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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20217G216 | 15 October 1999 | Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend | Fuel cladding |
| ML20207G226 | 7 June 1999 | SER Accepting Proposed Mod to Each of Four Core Shroud Stabilizers for Implementation During Current 1999 Refueling Outage at Plant,Unit 1 | |
| ML20206U535 | 17 May 1999 | SER Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant, Units 1 & 2 | Backfit |
| ML20155E200 | 2 November 1998 | Safety Evaluation Approving NMP 980227 Request for Extension of Reinspection Interval for Core Shroud Vertical Welds at NMP1 from 10,600 Hours to 14,500 Hours of Hot Operation | |
| ML20154D840 | 5 October 1998 | Safety Evaluation Accepting Proposed Changes Related to PT Limits in Plant,Unit 1 TSs | Hydrostatic |
| ML20217F434 | 19 March 1998 | SER Related to Proposed Restructuring New York State Electric & Gas Corp,Nine Mile Point Nuclear Station,Unit 2 | |
| ML20198H994 | 29 December 1997 | SE Supporting Approval of Application Re Long Island Power Authority Aquisition of Long Island Lighting Co,Subject to Discussed Condition | |
| ML20197C477 | 3 January 1997 | Safety Evaluation Supporting Nine Mile Point Unit 1 Reactor & Turbine Building Blowout Panels | |
| ML20197C454 | 2 January 1997 | Safety Evaluation Supporting Resolution of Nine Mile Point Reactor/Turbine Building Pressure Relief Panel Outside Design Basis Issue | Finite Element Analysis |
| ML20056H475 | 27 August 1993 | Safety Evaluation Accepting Licensee Proposal for Continued Insp & Repair of Flaw in Weld Joining HPCS Nozzle Safe to safe-end Extension | Weld Overlay Nondestructive Examination |
| ML20247K253 | 11 September 1989 | Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively | |
| ML20247E376 | 7 September 1989 | Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively | Offsite Dose Calculation Manual Process Control Program |
| ML20248C073 | 3 August 1989 | Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants | |
| ML20246L257 | 26 June 1989 | Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively | |
| ML20245J075 | 25 April 1989 | Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively | |
| ML20205R131 | 31 October 1988 | Safety Evaluation Supporting Amend 101 to License DPR-63 | Exemption Request |
| ML20205Q572 | 31 October 1988 | SER Re Const Mod & Licensing of Company Facility-1 Cpdf. Licensee Technically Qualified to Modify Existing Facility in Such Way as to Assure Adequate Protection of Common Defense & Security | Exemption Request |
| ML20205Q576 | 31 October 1988 | SER Re Application for CP for Alchemie Facility-2 Oliver Springs.Licensee Technically Qualified to Construct & Operate Proposed Facility in Such Way as to Assure Adequate Protection for Common Defense & Security | Exemption Request |
| ML20205M573 | 26 October 1988 | Safety Evaluation Supporting Amends 108,25,134 & 26 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively | |
| ML20155G480 | 28 September 1988 | Safety Evaluation Supporting Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-24,respectively | |
| ML20195G553 | 24 June 1988 | Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pools from Criticality Standpoint.Enrichment of Fuel to 4.5 Weight % U-235 May Be in Conflict W/ 10CFR51 Table S4 & Should Be Investigated by NRC | |
| ML20154H217 | 18 May 1988 | Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program | |
| ML20147D963 | 25 February 1988 | Safety Evaluation Accepting Util 860404 Evaluation of Environ Qualification of Equipment Considering Superheat Effects of high-energy Line Breaks for Plants,Per IE Info Notice 84-90 | |
| ML20147E926 | 23 February 1988 | Safety Evaluation Supporting Amends 100,14,125 & 15 to Licenses DPR-61,DPR-21,DPR-65 & NPF-45,respectively | |
| ML20236M963 | 6 November 1987 | Safety Evaluation Accepting Util Proposed ATWS Mitigating Sys Actuation Circuitry for Facilities,Per 10CFR50.62(c)(1) & Pending Final Resolution of Tech Spec Issue | Anticipated operational occurrence |
| ML20236L200 | 30 October 1987 | Safety Evaluation Supporting Amends 11 to Licenses NPF-37 & NPF-66,respectively & Amend 1 to License NPF-72 | |
| ML20195G550 | 28 October 1987 | Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pool.Licensee May Be Required to Perform Addl Analyses to Verify Maint of Required Subcriticality If Staff Boraflex Studies Reveal Gap Development in Subj Boraflex | Systematic Assessment of Licensee Performance |
| ML20235A733 | 18 September 1987 | Safety 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 | |
| ML20195G546 | 21 August 1987 | Safety Evaluation Accepting Proposed Util Tech Specs Change to Increase Max Allowed Enrichment of Reload Fuel to 4.2 Weight % U-235 | |
| ML20236Y022 | 8 July 1987 | Safety Evaluation Clarifying Determination of Acceptability of Test Duration for Performance of Integrated Leak Rate Test at Plant | Boric Acid |
| ML20214M336 | 22 May 1987 | Safety Evaluation Supporting Util Rept Entitled, Rod Swap Methodology Rept for Startup Physics Testing | Shutdown Margin |
| ML20214M149 | 21 May 1987 | Safety 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 | |
| ML20153F385 | 4 May 1987 | SER Accepting Util 870301 & 0407 Requests for Rev to Tech Specs,Modifying MSIV Actuation Control Sys,Per IEEE Std 279 & GDC 21 | |
| ML20153F367 | 30 April 1987 | Safety Evaluation Accepting Util 870311 Proposed Changes to Tech Spec Tables 2.2.1-1,3.6.1.2-1 & 3.6.3-1 Re MSIV-closure Setpoint | |
| ML20238C712 | 8 April 1987 | Safety Evaluation Concluding That Facility May Resume Operation W/O Leakage Control Sys But w/post-accident Leakage Mgt | |
| ML20207R648 | 11 March 1987 | Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification.Program Acceptable | |
| ML20212J404 | 2 March 1987 | Safety 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 | |
| ML20212B567 | 24 February 1987 | Safety Evaluation Re Util Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Reliability On-Line Testing. Response Acceptable | |
| ML20211Q297 | 18 February 1987 | Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) for Prairie Island Units 1 & 2 | Probabilistic Risk Assessment Emergency Lighting |
| ML20211G436 | 14 February 1987 | Safety Evaluation Supporting Util 831110 Response to Generic Ltr 83-28,Item 4.5.2 Re on-line Testing for Reactor Trip Sys Reliability | |
| ML20153F351 | 7 February 1987 | Safety Evaluation Accepting Util Latest Design Mods to MSIV Actuation Control Sys,Per IEEE 279 & GDC 21 | |
| ML20210R206 | 6 February 1987 | Safety 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 Acceptable | Boric Acid |
| ML20210T257 | 6 February 1987 | SER 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 | |
| ML20238C650 | 5 February 1987 | Safety Evaluation Accepting MSIVs for Facility Operation Up to First Refueling,Contingent on Successful Completion of Preoperational Tests & Prototype Testing Program.Briefing for Commissioner Asselstine Re MSIVs & SALP Input Also Encl | High Radiation Area Stroke time Weld Overlay Finite Element Analysis Liquid penetrant |
| ML20238C580 | 2 February 1987 | Safety Evaluation Concluding That Facility May Resume Startup Testing & Operation for First Operating Cycle W/ Installed Refurbished Msivs.Necessity of Addl Leak Testing to Be Determined After Review of Prototype Test Results | Coatings |
| ML20209B151 | 28 January 1987 | SER Supporting Util Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys on-line Testing | |
| ML20209C357 | 23 January 1987 | SER Supporting Facility Design,Per Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing | |
| ML20209C215 | 21 January 1987 | Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) at Prairie Island Units 1 & 2.Util Actively Pursuing Improvements in Sys Reliability & Reducing Sys Challenges | Emergency Lighting |
| ML20215E006 | 12 December 1986 | Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification of Reactor Trip Sys Components | |
| ML20214J991 | 24 November 1986 | SER 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 |