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MONTHYEARML19322E3811980-03-0505 March 1980 Responds to IE Bulletin 80-04 Re Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition.Details of Control Grade Automatic Initiation of Auxiliary Feedwater Scheme Are Being Finalized.Necessity of Installation Is Questionable Project stage: Other A01488, Responds to NRC Requesting Auxiliary Feedwater Pump Endurance Test & Compliance W/Requirement to Automate Steam Driven Auxiliary Feedwater Pump.Test Confirmed Pump Vibrations Did Not Exceed Allowable Limits1981-02-19019 February 1981 Responds to NRC Requesting Auxiliary Feedwater Pump Endurance Test & Compliance W/Requirement to Automate Steam Driven Auxiliary Feedwater Pump.Test Confirmed Pump Vibrations Did Not Exceed Allowable Limits Project stage: Other ML13330A2411981-03-0606 March 1981 Responds to IE Bulletin 80-04, Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Auxiliary Feedwater Sys Automatic Initiation Will Occur on Low Steam Generator Level W/Setpoint at 5% of Narrow Range Instrument Project stage: Other ML19347D4851981-03-19019 March 1981 Discusses Review of Util Providing Info Re 48-h Auxiliary Feedwater Pump Endurance Test & Compliance W/Nrc Requirement to Automate Start of steam-driven Pump.Item Re Pump Test Resolved Project stage: Approval ML20238E2381982-04-0505 April 1982 PWR Main Steam Line Break W/Continued Feedwater Addl Northwest Nuclear Energy Co Millstone Unit 2. Request for Addl Info Project stage: Request ML20244B9101982-05-20020 May 1982 Forwards Request for Addl Info Necessary to Complete NRC Review of Licensee 820125 & 0305 Responses to IE Bulletin 80-04, Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Response Due in 45 Days.W/O Encl Project stage: RAI ML20053C3161982-05-20020 May 1982 Forwards Request for Addl Info Necessary to Complete NRC Review of Licensee 820125 & 0305 Responses to IE Bulletin 80-04, Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Response Due in 45 Days.W/O Encl Project stage: RAI ML20069C5921982-06-23023 June 1982 PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),Toledo Edison Co,Davis-Besse Nuclear Power Station Unit 1, Technical Evaluation Rept Project stage: Other A02509, Responds to 820520 Request for Addl Info Re IE Bulletin 80-04, Main Steam Line Break W/Continued Feedwater Addition. No Damage Would Be Sustained If Pumps Ran for 30 Minutes Under Calculated Conditions1982-07-0606 July 1982 Responds to 820520 Request for Addl Info Re IE Bulletin 80-04, Main Steam Line Break W/Continued Feedwater Addition. No Damage Would Be Sustained If Pumps Ran for 30 Minutes Under Calculated Conditions Project stage: Request ML20062E2771982-07-22022 July 1982 Forwards Safety Evaluation of Util Analysis of Main Steam Line Break W/Continued Feedwater Addition,Submitted Per IE Bulletin 80-04.Analysis Acceptable Project stage: Approval ML13317A2561982-08-0303 August 1982 Informs That Pump Runout Protection on Low Discharge Pressure Similar to Protection Installed on Existing Pump Will Be Provided for New Auxiliary Feedwater Sys Pump Project stage: Other ML13317A3451982-09-27027 September 1982 Forwards Safety Evaluation Rept & Technical Evaluation Re Main Steam Line Break W/Continued Feedwater Addition. Analysis Acceptable Project stage: Approval ML13317A3491982-09-27027 September 1982 Safety Evaluation Re Main Steam Line Break W/Continued Feedwater Addition.Licensee Commitment Acceptable W/Installation of Auxiliary Feedwater Motor Driven Pump W/Pump Runout Protection Project stage: Approval ML20027D2541982-10-0707 October 1982 Forwards Safety Evaluation of Util 800125 & 820706 Responses to IE Bulletin 80-04 Re Resolution of Main Steam Line Break W/Continued Feedwater Addition.Util Analysis Acceptable. Issue Closed Project stage: Approval 1982-04-05
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JUL 22 G82 gocketFile NRC PDR L PDR NSIC ORB #3 Rdg Docket No. 50-285 DEisenhut JHeltemes OELD I&E Mr. W. C. Jones ACRS-10 Division Manager, Production PHearn Operations ETrouigny Omaha Public Power District RAClark 1623 Harney Street PMKreutzer-3 Omaha, Nebraska 68102 Gray File E.14
Dear Mr. Jones:
The staff and our consultant, Franklin Research Center, have completed our review of your analysis of a main steam line break with continued feedwater addition for the Fort Calhoun Station, Unit 1.
Your submittals dated May 15, 1980 and August 27, 1980 on this subject were in response to IE Bulletin 80-04 issued February 8, 1980.
In addition, we reviewed your safety grade auxiliary feedwater system auto initiation amendment application of November 17, 1981, which contains your subsequent Maint Steam Line Break analysis. Based on our review, we conclude that your analysis is acceptable and no further action is required of you regarding this subject. Our safety evaluation is enclosed.
Sincerely.
Originalsi;;ned by Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
As stated cc: See next page 8208090040 820722 PDR ADOCK 05000285 o
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i Omaha Public Power District cc:
Marilyn T. Shaw, Esq.
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, D. C.
20036 Mr. Jack Jensen Chairman, Washington County l
Board of Supervisors Blair, Nebraska 68023 U.S. Environmental Protection Agency Region VII ATTN: Regional Radiation Representative
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324 East lith Street Kansas City, Missouri 64106 Mr. Frank Gibson W. Dale Clark Library 215 South 15th Street Omaha, Nebraska 68102 Alan H. Kirshen, Esq.
Fellman, Ramsey & Kirshen 1166 Woodmen Tower Omaha, Nebraska 68102 Mr. Larry Yandel.1 U.S.N.R.C. Resident Inspector P. O. Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman Manager - Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.
4853 Cordell Avenue, Suite A-1 Bethesda, Maryland 20014
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Regional Administrator Nuclear Regulatory Commission, Region IV Office of Executive Director for Operations 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011
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