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 Issue dateTitleTopic
ML20148S52714 November 1978Safety Evaluation Supporting Amend 24 to License DPR-54 Concluding That Proposed Changes in Plant Org Are Admin in Nature & Preserve Intent of Tech Specs.Mods to Security & Emergency Plans Are Also Acceptable
ML20149L2769 February 1988Safety Evaluation Supporting Amend 94 to License DPR-54Offsite Circuit
ML20149L69612 February 1988Safety Evaluation Supporting Amend 95 to License DPR-54Design basis earthquake
ML20150F28528 March 1988Safety Evaluation Supporting Resolution of Tdi Diesel Engine Vibration Problems at Facility
ML20151A27713 July 1988SER Supporting Util Actions to Prevent Failure of Ammonia Tanks Which May Result in Incapacitation of Control Room & Technical Support Ctr Personnel
ML20151L55114 July 1988Redistributed Safety Evaluation Supporting Amend 99 to License DPR-54
ML20151X71923 January 1968AEC Safety Evaluation in Matter of Licensee PlantSafe Shutdown
Boric Acid
Design basis earthquake
Earthquake
Fuel cladding
ML20153B29115 March 1988Safety Evaluation Supporting Amend 97 to License DPR-54Shutdown Margin
Ultimate heat sink
ML20153F3517 February 1987Safety Evaluation Accepting Util Latest Design Mods to MSIV Actuation Control Sys,Per IEEE 279 & GDC 21
ML20153F36730 April 1987Safety Evaluation Accepting Util 870311 Proposed Changes to Tech Spec Tables 2.2.1-1,3.6.1.2-1 & 3.6.3-1 Re MSIV-closure Setpoint
ML20153F3854 May 1987SER Accepting Util 870301 & 0407 Requests for Rev to Tech Specs,Modifying MSIV Actuation Control Sys,Per IEEE Std 279 & GDC 21
ML20153F62927 August 1986Safety Evaluation Concurring W/Applicant 860703 Exemption Request Re Testing of 16 Relief Valves,Per 10CFR50,App JHydrostatic
Exemption Request
ML20154A40514 November 1985Safety Evaluation Supporting 831108 Response to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2,4.1 & 4.5.1 Re post-maint Testing & Reactor Trip Sys Reliability.Salp Input Encl
ML20154A4204 November 1985Safety Evaluation Supporting 831108 Response to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 Re post-maint Testing & Reactor Trip Sys Reliability
ML20154C36425 February 1986Suppl to Safety Evaluation Supporting Results of Tests Conducted by Wyle Labs Contained in Test Rept 17769-01 to Justify Less Separation Between Class 1E & non-Class 1E Cables than Required by Reg Guide 1.75
ML20154H21718 May 1988Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program
ML20155D31328 September 1988Safety Evaluation Supporting Amend 100 to License DPR-54
ML20155E98619 December 1973Draft Safety Evaluation Detailing Items Requiring Resolution Expected to Occur Prior to Issuance of Const PermitUltimate heat sink
Fuel cladding
ML20155G48028 September 1988Safety Evaluation Supporting Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-24,respectively
ML20195C5578 June 1988SER Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification (Reactor Trip Sys Components)
ML20195C9318 June 1988SER Accepting Util Response to Generic Ltr 83-28,Item 2.1 (Part 2) Re Vendor Interface Programs (Reactor Trip Sys)
ML20195G54621 August 1987Safety Evaluation Accepting Proposed Util Tech Specs Change to Increase Max Allowed Enrichment of Reload Fuel to 4.2 Weight % U-235
ML20195G55028 October 1987Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pool.Licensee May Be Required to Perform Addl Analyses to Verify Maint of Required Subcriticality If Staff Boraflex Studies Reveal Gap Development in Subj BoraflexSystematic Assessment of Licensee Performance
ML20195G55324 June 1988Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pools from Criticality Standpoint.Enrichment of Fuel to 4.5 Weight % U-235 May Be in Conflict W/ 10CFR51 Table S4 & Should Be Investigated by NRC
ML20198C55415 May 1986Safety Evaluation Accepting Util Response to Items 3.1.3 & 3.2.3 of Generic Ltr 83-28 Requiring Licensee Review of Existing Tech Specs for post-maint Testing Requirements That May Degrade Safety.Items Closed
ML20198G82722 August 1997Safety Evaluation Supporting Amend 125 to License DPR-54High Radiation Area
Annual Radioactive Effluent Release Report
ML20199G45319 March 1985Partially Withheld marked-up Rev 5 to Sser Re Allegation AQ-91 Concerning Inadequate Training of Personnel.Related Info Encl
ML20199G6145 October 1984Partially Withheld marked-up Rev 2 to Sser Re Allegation AQ-88 Concerning safety-related Work Performed by Illegal Aliens
ML20199G62013 March 1985Partially Withheld marked-up Rev 4 to Sser Re Allegation AQ-98 Concerning Extensive Delays in Repair of safety-related MatlHydrostatic
ML20199G6242 October 1984Partially Withheld marked-up Draft 4 to Sser Re Allegation A-130 Concerning Valve Disc Numbers on Repair Travelers That Differ from Code Data Rept
ML20199G6301 November 1984Partially Withheld marked-up Rev 3 to Sser Re Allegation AQ-131 Concerning Electrical Boxes That Were Shipped to Facility in Damaged Condition or Were Damaged & Repaired by Unauthorized Personnel.Related Info EnclCoatings
Nondestructive Examination
ML20199G77522 January 1985Partially Withheld marked-up Rev 1 to Sser Re Allegation AQ-41 Concerning Sandblasted Pipe Sections Which Removed Heat Markings Used for Traceability.Related Info EnclCoatings
ML20203N7968 April 1986Safety Evaluation Supporting Amend 79 to License DPR-54
ML20205C39513 March 1987Safety Evaluation Re Fracture Toughness Requirements for Protection Against PTS Events (10CFR50.61).Util 860123 Submittal Re Matl Properties & Fast Neutron Fluence of Reactor Vessel Acceptable
ML20205H15115 August 1986Safety Evaluation of Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification (Reactor Trip Sys Components)
ML20205J09711 March 1987Safety Evaluation Re Sys Selected for Facility Sys Review & Test Program.Sys Constitutes Adequate Scope for Sys Review & Test Program
ML20205M57326 October 1988Safety Evaluation Supporting Amends 108,25,134 & 26 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
ML20205Q57231 October 1988SER Re Const Mod & Licensing of Company Facility-1 Cpdf. Licensee Technically Qualified to Modify Existing Facility in Such Way as to Assure Adequate Protection of Common Defense & SecurityExemption Request
ML20205Q57631 October 1988SER Re Application for CP for Alchemie Facility-2 Oliver Springs.Licensee Technically Qualified to Construct & Operate Proposed Facility in Such Way as to Assure Adequate Protection for Common Defense & SecurityExemption Request
ML20205R78726 March 1987Safety Evaluation Concluding Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability On-Line Testing Permits on-line Functional Testing of Sys,Including Diverse Trip Features of Reactor Trip Breakers
ML20205T30231 March 1987Safety Evaluation Supporting Amend 84 to License DPR-54Time to boil
ML20206B65613 March 1987Corrected SER Re Fracture Toughness Requirements for Protection Against PTS Events (10CFR50.61).Util 860123 Submittal Re Matl Properties & Fast Neutron Fluence of Reactor Vessel Acceptable
ML20206F90719 May 1986Safety Evaluation Supporting Util Request for Exemption from Requirements of 10CFR50,App R,Subsection Iii.L Re Capability to Achieve Cold Shutdown in 72 HSafe Shutdown
Shutdown Margin
Exemption Request
ML20206K5554 November 1977Safety Evaluation & Eia Supporting Proposed Amend to License DPR-35,implementing App I Requirements Re ALARA Releases of Radioactive Matls in Liquid & Gaseous EffluentsAnticipated operational occurrence
ML20206K61613 March 1985SER Supporting Proposed Tech Spec Change to Permit Temporary Increase in Main Steam Line High Radiation Scram & Isolation Setpoints to Facilitate Testing of Hydrogen Addition Water Chemistry.Related Documentation Encl
ML20207R64811 March 1987Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification.Program Acceptable
ML20207T42430 December 1985SER Re SPDS Based on Documentation & 850513-15 Audit.Spds Does Not Fully Meet Requirements of Suppl 1 to NUREG-0737. Five Listed Variables Should Be Added to Spds.Interim Implementation Acceptable
ML20209B15128 January 1987SER Supporting Util Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys on-line Testing
ML20209C21521 January 1987Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) at Prairie Island Units 1 & 2.Util Actively Pursuing Improvements in Sys Reliability & Reducing Sys ChallengesEmergency Lighting
ML20209C35723 January 1987SER Supporting Facility Design,Per Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing
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