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 Issue dateTitleTopic
ML20212C29216 September 1999SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power StationCoatings
Nondestructive Examination
Incorporated by reference
ML20209C4737 July 1999Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co
ML20196H24529 June 1999SER Denying Licensee Proposed Alternative in Relief Request PRR-13,rev 2.Staff Determined That Proposed Alternative Provides Insufficient Info to Determine Adequacy of Scope of ImplementationHydrostatic
VT-2
Incorporated by reference
Through-Wall Leak
ML20209A89028 June 1999SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i)
ML20195K34315 June 1999Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for PlantUltimate heat sink
Weld Overlay
Through-Wall Leak
ML20207E74727 May 1999Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35
ML20206M19711 May 1999SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at PlantUltimate heat sink
Weld Overlay
Through-Wall Leak
ML20153D39022 September 1998Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power StationUltimate heat sink
ML20237E22526 August 1998Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station
ML20216J37419 March 1998Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B
ML20217D6431 October 1997Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for PilgrimUltimate heat sink
Through-Wall Leak
ML20137D05120 March 1997Safety Evaluation Approving Third 10 Yr Interval ISI Program & Requests for ReliefNondestructive Examination
VT-2
Incorporated by reference
ML20134K26210 February 1997Safety Evaluation Accepting Licensee one-time Request to Defer Insp of N2A & N2B safe-end Welds,Per GL 88-01Nondestructive Examination
ML20129H39030 October 1996Safety Evaluation Re Facility IPE Submittal for Internal Events & Internal FloodInternal Flooding
Hardened vent
ML20129F40327 September 1996Safety Evaluation Accepting Second ten-year Interval Inservice Insp Program Plan Request for ReliefHigh Radiation Area
Non-Destructive Examination
Nondestructive Examination
VT-2
Incorporated by reference
ML20059C37529 December 1993Safety Evaluation Granting Exemption & Approving Alternative DAC Values for Use in Place of Generic Value for Radionuclides Specified in App B to 10CFR20.1001 - 20.2402Exemption Request
ML20058G27829 November 1993Safety Evaluation Granting IST Program Relief Per 10CFR50.55a(f)(6)(i) & Approving Alternatives Per 10CFR50.55a(f)(4)(iv)
ML20056F53011 August 1993Safety Evaluation Re Licensee Response to Reg Guide 1.97, BWR Neutron Flux Monitoring. Criteria of NEDO-31558, Acceptable for Current BWR Operating License & Const Permit Holders
ML20127P54325 January 1993Safety Evaluation Supporting Amend 145 to License DPR-35
ML20126F81223 December 1992Safety Evaluation Accepting Facility Design W/Respect to RG 1.97
ML20244C2906 June 1989Draft Safety Evaluation of Util Compliance W/Atws Rule (10CFR50.62) Re Alternate Rod Injection & Recirculation Pump Trip Sys.Alternate Rod Injection Sys Not in Compliance W/Atws Rule Re DiversityAnticipated operational occurrence
Scram Discharge Volume
ML20235V7343 March 1989Safety Evaluation Accepting Util Revised Temp Profile,Per GE EAS-98-0887, Drywell Temp Analysis for Pilgrim Nuclear Power Station
ML20154P66128 September 1988SER Approving Rev 3 to Plant Second 10-yr Inservice Insp Program,Per 10CFR50.55a(g)(4)Hydrostatic
Incorporated by reference
ML20151D05518 July 1988Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components
ML20151E20415 July 1988Safety Evaluation Supporting Incorporation of Reactor Protection Sys Circuitry Into Tech Specs & Deletion of 6- Month Channel Functional Test
ML20154J91017 May 1988Safety Evaluation Accepting Util Technical Evaluations & Acceptance Criteria Re Fire door-to-frame,frame-to-wall & Anchor Bolt Irregularities
ML20155F88724 March 1988Safety Evaluation Concluding That Internal Smoke Seals for Conduits Passing Through Fire Barriers from One Fire Area to Another Consistent W/Branch Technical Position 9.5-1 & Acceptable,Per Util 880203 SubmittalSafe Shutdown
Fire Barrier
Fire Protection Program
ML20236Y39910 November 1987SER Accepting Util Responses to Generic Ltr 83-28,Item 2.1, Part 1 Re Equipment Classification.Salp Input EnclHydrostatic
Scram Discharge Volume
ML20236V30828 October 1987Safety Evaluation Supporting Acceptance of Offsite Dose Calculation Manual Updated Through Rev 1 on Interim Basis. App D to Technical Evaluation Rept EGG-PHY-7725 EnclGrab sample
Offsite Dose Calculation Manual
Process Control Program
ML20235M16130 September 1987Safety Evaluation Supporting Util 870708 Proposed Change to Tech Specs Concerning LPCI Subsystem Testing
ML20236Y35922 July 1987Safety Evaluation Accepting Licensee Request to Modify Standby Liquid Control Sys Tech Specs,Per Requirements of ATWS rule,10CFR50.62.C.4.SALP Input Also EnclSystematic Assessment of Licensee Performance
ML20206G81426 March 1987Safety Evaluation Re Util Requests for Relief from Inservice Insp Requirements for Surface & Volumetric Exam of RHR Sys HX Nozzles & Exam of 100% Required Vol for nozzle-to-vessel Welds.Requests Granted W/Listed ConditionsHydrostatic
Temporary Modification
ML20215H95817 March 1987Safety Evaluation Supporting Tech Spec Change Re Control Room High Efficiency Air Filter Sys.Salp Input EnclSystematic Assessment of Licensee Performance
ML20212L89415 January 1987Safety Evaluation Supporting Vacuum Breaker Analysis Performed to Predict Impact Velocities & Resulting Stresses
ML20236Y3503 September 1986Safety Evaluation Accepting Licensee 850813 Response Re Generic Ltr 83-28,Item 1.1 on post-trip Review.Salp Input Encl
ML20212N84022 August 1986SER Supporting Util Response to Item 1.C of NRC Re No Specific Time Limit Necessary on Containment Purging & Venting During Reactor Operation
ML20155F89320 August 1986Safety Evaluation Accepting Util 831116 Request for Four Exemptions from 10CFR50,App R,Section Iii.G.Level of Fire Safety in Listed Fire Zones Equivalent to Safety Achieved by Compliance W/RequirementsSafe Shutdown
Fire Barrier
Coatings
Exemption Request
Scaffolding
ML20206L95112 August 1986Safety Evaluation on Util Response to Generic Ltr 83-28, Items 3.1.1,3.1.2,.3.2.1,3.2.2 & 4.5.1 Re Maint & Test Procedures for safety-related Equipment & on-line Functional Testing of Reactor Trip Sys.Responses Acceptable
ML20205C06231 July 1986Safety Evaluation Accepting Util 831107 Response to Generic Ltr 83-28,Item 2.1, Post-Trip Review. BWR Parameter List Encl
ML20236Y33610 July 1986Safety Evaluation Supporting Util 831107 Response to Generic Ltr 83-28,Item 1.2 on post-trip Review & Data & Info Capability
ML20199L2541 July 1986Safety Evaluation Supporting Amend 96 to License DPR-35
ML20206D1746 June 1986Safety Evaluation Supporting Util Response to IE Bulletin 80-11 Re Reevaluation & Testing Requirements in Items 2(b) & 3 Concerning Masonry Wall DesignSafe Shutdown
ML20203N38030 April 1986Safety Evaluation Supporting Util 840625,1204,06,850521 & 1011 Responses to Generic Ltr 86-04 Concerning Recombiner Capability Requirements of 10CFR50.44(c)(3)(ii).Facility Does Not Require Recombiner Capability
ML20236Y3711 April 1986Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing of Reactor Trip Sys & All Other safety-related Components,Respectively. SALP Input Also Encl
ML20137V76212 February 1986SER Supporting Partial Relief from Generic Ltr 84-11 Re Performance of Visual Exam of Reactor Coolant Piping
ML20135E52111 September 1985Safety Evaluation Supporting post-trip Review Program & Procedures
ML20134H35713 August 1985Safety Evaluation Granting 821203,0804,831201,840628 & 850212 Relief Requests from ASME Code Requirements of Inservice Insp Program,Except for Items B9.10-B9.40 & C5.10-C5.32 Re Pressure Retaining WeldsHydrostatic
ML20140G1435 July 1985Interim Safety Evaluation Supporting Util Response to Generic Ltr 83-36 Re NUREG-0737 Tech Specs
ML20129C69016 May 1985Safety Evaluation Re Dcrdr.Supplemental Rept Addressing Concerns Identified Necessary to Meet Requirements of NUREG-0737,Suppl 1
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