Letter Sequence Request |
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Results
Other: 05000321/LER-1980-035, Forwards LER 80-035/03L-0, 05000321/LER-1980-035-03, /03L-0:on 800407,during Control Room Isolation Pressurization Lsft,Control Room Filter for 1241-C012A Tripped After Being auto-started.High Chlorine Isolation Trip Simulated.Caused by Flow Switch Out of Calibr, 05000366/LER-1980-023, Forwards Updated LER 80-023/03X-1, 05000366/LER-1980-023-03, While Pulling Rods in Starup Mode,Rod 46-43 Found Bypassed full-out in Rod Sequence Control Sys But Not Pulled to Presscribed Position Until Later.Caused by Personnel Error, 05000366/LER-1980-038, Forwards LER 80-038/03L-0, 05000366/LER-1980-038-03, /03L-0:on 800328,while Performing Reactor Bldg Isolation Sys Functional Test,Drywell to Torus Dp Isolation Valves Failed to Close on Isolation Signal.Caused by Component Failure.Valve Packings Loosened & Valves Closed, 05000366/LER-1980-057, Forwards LER 80-057/01T-0, 05000366/LER-1980-057-01, /01T-0:on 800415,during Vent Header Deflector Installation & Surveillance Outage,Rhr Lpic Pump Would Not Start When LOCA Signal Was Applied to Cross Channel Start Relay.Caused by Missing Relay Wire, ML19206B034, ML19260C689, NUREG-0312, Advises That Util 1979 Mod & Insp Program Is Acceptable & Satisfies NUREG-0312 requirements.NUREG-0619 Will Address BWR Nozzle & Control Rod Drive Return Line Cracking Problem
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MONTHYEARML19210A5751978-02-13013 February 1978 Forwards Completed Questionnaire Re Steam Generator Operating History Project stage: Request ML19206B0341978-03-22022 March 1978 Responds to & Concurs W/Plans for Feedwater Nozzle Insps.Requests Description of Plan for Cladding Removal & Insp Techniques within 90 Days of 1979 Insp Project stage: Other ML20244A6361979-05-16016 May 1979 Responds to D Verrellis Request for Addl Info Re Mod of Feedwater Nozzle & Sparger.Ge Licensing Rept NEDE-21821,dtd Mar 1978,provides Discussion of Causes & Proposed Solutions to Cracking Problems in BWRs Project stage: Request ML19260C6891980-01-0202 January 1980 Submits Info Re BWR Feedwater Nozzle Repair Rept,Per NUREG- 0312.GE Personnel Performed Cladding Removal on Feedwater Nozzles & Installed Piston Ring Feedwater Spargers.Each Worker Received Approx 1,251 Millirems Project stage: Other 05000366/LER-1980-023, Forwards Updated LER 80-023/03X-11980-04-10010 April 1980 Forwards Updated LER 80-023/03X-1 Project stage: Other 05000366/LER-1980-023-03, While Pulling Rods in Starup Mode,Rod 46-43 Found Bypassed full-out in Rod Sequence Control Sys But Not Pulled to Presscribed Position Until Later.Caused by Personnel Error1980-04-21021 April 1980 While Pulling Rods in Starup Mode,Rod 46-43 Found Bypassed full-out in Rod Sequence Control Sys But Not Pulled to Presscribed Position Until Later.Caused by Personnel Error Project stage: Other 05000366/LER-1980-057, Forwards LER 80-057/01T-01980-04-23023 April 1980 Forwards LER 80-057/01T-0 Project stage: Other 05000321/LER-1980-035, Forwards LER 80-035/03L-01980-04-23023 April 1980 Forwards LER 80-035/03L-0 Project stage: Other 05000366/LER-1980-038, Forwards LER 80-038/03L-01980-04-23023 April 1980 Forwards LER 80-038/03L-0 Project stage: Other 05000366/LER-1980-057-01, /01T-0:on 800415,during Vent Header Deflector Installation & Surveillance Outage,Rhr Lpic Pump Would Not Start When LOCA Signal Was Applied to Cross Channel Start Relay.Caused by Missing Relay Wire1980-04-23023 April 1980 /01T-0:on 800415,during Vent Header Deflector Installation & Surveillance Outage,Rhr Lpic Pump Would Not Start When LOCA Signal Was Applied to Cross Channel Start Relay.Caused by Missing Relay Wire Project stage: Other 05000366/LER-1980-038-03, /03L-0:on 800328,while Performing Reactor Bldg Isolation Sys Functional Test,Drywell to Torus Dp Isolation Valves Failed to Close on Isolation Signal.Caused by Component Failure.Valve Packings Loosened & Valves Closed1980-04-23023 April 1980 /03L-0:on 800328,while Performing Reactor Bldg Isolation Sys Functional Test,Drywell to Torus Dp Isolation Valves Failed to Close on Isolation Signal.Caused by Component Failure.Valve Packings Loosened & Valves Closed Project stage: Other 05000321/LER-1980-035-03, /03L-0:on 800407,during Control Room Isolation Pressurization Lsft,Control Room Filter for 1241-C012A Tripped After Being auto-started.High Chlorine Isolation Trip Simulated.Caused by Flow Switch Out of Calibr1980-04-23023 April 1980 /03L-0:on 800407,during Control Room Isolation Pressurization Lsft,Control Room Filter for 1241-C012A Tripped After Being auto-started.High Chlorine Isolation Trip Simulated.Caused by Flow Switch Out of Calibr Project stage: Other NUREG-0312, Advises That Util 1979 Mod & Insp Program Is Acceptable & Satisfies NUREG-0312 requirements.NUREG-0619 Will Address BWR Nozzle & Control Rod Drive Return Line Cracking Problem1980-05-0505 May 1980 Advises That Util 1979 Mod & Insp Program Is Acceptable & Satisfies NUREG-0312 requirements.NUREG-0619 Will Address BWR Nozzle & Control Rod Drive Return Line Cracking Problem Project stage: Other 1980-01-02
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Similar Documents at Hatch |
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Georgo Power Company 8
5 230 Peac'. tree Street 1
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Post Othee fmn 49s Acanta Cectra 30303 4
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May 16, 1979 M
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Georgia Power Cha s. F. Whitmar Vice President Engineenng ite sontun e.de tra v.ti m Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 FEEDWATER N0ZZLE AND SPARCER MODIFICATION Gentlemen:
Georgia Power Company submits the following information pursuant to Mr.
Dave Verrelli's request concerning the modification of the Plant Hatch Unit 1 feedwater nozzle and sparger. General Electric Company's Licensing Topical Report NEDE-21821 dated March 1978, supplemented in January 1979, provides a discussion of the causes of and proposed solutions to the cracking problems which have occurred in the feedwater nozzles and spargers of coiling water reactors. These reports and associated recommendations (Feedwater Nozzle Interim Examination Recommendation, dated February 23, 1976, and the Service Information Letter, No. 207, dated November 19, 1976) form the basis for our decision to conduct the preventative modifications to the system now being undertaken at Plant Hatch Unit 1.
The reactor pressure vessel (RPV) feedwater nozzle and sparger repair will involve four major steps:
the removal of the existing feedwater spargers, nozzle cladding removal by machining, extensive examination of RPV feedwater nozzles and saf e-ends, and the installation of the improved interf erence fit _
feedwater spargers. Each step of the modification is controlled by procedures and specifications.
If further specific details of these procedures and specifications are required, please contact this office.
Yours very truly, I y
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Ruble A. Thomas George F. Trowbridge, Esquire 190523o538 4
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