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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Georgia Power Company 333 Piecmont Avenue Atlanta, Georgia 30308 Telephone 404 526 6526 Ma;hng Address:
Post Ottice Box 4545 Atlanta. Georgia 30302 Georgia Power L T. Gucwa t?e southem eWJnc system Chiet Nuclear Engineer Power Generation Department E.83_341 June 8, 1983 Director of NtJclear 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 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 REVISION TO TIE ANALYSES APO REPAIRS ON LARGE-DIAMETER PIPING WELDS SUBMI1TAL abo RCS LEAKAGE DETECTION SLRVEILLANCE C0h44ITMENT Gentlemen:
Georgia Power Company (GPC) submits as Attachment 1 to this letter the final version of the NUTECH design report for weld overlay repairs and flaw evaluations in Recirculation System and Rm System piping at Plant Hatch Unit 2.
The final version of the design report supersedes the draft MJTECH design report submitted as Attachment 5 to our May 26, 1983 letter to you.
In Attachment 4 to the May 26, 1983 letter, GPC committed to augmenting leakage detection requirements for the rer tor coolant system (RCS) as a result of the discovery of unacceptabL, pe flaw indications in the Recirculation and R m systems.
These new requirements were intended to incorporate the surveillance frequencies suggested in Section IV.B.l.a.2 of NJREG-0313, Rev. 1.
The MC Hatch Licensing Project Manager has indicated, through conversation with GPC staff personnel, that additional commitments were required to meet the generic guidance stated in the subject NUREG.
Enclosed as Attachment 2 is a copy of our letter to you dated June 2,1983, which revises the requirements of RCS surveillance discussed in Attachment 4 to our May 26, 1983 letter.
- Further, pursuant to a subsequent conversation with the NRC Hatch Licensing Project Manager on June 7, 1983, it was indicated that an additional commitment in addition to those in our May 25, 1983 and June 2, 1983 letters was required concerning RCS leakage detection system technical specifications.
" Sensor" surveillance of the primary containment sump level and flow monitoring system was deemed necessary to assure operability.
Consequently, GPC commits to performing a " sensor" check at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the primary containment sump level and flow monitoring system.
This
" sensor" check would be in addition to the surveillance already specified in Technical Specification 4.4.3.1.b and will be implemented at the time of restart following the current maintenance / refueling outage.
8306100132 83060s
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DR ADOCK 05000366 PDR ll I J
e Georgia Power d Director of Nuclear Reactor Regulation Attention:. Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 June 8, 1983 Page Two This transmittal completes our submittal of information pertaining to the analyses and repairs of Recirculation System and RHR System piping welds observed to have flaw-like indications during the 1983 maintenance / refueling outage at Plant Hatch Unit 2.
A copy of this transmittal will be provided concurrently to the MIC regional office so they may assist in the review of the analyses and repairs performed.
Should you have any questions in this regard, please contact this office.
Sincerely yours, cf 7 &c~*
L. T. Gucwa JAE/mb Attachments xc:
J. T. Beckham, Jr.
H. C. Nix, Jr.
J. P. O'Reilly (NRC-Region II)
Senior Resident Inspector TlA)TTS
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