Letter Sequence Other |
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MONTHYEARML20041D0201982-02-0303 February 1982
Notifies That plant-specific Ref to GE 810506 & 28 Position Is Acceptable Basis for Request to Extend Burnup for All Fuel Types.Limits Inherent in 10CFR51.20 Re Environ Effects from Transport of Irradiated Fuel Should Not Be Neglected
Project stage: Other
ML20072T0491983-01-31031 January 1983
Suppl Reload Licensing Submittal for Edwin I Hatch Nuclear Plant Unit 2,Reload 3 (Cycle 4)
Project stage: Other
ML20071C6881983-02-23023 February 1983
Application for Amend to License NPF-5 Tech Specs,Supporting Installation of low-low Set Safety Relief Valve Logic Sys & GE Analog Transmitter Trip Sys.Proprietary Supporting Info Withheld (Ref 10CFR2.790)
Project stage: Request
ML20072T0451983-03-30030 March 1983
Proposed Tech Spec Reflecting Changes to Reactor Core Design for Cycle 4
Project stage: Other
ML20072T0371983-03-30030 March 1983
Application for Amend to License NPF-5 Changing Tech Specs to Reflect Changes to Reactor Core Design for Cycle 4
Project stage: Request
ML20023C2291983-05-0404 May 1983
Notice of Issuance & Availability of Amend 83 to License DPR-46
Project stage: Other
ML20074A8671983-05-10010 May 1983
Amends 830330 Submittal Re Extension of Malphgr Limits.Eccs Analysis Results Justify Operation of All Facility Fuel Types at Exposures Greater than 30,000 Mwd/St
Project stage: Other
ML20076G6081983-05-12012 May 1983
Notice of Consideration of Issuance of Amend to License NPF-5 & Proposed No Significant Hazards Consideration Determination & Opportunity for Hearing
Project stage: Other
ML20076E0751983-05-20020 May 1983
Submits GE Info Assuring That crud-induced Local Corrosion Failures Will Not Occur During Cycle 4,in Response to NRC 830519 Request
Project stage: Other
ML20076E9811983-05-26026 May 1983
Proposed Tech Specs Re Addl Surveillance Requirements for High Reactor Water Level Trip Function & Main Turbine Bypass Valves
Project stage: Other
ML20076E9671983-05-26026 May 1983
Application for Amend to License NPF-5,proposing Addl Tech Spec Surveillance Requirements for High Reactor Water Level Trip Function & Main Turbine Bypass Valves
Project stage: Request
ML20023E2371983-06-0909 June 1983
Forwards Revised Page B 3/4 3-6 of Proposed Tech Spec Changes Re Reactor Vessel Water Level Submitted on 830526,in Response to NRC 830512 Request
Project stage: Other
ML20023E2411983-06-0909 June 1983
Revised Page B 3/4 3-6 of 830526 Proposed Tech Spec Changes Re Reactor Vessel Water Level
Project stage: Other
ML20076M4101983-06-29029 June 1983
Amend 33 to License NPF-5,providing Addl & Revised Trip Setpoints Reflecting Design Mods to Reduce Containment Loads from Plant Transients
Project stage: Other
ML20076M4141983-06-29029 June 1983
Safety Evaluation Supporting Amend 33 to License NPF-5
Project stage: Approval
ML20076M4071983-06-29029 June 1983
Requests Fr Notice of Issuance of Amend 33 to License NPF-5 Providing Addl & Revised Trip Setpoints to Reflect Design Mods Reducing Containment Transient Loads
Project stage: Approval
1983-05-12
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Text
Georg a Power Company 333 Piedmont Avere e Atlanta. Georg a 30308 Telephone 404 526 6526 Ma iing Address' Post Off:ce Box 4545 Atlanta, Georg'a 30302 Georgia Power L T. Gucwa tre sa/them oectnc system Chief Nt.ctear Eng neer Power Generation Departtrent tED-83-312 May 20, 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 50-366 OPERATIiG LICENSE tPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Gentlemen:
Georgia Power Company (GPC) submits the following information in response to your letter of May 19, 1983, which requested GPC to "... provide some assurance that crud induced localized corrosion (CILC) failures will not occur during Cycle-4".
As noted in your letter, the tRC, General t:1ectric Company (GE), and GPC staffs have informally discussed this question.
GE has provided the following to GPC for use in responding to this request:
l No fuel from fuel rod lots / ingot combinations: which experienced failures in cycle 3 was reinserted in ' cycle 4 unless it passed both a visual and a NDT examination.
The fuel for cycle 4 has been analyzed with the approved models in GEST AR-II and meets the accepted criteria.
No fuel failures due to CILC are expected in the affected reload batch in cycle 4, and in any event the unit will be operated l
in compliance with the Technical Specifications.
Very truly yours, fS &"
l L. T. Gucwa DLT/mb xc:
J. T. Beckham, Jr.
H. C. Nix, Jr.
J. P. O'Reilly (NRC-Region II) 0[
Senior Resident Inspector 8
0 8305260298 830520 DR ADOCK 05000366 PDR
