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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20212D596 | 15 September 1999 | Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 | Hot Short High winds Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Earthquake Fire Protection Program |
| ML20196J425 | 30 June 1999 | Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 | |
| ML20207D675 | 22 February 1999 | Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars | |
| ML20206R900 | 13 January 1999 | SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 | Non-Destructive Examination Nondestructive Examination |
| ML20198C767 | 10 December 1998 | Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 | Incorporated by reference |
| ML20236Q316 | 10 July 1998 | Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 | Hydrostatic VT-2 Incorporated by reference Pressure Boundary Leakage Pressure boundary leak Through-Wall Leakage |
| ML20236L677 | 7 July 1998 | Safety Evaluation Approving Wepco Implementation Program to Resolve USI A-46 at Point Beach NPP Units 1 & 2 | Safe Shutdown Safe Shutdown Earthquake Emergency Lighting Finite Element Analysis Earthquake Fire Protection Program |
| ML20217F313 | 17 April 1998 | Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds,For Plant, Unit 1 | High Radiation Area Hydrostatic VT-2 Liquid penetrant |
| ML20217A850 | 19 March 1998 | SER Accepting Proposed Changes Submitted on 980226 by Wiep to Pbnp Final SAR Section 1.8 Which Will Impact Commitments Made in Pbnp QA Program Description.Changes Concern Approval Authority for Procedures & Interviewing Authority | |
| ML20216J010 | 17 March 1998 | Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Relief Request RR-1-18 for Plant | Incorporated by reference |
| ML20198L115 | 8 January 1998 | SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Point Beach Nuclear Plant,Units 1 & 2 | Boric Acid Power-Operated Valves Backfit |
| ML20198L467 | 2 January 1998 | SER Approving Request for Relief VRR-4B to Inservice Testing Program Wisconsin Electric Power Co,Point Beach Nuclear Plant,Units 1 & 2 | |
| ML20197J934 | 12 December 1997 | Safety Evaluation Accepting Licensee Request for Relief from Performing Inservice Volmetric Exam of Inaccessible Portions of RPV Lower Shell to Lower Head Ring Weld During 10-yr ISI Interval of Plant,Unit 2 | Incorporated by reference |
| ML20137U499 | 10 April 1997 | Safety Evaluation Accepting Proposed Alternatives Contained in Requests for Relief RR-1-17 & RR-2-21 | Incorporated by reference |
| ML20129G690 | 3 October 1996 | SER Accepting Request for Relief from ASME Code Repair Requirements for ASME Code Class Three Piping at Plant | Operability Determination Operability Assessment |
| ML20062J499 | 28 October 1993 | Safety Evaluation Granting IST Relief Requests Per 10CFR50.55a(a)(3)(ii) & 10CFR50.55a(f)(4)(iv) | Safe Shutdown Boric Acid Stroke time Incorporated by reference Cold shutdown justification |
| ML20062F136 | 25 September 1990 | SE Accepting Util Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review - Data & Info Capability | |
| ML20248A010 | 18 September 1989 | Safety Evaluation Re Containment Liner Leak Chase Channel Venting.Concurs W/Licensee That Plant Does Not Need to Vent Containment Liner Weld Leak Chase Channels During Test | |
| ML20246H012 | 7 July 1989 | Safety Evaluation Accepting Util 880325 & 1117 Responses to NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes | |
| ML20245B031 | 14 June 1989 | Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Item 4.5.3 Re on-line Functional Testing of Reactor Trip Sys.Existing Intervals for on-line Functional Testing Consistent W/High Reactor Trip Sys Availability | |
| ML20207E419 | 4 August 1988 | Safety Evaluation Supporting Compliance W/Atws Rule 10CFR50.62, Requirements for Reduction of Risk from ATWS Events for Light Water Cooled Nuclear Power Plants | Anticipated operational occurrence |
| ML20151R677 | 2 August 1988 | Safety Evaluation Granting Request for Relief from ASME Code,Section XI Evaluation Requirements | Reactor Vessel Water Level Hydrostatic VT-2 |
| ML20151N219 | 27 July 1988 | Safety Evaluation Supporting Util Proposal Re Design of Switchgear Room,Per Sections Iii.G & Iii.L of App R to 10CFR50 | Safe Shutdown Fire Protection Program |
| ML20150C131 | 21 June 1988 | Safety Evaluation Accepting Responses to Generic Ltr 83-28, Item 2.1,confirming That Program Exists for Identifying, Classifying & Treating Components Required for Performance of Reactor Trip Function as safety-related | |
| ML20154H579 | 12 May 1988 | Safety Evaluation Supporting Conclusions That Rev 1 to Offsite Dose Calculation Manual (ODCM) Uses Methods Consistent W/Staff Requirements,However Some Discrepancies Identified.Odcm & Environ Manual Should Be Revised | Offsite Dose Calculation Manual |
| ML20148H455 | 24 March 1988 | Safety Evaluation Accepting Util 840405 Response to Generic Ltr 83-28,Item 2.1,(Part 2) Re Vendor Interface Programs & Reactor Trip Sys Components | |
| ML20235K924 | 9 July 1987 | Safety Evaluation Re Reactor Pressure Vessel Flaw.Flaw Conditionally Acceptable Per Subarticle IWB-3123 of Section XI of ASME Code & Therefore Requires Augmented Inservice Insps Based on 10CFR50.55(g)(4) | Anticipated operational occurrence |
| ML20213G580 | 7 May 1987 | Safety Evaluation Re Util 861027 Request for Relief from Exam Requirements of Section XI of ASME Boiler & Pressure Vessel Code for Shell & Nozzle Welds in Regenerative Hxs. Request Granted | |
| ML20206K601 | 10 April 1987 | SER Supporting Util 860513 Proposed Replacement of Hydraulic Snubbers W/Energy Absorbers on Main Steam Bypass Line | Earthquake Water hammer |
| ML20210P278 | 5 February 1987 | Safety Evaluation Supporting Util 831107 & 860411 Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys Reliability on-line Testing.Plant Designed to Permit on-line Functional Testing of Diverse Trip Features of Breakers | |
| ML20214U608 | 26 November 1986 | Safety Evaluation Supporting Util 850516 Capsule T Summary Rept Re Use of Reactor Vessel Pressure Temp Limits Specified in Figures 15.3.1-1 & 15.3.1-2 of Tech Specs.Temp Limits Valid & May Continue to Be Used | |
| ML20206S709 | 16 September 1986 | Safety Evaluation on Util 850426 Response to Open Items Re Generic Ltr 81-14, Seismic Qualification of Auxiliary Feedwater Sys (Afws). Reasonable Assurance Exists That Afws Will Perform Required Safety Function Following SSE | Safe Shutdown Safe Shutdown Earthquake Earthquake |
| ML20214L931 | 4 September 1986 | Corrected Safety Evaluation Re Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.Licensee Projections Acceptable | |
| ML20207D678 | 11 July 1986 | Safety Evaluation Accepting Util Responses to Generic Ltr 82-33 Re post-accident Monitoring Instrumentation Compliance W/Guidelines of Reg Guide 1.97,Rev 2,subj to Listed Condition.Portions of Rev 1 to EGG-EA-6771 Encl | Boric Acid High Radiation Area Grab sample Anticipated operational occurrence Overexposure |
| ML20138N780 | 31 October 1985 | Safety Evaluation Granting Util 840706 Relief Requests for Second 10-yr Inservice Insp Interval.Review of Requests for Relief from ASME Code Section XI Requirements Summarized in Encl Tables | Hydrostatic VT-2 |
| ML20134A482 | 24 October 1985 | Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Items 3.1.1,3.1.2,4.1 & 4.5.1 Re post-maint Testing (Reactor Trip Sys Components) & Reactor Trip Sys Reliability.Programs Outlined in Acceptable | |
| ML20134A605 | 22 October 1985 | Safety Evaluation Re Util 831107 & 850910 Responses to Generic Ltr 83-28,Item 1.1, Post-Trip Review Program Description & Procedures. Program & Procedures Acceptable | |
| ML20138H172 | 18 October 1985 | Safety Evaluation Accepting Util 831107 Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing | |
| ML20133G417 | 29 July 1985 | Safety Evaluation Accepting Util 831108 Response to Generic Ltr 83-28,Item 1.1 Re post-trip Review.Response to Listed Deficiencies,Including Development of Systematic Safety Assessment Program for Unscheduled Reactor Trips Required | |
| ML20129H787 | 16 May 1985 | Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Re Reactor Trip Sys Reliability,Provided Corrective Action Taken If Higher than Normal Valves Observed in Trip Force & Response Time Values | |
| ML20205H217 | 10 September 1984 | Supplemental Safety Evaluation Re Util 820820 & 860113 Requests for Relief from Inservice Insp Requirements. Volumetric Exam Acceptable Method for Detecting O.D. Initiated Flaws.Relief from Surface Exams Should Be Granted | |
| ML20204F538 | 25 April 1983 | Safety Evaluation of Util Preferred Ac Power Sys Conformance GDC 17.Proximity of Low Voltage Transformers Does Not Fully Meet GDC 17 Requirements for Physical Separation,But Deluge Sprinkler Sys Adequate | Safe Shutdown Earthquake |