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 Issue dateTitleTopic
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
Overspeed trip
Overspeed
ML20209C35723 January 1987SER Supporting Facility Design,Per Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing
ML20209D38728 August 1986SER Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re safety-related Reactor Trip Sys Components
ML20209J1095 November 1985SER Supporting Licensee Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Test Requirements That May Degrade Rather than Enhance Safety
ML20210P2806 May 1986Safety Evaluation Accepting Licensee Response to Items 3.1.3 & 3.2.3, Post-Maint Testing of...Safety-Related Components, of Generic Ltr 83-28
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
Operator Manual Action
High Energy Line Break
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
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
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
ML20211Q29718 February 1987Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) for Prairie Island Units 1 & 2Probabilistic Risk Assessment
Emergency Lighting
Overspeed trip
ML20212B56724 February 1987Safety Evaluation Re Util Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Reliability On-Line Testing. Response Acceptable
ML20212H75424 July 1986Safety Evaluation Supporting Licensee 841104,850208 & 0726 Responses to Generic Ltr 83-28,Item 2.1,Part 1, Equipment Classification
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
ML20214J29120 December 1979Safety Evaluation Re Preliminary Design for safety-grade Anticipatory Reactor Trips on Loss of Main Feedwater &/Or Turbine Trip
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
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
ML20214M33622 May 1987Safety Evaluation Supporting Util Rept Entitled, Rod Swap Methodology Rept for Startup Physics TestingShutdown Margin
ML20214N7209 September 1986Safety Evaluation Conditionally Supporting Rod Swap Technique & Util Nuclear Analysis Methods for Control Rod Worth Measurements
ML20214P0189 September 1986Safety Evaluation Supporting Amends 83,111,112 & 1 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectivelyFire Protection Program
ML20214T80619 November 1986Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Item 2.1 Re Equipment Classification of Reactor Trip Sys Components
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
Overspeed
ML20215A7828 May 1986Sser Re Util Response to Generic Ltr 83-28,Item 4.3, Reactor Trip Breaker Automatic Shunt Trip. Licensee Should Submit Proposed Tech Specs Consistent W/Generic Ltr 85-09 Guidance for NRC Review.Salp Input Also Encl
ML20215A96722 May 1986SER Re Util 851207 Proposed Changes to Tech Specs Pertaining to Reactor Trip Sys Instrumentation & Surveillance,Per Generic Ltr 85-09.Proposed Tech Specs Should Be Submitted for Review,Per Generic Ltr.Salp Input Also Encl
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
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
ML20215G01729 October 1985SER Re Util 830202,1216,840113 & 850528 Responses to Generic Ltr 82-33 Re Conformance to Reg Guide 1.97,Rev 2,as Applied to Emergency Response Facilities.Design Acceptable.Salp Input Encl
ML20215G11311 April 1986SER Re Util 830414,850315,0620,0906 & 860121 Responses to Reg Guide 1.97.Design Acceptable W/Respect to Conformance to Reg Guide 1.97,Rev 2,w/exception of Containment Sump Water Temp
ML20215G16911 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
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 AcceptableLoss of condenser vacuum
ML20235B40110 May 1972Errata Sheet to Safety Evaluation for PlantOperating Basis Earthquake
ML20235C00728 February 1983Evaluation Re Deficiencies Discovered in Facility Tech Specs Concerning Contaoinment Cooling Sys Operability.Recommends Mod to Tech Spec 3.3.b.2 to Correct Deficiencies
ML20235C01029 November 1971Safety Evaluation of Util Application for CP & OL for Dual Unit Nuclear Power Plant Facility
ML20235C65818 February 1972Div of Reactor Licensing Safety Evaluation Re Plant
ML20235D09730 December 1966Safety Evaluation Supporting Util 660531 Proposal to Const & Operate Single Cycle BWR of 2,255 MwtSafe Shutdown
ML20235F08311 October 1974Draft Safety Evaluation Re GE Std SARSafe Shutdown
Shutdown Margin
Reactor Vessel Water Level
Ultimate heat sink
Anticipated operational occurrence
Safe Shutdown Earthquake
Hydrostatic
Operating Basis Earthquake
Finite Element Analysis
Tornado Generated Missile
Abnormal operational transient
Feedwater Heater
Stress corrosion cracking
Earthquake
Turbine Missile
Fuel cladding
Power change
Flow Induced Vibration
Loss of condenser vacuum
Control Room Habitability
ML20235F1594 April 1968Safety Evaluation Re FacilitySafe Shutdown
Operating Basis Earthquake
Design basis earthquake
Earthquake
Fuel cladding
ML20235T66318 January 1985Safety Evaluation Supporting Util Technical Justification for Not Providing Protective Devices Against Dynamic Effects of Postulated Pipe BreaksSafe Shutdown
Intergranular Stress Corrosion Cracking
Stress corrosion cracking
Pressure boundary leak
Water hammer
ML20235T69122 February 1985Safety Evaluation Supporting Util Request for Exemption from GDC-4 for Facility.Util Occupational Dose Saving Estimate for Plant Personnel of Approx 1,400 Person Rem Is Reasonable
ML20235U00331 March 1985Safety Evaluation Supporting Util 850207 Request to Eliminate Arbitrary Intermediate Pipe Breaks in All High Energy Piping Sys Except Main Feedwater Sys at FacilityOperating Basis Earthquake
Stress corrosion cracking
Thermal fatigue
ML20235U60217 June 1986Sser Supporting Util 860528 Request for Relief from Impractical Preservice Insp Requirements of ASME Code Section XIWeld Overlay
Hydrostatic
Incorporated by reference
ML20236B44016 October 1974Safety Evaluation Supporting Util 730710 Application for OLSafe Shutdown
Boric Acid
High Radiation Area
Ultimate heat sink
Anticipated operational occurrence
Tornado Missile
Safe Shutdown Earthquake
Hydrostatic
Operating Basis Earthquake
High Energy Line Break
Intergranular Stress Corrosion Cracking
Stress corrosion cracking
Earthquake
Fuel cladding
Pressure Boundary Leakage
Overspeed trip
Operational leakage
Control Room Habitability
ML20236B93818 November 1969Safety Evaluation Supporting Util 680701 Application & Amends to Construct & Operate Second PWR at Diablo Canyon SiteEmergency Lighting
Design basis earthquake
Earthquake
Fuel cladding
ML20236L20030 October 1987Safety Evaluation Supporting Amends 11 to Licenses NPF-37 & NPF-66,respectively & Amend 1 to License NPF-72
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
ML20236X53722 October 1985SER Re Seismic Qualification of Plant Auxiliary Feedwater Sys.Nrr Request for Addl Info EnclSafe Shutdown
High winds
Ultimate heat sink
Safe Shutdown Earthquake
Probabilistic Risk Assessment
Operating Basis Earthquake
Earthquake
ML20236X57729 December 1982SER Addressing Concerns of Safe Shutdown of Plant Following Fire,Internal Flooding of Turbine Bldg & Security IncidentsSafe Shutdown
Shutdown Margin
Fire Barrier
Internal Flooding
Operator Manual Action
Tornado Generated Missile
Earthquake
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
ML20236Y0228 July 1987Safety Evaluation Clarifying Determination of Acceptability of Test Duration for Performance of Integrated Leak Rate Test at PlantBoric Acid
Integrated leak rate test
ML20245C13420 June 1989SER Supporting Issuance of Amend 1 to CP CPEP-1,specifying 891103 as Latest Date for Completion of Mods to Facility
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