Letter Sequence Other |
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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
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Similar Documents at Hatch |
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Text
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4 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION GEORGIA POWER COMPANY, ET AL.
DOCKET NO. 50-321 NOTICE OF DENIAL OF AMENDMENT TO FACILITY OPERATING LICENSE AND OPPORTUNITY FOR HEARING The U.S. Nuclear Regulatory Commission (the Commission) has denied in part a request by the licensee for an amendment to Facility Operating License No. OPR-57, issued to the the Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, City of Dalton, Georgia (the licensee), for operation of the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility), located in Appling County, Georgia.
The amendment, as proposed by the licensee, modified the Hatch Unit 1 Technical Specifications, Section 3.7 to delete Tables 3.7-2, 3.7-3 and 3.7-4.
These Tables contain lists of primary containment penetrations and containment isolation valves.
It also deletes the reference to a specific revision of Appendix J.
The licensee's application for the amendment was dated March 5, 1979 and supplemented February 7,1984. Notice of Consideration of Issuance of this amendment was published in the FEDERAL REGISTER on April 25, 1984 (49 FR 17860). All of the requested changes were granted, except the request to delete Tables 3.7-2, 3.7-3 and 3.7-4.
Notice of Issuance of Amendment No.131 will be published in the Connission's Bi-Weekly FEDERAL REGISTER Notice.
The portion of the application which requested deletion of Tables 3.7-2, 3.7-3 and 3.7-4 was denied.
SehinnSt!8)y P
'I g
A The request to delete Tables 3.7-2, 3.7-3 and 3.7-4 was found to be unacceptable because they provide guidance in measuring the compliance of the licensee with the requirements of Appendix J and because deletion would be contrary to current Standard Technical Specifications.
The licensee was notified of the Commission's denial of this request by letter dated By the licensee may demand a hearing with respect to the denial described above and any person whose interest may be affected by this proceeding may file a written petition for leave to intervene.
A request for a hearing or petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, Attention: Docketing and Service Branch, or may be delivered to the Corcission's Public Document Room,1717 H. Street, N.W.,
Washington, D.C., by the above date.
A copy of any petitions should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, and to Bruce W. Churchill, Esquire, Shaw, Pittman, Potts and Trowbridge, 2300 N Street, N.W., Washington, D.C.
20036.
For further details with respect to this action, see (1) the application for amendment dated March 5,1979, as supplemented February 7,1984, and (2) the Commission's letter to Georgia Power Company dated October 30, 1986 which
4 k,, 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, Georiga. A copy of Item (2) may be obtained upon request addressed to the U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, Attention: Director, Division of BWR Licensing.
Dated at Bethesda, Maryland, this 30th day of October 1986.
FOR THE NUCLEAR REGULATORY COMMI SION
/w
/d Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
