Semantic search
Jump to navigation
Jump to search
Issue date | Title | Topic | |
---|---|---|---|
ML20212C292 | 16 September 1999 | SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station | Coatings Nondestructive Examination Incorporated by reference |
ML20209C473 | 7 July 1999 | Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co | |
ML20196H245 | 29 June 1999 | SER 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 Implementation | Hydrostatic VT-2 Incorporated by reference Through-Wall Leak |
ML20209A890 | 28 June 1999 | SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) | |
ML20195K343 | 15 June 1999 | Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for Plant | Ultimate heat sink Weld Overlay Through-Wall Leak |
ML20207E747 | 27 May 1999 | Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35 | |
ML20206M197 | 11 May 1999 | SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at Plant | Ultimate heat sink Weld Overlay Through-Wall Leak |
ML20153D390 | 22 September 1998 | Safety 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 Station | Ultimate heat sink |
ML20237E225 | 26 August 1998 | Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station | |
ML20216J374 | 19 March 1998 | Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B | |
ML20217D643 | 1 October 1997 | Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for Pilgrim | Ultimate heat sink Through-Wall Leak |
ML20137D051 | 20 March 1997 | Safety Evaluation Approving Third 10 Yr Interval ISI Program & Requests for Relief | Nondestructive Examination VT-2 Incorporated by reference |
ML20134K262 | 10 February 1997 | Safety Evaluation Accepting Licensee one-time Request to Defer Insp of N2A & N2B safe-end Welds,Per GL 88-01 | Nondestructive Examination |
ML20129H390 | 30 October 1996 | Safety Evaluation Re Facility IPE Submittal for Internal Events & Internal Flood | Internal Flooding Hardened vent |
ML20129F403 | 27 September 1996 | Safety Evaluation Accepting Second ten-year Interval Inservice Insp Program Plan Request for Relief | High Radiation Area Non-Destructive Examination Nondestructive Examination VT-2 Incorporated by reference |
ML20059C375 | 29 December 1993 | Safety Evaluation Granting Exemption & Approving Alternative DAC Values for Use in Place of Generic Value for Radionuclides Specified in App B to 10CFR20.1001 - 20.2402 | Exemption Request |
ML20058G278 | 29 November 1993 | Safety Evaluation Granting IST Program Relief Per 10CFR50.55a(f)(6)(i) & Approving Alternatives Per 10CFR50.55a(f)(4)(iv) | |
ML20056F530 | 11 August 1993 | Safety 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 | |
ML20127P543 | 25 January 1993 | Safety Evaluation Supporting Amend 145 to License DPR-35 | |
ML20126F812 | 23 December 1992 | Safety Evaluation Accepting Facility Design W/Respect to RG 1.97 | |
ML20244C290 | 6 June 1989 | Draft 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 Diversity | Anticipated operational occurrence Scram Discharge Volume |
ML20235V734 | 3 March 1989 | Safety Evaluation Accepting Util Revised Temp Profile,Per GE EAS-98-0887, Drywell Temp Analysis for Pilgrim Nuclear Power Station | |
ML20154P661 | 28 September 1988 | SER Approving Rev 3 to Plant Second 10-yr Inservice Insp Program,Per 10CFR50.55a(g)(4) | Hydrostatic Incorporated by reference |
ML20151D055 | 18 July 1988 | Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components | |
ML20151E204 | 15 July 1988 | Safety Evaluation Supporting Incorporation of Reactor Protection Sys Circuitry Into Tech Specs & Deletion of 6- Month Channel Functional Test | |
ML20154J910 | 17 May 1988 | Safety Evaluation Accepting Util Technical Evaluations & Acceptance Criteria Re Fire door-to-frame,frame-to-wall & Anchor Bolt Irregularities | |
ML20155F887 | 24 March 1988 | Safety 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 Submittal | Safe Shutdown Fire Barrier Fire Protection Program |
ML20236Y399 | 10 November 1987 | SER Accepting Util Responses to Generic Ltr 83-28,Item 2.1, Part 1 Re Equipment Classification.Salp Input Encl | Hydrostatic Scram Discharge Volume |
ML20236V308 | 28 October 1987 | Safety Evaluation Supporting Acceptance of Offsite Dose Calculation Manual Updated Through Rev 1 on Interim Basis. App D to Technical Evaluation Rept EGG-PHY-7725 Encl | Grab sample Offsite Dose Calculation Manual Process Control Program |
ML20235M161 | 30 September 1987 | Safety Evaluation Supporting Util 870708 Proposed Change to Tech Specs Concerning LPCI Subsystem Testing | |
ML20236Y359 | 22 July 1987 | Safety Evaluation Accepting Licensee Request to Modify Standby Liquid Control Sys Tech Specs,Per Requirements of ATWS rule,10CFR50.62.C.4.SALP Input Also Encl | Systematic Assessment of Licensee Performance |
ML20206G814 | 26 March 1987 | Safety 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 Conditions | Hydrostatic Temporary Modification |
ML20215H958 | 17 March 1987 | Safety Evaluation Supporting Tech Spec Change Re Control Room High Efficiency Air Filter Sys.Salp Input Encl | Systematic Assessment of Licensee Performance |
ML20212L894 | 15 January 1987 | Safety Evaluation Supporting Vacuum Breaker Analysis Performed to Predict Impact Velocities & Resulting Stresses | |
ML20236Y350 | 3 September 1986 | Safety Evaluation Accepting Licensee 850813 Response Re Generic Ltr 83-28,Item 1.1 on post-trip Review.Salp Input Encl | |
ML20212N840 | 22 August 1986 | SER Supporting Util Response to Item 1.C of NRC Re No Specific Time Limit Necessary on Containment Purging & Venting During Reactor Operation | |
ML20155F893 | 20 August 1986 | Safety 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/Requirements | Safe Shutdown Fire Barrier Coatings Exemption Request Scaffolding |
ML20206L951 | 12 August 1986 | Safety 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 | |
ML20205C062 | 31 July 1986 | Safety Evaluation Accepting Util 831107 Response to Generic Ltr 83-28,Item 2.1, Post-Trip Review. BWR Parameter List Encl | |
ML20236Y336 | 10 July 1986 | Safety Evaluation Supporting Util 831107 Response to Generic Ltr 83-28,Item 1.2 on post-trip Review & Data & Info Capability | |
ML20199L254 | 1 July 1986 | Safety Evaluation Supporting Amend 96 to License DPR-35 | |
ML20206D174 | 6 June 1986 | Safety Evaluation Supporting Util Response to IE Bulletin 80-11 Re Reevaluation & Testing Requirements in Items 2(b) & 3 Concerning Masonry Wall Design | Safe Shutdown |
ML20203N380 | 30 April 1986 | Safety 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 | |
ML20236Y371 | 1 April 1986 | Safety 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 | |
ML20137V762 | 12 February 1986 | SER Supporting Partial Relief from Generic Ltr 84-11 Re Performance of Visual Exam of Reactor Coolant Piping | |
ML20135E521 | 11 September 1985 | Safety Evaluation Supporting post-trip Review Program & Procedures | |
ML20134H357 | 13 August 1985 | Safety 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 Welds | Hydrostatic |
ML20140G143 | 5 July 1985 | Interim Safety Evaluation Supporting Util Response to Generic Ltr 83-36 Re NUREG-0737 Tech Specs | |
ML20129C690 | 16 May 1985 | Safety Evaluation Re Dcrdr.Supplemental Rept Addressing Concerns Identified Necessary to Meet Requirements of NUREG-0737,Suppl 1 | |
ML20206K616 | 13 March 1985 | SER 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 |