Letter Sequence Other |
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Results
Other: ML20076E095, ML20091M307, ML20091M320, ML20094B621, ML20098C812, ML20100M526, ML20101C657, ML20101E354, ML20101L452, ML20108E123, ML20108E126, ML20112G155, ML20132C519, ML20132C558
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MONTHYEARML20076E0951983-08-12012 August 1983 Forwards Revised Inservice Insp Program.Upgraded Program Will Go Into Effect on 840101 Project stage: Other ML20091M3201984-05-31031 May 1984 Recirculation,Rhr & Reactor Water Cleanup Weld Joint Insp Program - 1984 Maint/Refueling Outage Project stage: Other ML20091M3071984-05-31031 May 1984 Forwards Program for Insp of Recirculation & Other Coolant Boundary Stainless Steel Piping Sys for 1984 Maint/Refueling Outage.Criteria Consistent W/Generic Ltr 84-11, Insp of BWR Stainless Steel Piping. Outage Scheduled for 840901 Project stage: Other ML20094B6211984-07-27027 July 1984 Forwards Discussion of Exams Conducted on Six Inlet & Outlet Nozzles & safe-end & Recirculation Sys Jet Pump Instrumentation Inconel 182 Nozzles.Exams Prompted by Cracking Problems Discussed in IE Info Notice 84-41 Project stage: Other ML20098C8121984-09-19019 September 1984 Requests Info Re Status of 1984 Refueling Outage Insp Program Approval & Issuance of SER for Second Cycle Operation W/Weld Overlays.Maint/Refueling Outage Tentatively Scheduled to Begin on or About 840929 Project stage: Other ML20098F0701984-09-26026 September 1984 Responds to 840917 Request for Addl Info Re 1984 Refueling Outage Insp Program for Stainless Steel Piping.Topics Addressed Include Sampling Plan,Qualification of Exam Personnel,Leak Detection & Leakage Limits Project stage: Request ML20101C6571984-11-21021 November 1984 Responds to IE Bulletin 80-13, Cracking in Core Spray Spargers. Visual Insp of Core Spray Spargers & Associated Piping Performed.Circumferential Crack Discovered in heat- Affected Zone of Lower Sparger to T-box Weld Project stage: Other ML20108E1261984-11-30030 November 1984 Core Spray Sparger Crack Analysis for Ei Hatch Nuclear Power Station,Unit 1 Project stage: Other ML20108E1231984-12-0606 December 1984 Forwards NEDO-30825, Core Spray Sparger Crack Analysis for Ei Hatch Nuclear Power Station,Unit 1, in Response to IE Bulletin 80-13, Cracking in Core Spray Spargers Project stage: Other ML20100M5261984-12-10010 December 1984 Forwards Inservice Insp Rept Re Stainless Steel Piping & Corrective Actions Taken for Cracked Welds Reported During Fall 1984.Insp Performed During 1984 Refueling Outage Project stage: Other ML20101E3541984-12-19019 December 1984 Submits Addl Info on IGSCC Evaluations of Repairs to Welds in Recirculation Sys Piping,Per 841217 Telcon Request. Summary of Total Stresses Encl Project stage: Other ML20101L4521984-12-21021 December 1984 Advises of Intent to Submit Rept During Second Quarter 1985 Re Recirculation Sys Piping Replacement During 1984 Maint/ Refueling Outage Project stage: Other ML20112G1551985-01-0909 January 1985 Informs That Hydrostatic Test Cannot Be Performed as Indicated in 841210 Submittal.Required Removal of Main Steam Safety/Relief Valves from Svc Would Violate Tech Specs Requiring Valves to Be Operable W/Irradiated Fuel in Vessel Project stage: Other ML20132C5581985-05-17017 May 1985 Rev 0 to Design Rept for Evaluation & Disposition of IGSCC Flaws at Plant Ei Hatch Unit 1 Project stage: Other ML20132C5191985-09-17017 September 1985 Forwards Rev 0 to XGP-09-106, Design Rept for Evaluation & Disposition of IGSCC Flaws at Plant Ei Hatch Unit 1, to Complete All Necessary Submittals to NRC Re Piping Insps & Repairs During 1984 Maint/Refueling Outage Project stage: Other 1984-12-06
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_ Georgia Power Company 333 Piedmont Avenue
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Atlanta, Georgia 30308 Telephone 404 526 6526 Maihng Actess:
Post Office Box 4545 At!anta Georg'a 30302 Georgia Power L.T.Gucwa tN souvern twinc wem Manager Nuclear Eng:neenng and Ch:ef Nuctear Engineer NED-85-009 1336N January 9, 1985 Director of Nuclear Reector Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Consnission Washington, D. C.
20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 POST-WELD OVERLAY REPAIRS TESTING Gentlemen:
Our submittal dated December 10, 1984 discussed repair activities conducted during the 1984 Unit 1 refueling outage.
We. indicated therein
-that a hydrostatic test was scheduled to be conducted following weld overlay of certain piping welds in the Recirculation and Residual Heat Removal systems which had been found to have crack-like indications.
Hydrostatic testing following such repairs would normally be performed per ASME-Section from service or gagging. those valves and thMain Steam safety / relief ' valve XI Code requirements by either removing the en pressurizing the system.
A review of Hatch Unit 1 Technical Specificatioi
- 2.A.1 indicates, however, that the safety / relief valves are required to be operable when irradiated fuel is present in the vessel and the vessel head is installed. As a result of this limitation, a hydrostatic test cannot be performed.
IWA-5214(d) of the 1980 Edition of the ASME Section XI Code with Addenda through Winter 1980 states that when a hydrostatic test performed as a result of repairs conflicts -with the Technical Specifications, a system inservice test -is acceptable in lieu of the hydrostatic test.
It is our position that this code provision may be applied in the case of the Unit I repair. The appropriate systems will, therefore, be visually examined while in service at operating pressure rather. than hydrostatically tested as
,previously planned.
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1
- . oi iGeorgia Power
- Director'of Nuclear Reactor Regulation Attention:
Mr.' John F. Stolz, Chief
' Operating Reactors Branch No. 4 January 9, 1985 Page Two
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Should you have any questions in this regard, please contact this office.
Sincerely yours, Y
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L. T. Gucwa JAE/mb xci H. C. Nix, Jr.
J. P. O'Reilly (NRC-Region II)
Senior Resident Inspector 4
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