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 Issue dateTitleTopic
ML20247K25311 September 1989Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively
ML20247E3767 September 1989Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectivelyOffsite Dose Calculation Manual
Process Control Program
ML20248C0733 August 1989Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants
ML20246L25726 June 1989Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
ML20245C13420 June 1989SER Supporting Issuance of Amend 1 to CP CPEP-1,specifying 891103 as Latest Date for Completion of Mods to Facility
ML20245J07525 April 1989Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
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
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
ML20205M57326 October 1988Safety Evaluation Supporting Amends 108,25,134 & 26 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
ML20155G48028 September 1988Safety Evaluation Supporting Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-24,respectively
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
ML20154H21718 May 1988Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program
ML20147D96325 February 1988Safety Evaluation Accepting Util 860404 Evaluation of Environ Qualification of Equipment Considering Superheat Effects of high-energy Line Breaks for Plants,Per IE Info Notice 84-90
ML20147E92623 February 1988Safety Evaluation Supporting Amends 100,14,125 & 15 to Licenses DPR-61,DPR-21,DPR-65 & NPF-45,respectively
ML20236M9636 November 1987Safety Evaluation Accepting Util Proposed ATWS Mitigating Sys Actuation Circuitry for Facilities,Per 10CFR50.62(c)(1) & Pending Final Resolution of Tech Spec IssueAnticipated operational occurrence
ML20236L20030 October 1987Safety Evaluation Supporting Amends 11 to Licenses NPF-37 & NPF-66,respectively & Amend 1 to License NPF-72
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
ML20235A73318 September 1987Safety Evaluation Re Installation of Alternate Rod Injection (ARI) Sys & Adequacy of Plant Reactor Coolant Recirculating Pump Trip (RPT) Sys,In Compliance W/Atws Rule 10CFR50.62. ARI & RPT Acceptable
ML20195G54621 August 1987Safety Evaluation Accepting Proposed Util Tech Specs Change to Increase Max Allowed Enrichment of Reload Fuel to 4.2 Weight % U-235
ML20236Y0228 July 1987Safety Evaluation Clarifying Determination of Acceptability of Test Duration for Performance of Integrated Leak Rate Test at PlantBoric Acid
ML20214M33622 May 1987Safety Evaluation Supporting Util Rept Entitled, Rod Swap Methodology Rept for Startup Physics TestingShutdown Margin
ML20214M14921 May 1987Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 2) Re Established Interface W/Nsss or Vendors of Each Component of Reactor Trip Sys
ML20153F3854 May 1987SER Accepting Util 870301 & 0407 Requests for Rev to Tech Specs,Modifying MSIV Actuation Control Sys,Per IEEE Std 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
ML20207R64811 March 1987Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification.Program Acceptable
ML20212J4042 March 1987Safety Evaluation Re Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing. Licensee Meets NRC Position
ML20212B56724 February 1987Safety Evaluation Re Util Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Reliability On-Line Testing. Response Acceptable
ML20211Q29718 February 1987Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) for Prairie Island Units 1 & 2Probabilistic Risk Assessment
Emergency Lighting
ML20211G43614 February 1987Safety Evaluation Supporting Util 831110 Response to Generic Ltr 83-28,Item 4.5.2 Re on-line Testing for Reactor Trip Sys Reliability
ML20153F3517 February 1987Safety Evaluation Accepting Util Latest Design Mods to MSIV Actuation Control Sys,Per IEEE 279 & GDC 21
ML20210T2576 February 1987SER Re Util 850802 Submittal Describing Design Details of Steam Generator Blowdown & Auxiliary Steam Sys to Detect & Isolate High Energy Line Breaks.Sys Design Acceptable, However,Two Deviations from IEEE-STD-297 Criteria Apparent
ML20210R2066 February 1987Safety Evaluation Supporting Util 850517,0802,0823,1211 & 860429 Submittals Re Environ Effects of High Energy Line Breaks in Auxiliary Steam or Steam Generator Blowdown Sys. Design of Blowdown Sys AcceptableBoric Acid
ML20209B15128 January 1987SER Supporting Util Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys on-line Testing
ML20209C35723 January 1987SER Supporting Facility Design,Per Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,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
ML20215E00612 December 1986Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification of Reactor Trip Sys Components
ML20214J99124 November 1986SER Re Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) on Equipment Classification (Reactor Trip Sys Components) at Selected GE BWR Plants.Part 1 Requirements Met
ML20214T80619 November 1986Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Item 2.1 Re Equipment Classification of Reactor Trip Sys Components
ML20215D7341 October 1986Safety Evaluation Re Util 860623 Request That One Startup Test Be Modified & Five Startup Tests Be Eliminated.Mod to Rod Drop Measurement Test & Elimination of Certain Other Startup Tests Acceptable
ML20214P0189 September 1986Safety Evaluation Supporting Amends 83,111,112 & 1 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectivelyFire Protection Program
ML20214N7209 September 1986Safety Evaluation Conditionally Supporting Rod Swap Technique & Util Nuclear Analysis Methods for Control Rod Worth Measurements
ML20209D38728 August 1986SER Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re safety-related Reactor Trip Sys Components
ML20153F62927 August 1986Safety Evaluation Concurring W/Applicant 860703 Exemption Request Re Testing of 16 Relief Valves,Per 10CFR50,App JHydrostatic
Exemption Request
ML20205H15115 August 1986Safety Evaluation of Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification (Reactor Trip Sys Components)
ML20236X6945 August 1986Supplemental Safety Evaluation Supporting Seismic Qualification of Auxiliary Feedwater Sys (Multi-Plant Action C-14).SALP Input & 861029 Fr Re Proposed Rules Section EnclSafe Shutdown
Safe Shutdown Earthquake
Exemption Request
Earthquake
Backfit
ML20212H75424 July 1986Safety Evaluation Supporting Licensee 841104,850208 & 0726 Responses to Generic Ltr 83-28,Item 2.1,Part 1, Equipment Classification
ML20215A7527 July 1986SER Supporting Util 860523 Proposed Changes to Tech Specs Re Reactor Trip Sys Instrumentation & Surveillance in Response to Generic Ltr 85-09.SALP Input Also EnclCoatings
Process Control Program
ML20235U60217 June 1986Sser Supporting Util 860528 Request for Relief from Impractical Preservice Insp Requirements of ASME Code Section XIWeld Overlay
Hydrostatic
Incorporated by reference
ML20211F02412 June 1986Safety Evaluation Supporting Util Listed Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Identification & Classification of Reactor Trip Sys Components
IA-87-213, SER Finding Facility Design Acceptable W/Respect to Conformance to Reg Guide 1.97,Rev 3,except for Accumulator Tank Level & Pressure Instrumentation,Containment Sump Water Temp Instrumentation & Quench Tank Temp Instrumentation11 June 1986SER Finding Facility Design Acceptable W/Respect to Conformance to Reg Guide 1.97,Rev 3,except for Accumulator Tank Level & Pressure Instrumentation,Containment Sump Water Temp Instrumentation & Quench Tank Temp InstrumentationBoric Acid
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