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
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Georga Po4er Cor"pany 230 Peachtree Street Post O'f:ce Box 4545 Atanta. Georgia 30302 Tetophore 404 522 6060 R. J. K elly October 2, 1979 Georgiti Power vice Presdent ano Gen..rai Manager Power Generation r
e Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS Gentlemen:
Pursuant to 10 CFR 50.90 as required oy 10 CFR 50.59(c)(1), Georgia Power Company hereby proposes an amendement to the Plant Hatch Unit 2 Technical Specifications (Appendix A to the Operating License).
The proposed amendment here-in is a supplement to our previous submittal of July 27, 1979 which was subsequently denied by your letter of August 29, 1979. The proposed change would revise the ACTION statements of Technical Specification 3.6.4.1 to allow continued operation until the next COLD SHUTDOWN with one or two suppression chamber to drywell vacuum breakers inoperable but known to be in the closed position.
The HNP-2 FSAR (Section 6.2.1.2.1.6.1) supports continued operation with 9 operable valves and 3 inoperable valves which are known to be closed. Clearly, with one or two inoperable valves, the vacuum relief capacity is adequate such that a failure of a single active component can be tolerated without compromising the relief capacity.
Sufficient redundancy exists with two valves inoperable to allow start-up from a HOT SHUTDOWN condition without requiring that maintenance be performed on the inoperable valves. Maintenance on inoperable torus to drywell vaccum breakers can not safely be performed in the HOT SHUTDOWN condition and requiring the unit to go to the COLD SHUTDOWN condition to repair one or two valves places an unnecessary burden on plant operations.
The proposed amendment has not changed the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety which has been previously analyzcd because no change in the mode of operation is effected as a result of the proposal.
Similarly, the possibility of an accident or malfunction of a different type does not result from this change because no equipment design or operation is altered. Margins of safety are not reduced from those afforded by the existing Specification because operating limits have not been changed.
n g-p 7910090 3M ilaIU
k Georgia Power h The Plant Review Board and the Safety Review Board have reviewed and approved the proposed amendment, and in consideration of the above have d '_crmined that the proposed amendment does not constitute an unreviewed safety question.
Yours very truly, R. J. Kelly JAB /mt Sworn to and subscribed before me this 2nd day of October, 1979.
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Notary I'ublic xc: Ruble A. Thomas Notary PubHe, Georgia, State at Large y
n ssi n ru uY 28, M80 George F. Trowbridge, Esquire R. F. Rogers r-
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