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A list of all pages that have property "Title" with value "SER - Appendix a - Commitment Table". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML20039G501  + (SEP Topic VII-2,ESF Sys Control Logic & Design,Ginna Nuclear Power Plant 1)
  • ML20040F534  + (SEP Topic VII-2,ESF Sys Control Logic & Design,Big Rock Point,Oct 1981)
  • ML20040F413  + (SEP Topic VII-2,ESF Sys Control Logic & Design,Millstone Nuclear Power Station,Unit 1)
  • ML20040F026  + (SEP Topic VII-2,ESF Sys Control Logic & Design,Yankee Nuclear Power Station, Informal Rept)
  • ML20028B494  + (SEP Topic VII-3,Electrical,Instrumentation & Control Features of Sys Required for Safe Shutdown,Lacbwr, Interim Rept)
  • ML20040F771  + (SEP Topic VII-3,Electrical,Instrumentation & Control Features of Sys Required for Safe Shutdown, Technical Evaluation Rept)
  • ML20040F830  + (SEP Topic VII-3,Electrical,Instrumentation & Control Features of Sys Required for Safe Shutdown, Technical Evaluation Rept)
  • ML20039G814  + (SEP Topic VIII-04,Electrical Penetrations of Reactor Containment,San Onofre Nuclear Station,Unit 1)
  • ML19337A969  + (SEP Topic VIII-2, Onsite Emergency Power Sys - Diesel Generator for Haddam Neck)
  • ML20058A730  + (SEP Topic VIII-2,Diesel Generator,Big Rock Point, Interim Rept for May 1982)
  • ML20054K047  + (SEP Topic VIII-2,Diesel Generator,Big Rock Point, Informal Rept)
  • ML20041C423  + (SEP Topic VIII-3.B,DC Power Sys Bus Voltage Monitoring & Annunciation,Big Rock Point, Interim Technical Evaluation Rept)
  • ML20031F048  + (SEP Topic VIII-4,Electrical Penetrations of Reactor Containment,Re Ginna Nuclear Station,Unit 1)
  • ML20052H933  + (SEP Topic VIII-4,Electrical Penetrations of Reactor Containment,Haddam Neck Nuclear Station, Interim Rept)
  • ML17258A224  + (SEP Topic VIII-4,Electrical Penetrations of Reactor Containment,Re Ginna Nuclear Station,Unit 1, Informal Rept)
  • ML13317A805  + (SEP Topic VIII-4,Electrical Penetrations of Reactor Containment,San Onofre Nuclear Station,Unit 1, Informal Rept)
  • ML16067A144  + (SEP-ISI-PNPS-002, Rev 2, Pilgrim, Fifth Ten-Year Interval Inservice Inspection (Isi/Iwe) Program Plan)
  • ML003765714  + (SEPT/2000 Exam 50-338/2000-301 Initial Outlines, Jpms, Simulator Scenarios, Ro/Sro Written Exam)
  • IR 05000338/2000301  + (SEPT/2000 Exam, 50-338/2000-301 Final Outlines, Simulator Scenarios)
  • IR 05000327/2016404  + (SEQ MCA - Report 2016-404 w-o Encl. Rev 0)
  • ML063630424  + (SER)
  • ML20236B364  + (SER - 1988)
  • ML031120039  + (SER - Appendix B - Chronology)
  • ML031120041  + (SER - Appendix C - RAIs)
  • ML031120044  + (SER - Appendix D - Principal Contributors, License Renewal & Environmental Impacts Program)
  • ML23067A277  + (SER - Certificate of Compliance No. 9269, Revision No. 13, for the Model No. 650L)
  • ML22306A241  + (SER - Certificate of Compliance No. 9356, Rev. 4, 71-9356)
  • ML031120013  + (SER - Section 1, Related to License Renewal of Fort Calhoun Station, Unit 1)
  • ML031120018  + (SER - Section 2, Structures & Components Subject to Aging Management Review)
  • ML032481261  + (SER - Section 3, Aging Management Review)
  • ML031120024  + (SER - Section 4, Time-Limited Aging Analyses)
  • ML031120028  + (SER - Sections 5 & 6, Review & Conclusions by Advisory Committee on Reactor Safeguards)
  • ML20293A176  + (SER - Termination of Special Nuclear Materials License Number SNM-2019 for the Global Laser Enrichment Facility)
  • ML16074A079  + (SER 2016 for Mit SNM-986, R-37)
  • ML19360A020  + (SER 2019-12-23 for ADAMS)
  • ML22096A082  + (SER 71-3036 for JRF-90Y-950K Kuca Fuel Revalidation)
  • ML22153A090  + (SER 71-3092)
  • ML20247M086  + (SER Accepting 1997 Rev to Catawba UFSAR Submitted on 970925. Rev Added Analysis for Postulated Accident Involving Dropping of Sf Pool Weir Gate Onto Sf Assemblies)
  • ML20211A797  + (SER Accepting 840710 Updated Inservice Testing Program for Remainder of Second 10-yr Interval)
  • ML20206M562  + (SER Accepting 840808 & 850621 Responses to IE Info Notice 84-90, Main Steam Line Break Effect on Environ Qualification of Equipment. Higher Temp Will Not Preclude Ability to Shut Down Reactor in Safe Shutdown Condition)
  • ML20129H907  + (SER Accepting 850605 Submittal Re Generic Ltr 83-28,Item 1.1 on post-trip Review Program & Procedures)
  • ML20213F472  + (SER Accepting 870113 Application to Amend License SNM-1972 to Increase Max Enrichment & Quantity of U-235 Contained in Unirradiated Fuel Assemblies)
  • ML20248B521  + (SER Accepting 890322 Application for Amend to License SNM-33 Re Startup & Test of New Pellet Production Lines & Use of Addl Warehouse Space)
  • ML19354E563  + (SER Accepting 891211 Amend Application & Suppls & 20 Re Organizational Changes)
  • ML18153D011  + (SER Accepting 920210 & 0317 Responses to Station Blackout Rule)
  • ML20046B942  + (SER Accepting 930429 Application for Amend to License SNM-1227)
  • ML20136G074  + (SER Accepting 930723 Proposed Changes to Slp,Units 1 & 2 TSs in Support of Plan to Implement Rev 10CFR20)
  • ML18153B108  + (SER Accepting 940622 Request to Use ASME Code Case N-416-1 in Lieu of Performing Code Required Hydrostatic Pressure Test for Welded Repairs or Instsllation or Replacement Items by Welding)
  • ML20138M330  + (SER Accepting 961217 Request for Amend to License SNM-1097 Authorizing Minor Revs to Radiological Contingency & Emergency Plan)
  • ML20203E730  + (SER Accepting 980105 Request to Use Mechanical Nozzle Seal Assembly as Alternate Repair Method,Per 10CFR50.55a(a)(3)(1) for Plant,Units 2 & 3)
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