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 Issue dateTitleTopic
ML20207Q58515 January 1987SER Re Generic Ltr 83-28,Item 2.1 (Part 2) Concerning Vendor Interface Programs for Reactor Trip Sys Components.Util Response Acceptable.Item Closed
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
ML20209D38728 August 1986SER Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re safety-related Reactor Trip Sys Components
ML20209E4369 July 1999SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation
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
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
ML20211A97920 August 1999Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2Incorporated by reference
ML20211E42510 June 1986Draft SER Re Util 850624 Response to Generic Ltr 83-28,Items 4.1,4.2.1 & 4.2.2 Re Preventive Maint Program for Reactor Trip Breakers/Maint & Trending.Position on Item 4.1 Acceptable.Position on Items 4.2.1 & 4.2.2 Unacceptable
ML20211E68722 September 1997SER Accepting DPC Responses to GL-95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate ValvesBackfit
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
ML20211F88022 September 1997Safety Evaluation Supporting Second ten-year Interval Inservice Inspection Program Plan & Associated Requests for Relief for Catawba Nuclear Station Unit 1Incorporated by reference
Unidentified leakage
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
ML20211G52624 August 1999SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1VT-2
Incorporated by reference
Dissimilar Metal Weld
Unidentified leakage
ML20211Q29718 February 1987Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) for Prairie Island Units 1 & 2Probabilistic Risk Assessment
Emergency Lighting
ML20212B56724 February 1987Safety Evaluation Re Util Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Reliability On-Line Testing. Response Acceptable
ML20212D19120 September 1999SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2
ML20212D72729 December 1986SER Re Util 831104 Response to Generic Ltr 83-28,Item 2.1 (Part 2), Vendor Interface Programs for Reactor Trip Sys Components. Response Acceptable.Item 2.1 Closed
ML20212D74129 December 1986Safety Evaluation Re Util 850827 Request for Relief from Hydrostatic Testing Requirements of ASME Code Section XI for Portions of Safety Injection Sys.Relief JustifiedHydrostatic
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
ML20214T4062 June 1987Safety Evaluation Supporting Util 860424 Submittal Re Turbine Sys Maint Program for Early Detection of Cracking in Low Pressure Turbine WheelsStress corrosion cracking
Turbine Missile
Coast down
Overspeed trip
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
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
ML20215D27011 June 1987SER Accepting Rev 13 to Unit 1 & Rev 4 to Unit 2 Pump & Valve Inservice Testing,Per Generic Ltr 83-28,Item 2.1 (Part 2)
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
ML20216E17713 April 1998Safety Evaluation Accepting Relief Request 98-01 for Catawba Nuclear Station Units 1 & 2 from Requirements of ASME Boiler & PV Code for Second 10-year Interval Program for Inservice Testing of Pumps & Valves
ML20217M4213 April 1998Safety Evaluation Approving Request for Relief 97-04, non-code Repair Valves.Relief Granted Retroactively to Unit 1 & Expired Dec 1997.Relief for Unit 2 Will Expire at End of Cycle 9 Outage or Next Scheduled Outage Exceeding 30 DaysThrough-Wall Leakage
Operability Assessment
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
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
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