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MONTHYEARML20041D0201982-02-0303 February 1982
Notifies That plant-specific Ref to GE 810506 & 28 Position Is Acceptable Basis for Request to Extend Burnup for All Fuel Types.Limits Inherent in 10CFR51.20 Re Environ Effects from Transport of Irradiated Fuel Should Not Be Neglected
Project stage: Other
ML20073R3581983-04-22022 April 1983
Revised Tech Specs Re TMI Action Plan Items I.A.1.1.3, I.A.1.3,II.E.4.1,II.E.4.2.5-7,II.K.3.3,II.K.3.13,II.K.3.22, II.K.3.15,II.K.3.19,II.K.3.27,II.K.3.45 & II.F.1-4
Project stage: Other
ML20073R3351983-04-22022 April 1983
Application to Amend Licenses DPR-57 & NPF-5,revising Tech Specs Re TMI Action Plan Items I.A.1.1.3,I.A.1.3,II.E.4.1, II.E.4.2.5-7,II.K.3.3,II.K.3.13,II.K.3.22,II.K.3.15, II.K.3.19,II.K.3.27,II.K.3.45 & II.F.1-4
Project stage: Request
ML20023B7761983-05-0202 May 1983
Requests That Portion of 830422 Response to Generic Ltr 83-02 Be Withdrawn.Portion Re Item II.F.1, Addl Accident Monitoring Instrumentation, Will Be Reevaluated Upon Receipt of NRC Guidance
Project stage: Other
ML20076K7191983-09-0909 September 1983
Proposed Tech Spec Changes to Reflect Implementation of TMI Action Plan Item II.K.3.22, RCIC Suction Automatic Transfer
Project stage: Other
ML20076K7051983-09-0909 September 1983
Application for Amend to License NPF-5,proposing Tech Spec Changes to Reflect Implementation of TMI Action Plan Item II.K.3.22, RCIC Suction Automatic Transfer, as Required by Generic Ltr 83-02
Project stage: Request
ML20080P6201983-09-29029 September 1983
Proposed Changes to Tech Specs Re MAPLHGR Curve Design for Core Reconstitution
Project stage: Request
ML20080P6161983-09-29029 September 1983
Application to Amend License DPR-57,changing Tech Specs to Allow Increased Flexibility in Core Design for Core Reconstitution Schedule for Nov 1983 Replacement of Damaged Fuel
Project stage: Request
ML20081C6501983-10-24024 October 1983
Clarification to 830929 Application to Amend License DPR-57, Revising Tech Specs to Support Planned Shutdown for Core Reconstitution
Project stage: Supplement
ML20081C5081983-10-24024 October 1983
Notifies of Possible Problem Re 10CFR50.49 Equipment Qualification Deadline for Electrical Components of HPCI Control Sys.Problems First Discovered on 830825.Extension of Rulemaking Deadline May Be Requested.Util Awaiting Data
Project stage: Other
ML20078Q9831983-10-27027 October 1983
Notice of Consideration of Issuance of Amend to License DPR-57 & Proposed NSHC Determination & Opportunity for Hearing
Project stage: Other
ML20082B9341983-11-15015 November 1983
Responds to Inquiries Re Amplification of Plans for Current Core Reconstitution Due to Leaking Fuel Rods.Ge Developed Program to Minimize Future Crud Induced Localized Corrosion Failures
Project stage: Other
ML20082V3441983-12-0606 December 1983
Amend 96 to License DPR-57,modifying Tech Specs to Reflect Changes to Core Design Associated W/Replacement of Leaking Fuel Assemblies & Extending Allowable Fuel Burnup Limit from 30 Gwd/T to 40 Gwd/T
Project stage: Other
ML20082V3521983-12-0606 December 1983
Safety Evaluation Supporting Amend 96 to License DPR-57
Project stage: Approval
1983-12-06
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Similar Documents at Hatch |
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Georg a Power Corrpany 333 Piedmont Avenue Atlanta, Georgia 30308 Telephone 404 52G6526 Maing Address:
Post Ottee Box 4545 AtlaMa, Georg a 30302 g
Georgia Power ban'a
[uclear Eng.neertng October 24, 1983 and Ch:ef Nuclear Eng neer NED-83-518 Director of Nuclear Reactor Regulation Attn: Mr. John F. Stolz, Chief.
Operating Reactor Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Ccmnission Washington, D. C.
20555 NRC Docket 50-321 Operating License DPR-57 Edwin I. Hatch Nuclear Plant Unit 1 Amendnent to Request For 01ange To Plant Hatch Unit 1 Technical Specifications Gentlenen:
Georgia Power Cmpany wishes to clarify our Septenber 29, 1983 subnittal which proposed Technical Specification changes in support of our planned shutdown for core reconstitution. We would clarify the second paragraph of the first page as follows:
'Ihe ECG calculations were done using approved General Electric models which meet the criteria specified in 10 CFR 50 Appendix K.
We reviewed the peak clad tenperatures resulting frm these models for the proposed fuel types and concluded that the results conform to the criteria of 10 CFR 50.46 and of References 2, 3, and 4.
If you have any questions regarding this clarification, please contact this office.
Yours very truly,
/T %
L. T. Gucwa Manager Nuclear Engineering and Chief Nuclear Engineer DLT/blm xc:
H. C. Nix, Jr.
T. V. Greene J. P. O'Reilly N
Site Resident Inspector J. L. Ledbetter IfO 8310310308 831024 PDR ADOCK 05000321 PDR p
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