Letter Sequence Other |
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Results
Other: ML20071M059, ML20071M081, ML20071M093, ML20071N589, ML20072A430, ML20072A439, ML20076G175, ML20076N368, ML20077F351, ML20077F367, ML20078M193, ML20083N619, ML20083N636
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MONTHYEARML20083N6361983-03-19019 March 1983
Rev 1 to Design Rept for Weld Overlay Repairs & Flow Evaluations in Recirculation & RHR Sys
Project stage: Other
ML20151H6271983-04-28028 April 1983
Notification of 830429 Meeting W/Util in Atlanta,Ga to Discuss Results of Ongoing Ultrasonic Insp of Pipes, Details of Crack Length & Depth Determinations,Proposed Repairs & Bases for Repairs
Project stage: Meeting
ML20071G5191983-05-19019 May 1983
Advises That Startup Expected to Occur Between 830607-14 Assuming Resolution of Outstanding Licensing Issues.Unknowns Still Exist in Schedule Due to Existence of Pipe Flaw Indications.Draft Rept on Weld Repairs Expected by 830530
Project stage: Draft Other
ML20071M0931983-05-25025 May 1983
Discusses Possible Imposition of Augmented Leak Detection Requirements for RCS Due to Discovery of Unacceptable Pipe Flaw Indications in Recirculation & RHR Sys.Util Commitments to Incorporate NUREG-0313,Rev 1,Section IV.B.1.a.2
Project stage: Other
ML20071M0811983-05-26026 May 1983
Provides Response to IE Bulletin 83-02 Re Stress Corrosion Cracking in large-diameter Stainless Steel Recirculation Sys Piping at BWR Plants
Project stage: Other
ML20071M0591983-05-26026 May 1983
Submits Info Re Analyses & Repairs of large-diameter Stainless Steel Piping Welds Per Inservice Insp Conducted During 1983 Maint/Refueling Outage Identifying Unacceptable Ultrasonic Indications in Recirculation & RHR Sys
Project stage: Other
ML20076G1751983-05-26026 May 1983
Corrected Response to IE Bulletin 83-02 Re Inservice Insp Activities Concerning Stress Corrosion Cracking in Large Diameter,Stainless Steel Recirculation Sys Piping at BWR Plants.Weld Exam List Encl
Project stage: Other
ML20071M1091983-05-31031 May 1983
Draft Rev a to Design Rept for Weld Overlay Repairs & Flaw Evaluation in Recirculation & RHR Sys, Preliminary Rept
Project stage: Draft Other
ML20071N5891983-06-0202 June 1983
Submits Revs to 830525 Augmented RCS Leak Detection Submittal & Inservice Insp Program Commitment,Incorporating Surveillance Frequencies Per NUREG-0313,Rev 1.Insp &/Or Mod Plans for Recirculation & RHR Sys Piping Forthcoming
Project stage: Other
ML20072A4391983-06-0707 June 1983
Rev 0 to Design Rept for Weld Overlay Repairs & Flaw Evaluations in Recirculation & RHR Sys
Project stage: Other
ML20072A4301983-06-0808 June 1983
Forwards Rev 0 to Design Rept for Weld Overlay Repairs & Flaw Evaluations in Recirculation & RHR Sys. Sensor Check Will Be Performed Every 4 Hours in Addition to Interval Required by Tech Specs,Effective at Restart
Project stage: Other
ML20077F3671983-06-10010 June 1983
Rev 0 to Investigation of Cause of Cracking in Hatch Unit 2 RCS Piping - Comparison W/Unit 1 Cracking Experience
Project stage: Other
ML20244C3671983-06-20020 June 1983
Summary of 830601 Meeting W/Util in Bethesda,Md Re Util Evaluation & Repair of Cracks in Weld Area of Reactor Heat Removal & Recirculation Sys Piping.Supporting Documentation & Viewgraphs Encl
Project stage: Meeting
ML20076N3681983-07-0808 July 1983
Order Confirming Licensee Commitments to Repair Recirculation Pipe Sys Cracks & Authorizing Restart
Project stage: Other
ML20076K7821983-07-0808 July 1983
Commits to Addl Volumetric Testing of Welds to Determine Extent of Intergranular Stress Corrosion Cracking in Recirculation Sys & RHR Sys Piping,Per 830707 Meeting W/Nrc. Proposed Insp Plan Will Be Submitted by 830805
Project stage: Meeting
ML20077F3511983-07-12012 July 1983
Forwards Rev 0 to Investigation of Cause of Cracking in Hatch Unit 2 Rcs,Piping - Comparison W/Unit 1 Cracking Experience. Areas Investigated:Fabrication History, Applied & Residual Stresses & Operational History
Project stage: Other
ML20078M1931983-10-19019 October 1983
Ro:On 831018,drywell Equipment Drain Sump Pump 2G11-C006B Became Inoperable W/Redundant Pump Also Inoperable.Cause Not Stated.Increase of 1.9 Gpm Unidentified Leakage Into Sump Drain Requested for 30-day Period
Project stage: Other
ML20083N6191984-03-29029 March 1984
Forwards Rev 1 to Nutech Rept, Design Rept for Weld Overlay Repairs & Flaw Evaluations in Recirculation & RHR Sys
Project stage: Other
1983-06-10
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Similar Documents at Hatch |
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Text
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Georgta Power Corroar'y 333 Piedmont Avenue Atlanta. Georg a 30308 Telephore 404 526-6526 Malog Address:
Post Oftce Box 4545 Atlanta. Georgia 30302 h
Georgia Power L T. Gucwa me souten mM SM Manager Nuclear Engineer ng and Chsef Nuclear Eng;neer NED-84-181 March 29, 1984 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Cmmission Washington, D. C.
20555 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HAICH NUCLEAR PLANT UNIT 2 DESIGN REPORT REVISION - RECIRCULATION AND RHR SYSTEMS ANALYSES AND REPAIRS Gentlenen:
By letter dated' June 8, 1983, Georgia Power Company (GPC) subnitted information regarding the analyses and repairs of Recirculation Systen and Residual Heat Renoval (RHR) Systen piping welds which were inspected during the 1983 Hatch Unit 2 maintenance / refueling outage and found to have unacceptable flaw indications.
Enclosed as Attachnent 1 to that subnittal was Revision 0 of NUTECH report no. GPC-07-102, " Design Report for Weld
- Overlay Repairs and Flaw Evaluations in Recirculation and RHR Systens_ at E. I. Hatch Nuclear Plant, Unit 2."
Since our subnittal of June 8, 1983, NUTECH has - revised the design report. Enclosed herein are seven (7) copies of _ Revision 1 of the subject report. The revised NUIECH report supercedes that subnitted as Attachnent 1 in our June 8,1983 subnittal. ~ Sane of the changes in Revision 1 of the NUIECH design report include:
o Correction of recirculation systen conceptual drawing to add weld
. numbers inadvertently anitted.
o Correo ion of weld listing regarding through-wall depth of crack and ext < " (length) of cracking, o
Addition of discussion on end cap replacanent.
o.
Reassessment of maximarr ~ exial. shrinkage and maximtsn calculated
. stress.
Affected pages are so noted in the " Revision Control Sheet" contained in the 9
revised NUTECH report.
x wang e
,. sg.
k GeorgiaPower h Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, 011ef Operating Reactors Branch No. 4 March 29, 1984 Page 'IWo
'Ihe overall conclusions of the original report are not changed as a result of these revisions.
Subnittal of the revised NITIECH report cmpletes all transnittals regarding weld overlays on Hatch Unit 2.
By copy of this letter, a copy of.the revised NITIECH design report is being supplied to NRC Region II for their information.
Should you have any questions in this regard, please contact this office.
Sincerely yours, f *]~ & -- +
L. T. Gucwa JAE/inb Enclosures (7) xc:
(all w/l encl.)
H. C. Nix, Jr.-
J. P. O'Reilly (NRC-Region II)
Senior Resident Inspector k
h 7700775
-
