Letter Sequence Request |
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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
Georg'a Power Company 333 Piedmont Avenue Atlanta, Georg a 30308 Televone 404 526 6526 Mai!ang Address.
Ibst Office Box 4545 Allarta Georgia 30302 b
Georgia Power L T. Gucwa
" " " ' " ^"' % M Manager Nuclear SWty and Licens ng SL-2350 1300C X7GJ17-H600 April 21, 1987 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Hashington, D.C.
20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 PLANT HATCH UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS PRIMARY CONTAINMENT ISOLATION VALVES:
REVLSI0fLLO_P_REVIOULSWhi1IIAL Gentlemen:
Georgia Power Company's (GPC'O submittal of March 4, 1987 sought to revise Technical Specificat!cas (TS) providing primary containment isolation valve leak rate testing requirements for Plant Hatch Unit 1.
Based upon discussions with the NRC on April 2,1987, and April 6,1987, we now wish to revise the subject submittal as follows:
1.
Proposed changed TS page 3.7-26, as provided in the subject submittal, assigned valve E11-F028A to penetration X-210A.
The correct penetration for this valve should be X-211A.
Proposed changed TS page 3.7-26a, as provided in the subject submittal, assigned valve E11-F028B to penetration X-2108.
The correct penetration for this valve should be X-2118.
2.
Valves E11-F027A and B were proposed to be deleted from the table.
He understand that this request will not be acted upon at this
- time, but will be the subject of further review.
Revised TS pages 3.7-26 and 3.7-26a, incorporating the corrections noted in item I above, are hereby provided, with valves E11-F027A and B
restored to the table for your convenience in preparation of the amendment for issuance.
3.
Valves E11-F0118 and F0260 should be deleted from proposed TS page 3.7-26a.
The basis for this proposed change was discussed in the March 4,1987, submittal; however, the actual change was not reflected on proposed TS page 3.7-26a.
The enclosed revised page 3.7-26a correctly reflects the deletion of the subject valves U[)0 # $0t b O v
9
GeorgiaPower A U. S. Nuclear Regulatory Commission ATTN: Document Control Desk April 21, 1987 Page Two These changes are editorial in nature and do not impact the safety evaluation or determination of No Significant Hazards previously provided.
Should you have any questions or concerns, please contact this office at any time.
Sincerely, L. T. Gucwa JDH/lc
Enclosure:
Revised TS pages c: Georaia Power Comoany U.S. Nuclear Regulatory Commission Mr. J. P. O'Reilly Dr. J. N. Grace, Regional Administrator Mr. J. T. Beckham, Jr.
Mr. P. Holmes-Ray, Senior Resident GO-NORMS Inspector - Hatch Mr. L. P. Crocker, Licensing Project Manager - Hatch l
l 1300C 700775
__
