Letter Sequence Other |
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Results
Other: ML19209B217, ML19210E687, ML19250C166, ML19261C487, ML19270F761, ML19338C686, ML19341C283, ML19344D978, ML20039B447, ML20070S058, ML20071C377, ML20076C882, ML20076H077, ML20080K634, ML20082N526, ML20082N549, ML20244A626
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MONTHYEARML19261C4871979-02-27027 February 1979
SER of Interim Assessments of MSIV Actuations in Mark I Containment Plants
Project stage: Other
ML19270F7611979-03-12012 March 1979
Discusses Status of Mark I Containment long-term Program. Requests Schedule Showing Time Periods for Installation of Specific Plant Mods.Discusses Safety Relief Valve Discharge Device Installation & Forwards Staff Evaluation
Project stage: Other
ML20244A6261979-05-14014 May 1979
Forwards Schedule for Implementation & Resolution of Mark I Containment long-term Program.Only Vent Header Deflectors Are Necessary as Major Mod for Conformance to long-term Program Acceptance Criteria
Project stage: Other
ML19209B2171979-10-0202 October 1979
Forwards Proposed Amend to License NPF-5,changing Tech Specs,App a
Project stage: Other
ML19250C1661979-10-31031 October 1979
Forwards Rept, NRC Acceptance Criteria for Mark I Containment Long-Term Program. Requests Schedule for Submittal of long-term Program plant-unique Analysis
Project stage: Other
ML19210E6871979-11-30030 November 1979
Commits to Addl Confirmatory Condensation Oscillation Tests in full-scale Test Facility,Outlined in GE Re Mark I Containment Program.Schedule for Submittal of Plant Unique Analysis Will Be Provided Following NRC Resolution
Project stage: Other
ML19320B1581980-06-26026 June 1980
Notification of 800703 Meeting W/Util in Bethesda,Md to Discuss Util Basis for Delayed Schedule for Installing T-quenchers
Project stage: Meeting
ML19338C6861980-08-0707 August 1980
Submits Documentation Re Previous Mod,Future Installations & Completion Schedule Per Ongoing Mark I long-term Program. Mods Performed to Strengthen Torus Shell & Related Structures
Project stage: Other
ML19344D9781980-08-14014 August 1980
Provides Clarification Re Util Outlining Schedule for Resolution of Mark I Program Concerns.Recent Tests Indicated That Submerged Structure Loads Caused by SRV Actuation Are Negligible
Project stage: Other
ML20003A6761981-01-13013 January 1981
Order Granting Extension of Exemption from General Design Criteria 50 & Requiring Licensee to Reassess Containment Design for Suppression Pool Hydrodynamic Loading
Project stage: Approval
ML20037C3601981-01-13013 January 1981
Order Granting Extension of Exemption from General Design Criteria 50 & Requiring Licensee to Reassess Containment Design for Suppression Pool Hydrodynamic Loading
Project stage: Approval
ML19345F7441981-02-13013 February 1981
Summary of 810210 Meeting W/Util Re Impact of Mark I Containment Orders on long-term Program for Facilities. Attendance List Encl
Project stage: Meeting
ML19341C2831981-02-24024 February 1981
Requests Mod of Schedules for Completion of Mark I Program Per NRC 810113 Orders.Completion Is Tied w/1982 Refueling Outage for Each Unit.Requests Hearing in Event NRC Does Not Approve or Act Upon Request
Project stage: Other
ML20039B4471981-12-14014 December 1981
Commits to Complete BWR Mark I Containment long-term Program Prior to Startup for Fuel Cycle 7 (Unit 1) & Fuel Cycle 4 (Unit 2)
Project stage: Other
ML20070S0581983-01-26026 January 1983
Forwards, Mark I Containment Long-Term Program Plant Unique Analysis Rept. Suppls Re Safety/Relief Valve Discharge Line Drywell Supports & Torus Attached Piping & Supports Scheduled for 830228 Submittal
Project stage: Other
ML20071C3771983-02-28028 February 1983
Forwards, Mark I Containment Long-Term Program Plant Unique Analysis Rept-Suppl. Rept Addresses safety-relief Valve Discharge Line Drywell Supports,Torus Attached Piping & Supports,Valves,Pumps & Torus Shell Nozzles
Project stage: Other
ML20069G1691983-02-28028 February 1983
Public Version of Rev 15 to Emergency Plan Implementing Procedure HNP-8008, Radiation Work Permit
Project stage: Request
ML20076C8821983-05-16016 May 1983
Commits to Submit Results of plant-unique Calculations Re Acceptability of Mod to Torus Vacuum Breakers by 830615, in Response to Generic Ltr 83-08
Project stage: Other
ML20076H0771983-06-0202 June 1983
Forwards Revised Pages to Plant Unique Analysis Rept Re Resolution of torus-attached Piping Pump & Valve Evaluation. Pages Reflect Satisfactory Results of Evaluation of 14 Valves & Two Pumps
Project stage: Other
ML20024E0591983-08-0101 August 1983
Forwards Request for Addl Info Re Mark I Containment long- Term Program plant-unique Analysis Rept on Loads & Structural Evaluations.Meeting at Contractors Ofc to Resolve Issues Suggested
Project stage: RAI
ML20080J4881983-09-16016 September 1983
Forwards Explanation of Use of Srss in Lieu of Absolute Sum in Calculations Involving Certain Multiple Valve Actuations, Per 830831 Meeting.Replacement Pages in Response to Questions Raised in Also Encl
Project stage: Meeting
ML20080K6341983-09-27027 September 1983
Audit for Mark I Containment Long-Term Program - Structural Analysis for Operating Reactors,Ei Hatch Nuclear Plant Units 1 & 2, Technical Evaluation Rept
Project stage: Other
ML17194B7301983-09-30030 September 1983
Forwards Proprietary Dresden 2/3 Nuclear Generating Plant Suppression Pool Temp Response, Ei Hatch Nuclear Power Station Units 1 & 2 Suppression Pool Temp Response & Mark I 830825 Meeting Viewgraphs.Repts Withheld (Ref 10CFR2.790)
Project stage: Meeting
ML20082N5261983-12-0505 December 1983
Forwards Revised Pages to plant-unique Analysis Rept, Reflecting 10 Valve Evaluations Unavailable in 830228 Rept
Project stage: Other
ML20082N5491983-12-31031 December 1983
Rev 2 to Plant-Unique Analysis Rept for Ei Hatch Nuclear Plant Unit 1,Mark 1 Containment Long-Term Program
Project stage: Other
1981-02-13
[Table View] |
Similar Documents at Hatch |
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Text
Georg'c Power Company 230 Peachtree Street Post OfSce Box 4545 Atlanta Georgia.30302 Teiconoce 4C4 522 6060 August 14, 1980 GeorgiaPower W. A. Widner lL'e'e',','fe'"e',, jo*'" ~ "***'
ene sournem ewrc sys:em U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C.
20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 MARK I PROGRAM SCHEDULE Gentlemen:
Georgia Power Company wishes to provide clarification of two points in our Augurt 7,1980, letter to you outlining our schedule for resolution of the Mark i program concerns.
Recent tests have indicated that submerged structure loads caused by SRV actuation are negligible. The test results contradict the analytical prediction for the same loading phenomenon. Georgia Power Company is in the process of receiving material and fabricating equipment for installation during the scheduled outages. Should near future activities clearly show that a particular modification is not justifiable, such modifications will not be accomplished.
Dates are listed in our August 7,1980, letter for scheduled refueling outages in 1980, 1981 and 1982. These dates, of course, are estimates of when the units will be brought down for refueling. Should the refueling outage dates change, due to either higher or lower capacity factors than projected, the Mark I work associated with the outage would be performed during the scheduled refueling outage.
Very truly yours, W. A. Widner RDB/SAW/mb xc: Ruble A. Thomas j
l George F. Trowbridge, Esquire R. F. Rogers, III 4
%,\\ D 8008260458 l
