Letter Sequence Other |
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Results
Other: ML19350D413, ML19350D417, ML20028C826, ML20032D142, ML20041F645, ML20054E028, ML20054E548, ML20054F828, ML20054F837, ML20069B852, ML20070W176, ML20071P933, ML20077J689, ML20080E860
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MONTHYEARML20003F4831981-04-0202 April 1981
Application to Amend License DPR-57,revising Diesel Generator Operability Requirements When Reactor Is in Shutdown or Refuel Modes & Fuel Is Not in Reactor Pressure Vessel
Project stage: Request
ML20003F5031981-04-0202 April 1981
Proposed Changes to Tech Spec Page 3.9-6
Project stage: Request
ML19350D4131981-04-0808 April 1981
Amend 82 to License DPR-57,relieving Licensee of Necessity to Maintain Two Operable Diesel Generators When Fuel Has Been Removed from Reactor Vessel
Project stage: Other
ML19350D4171981-04-0808 April 1981
Notice of Issuance & Availability of Amend 82 to License DPR-57
Project stage: Other
ML20032D1421981-11-0404 November 1981
Requests Exception to NUREG-0737,Item II.F.1.2 Re Effluent Monitoring of Radioiodines for Accident Conditions
Project stage: Other
ML20041F6451982-03-0505 March 1982
Responds to Re Deviations from Design Specs or Schedule Implementing NUREG-0737 Item II.F.1.3,accident Monitoring.Due to Inability to Obtain Parts & Documentation for Complete Installation,Extension Was Requested on 811104
Project stage: Other
ML20054E0281982-04-20020 April 1982
Forwards Completion Schedule for NUREG-0737 Requirements & Explanation of Requested Extensions of Schedule for Certain Items
Project stage: Other
ML20054E5481982-06-0404 June 1982
Forwards Response to 820505 Generic Ltr 82-10 Re post-TMI Requirement Implementation Schedule,Per NUREG-0737
Project stage: Other
ML20054F8371982-06-0707 June 1982
Forwards NUREG-0737 post-TMI Requirements Implementation Schedule Revision & Explanation in Response to Generic Ltr 82-05 & 820526 Request.Info Supersedes
Project stage: Other
ML20054F8281982-06-11011 June 1982
Revises Implementation Completion Date to Sept 1983 for NUREG-0737,Item II.K.3.22 Re Automation of Reactor Core Isolation Cooling Suction Transfer
Project stage: Other
ML20071P9331982-12-20020 December 1982
Revises Estimated Completion Date for Implementation of NUREG-0737,Item II.B.3 to 830401,in Response to Generic Ltr 82-05.Interim Sampling Capabilities Per NUREG-0578 Provided in
Project stage: Other
ML20028C8261983-01-0707 January 1983
Notifies of Intention to Revise Schedule for Implementation of NUREG-0737,Items I.C.1, Revise Emergency Procedures & III.A.2.2, Meteorological Data, in Response to Generic Ltr 82-33
Project stage: Other
ML20070Q7891983-01-18018 January 1983
Informs That Response to NRC 821217 Request for Addl Info in Support of post-implementation Review of NUREG-0737,Items II.F.1.4,II.F.1.5 & II.F.1.6 Cannot Be Submitted within 30 Days.All Requested Info Will Be Submitted by 830419
Project stage: Request
ML20070W1761983-02-11011 February 1983
Advises That Implementation of NUREG-0737,Items II.F.1(1) Re Noble Gas Effluent Monitor & II.F.1(2) Re Sampling & Analysis of Plant Effluents,Will Be Delayed Until 830315 Due to Component Failure
Project stage: Other
ML20069B8521983-03-11011 March 1983
Revises Estimated Completion Date to 830701 for Implementation of NUREG-0737,Item II.B.3, Post-Accident Sampling. Grab Sample Analysis Will Be Used in Interim
Project stage: Other
ML20077J6891983-08-15015 August 1983
Clarifies Re Schedule for Implementation of NUREG-0737,Item II.F.1(1), Noble Gas Effluent Monitor & II.F.1(2), Sampling & Analysis of Plant Effluents. Third high-range Monitor Installed.Implementation Completed
Project stage: Other
ML20080E8601984-02-0303 February 1984
Discusses Time at Which Hydrogen Monitoring Is Initiated. Intent of TMI Item II.F.1(6) Is to Ensure Timely Hydrogen Monitoring in Event of Core Uncovery During Loca.Definition for Onset of LOCA Undefinable
Project stage: Other
1982-06-04
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Similar Documents at Hatch |
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Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION 7590-01 DOCKET NO. 50-321 p
GEORGIA POWER COMPANY, ET AL.
f f
Nn! ICE OF ISSUANCE OF Af1ENDf1EflT TO FACILITY OPERATING LICENSE The U. S. fluclear Regulatory Commission (the Commission) has issued Amendment flo. 82 to Facility Operating License No. DPR-57, issued to Georgia 1
Power Company, Oglethorpe Power Corporation, flunicipal Electric Authority of Georgia, and City of Dalton, Georgia, which revised Technical Specifications for operation of the Edwin I. Hatch Nuclear Plant, Unit No.1, (the facility) located in Appling County, Georgia.
The amendment is effective as of its l
date of issuance.
The amendment revises the Technical Specifications as they relate to diesel generator operability to relieve the licensee of the necessity to maintain two diesels operable when the fuel has been removed from the reactor vessel.
l' Taa spplication for the amendment complies with the standards and requirenents of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Comission has made appropriate findings as required by the Act and the Comission's rules and regulations l
in 10 CFR Chapter I, which are set forth in the license amendment.
Prior public notice of this amendment was not required since the amendment does not involve a significant hazards consideration.
l The Commission has detemined that the issuance of this anendment will not result in any significant environnental impact and that pursuant to 10 CFR 951.5(d)(4), and environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of this amendment.
8104150L %
1 7590-01 1
For further details with respect to this action, see (1) the application for amendment dated April 2,1981,(2) Amendment No. 82 to License No. DPR-57, and (3) the Comission's letter to Georgia Power Company dated April 8, 1981.
All of these items are available for public inspection at the Commission'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. A copy of items (2) and (3) may be obtained upon request addressed to the U. S. fluclear Regulatory Comission, Washington, D. C.
20555, Attention: Director, Division of Licensing.
Dated at Bethesdd, Maryland, this 8th day of April 1981.
F THIS fiUCLK REGULATORY C0 fit SSION Ac r # ~
John F. Stolz, Chief l
@pe ating Reactors Branch #4 ision of Licensing l
l l
i l
l I
