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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20212J201 | 30 September 1999 | Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico | |
| NUREG-1482, SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant | 9 August 1999 | SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant | Incorporated by reference |
| ML20207G274 | 7 June 1999 | Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application | Weld Overlay |
| ML20206G645 | 3 May 1999 | Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp | Coatings Nondestructive Examination |
| ML20206E226 | 29 April 1999 | Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 | Non-Destructive Examination Weld Overlay Dissimilar Metal Weld |
| ML20205P437 | 15 April 1999 | Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding | Power-Operated Valves Backfit |
| ML20205G422 | 31 March 1999 | Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 | |
| ML20205C376 | 26 March 1999 | Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 | Exemption Request |
| ML20205D310 | 26 March 1999 | Safety Evaluation Supporting Amend 103 to License NPF-58 | Earthquake |
| ML20203A596 | 2 February 1999 | Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR | |
| ML20203A521 | 27 January 1999 | Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps | Safe Shutdown Design basis earthquake Earthquake Backfit |
| ML20198R892 | 7 January 1999 | SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable | |
| ML20198J003 | 22 December 1998 | SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 | Fire Barrier |
| ML20195F689 | 5 November 1998 | Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position | |
| ML20153B822 | 16 September 1998 | Safety Evaluation Accepting Changes to USAR Section 13.4.3, 17.2.1.3.2.2,17.2.1.3.2.2.3 & App 1A | |
| ML20249A189 | 11 June 1998 | SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER | Safe Shutdown Safe Shutdown Earthquake Design basis earthquake Earthquake |
| ML20217D205 | 20 April 1998 | SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 | Incorporated by reference |
| ML20216G390 | 11 March 1998 | SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc | |
| ML20211H679 | 18 September 1997 | Safety Evaluation Authorizing Licensees Request for Alternative from Augmented Insp of Reactor Pressure Vessel Circumferential Weld in Plant,Unit 1 | Incorporated by reference |
| ML20211A588 | 11 September 1997 | Safety Evaluation Supporting Evaluation of First 10-yr Interval ISI Program Plan Requests for Relief PT-004,PT-005 & PT-006 for Plant,Unit 1 | Hydrostatic Nondestructive Examination VT-2 Through-Wall Leakage |
| ML20217K906 | 12 August 1997 | Safety Evaluation Accepting Plant First 10-yr Interval ISI Program Plan Relief Request PT-007 | Hydrostatic VT-2 Incorporated by reference Scaffolding |
| ML20141L913 | 27 May 1997 | Safety Evaluation Accepting Relief Requests for First 10-yr Interval Inservice Insp Program Plan for Plant,Unit 1 | |
| ML20147H421 | 1 April 1997 | Safety Evaluation Accepting Changes to USAR Sections,Which Continue to Satisfy Criteria of App B of 10CFR50 | |
| ML20134D106 | 27 January 1997 | Safety Evaluation on Revised EALs for Plant.Proposed EALs Changes Are Consistent W/Guidance in NUMARC/NESP-007,with One Exception,& Meets Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 | High winds Reactor Vessel Water Level Internal Flooding Pressure Boundary Leakage |
| ML20058M676 | 29 September 1993 | Safety Evaluation Accepting Rev 10 to Plant Emergency Plan for NRC Review Under 10CFR50.54(q) | Ultimate heat sink Pressure Boundary Leakage |
| ML20246F648 | 23 August 1989 | Safety Evaluation Accepting Proposed Turbine Sys Maint Program | Turbine Missile |
| ML20246Q029 | 14 July 1989 | Safety Evaluation Re Updated Safety Analysis Rept Appendix 1B,license Commitment Revs | |
| ML20244D635 | 7 June 1989 | Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 4.5.3 Re Reactor Trip Sys Reliability | |
| NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance | 5 June 1989 | Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance | |
| ML20246Q077 | 9 May 1989 | Safety Evaluation Supporting Proposed Mod to Delete K74B & K74D Relays from Electrical Control Circuitry of MSIV to Resolve Spurious Opening of MSIV on Loss of Reactor Protection Sys Bus a or B | |
| ML20248G292 | 30 March 1989 | Safety Evaluation Accepting Util 840406 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability On-Line Testing | |
| ML20236E014 | 15 March 1989 | Safety Evaluation Supporting Util Implementation of 10CFR50.62 ATWS Rule | Reactor Vessel Water Level Anticipated operational occurrence |
| ML20196D431 | 6 December 1988 | Safety Evaluation Documenting NRC Review of Licensee Response to Generic Ltr 83-28.Evaluation Concludes That Licensee Adequately Meets Provisions of Part 1 of Item 2.2 to Generic Ltr 83-28 | Safe Shutdown |
| ML20213A566 | 20 April 1987 | Safety Evaluation Supporting Amend 4 to License NPF-58 | Reactor Vessel Water Level |
| ML20205Q977 | 1 April 1987 | Safety Evaluation Supporting Amend 3 to License NPF-58 | Safe Shutdown |
| ML20203N695 | 10 October 1986 | Safety Evaluation Supporting Request for Relief from ASME Code Exam Requirements in Preservice Insp Program | |
| ML20203N698 | 10 October 1986 | Sser Supporting Util Request for Relief from Preservice Insp Program Requirements | |
| ML20202G432 | 8 July 1986 | SER Approving Tdi Diesel Generator Owners Group Program to Validate & Upgrade Design & Mfg Quality of Tdi Diesel Generators for Nuclear Emergency Standby Svc | Liquid penetrant |
| ML20198C395 | 5 November 1985 | Safety Evaluation Re Reliability of Tdi Standby Emergency Diesel Generators for Application at Domestic Nuclear Plants.Diesel Generators Will Provide Reliable Standby Source of Onsite Power,W/Listed License Conditions | Liquid penetrant |
| ML20138N746 | 28 October 1985 | SER Supporting Reliability of Tdi Standby Emergency Diesel Generators.Viewgraphs & Final Draft Tech Specs Encl | Liquid penetrant |