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
Georg a Pe.ver Company
(
\\.
333 P edmont Avese i
At'anta. Georg a 30308 Te!cphone 404 5264526 Madmg Adcess.
Post OffcCO 80x 4545 Atlanta Georg a 30302 Georgia Power L.T.oucwa tv ou: men ecctrc sys:cm Chef Nuclear Engmeer Power Generat:on Deparin:ent NED-83-265 April 2E, 1983 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKET 50-321 OPERATItG LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 DESIGN REPORT REVISION - RECIRCULATION AND RHR SYSTEMS ANALYSES AND REPAIRS Gentlemen:
By letter dated January 27, 1983, Georgia Power Company submitted information regarding the analyses and repairs of Recirculation System and Residual Heat Removal (RHR) System piping welds which were inspected during the 1982 Hatch Unit 1 maintenance / refueling outage and found to have unacceptable flaw indications.
Enclosed as Attachment 6 to that submittal was Revision 0 of NUTECH report no.
GPC-04-104,
" Design Report For Recirculation System and Residual Heat Removal System Weld Overlay Repairs and Flaw Evaluation at E. I. Hatch Nuclear Power Plant, Unit 1."
Since our submittal of January 27, 1983, NUTECH has revised the design report. Enclosed herein are two copies of Revision 1 of the subject NUTECH l
rep rt.
The revised NUTECH report supersedes that submitted as Attachment 6
- 00 in our January 27, 1983, letter.
Some of the changes in Revision 1 of the NUTECH design report include:
e Re-calculation of fatigue crack growth for the 5-year design life.
e Resolution of third party reviewer comments regarding any sensitization caused by the weld overlay, and the recirculation sweepolet code stress analysis.
8305060051 830428 PDR ADOCK 05000321 P
PDR
l
'e A
Georgia Power h Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 April 28, 1983 Page Two e
Addition of Section 9.0 which discusses engineering changes to RHR pipe-to-pipe weld overlay.
(Note:
The engineering changes were discussed in our February 1, 1983 meeting with the NRC staff.)
Typically, changes are noted in the revised NUTECH report by vertical lines in the margins.
The overall conclusions of the original report are not changed as a result of these revisions.
By copy of this letter, a copy of the revised NUTECH design report is being supplied to NRC Region II for their review.
Should you have any questions in this regard, please contact this office.
Sincerely yours,
- f. T 4<~a L. T. Gucwa JAE/mb Enclosures (2) xc:
(all w/ 1 encl.)
J. T. Beckham, Jr.
H. C. Nix, Jr.
J. P. O'Reilly (NRC Region II)
Senior Resident Inspector I
700775
