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A list of all pages that have property "Title" with value "Forwards SER Suppl 1.W/o Encl". Since there have been only a few results, also nearby values are displayed.

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List of results

  • IR 05000260/1989042  + (Forwards SER Re Util Responses to Open Item CSG-9 Documented in Insp Rept 50-260/89-42 Re HVAC Ductworks & Supports for Plant.New Amplified Spectra Impact Evaluation Meets Restart Requirements for Unit)
  • ML20148D000  + (Forwards SER Re Util Submittals on Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip reliability-on-line Testing.Response Acceptable)
  • ML20148D004  + (Forwards SER Re Util Submittals on Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip reliability-on-line Testing.Response Acceptable)
  • ML20196A278  + (Forwards SER Re Util Submitted 981106 Flaw Evaluation Related to Flaw Indications Found in Core Spray Piping Welds A-1 & A-2 at Cooper Nuclear Station.Review Finds Licensee Flaw Evaluation Meets Rules of ASME Code)
  • ML17279A694  + (Forwards SER Re Util post-trip Review Program & Procedures, Per Item 1.1 of Generic Ltr 83-28.Program & Procedures Acceptable)
  • ML18092A371  + (Forwards SER Re Valve Operability Demonstration Info for 10-inch Vacuum Relief Isolation Valves,Based on Review of 791108,21,810731,820218 & 830607 Submittals.License Change Request Should Be Submitted within 45 Days.W/O Encl)
  • ML13310B226  + (Forwards SER Re Valve Operability Reviews for 6-inch Butterfly Valves Used for Containment Vent,Per Util 791214, 800229 & s.Info Demonstrating Valve Ability to Close in Event of LOCA Requested within 30 Days)
  • ML20138L788  + (Forwards SER Re Valve Relief Request VR-45-R1 Where Licensee Proposed to Perform Disassembly & Insp of Associated Check Valves in Lieu of Stroke Testing Required by Code.In Accordance W/Gl 89-04,position 2 Relief Not Required)
  • ML20138L791  + (Forwards SER Re Valve Relief Request VR-45-R1 Where Licensee Proposed to Perform Disassembly & Insp of Associated Check Valves in Lieu of Stroke Testing Required by Code.In Accordance W/Gl 89-04,position 2 Relief Not Required)
  • ML14138A196  + (Forwards SER Re Vertical Seismic Ground Motion for Facility, Per SEP Topic III-6.Original Estimate for free-field Ground Motion Described in Appropriate for Seismic Reevaluation)
  • ML20236B648  + (Forwards SER Re West Valley Demonstration Project Supernatant Treatment Sys.Recommends That Project Make Formal Commitment to Min Cesium Removal Fraction.Requests Notification Re Plans to Deal W/Recommendations)
  • ML13324A719  + (Forwards SER Re long-term Svc Plan - SEP Seismic Reevaluation Criteria & Methodology.Proposed Methods & Criteria Provide Reasonable Basis to Complete Seismic Reevaluation of Plant.Technical Evaluation Repts Also Encl)
  • ML20204H628  + (Forwards SER Reflecting Status of Staff Review of Util License Renewal for Calvert Cliffs Nuclear Power Plants, Units 1 & 2)
  • ML19263B614  + (Forwards SER Related to Spent Fuel Storage)
  • ML19289C680  + (Forwards SER Related to Spent Fuel Storage)
  • ML20023C960  + (Forwards SER Resolving Multi-Plant Action Item B-04, Reactor Vessel Overpressure Protection, as Part of Low Temp Overpressure Mitigating Sys Review.Review of Electrical Instrumentation & Control Aspects Continuing)
  • ML19220C318  + (Forwards SER Review of Proposed Mods to Steam Generator Instrumentation Program)
  • ML20136E700  + (Forwards SER Secondary Review Input Re FSAR Sections 4.5.2, 5.2.3,5.4.21,6.1.1 & 10.3.6 Concerning Matls Compatibility & Corrosion Aspects.Matls Compatibility Adequate & Acceptable)
  • ML20039F110  + (Forwards SER Section 4.4, Thermal & Hydraulic Design, for Review & Comment)
  • ML20203B116  + (Forwards SER Section 6.4 Open Items Associated w/AP600 Main Control Room Habitability Sys)
  • ML20210S947  + (Forwards SER Sections 3.9.1.1,3.9.1.2 & Portion of Sections 3.9.2,3.10 & 5.2.8.7.Sections 3.6,3.9.1.3 & Final Portion of Section 3.9.2 Will Be Furnished Following Review of Info Expected During Wk of 750616)
  • ML20213E010  + (Forwards SER Sections List of Open Items.W/O Encl)
  • ML19261E978  + (Forwards SER Sections Prepared in Reponse to H Schierling Request.Applicant Must Provide Analysis to Assure Integrity of Pressurizer Relief Valve Sys.W/O Encls)
  • ML20112G057  + (Forwards SER Summary Rept of Tests & Changes to Procedures & Facility,Per 10CFR50.59.Future Repts Will Be Included in Annual Rept.Rept Covering Interval Between Encl & Annual Submittal Will Be Included in Annual Rept Due Mar 1985)
  • ML19329C267  + (Forwards SER Suppl 1 Performed by Accident Analysis Branch)
  • ML19329C216  + (Forwards SER Suppl 1 for Facility.W/O Encl)
  • ML17139A406  + (Forwards SER Suppl 2)
  • ML19329A644  + (Forwards SER Suppl 2 for Facility)
  • ML20039A652  + (Forwards SER Suppl 3 Input Consisting of Update of Unresolved Safety Issues A-43 Through A-48.Issues That Have Been Technically Resolved Since Issuance of SER Include A-9, A-10,A-24,A-31,A-36 & A-42)
  • ML19317F296  + (Forwards SER Suppl 3 for Facility.W/O Encl)
  • ML20028C264  + (Forwards SER Suppl 3.W/o Encl)
  • ML17298A273  + (Forwards SER Suppl 4.W/o Encl)
  • ML20028C339  + (Forwards SER Suppl 6.W/o Encl)
  • NUREG-0484, Forwards SER Suppl Info on Applicant 830203 Submittal Re Applicability of Square Root of Sum of Squares Combination of Dynamic Responses.Method Applicable & Complies w/NUREG-0484  + (Forwards SER Suppl Info on Applicant 830203 Submittal Re Applicability of Square Root of Sum of Squares Combination of Dynamic Responses.Method Applicable & Complies w/NUREG-0484)
  • ML19206B213  + (Forwards SER Suppl Input Re Conformance W/Requirements of App I to 10CFR50.Radwaste Sys Sufficiently Reduced Levels of Radioactive Effluents)
  • ML19220C371  + (Forwards SER Suppl Input for TMI Re Containment Air Purification & Cleanup Sys & Re LOCA)
  • ML20037C869  + (Forwards SER Suppl Re Implementation of Improvements to Auxiliary Feedwater Sys.Preliminary Implementation Approval for Item II.E.1.1 of TMI Task Action Plan Is Complete.Two Remaining Open Items Exist)
  • ML20197G103  + (Forwards SER Suppl Re Preliminary Design Assessment Audit of Control Room & Remote Shutdown Facility.Applicant Must Submit Detailed Control Room Design Review (Dcrdr) Program & Plan,Conduct post-licensing Dcrdr & Submit Summary Rept)
  • ML19329F340  + (Forwards SER Suppl Reflecting Application of ECCS Performance Interim Acceptance Criteria & AEC Evaluation of Radwaste Disposal Sys Design Mod & Updated Financial Info. W/O Encl)
  • ML20009B791  + (Forwards SER Suppl on Emergency planning,810715 Interrogatory Answers & Affidavit to Be Notarized.W/O Encl)
  • ML19268C086  + (Forwards SER Suppl on TMI-1 QA Program for Operations.Areas Needing Addl Info Identified)
  • ML18051A748  + (Forwards SER Supporting 811116 & 831117 Responses to Generic Ltr 81-21, Natural Circulation Cooldown. Corrective Actions Resulting from Recent Steam Generator Eddy Current Testing Must Be Addressed in Next Submittal)
  • ML14184A369  + (Forwards SER Supporting 830211 Justification for Continued Operation of Equipment in Categories I.B,Ii.A & Ii.B in Response to 830103 SER of Environ Qualification of Electrical Equipment)
  • ML17345B035  + (Forwards SER Supporting 830301 Justification for Continued Operation for Category Ii.B Equipment Identified in 821213 SER Re Environ Qualification of safety-related Electrical Equipment)
  • ML13324A634  + (Forwards SER Supporting 831128 & 840718 Responses to Generic Ltr 83-28,Item 1.1, Post-Trip Review - Program Description & Procedure)
  • ML20132A441  + (Forwards SER Supporting 850611,0703 & 0809 Requests for Authorization to Eliminate Arbitrary Intermediate Pipe Breaks.Use of ASME Code Case N-411 & Portions of ASME Code Section III Acceptable)
  • ML20132A445  + (Forwards SER Supporting 850611,0703 & 0809 Requests for Authorization to Eliminate Arbitrary Intermediate Pipe Breaks.Use of ASME Code Case N-411 & Portions of ASME Code Section III Acceptable)
  • ML20137P622  + (Forwards SER Supporting 850923 Amend 6 to License SNM-1067, Authorizing Identified Licensee Personnel to Conduct Monthly Criticality Safety Audits of Nuclear Fuel Mfg Operations)
  • ML20137P627  + (Forwards SER Supporting 850923 Amend 6 to License SNM-1067, Authorizing Identified Licensee Personnel to Conduct Monthly Criticality Safety Audits of Nuclear Fuel Mfg Operations)
  • ML20137V748  + (Forwards SER Supporting 851125 Request for Partial Relief from Generic Ltr 84-11 Re Performance of Visual Exam of Reactor Coolant Piping)
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