ML20052E369
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Results Other: 05000206/LER-1981-013, Forwards LER 81-013/99X-0.Detailed Event Analysis Submitted, 05000206/LER-1981-013-99, /99X-0:on 810618,power Operated Relief Valve Controller Opened Twice During Normal Pressure Transient Following Reactor Trip.Caused by Setting Time Constant to Off to Satisfy NUREG-0737,Item II.K.3.9, L-81-029, Forwards Proposed Licensing Exam Schedule for 1981-82 for Reactor & Senior Operator Candidates,Per 810807 Request, L-82-002, Informs That Necessary Procedures Per NUREG-0737,Item I.A.1.3 Re Use of Overtime Required by Generic Ltr 82-12 Will Be Implemented by 821001.Tech Spec Will Not Be Submitted for Review Pending Receipt of Model Tech Specs, ML13308A671, ML13308B064, ML13308B821, ML13308B925, ML13310A775, ML13310A777, ML13310A778, ML13310A826, ML13310A828, ML13310A923, ML13310A926, ML13310B078, ML13310B081, ML13310B120, ML13310B280, ML13310B546, ML13310B619, ML13311B030, ML13316B714, ML13317A133, ML13317A134, ML13317A166, ML13317A190, ML13317A263, ML13317A267, ML13317A289, ML13317A367, ML13317A369, ML13317A377, ML13317A391, ML13317A427, ML13317A450, ML13317A454, ML13317A468, ML13317A478, ML13317A479, ML13317A484, ML13317A488, ML13317A490, ML13317A507, ML13317A512, ML13317A519, ML13317A553, ML13317A567, ML13317A581, ML13317A616... further results | |
MONTHYEARML13333A4221979-10-22022 October 1979
[Table View]Forwards Responses to NRC post-TMI Requirements Re Design & Analysis,Operations,Rcs High Point Vents,Emergency Preparedness & Instrumentation to Monitor Containment Conditions Project stage: Other ML13303A7381979-10-30030 October 1979 Summary of 790927 Meeting W/Utils in San Clemente,Ca Re Emergency Plan Review Project stage: Request ML13322A6191979-11-15015 November 1979 Summary of 791108 Telcon W/Util Re Unacceptable Schedule for Implementing Lessons Learned Task Force Items Project stage: Other ML13333A4571979-12-14014 December 1979 Forwards Revisions to Util 790913 Commitments Re Compliance w/short-term TMI Lessons Learned Task Force Requirements Per NUREG-0578 Project stage: Other IR 05000206/19790161980-01-0404 January 1980 IE Insp Rept 50-206/79-16 on 791101-02 & 26.No Noncompliance Noted.Major Areas Inspected:Scope & Methods of Field Insp for IE Bulletin 79-14,repair of Shorted Electrical Buswork & Licensee Design Change Proposal Project stage: Request ML13311B0301980-01-21021 January 1980 Discusses Response to NRC 800102 Order to Show Cause Re Implementation of NUREG-0578 Category a Requirements.Will Continue Operation Until 800315.Shutdown on 800131 Would Severely Impact Power Reliability in Pacific Northwest Project stage: Other ML13333A4781980-01-23023 January 1980 Advises That Responses to NRC Requesting Info Re Small Break LOCA Guidelines Will Be Submitted by 800228. Bulletin Response Will Be Sent by 800228 Project stage: Other ML13333A4811980-01-24024 January 1980 Forwards Corrected Page 3 of App 10 to Enclosure a of Re Power Reliability Info.Omitted Info Sent to R Weiner of DOE on 800118 Project stage: Other ML13333A4831980-01-29029 January 1980 Confirms 800124 & 25 Telcons Re Facility 800126 Shutdown for Implementation of Lessons Learned Task Force Category a short-term Requirements Re Reopening of Containment Isolation Valves Project stage: Other ML13308B0641980-01-30030 January 1980 Concludes That Inadequate Justification Exists to Extend Util 800131 Deadline to 800315 for Response to 800102 Order to Show Cause Why All Category a Lessons Learned Requirements Should Not Be Implemented Project stage: Other ML19290E8091980-02-0101 February 1980 Denies Request for Shutdown Extension Until 800315 to Complete Category a Requirements W/Available Equipment. Reopening of Containment Isolation Valves Until Further Mods Completed Acceptable Project stage: Other ML13333A4981980-02-0808 February 1980 Submits Addl Info Re Commitment Schedule for short-term Lessons Learned Task Force Requirements.Circuitry to Close Auxiliary Feedwater Motor Operated Discharge Valve Will Be Installed During Apr 1980 Refueling Outage Project stage: Other ML13333A5031980-02-13013 February 1980 Forwards Justification for RCS Subcooling Setpoint,In Response to NRC 791227 Request.Addl Info Will Be Forwarded in Response to IE Bulletin 79-27 by 800228 Project stage: Other ML13316B7141980-03-0707 March 1980 Advises NRC of Delay in Responding to Item 4 of as Part of Response to IE Bulletin 79-27.Submittal Rescheduled from 800228 to 800701 Project stage: Other ML13330A0251980-03-25025 March 1980 Forwards Addl Info for Implementation of TMI short-term Lessons Learned Task Force Requirements.Describes Mods to Backup Nitrogen Pneumatic Supply & Valve Position Indication.Drawing Available in Central Files Only Project stage: Other ML13330A0271980-03-28028 March 1980 Responds to NRC 800117 Request for Review of Draft Evaluation of SEP Topic XV-20, Radiological Consequences of Fuel Damaging Accidents,(Inside & Outside Containment). Review Confirms Facts as Correct Project stage: Request ML13330A0321980-04-11011 April 1980 Confirms 800410 Telcons W/Regulatory Personnel Re Implementation of Several Category a TMI Lessons Learned Task Force Requirements Described in Project stage: Other IR 05000206/19800041980-04-11011 April 1980 IE Insp Rept 50-206/80-04 on 800128-0229.Noncompliance Noted:Failure to Rept Reactor Protection Sys Setpoints Less Conservative than Those Established by Tech Specs & Use of Nonstandard Fitting Project stage: Request ML13331B3711980-05-0707 May 1980 Ro:On 800506,during Refueling Operations,After Lowering of Reactor Internal Instrumentation Package,Incore Instrumentation Package for Thimble Location D-7 Found Bent Outward.Caused by No Provision for Thimble Passage to Core Project stage: Request ML13330A0521980-05-22022 May 1980 Discusses Open Items Re Implementation of Category a Lessons Learned Task Force Requirements Per NRC 800502 Request.Open Items Involve Instrumentation for Inadequate Core Cooling, post-accident Sampling & Reactor Cooling Sys Venting Project stage: Other ML13330A0621980-06-13013 June 1980 Discusses Completed Review of NRC Forwarding Five Addl Items Resulting from post-TMI Reviews.Forwards Commitments to Meet Implementation Requirements for Items 1-5 Project stage: Other ML13319A2131980-07-0909 July 1980 Forwards Post-Accident Sampling Sys,Capabilities & Description, & Drawings,In Response to Open Item Identified in NRC Re Implementation of TMI Lessons Learned Requirements.Drawings Available in Central Files Only Project stage: Other IR 05000206/19800201980-07-0909 July 1980 IE Insp Rept 50-206/80-20 on 800616-19.No Noncompliance Noted.Major Areas Inspected:Major Maint,Major Surveillance, IE Bulletin & Circular Followup & Independent Insp Effort Project stage: Request ML13322A7711980-07-0909 July 1980 Post-Accident Sampling Sys,Capabilities & Description Project stage: Other ML13302A4691980-09-12012 September 1980 Forwards Amend 20 to Fsar.Amend Contains Responses to NUREG- 0660 & NUREG-0694, TMI-Related Requirements for New Ols Project stage: Request ML13322A9461980-09-12012 September 1980 Notifies That Actions Required in NRC Re License Amend Application Concerning Implementation of TMI Lessons Learned Requirements Cannot Be Accomplished by 800912. License Amend Application Will Be Submitted by 810116 Project stage: Other ML13330A1321980-10-0909 October 1980 Notifies That Date for Submittal of Info Re Design Details for Reactor Coolant Vents & Addl Info for Main Steam Line Piping Integrity Evaluation Will Be Submitted 801101 & 1201,respectively Project stage: Other ML13330A1351980-10-15015 October 1980 Provides Plans,Schedules & Commitments to Meet Interim Criteria for Shift Staffing & Administrative Controls,In Response to NRC 800731 Request.Full Compliance W/Criteria Will Be Achieved No Later than 820701 Project stage: Other ML13316A5161980-10-31031 October 1980 Environ Qualification of Electrical Equipment Project stage: Request ML13330A1581980-12-23023 December 1980 Advises That Response to NRC Requesting Confirmation for Implementation Dates of TMI-related Items Will Be Submitted by 810105 Project stage: Other ML13308B8211980-12-30030 December 1980 Submits Addl Info Re Description of Shift Technical Advisor Training Program & Plans for Requalification Training Per 791031 Request Project stage: Other ML13330A1661981-01-0707 January 1981 Notifies That License Amend Application to Incorporate Applicable Tech Specs for Implementing TMI-2 Lessons Learned Category a Items Will Be Submitted by 810401 Project stage: Request ML13308A6711981-01-13013 January 1981 Advises That Licensee Inadvertently Omitted Info from Re Plans for Implementation of Action Item II.K.3.25 in NUREG-0737 Re Effect of Loss of Ac Power on Pump Seals. Evaluation Will Be Submitted by 820101 Project stage: Other ML13330A1911981-01-14014 January 1981 Informs That Radiochemical & Chemical Analysis Mods Promised in Util No Longer Necessary.Due to Other TMI Recommendations,Samples Can Be Analyzed Outside Lab.Cart Mounted Iodine Sampler W/Single Channel Analyzer to Be Used Project stage: Other ML14135A0051981-01-23023 January 1981 High Radiation Sampling Station General Piping Arrangement Plan Project stage: Other ML13330A1931981-02-0202 February 1981 Forwards Application for Amend 96 of License DPR-13 Project stage: Request IR 05000206/19810041981-02-25025 February 1981 IE Insp Rept 50-206/81-04 on 801229-810130.No Noncompliance Noted.Major Areas Inspected:Followup on Systematic Appraisal of Licensee Performance & Allegation by Contractor Employee Project stage: Request 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 ML13330A2661981-03-17017 March 1981 Forwards Listing Containing Brief Description of Design Changes Completed During 1980 Per 10CFR50.59b & Rept on Challenges to Relief & Safety Valves Per NUREG-0578 Project stage: Other ML13330A2671981-03-18018 March 1981 Advises That post-accident Sampling Sys,Described in Licensee ,Will Not Include Capability to Perform Chloride Analysis,Per NUREG-0737 & NUREG-0578.Chloride Analyses Using Dilute Samples Are Inaccurate Project stage: Other ML13330A2911981-04-13013 April 1981 Responds to NRC 801031 Request for Clarification of NUREG-0737 Requirements & Confirmation of Implementation Date.Rept by NUS Corp, Control Room Habitability Evaluation San Onofre Generating Station,Unit 1 Encl Project stage: Request ML13302B0341981-04-13013 April 1981 Summary of 810310 Meeting W/Utils in Bethesda,Md Re Explosion Hazards.Attendance List & Applicant Handouts Encl Project stage: Request ML13331A0741981-04-17017 April 1981 Requests That NRC Finish Review of Util Compliance W/Ie Bulletin 79-06C, Nuclear Incident at TMI - Suppl. Review Completion Needed for Util to Complete Design Change to Assure Automatic Tripping of Reactor Coolant Pumps Project stage: Other ML13330A2991981-04-20020 April 1981 Forwards Response to NUREG-0737,Item II.K.3.17 Re ECCS Equipment Outages.Also Forwards Analysis of Probability of Toxic Gas Hazard for San Onofre Nuclear Generating Station as Result of Truck Accidents Near Plant Project stage: Other ML13317A6101981-05-0707 May 1981 Forwards Addl Info Re SEP Topic XV-16, Radiological Consequences of Failure of Small Lines Carrying Primary Coolant Outside Containment, Per 801215 & 810319 Requests Project stage: Request ML13317A6161981-05-12012 May 1981 Advises That TMI Action Plan Item II.K.3.9 Was Not Completed by 810101.Facility Has Been Shut Down Since Apr 1980.Item Will Be Completed Prior to Restart.Also Lists Completion Schedules for Items II.D.3,II.E.4.2.,II.G.1 & III.D.3.3 Project stage: Other ML13317A6271981-06-0808 June 1981 Submits Results of Evaluation of Containment post-accident Pressure Reanalysis on Operational Limits,In Response to TMI Action Plan Item II.E.4.2(5).Peak post-accident Pressure & Temp in 770119 Analysis Is Still Applicable Project stage: Other ML20196A6141981-06-15015 June 1981 IE Review & Evaluation of Licensee Implementation of TMI Action Plan Requirement 1.C.5, `Procedures for Feedback of Operating Experience to Plant Staff Project stage: Other ML20196A6061981-06-15015 June 1981 IE Review & Evaluation of Licensee Conformance W/Tmi Action Plan Requirements 1.A.1.3, `Shift Manning Part 1,Limit Overtime Project stage: Other ML13317A6371981-06-17017 June 1981 Advises That Effluent Monitoring Sys,Per NUREG-0737,Item II.F.1 Will Not Be Completed Prior to Startup,As Remote Readout Gm Detector Has Been Removed.Interim Requirements of NUREG-0578 Will Be Met Per Project stage: Other 1980-04-11 |
| ML20052E369 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/29/1982 |
| From: | Tauber H DETROIT EDISON CO. |
| To: | Kintner L Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20052E370 | List: |
| References | |
| TASK-2.B.3, TASK-TM EF2-57-547, EFF2-57-547, TAC-44467, TAC-44468, NUDOCS 8205110061 | |
| Download: ML20052E369 (2) | |
Similar Documents at Fermi | |
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Text
e Harry Tcuber Ir$ e nd Conmet.on p
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/f pril 29,1982 4
EF2 - 57,547 Mr. L. L. Kintner U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Washington, D. C. 20555
Dear Mr. Kintner:
Reference:
Enrico Fermi Atomic Power Plant, Unit 2 NRC Docket No. 50-341
Subject:
Estimation of Core Damage Procedure Attached is a procedure for the estimation of core damage for Enrico Fermi 2, fulfilling our commitment of December 18, 1981 as identified in your SSER No. 2, Item 22.2, II.B.3 Initially, Detroit Edison indicated an interim proce-dure for this estimation would be provided based solely on gaseous activity.
However, since the meeting of September 16, 1981, General Electric has provided a more detailed procedure relating radionuclide concentrations to fuel damage based on both volatile and non-volatile nuclides.
By appropriately normalizing actual Fermi 2 plant-specific parameters with reference plant data under postulated LOCA conditions from a BWR-6/238 with a Mark III containment, an estimation of core damage can be provided.
Edison has also indicated the sample locations that will provide the most representative samples consistent with breakcase and system con-ditions.
00\\sj F205110061 820429 PDR ADOCK 05000341 P
Mr. L. L. Kintner April 29, 1982 EF2 - 57,547 Page 2 Detroit Edison regards its information submittal on this subject to be complete.
Should you have any further questions on this matter, please contact Mr. L. E. Schuerman, (313) 649-7562.
Sincerely, A
I' y
Attachment cc:
Mr. B.
Little
,
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