Letter Sequence Approval |
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MONTHYEARML20104A2851979-03-0505 March 1979
Containment Leak Rate Test Program Incorporating Updated NRC Positions
Project stage: Other
ML19282B1571979-03-0505 March 1979
Forwards Reevaluation of Containment Leak Rate Test Program & Proposed Changes to Tech Specs Reflecting Provisions of Updated Program
Project stage: Request
ML20080J0871984-02-0707 February 1984
Informs That NRC Has Agreed to Issue Changed Pages Re Removal of Ref to Tech Spec 4.7.E Concerning 10CFR50,App J, Per 840127 Telcon
Project stage: Other
ML18031B3151986-05-14014 May 1986
Informs That Engineering Expertise on Shift Provided by Having Shift Technical Advisor on Duty,In Response to Generic Ltr 86-04.Bachelor Degree in Engineering Discipline Is Min Requirement for Shift Technical Advisor
Project stage: Request
ML20198B4641986-05-14014 May 1986
Submits Addl Info to Support 771116 Request for Changes to Containment Leak Test Program,Per Rivenbark & Kudrick Requests
Project stage: Request
ML20215N2381986-10-0707 October 1986
Environ Assessment & Finding of No Significant Impact Re Proposed Exemption from App J Containment Leak Test Requirements
Project stage: Approval
ML20215N2241986-10-30030 October 1986
Amend 131 to License DPR-57,revising Tech Specs to Delete Ref to Specific Dtd Versions of App J Re Containment Leak Testing Requirements
Project stage: Other
ML20215N2461986-10-30030 October 1986
Exemption from Certain Requirements of 10CFR50,App J Re Containment Leak Testing
Project stage: Approval
ML20215N2511986-10-30030 October 1986
Notice of Denial of Application to Amend License DPR-57, Deleting Specific Dtd Version of App J Re Containment Leak Testing Requirements.Hearing May Be Requested
Project stage: Other
ML20215N2911986-10-30030 October 1986
Safety Evaluation Supporting Exemption from 10CFR50,App J & Amend 131 to License DPR-57
Project stage: Approval
ML20212N0121987-03-0404 March 1987
Proposed Tech Specs Deleting App J Leak Rate Testing Requirements for Certain Valves from Table 3.7-4 & Providing Administrative Correction to MSIV Test Pressure Requirement
Project stage: Other
IR 05000321/19870041987-03-0404 March 1987
Insp Rept 50-321/87-04 & 50-366/87-04 on 870223-27.No Violations Noted.Major Areas Inspected:External Exposure Controls,General Employee Training,Facilities & Equipment & Licensee Program to Maintain Low Exposures
Project stage: Request
ML20212N0011987-03-0404 March 1987
Application for Amend to License DPR-57,deleting App J Leak Rate Testing Requirements for Certain Valves from Table 3.7-4 & Providing Administrative Correction to MSIV Test Pressure Requirements.Fee Paid
Project stage: Request
ML20209D0861987-04-21021 April 1987
Revised Application for Amend to License DPR-57,revising Tech Spec Page 3.7-26 to Assign Valve X-211A to Penetration X-210A & Withdrawing Request to Delete Valves E11-F027A & B from Table 3.7-4
Project stage: Request
ML20209D1181987-04-21021 April 1987
Proposed Tech Spec Table 3.7-4 Assigning Valve E11-F028A to Penetration X-211A,restoring Valves E11-F027A & B & Deleting Valves E11-F011B & F026B
Project stage: Other
ML20214T6741987-05-29029 May 1987
Environ Assessment & Finding of No Significant Impact Re Licensee 870304 Application for Amend to Tech Specs,Deleting Certain Valves from Table 3.7-4 That Lists Containment Isolation Valves Subj to Leak Rate Testing,Per 10CFR50
Project stage: Other
ML20214T6401987-06-0101 June 1987
Forwards Environ Assessment & Finding of No Significant Impact Re 870304 Application to Amend License DPR-57 by Revising Tech Specs to Delete Certain Valves from Table 3.7-4
Project stage: Other
ML20214V6631987-06-0505 June 1987
Environ Assessment & Finding of No Significant Impact Re Amend to License DPR-57,revising Tech Specs to Delete Some Valves from Table 3.7-4 That Lists Containment Isolation Valves Subj to Leak Rate Testing Per 10CFR50,App J
Project stage: Other
ML20214V6421987-06-0505 June 1987
Safety Evaluation Supporting Amend 140 to License DPR-57
Project stage: Approval
ML20214V6531987-06-0505 June 1987
Notice of Issuance of Amend 140 to License DPR-57.Amend Modifies Tech Specs to Delete Certain Valves Listed in Table 3.7-4 as Containment Isolation Valves Requiring Leak Tests & Changing Pressure at Which MSIVs Required to Be Tested
Project stage: Approval
ML20214V6391987-06-0505 June 1987
Amend 140 to License DPR-57,modifying Tech Spec Table 3.7-4 to Delete Certain Valves Listed as Containment Isolation Valves Requiring Leak Tests & Changing Pressure at Which MSIVs Required to Be Tested
Project stage: Other
1986-05-14
[Table View] |
Similar Documents at Hatch |
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Text
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7590-01 U. S. NUCLEAR REGULATORY COM4ISSION
_ GEORGIA POWER COMPANY, ET. AL.
1
_ DOCKET NO. 50-321 NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Commission (Commission) has issued Am No.140to Facility Operating License No. DPR-57, issued to Georgia Oglethorpe Power Corporation, Municipal Electric Authority of Georg of Dalton, Georgia (the licensee), which revised the Technical Specifications for operation of the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) located in Appling County, Georgia. This amendment was effective as of the date of its issuance.
The amendment modified the Technical Specifications to delete certain valves listed in Table 3.7-4 as containment isolation valves requiring leak
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test, correct information errors in Table 3.7-4, and change the pressure at which main steam isolation valves are required to be tested.
The application for the amendment complies with the standards and re-quirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
Notice of Consideration of Issuance of Amendment and Opportunity for Prior Hearing in connection with this action was published in the FEDERAL REGISTER on March 27, 1987 (52 FR 9980). No request for a hearing or petition for leave to intervene was filed following this notice.
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. The Commission has prepared an Environmental Assessment andsFir; ding of No Significant Impact related to the action and has concluded that an environ-mental impact statement is not warranted because there will be no environmental impact attributable to the action beyond that which has been predicted and described in the Commission's Final Environmental Statement for the facility dated October 1972 For further details with respect to the action see (1) the application for amendment dated March 4,1987, as supplemented April 21,1987,(2) Amend-ment No.140 to License No. DPR-57, (3) the Commission's related Safety Evaluation, and (4) the Commission's related Environmental Assessment and Finding of No Significant Impact. All of these items are available for public inspection at the Lomission's Public Document Room,1717 H Street, N.
W.,
Washington, D. C., and at the Appling County Public Library, 301 City Hall Drive, "axley, Georgia 31513. A copy of items (2), (3), and (4) may be obtained upon request addressed to the U. S. Nuclear Regulatory Conmission, Washington, D. C., 20555, Attention: Director, Division of Reactor Projects-I/II.
Dated at Bethesda, Maryland this 5th day of June 1987.
FOR THE NUCLEAR REGULATORY COMMISSION
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Lawrence P. Crocker, Project Manager Project Directorate II-3 Division of Reactor Projects-I/II PD#II-3/DRP-I/II PD#IJd/DRP-I/II PDd DRP-I/II LCrocker/mac MDun'can BJYo r t od 05/jl /87 05/y' /87 05/g 8
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