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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Georgei Power Company 333 P edmont Avenue At:anta, Georgia 30308 Te:ephone 404 5264526 Ma hng Address:
Post Off.ce Box 4545 Atlanta, Georg:a 30302 Georgia Power L. T. Gucwa tN soothem e'&frc satem EcNc$e$e'r'at50Ee*partment NED-83-332 June 2, 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 m C DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 REVISION TO THE AUGMENTED RCS LEAK DETECTION SUBMITTAL Ato IN-SERVICE INSPECTION PROGRAM COMMITMENT Gentlemen:
Our letter to you, dated May 25, 1983, committed Georgia Power Company (GPC) to augmented leak detection requirements for the Plant Hatch Unit 2 reactor coolant system.
These new requirements, which were intended to incorporate the surveillance frequencies suggested in NUREG-0313, Rev.
1, Sectio'1 IV.B.1.a.2, were requested by the EC staff as a result of our detecting pipe flaw indications in the RHR and Recirculation systems during the current (111t 2 outage.
However, the MC Hatch Licensing Project Manager has indicated, through conversation with GPC staff personnel, that additional commitments were required in order to meet the generic guidance stated in NUREG-0313, Rev. 1.
Therefore, GPC submits the following revisions to the letter of May 25, 1983, and commits to implementation of these revised requirements at the time of unit startup following the current refueling / maintenance outage:
1.
Surveillance requirement No. 3 of the May 25 letter shall be revised to require implementation of Technical Specification 3.4.3.2 ACTION c. any time that unidentified leakage increases by 2 gpm over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less.
2.
In addition to the present requirements of Technical Specification 3.4.3.1, operability of at least one of the leakage measurement instruments associated with each sump shall be maintained per Surveillance Requirement 4.4.3.1.b.
8306070125 830602 A th PDR ADOCK 05000366 D
G PM flC
. ~ _
o Georgia Power b Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 June 2, 1983 Page Two Further, pursuant to a subsequent conversation with the EC Hatch Licensing Project Manager on June '2,1983, we hereby propose to submit for WC review and approval our plans for inspection and/or modification during the next refueling outage (following cycle 4) of the recirculation and Residual Heat Removal System piping.
These plans will be submitted to ~ the NRC at least three months prior to the start of that refueling outage.
Please contact this office if further information is required.
Very truly yours,
/7 &w L. T. Gucwa CBS/mb xc:
H. C. Nix, Jr.
J. P. O'Reilly (NRC-Region II)
Senior Resident Inspector 700775
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