition Rept. 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List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20059E0261994-01-0404 January 1994 Notification of 940105 Meeting W/Util in Rockville,Md to Conduct AIT Meeting & Discuss Results of Licensee Investigation of Recent Loss of off-site Power Event at McGuire Plant ML20058J5061993-11-29029 November 1993 Notification of Significant Licensee Meeting W/Util on 931203 to Discuss Licensee Intended EAL Changes for All Three Plants Relative to NUMARC Issues & Implementation of EPA-400 ML20058J4911993-11-24024 November 1993 Notification of Significant Licensee Meeting W/Util on 931206 to Discuss self-assessment of Plant Performance Since 930802-1130 ML20058C9631993-11-19019 November 1993 Notification of 931201 Meeting W/Util in Rockville,Md to Update NRC on Mcguire,Units 1 & 2 & Catawba,Unit 1 Steam Generator Replacement Project ML20057D1651993-09-27027 September 1993 Notification of 930929 Meeting W/B&W in Rockville,Md to Discuss Installation Process Used for B&W Kinetic Sleeves at McGuire Nuclear Station ML20057C5441993-09-23023 September 1993 Notification of 930929 Meeting W/Util in Rockville,Md to Discuss Results of Util Investigation of Unit 1 SG Tube Leaks & Util Actions as a Result of Findings from Investigation ML20056H3141993-08-24024 August 1993 Forwards Safety Evaluation Accepting Critical Aspects of Proposed TS Changes Involving Increasing Min Rswt Boron Concentrations from 2,000 Ppm to 2,275 Ppm & Increasing Min Cla Boron Concentration from 1,900 Ppm to 2,000 Ppm ML20134B2531993-02-11011 February 1993 Responds to 930113 Request for Exceptions to N+1 Policy for Listed Plants.Approved Exceptions W/Stated Conditions Effective for Period of 2 Yrs ML20128G8201993-02-0101 February 1993 Notification of Significant Licensee Meeting W/Util on 930211 to Discuss Enforcment Conference on Safeguards Issues ML20126F2821992-12-24024 December 1992 Forwards Description of Valves Affected by Stroke Testing & Effect of Valves Being Opened or Closed During Testing,W/ Respect to Encl LER 369/90-022-1 Re RHR Sys Being Inoperable ML20128A0361992-11-30030 November 1992 Notification of 921215 Meeting W/Util in Rockville,Md to Discuss Status of Licensees Plans to Implement Pilot Program for Use of Seismic Stops in Lieu of Snubbers at Plant ML20059H7861990-09-10010 September 1990 Forwards Revised Resolution of Plant-Specific Differing Prof Opinion (DPO) Issues Concerning McGuire Tech Specs, in Support of Completion of Dpos,Per Author 891229 Memo.Actions Re Tech Specs Listed ML20055D9791990-07-0505 July 1990 Notification of 900719 Meeting W/Util in Rockville,Md to Discuss Cause,Morphology & Future Plans Re Cracking Tubes at Expansion Transition Zone & at Tube Support Locations in Steam Generators.Agenda Encl ML20246P6001989-09-0505 September 1989 Notification of 890907 Site Visit & Meeting W/Util to Observe Existing Corrosion of Unit 1 Steel Containment Vessel & Discuss Adequacy of Remaining Wall Thickness for Units 1 & 2 ML20246B8381989-08-22022 August 1989 Notification of 890831 Meeting W/Util in Rockville,Md to Discuss Util Findings from Steam Generator Tubes & Plugs Inspected During Present Refueling Outage of Unit 2 from Earlier Related Metallurgical Analyses of Unit 1 Specimens ML20245K3261989-04-26026 April 1989 Notification of 890505 Meeting W/Util in Rockville,Md to Discuss Cause of Unit 890307-08 Tube Rupture,Corrective Actions & Plans for Restart ML20247B7351989-03-24024 March 1989 Notification of 890503 Meeting W/B&W,Inel & Util in Rockville,Md to Discuss Licensing Submittals for Plants ML20236E2931989-03-15015 March 1989 Discusses Closure of Outstanding Tech Spec Concerns Deriving from R Licciardo Differing Prof Opinion Review of Plant Tech Specs.Requests That Priority Be Given to Final Closure Including Completion of Remaining 45 Specific Items ML20236E2971989-03-15015 March 1989 Discusses Incorporation of Items Into Westinghouse STS Deriving from NRC Confirmation of Generic & multi-plant Action Concerns from R Licciardo Review of Plant Tech Specs ML20206E5691988-11-15015 November 1988 Summarizes 881109 Telcon W/Util Re Control Area Ventilation Sys Mod & Associated Tech Spec Change.Addl Info Requested Stated ML20058N6761988-10-18018 October 1988 Discusses Action Item 5 Assigned in 880406 Memo Related to Diagnostic Evaluation Team Report for Plant on Pump Damage Due to Low Flow Cavitation 1999-09-30 |
Text
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, g[2?arg# UNITED STATES
- h, NUCLEAR REGULATORY COMMISSION j g WASHINGTON, D. C. 20555 n- ,;
%,*****,/ APR 141983 l
MEMORANDUM FOR: Karl V. Seyfrit, Chief AE00/E306 Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operation Data FROM: Dorothy J. Zukcr Reactor Operations Analysis Branch
SUBJECT:
C00LDOWN DURING LOSS OF CONTROL ROOM TEST Enclosed please find the engineering evaluation on the loss of control room test at McGuire Unit 1.
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&ckt7 Dorothy Ji Z ord Reactor Operations Analysis Branch !
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