Letter Sequence Other |
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Results
Other: ML20008G315, ML20023B690, ML20023B693, ML20064D127, ML20064G097, ML20064K897, ML20064N491, ML20070W125, ML20070W130, ML20071A617, ML20079N907, ML20083N032, ML20083N079
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MONTHYEARML20008G3151981-06-29029 June 1981
Responds to Generic Ltr 81-04 Re Implementation of NUREG-0313,Revision 1, Technical Rept on Matl Selection & Processing Guidelines for BWR Coolant Pressure Boundary Piping, Per NRC 810226 Request
Project stage: Other
ML20064D1271982-12-15015 December 1982
Responds to Items 1 & 4 of IE Bulletin 82-03 Re Stress Corrosion Cracking in Austenitic Stainless Steel Recirculation Sys Piping.Total of 51 Circumferential & Branch Connection Welds & 6 Longitudinal Welds Examined
Project stage: Other
ML20064G0971983-01-0606 January 1983
Forwards Documentation of 821207,13 & 14 Telcons Re Inservice Insp Findings & Resultant Repair Activities Conducted During Maint/Refueling Outage Presently in Progress
Project stage: Other
ML20064K8971983-01-26026 January 1983
Responds to IE Bulletin 82-03 Re Stress Corrosion Cracking in Austenitic Stainless Steel in BWR Recirculation Sys Piping.Info Re Items 1 & 4 Submitted 821215.Info Completes Response
Project stage: Other
ML20083N0321983-01-26026 January 1983
Responds to Items 2 & 3 of IE Bulletin 82-03 Re Stress Corrosion Cracking in Austenitic Stainless Steel BWR Recirculation Sys Piping.Responses to Items 1 & 4 Provided in Util .Recirculation Sys Welds Will Be Repaired
Project stage: Other
ML20083M9661983-01-27027 January 1983
Forwards Info Re Analyses & Repairs of Recirculation & RHR Sys Piping Welds.Details of Inservice Insp Discussed.Util Intends to Return Unit to Power Operation Upon Completion of Current Outage.Meeting Scheduled for 830201 to Discuss Subj
Project stage: Meeting
ML20083N0791983-01-31031 January 1983
Rev 0 to Design Rept for Recirculation Sys & RHR Sys Weld Overlay Repairs & Flaw Evaluation at Ei Hatch Nuclear Power Plant Unit 1
Project stage: Other
ML20064N4771983-02-10010 February 1983
Application for Amend to License DPR-57,revising Tech Specs on Reactor Coolant Leakage Limiting Conditions for Operation & Surveillance Requirements
Project stage: Request
ML20064N4911983-02-10010 February 1983
Proposed Tech Specs Re Reactor Coolant Leakage Limiting Conditions for Operation & Surveillance Requirements
Project stage: Other
ML20070W1251983-02-11011 February 1983
Forwards Corrected Proposed Tech Specs Re Recirculation & RHR Sys Piping Repairs Submitted on 830210.Typographical Errors Contained in Paragraphs 2.a & 2.b of Page 3.6-8
Project stage: Other
ML20071A6171983-02-11011 February 1983
Notice of Issuance & Availability of Amend 93 to License DPR-57
Project stage: Other
ML20070W1301983-02-11011 February 1983
Corrected Proposed Tech Spec Page 3.6-8 Re Reactor Coolant Leakage
Project stage: Other
ML20071A6061983-02-11011 February 1983
Safety Evaluation Supporting Amend 93 to License DPR-57
Project stage: Approval
ML20079N9071983-02-18018 February 1983
Documents 830124 Telcon Re Replacement of Selected Portion of Stainless Steel 4-inch Diameter Reactor Water Cleanup Return Line Piping
Project stage: Other
ML20023B6931983-03-0404 March 1983
Rev 1 to Design Rept for Recirculation Sys & RHR Sys Weld Overlay Repairs & Flaw Evaluation at Ei Hatch Nuclear Power Plant,Unit 1
Project stage: Other
ML20023B6901983-04-28028 April 1983
Forwards Rev 1 to Design Rept for Recirculation Sys & RHR Sys Weld Overlay Repairs & Flaw Evaluation at Ei Hatch Nuclear Power Plant,Unit 1
Project stage: Other
1983-01-06
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Similar Documents at Hatch |
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Text
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7590-01 UNITED STATES NUCLEAR REGULATORY COMISSION DOCKET NO. 50-321 GEORGIA POWER COMPANY, ET AL.
NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Commission (the Comission) has issue.d Amendment No fj to Facility Operating License No. DPR-57, issued to Georgia Power Company, Oglethorpe Power Corporation, Municipal Eicctric Authority of Georgia, and City of Dalton, Georgia, which added a license dondition and revised Technical Specifications (TSs) for operation of the Edwin I.
Haten Nuclear Fjant, Unit No.1 (the fa ility) located in Appling County, Georgia. The amendment is effective as of the date of issuance.
The amendment revises the license for Hatch Unit No.1 to:
(1) add a condition concerning submittal of plans for inspection of the Recirculation and Reactor Heat Removal Piping Systems during the next refueling outage for Comission review and approval, and (2) change the TSs to augment the leak detection requirements.
The application for the amendment complies with the standards and requirements of the Atomic Ener9y Act of 1954, as amended (the Act), and the Comission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's'. rules and regu'lations in 10 CFR Chapter I, which are set forth in the license amendment. PrioF public notice of this amendment was not required since the amendment does not involve a significant hazards consideration.
The Commission has determined that the issuance of this amendment will not result in any significant environmental impact and that pursuant to 10 CFR Section 51.5(d)(4) an environmental impact statement, or negative declaration 8302240268 830211 PDR ADOCK 05000321 P
PDR
. 7590-01 and environmental impact appraisal need not be prepared in connection with issuance of this amendment.
For further details with respect to this action, see (1) the applica-tion for amendment dated. February 10, 1983,(2) Amendment No.73 to Lice.nse No. DPR-57, and (3) the Commission's related Safety Evaluation. All of these items are available for public inspection at the Consnission's
~
Public Document Room, 1717 H Street, N.W., Washington, D. C. and at the Appling County Public Library, 301 City Hall Drive,'Baxley. Georgia 31513. Acopi of items (2) anc} (3) may be obtained upon T quest addressed to the U. S.
b Nuclear Regulatory Commission, Washington, D. C.
20555, Attention: Director, Division of Licensing.
Dated at Bethesda, Maryland, this lith day of February 1983.
FOR M W M R M d ORY M SS M FEBRUARY 1 1 1983 j
Joh F. Stolz, Chief l Op ating Reactors Branch d4 vision of Licensing 4
e O
4
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