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A list of all pages that have property "Title" with value "Forwards Reactor Restart Rept". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • ML19331B615  + (Forwards Reactor Operator Training Program, in Response to 800329 Ltr Re Qualification & Requalification of Reactor Operator Instructors)
  • ML20155G112  + (Forwards Reactor Operator Written Exam Outline Which Plant Planning to Submit for Review,Comment & Approval for Initial License Exam Scheduled for Wk of 980914.Outline Has Been Developed IAW Interim Rev 8 of NUREG-1021)
  • ML20134Q122  + (Forwards Reactor Operator/Senior Operator License Certificates.W/O Encls)
  • ML19319B049  + (Forwards Reactor Physics Review for Inclusion in Rept to ACRS)
  • ML19319B142  + (Forwards Reactor Physics Review for Inclusion in Rept to ACRS)
  • ML16299A350  + (Forwards Reactor Physics Section Evaluation of Util Application to Reload for Cycle 6.Proposed Changes in LOCA-related Requirements Are Acceptable)
  • ML20003J255  + (Forwards Reactor Physics Section Request for Addl Info Re Cycle 2 Reload at Facility)
  • ML20213D840  + (Forwards Reactor Physics Section,Core Performance Branch Draft SER Input.No Open Items Remain)
  • ML19308E043  + (Forwards Reactor Physics Tech Specs Questions from Core Performance Branch)
  • ML20094H301  + (Forwards Reactor Pressure Vessel Core Shroud Insps Final Rept for PBAPS Unit 3)
  • ML20055E153  + (Forwards Reactor Pressure Vessel Evaluation Rept, in Response to NRC 900501,07 & 15 Requests for Addl Info. Specific Chapters Re Requests Listed)
  • ML18017A175  + (Forwards Reactor Pressure Vessel Internals Vibration Test. Rept Available in Central Files Only)
  • ML17138B780  + (Forwards Reactor Pressure Vessel Internals Vibration Test. Rept Available in Central Files Only)
  • PLA-2471, Forwards Reactor Pressure Vessel Internals Steam Dryer Rept Summarizing Indications Found During Unit 1 Refueling Outage,Per Request.Indications Will Not Impact Safe Operation of Facility.Related Info Encl  + (Forwards Reactor Pressure Vessel Internals Steam Dryer Rept Summarizing Indications Found During Unit 1 Refueling Outage,Per Request.Indications Will Not Impact Safe Operation of Facility.Related Info Encl)
  • ML19330B431  + (Forwards Reactor Pressure Vessel Support Mod for Midland Nuclear Power Plant, Preliminary Rept,Requested at 800523 Meeting W/Nrc in Bethesda,Md.Nrc Review Requested by Dec 1980)
  • ML19330B433  + (Forwards Reactor Pressure Vessel Support Mod for Midland Nuclear Power Plant, Preliminary Rept,Requested at 800523 Meeting W/Nrc in Bethesda,Md.Nrc Review Requested by Dec 1980)
  • ML20101E662  + (Forwards Reactor Pressure Vessel Water Level Measurement Sys Evaluation Rept in Response to Generic Ltr 84-23, Reactor Vessel Water Level Instrumentation in Bwrs)
  • ML20080L420  + (Forwards Reactor Primary Containment Bldg Integrated Leak Rate Test,830629-0703. Next Type a Test Scheduled During First Refuel Outage in 1986)
  • ML20084Q227  + (Forwards Reactor Primary Sys Investigation at Nine Mile Point Nuclear Station,Rept 2 & Program for Restoration to Svc Based on Reps of Primary Sys Investigation Nine Mile Point Nuclear Station. W/O Encl)
  • ML20084Q318  + (Forwards Reactor Primary Sys Investigation at Nine Mile Point Nuclear Station, Superseding Primary Rept Core Spray Nozzle Safe-End,Nine Mile Point Power Station. W/O Encl)
  • ML17213A623  + (Forwards Reactor Protection Sys Matrix Mockup Fault Isolation & Surge Withstand Qualification Test Rept,Fl Power & Light,St Lucie Unit 2.)
  • L-82-470, Forwards Reactor Protection Sys Matrix Mockup Fault Isolation & Surge Withstand Qualification Test Rept,Fl Power & Light,St Lucie Unit 2  + (Forwards Reactor Protection Sys Matrix Mockup Fault Isolation & Surge Withstand Qualification Test Rept,Fl Power & Light,St Lucie Unit 2)
  • ML19347F429  + (Forwards Reactor Protection Sys Power Supply Conceptual Design Info Committed to in 810119 Response to NRC 800924 Request.Mods Will Provide Redundant Class IE Protection at Interface of non-Class IE Power Supplies)
  • ML20071D610  + (Forwards Reactor Protection Sys Setpoint Methodology & Safety-Related Instrument Setpoint Methodology for Balance of Plant Equipment, Per SER Confirmatory Item 15)
  • ML13330B166  + (Forwards Reactor Protection Sys Single Failure Analysis, Per NRC 860923 Request.Results of Evaluation Determined That Reactor Protection Sys Meets Design Basis Criteria W/ Exception of Mismatch Trip)
  • ML19209B988  + (Forwards Reactor Restart Rept.)
  • ML20237D141  + (Forwards Reactor Safeguards Branch Comments & Request for Addl Info Re Chapter 1, Safeguards, Amend 12 to 80+ CESSAR-DC.Info Requested within 90 Days)
  • ML20214G488  + (Forwards Reactor Safety & Electrical,Instrumentation & Control Sys Branches Evaluation of Psar.Listed Items Must Be Resolved Prior to ACRS Meeting.Hydrogen Control Sys Design & Rod Worth Minimizer Concern Deferrable.W/O Encl)
  • ML16148A328  + (Forwards Reactor Safety Branch Evaluation of Facility Fuel Load for Cycle 5 Operation & Associated Tech Specs.Util Has Not Submitted Acceptable Startup Test Program as of 800630.W/o Encl)
  • ML19316A351  + (Forwards Reactor Safety Branch Evaluation of Cycle 5.W/o Encl)
  • ML19256D739  + (Forwards Reactor Safety Branch First Round Questions for Completion of Safety Evaluation.W/O Encl)
  • ML19256D733  + (Forwards Reactor Safety Branch Safety Evaluation Accepting Util Proposal Re Cycle 3 Reload)
  • ML20091K537  + (Forwards Reactor Safety Branch Safety Evaluation of non-ECCS Portions of Util Request for Single Loop Operation. Analysis Branch Reviewed ECCS Analysis & Plant Sys Branch Reviewed Single Failures in One Loop Operation)
  • ML20133P892  + (Forwards Reactor Safety Research Summary of Activities & Results - FY84 for Nrc. Rept Condenses Details Described in Bimonthly Progress Repts.Some Observations Preliminary & Subj to Rev as More Work Completed)
  • NUREG/CR-1659, Forwards Reactor Safety Study Methodology Applications Program Rept for plant,NUREG/CR-1659.Safety Evaluation Based on Rept & Other Info to Be Prepared by Nrc.Util Views Requested.W/O Encl  + (Forwards Reactor Safety Study Methodology Applications Program Rept for plant,NUREG/CR-1659.Safety Evaluation Based on Rept & Other Info to Be Prepared by Nrc.Util Views Requested.W/O Encl)
  • ML20053D508  + (Forwards Reactor Site Criteria:Rept to Director of Regulation by Director,Licensing & Regulation)
  • ML20053D552  + (Forwards Reactor Site Criteria:Rept to General Manager by Director,Div of Licensing & Regulation)
  • ML20053D543  + (Forwards Reactor Site Criteria:Rept to General Manager by Director,Div of Licensing & Regulation)
  • ML20053D517  + (Forwards Reactor Site Criteria:Rept to General Manager by Director,Div of Licensing & Regulation)
  • ML19345F108  + (Forwards Reactor Siting Risk Comparisons Re Recommendations of NUREG-0625 as Supplemental Comment on Proposed Rules 10CFR50,51 & 100 Re Revision of Reactor Siting Criteria)
  • ML19261B490  + (Forwards Reactor Standby Condition for Nasa Plum Brook Mockup Reactor,Annual Rept for 1978)
  • ML19322C694  + (Forwards Reactor Startup Certification Training Program for Review & Comment)
  • ML20090B439  + (Forwards Reactor Sys Branch & Accident Evaluation Branch Response to Mk Udall 820205 Questions 6,10,11,15 & 17 Part II Re 820125 Steam Generator Tube Rupture)
  • ML20132C158  + (Forwards Reactor Sys Branch (Rsb) Input to Draft SER Chapter 15, Accident Analyses, W/Evaluations of TMI-related Issues Under Rsb Purview.Rsb Input to SALP Also Encl)
  • ML20132C153  + (Forwards Reactor Sys Branch (Rsb) Input to Draft SER Chapter 15, Accident Analyses, W/Evaluations of TMI-related Issues Under Rsb Purview.Rsb Input to SALP Also Encl)
  • ML19283A654  + (Forwards Reactor Sys Branch Draft Responses to Intervenor Environ Coalition on Nuclear Power Contentions 1d & 1e, Intervenor Sholly Contentions 3 & 7 & Intervenor Ucs Contentions 1,2,5 & 8)
  • ML16148A326  + (Forwards Reactor Sys Branch Evaluation of Facility Fuel Load for Cycle 5 Operation & Associated Tech Specs.Review Considered Effects of Normal Operation,Anticipated Transients & Postulated Accidents.W/O Encl)
  • ML20213D940  + (Forwards Reactor Sys Branch Input to Draft Safety Evaluation Re Amend 17 to FSAR & Draft Responses to Formal Reactor Sys Branch Questions.Formal Documentation of Util Responses Required by 820101)
  • ML20132C076  + (Forwards Reactor Sys Branch Input to Draft SER Re Rcs. Section 15 Will Be Forwarded by 840518)
  • ML19275H308  + (Forwards Reactor Sys Branch Input to First Round Questions. Open Items Remain)
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