Semantic search
Jump to navigation
Jump to search
Issue date | Title | Topic | |
---|---|---|---|
ML20205L040 | 9 April 1999 | SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2 | Boric Acid Nondestructive Examination VT-2 Incorporated by reference Dissimilar Metal Weld |
ML20203E118 | 10 February 1999 | SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description | |
ML20199F534 | 29 December 1998 | Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1 | Boric Acid VT-2 Incorporated by reference |
ML20198K855 | 21 December 1998 | SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1 | Incorporated by reference |
ML20198A163 | 9 December 1998 | SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request | Safe Shutdown Safe Shutdown Earthquake Nondestructive Examination Design basis earthquake Earthquake |
ML20195J313 | 12 November 1998 | Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief | VT-2 Incorporated by reference |
ML20154R912 | 20 October 1998 | Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept | |
ML20154P749 | 19 October 1998 | SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1 | Incorporated by reference |
ML20154C671 | 1 October 1998 | Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity | Fire Barrier Aging Management |
ML20202B857 | 18 November 1997 | SE Approving Relief Requests for Second 10-Yr Interval for Pumps & Valves Inservice Testing Program for Beaver Valley Power Station,Unit 2 | Boric Acid Stroke time Incorporated by reference Cold shutdown justification Power-Operated Valves |
ML20199F464 | 13 November 1997 | SER Related to Reactor Pressure Vessel,Pressurized Thermal Shock Assessment for Beaver Valley Power Station,Unit 2 | |
ML20212G496 | 28 October 1997 | SER Accepting Pressurized Thermal Shock Assessment for Beaver Valley Unit 2 Reactor Vessel | |
ML20217J531 | 8 October 1997 | Safety Evaluation Re First,Second & Third 10-year Interval Inservice Inspection Program Plan Requests for Relief for Plant,Units 1 & 2 | Boric Acid VT-2 Incorporated by reference Stress corrosion cracking Through Wall Leak Scaffolding |
ML20217J589 | 7 October 1997 | Safety Evaluation Related to Reactor Pressure Vessel Pressurized Thermal Shock for Beaver Valley Power Station, Unit 1 | |
ML20211D844 | 17 September 1997 | SER Approving SG 90-day Rept Submitted by Duquesne Light Co for Beaver Valley Power Station,Unit 1,per GL 95-05 | |
ML20216J586 | 4 September 1997 | Safety Evaluation Re Third 10-year IST Program.Approves Valve Relief Requests 1,3 & 4.Valve Relief Request 2 Not Required.Authorizes Pump Relief Requests 1,2,3 & 4 | Safe Shutdown Stroke time Incorporated by reference Power-Operated Valves |
ML20148E105 | 28 May 1997 | Safety Evaluation Supporting Amend 204 to License DPR-66 | |
ML20137X144 | 9 April 1997 | Safety Evaluation Supporting Proposed Rev to RPV Surveillance Capsule Withdrawal Schedule | |
ML20057B064 | 13 September 1993 | Safety Evaluation Granting Relief for IST of Reactor Plant Component Cooling Water Pumps of Plant | Incorporated by reference |
ML20056F356 | 12 August 1993 | Safety Evaluation Granting Licensee 930607 Request for Relief from Certain ASME Code Requirements for Temporary Repairs to Svc Water Sys | Safe Shutdown Dissimilar Metal Weld |
ML20126H760 | 30 December 1992 | Safety Evaluation Approving Valve Relief Requests VRR-27, VRR-43 & VRR-44 & Will Provide Reasonable Assurance of Operational Readiness of Valves to Perform Intended Functions.Relief Request PRR-11 Cannot Be Approved | Boric Acid Stroke time Intergranular Stress Corrosion Cracking Cold shutdown justification Power Operated Valves |
ML20127P208 | 20 November 1992 | SER Accepting Util Commitment to Entire GIP-2,including Both SQUG Commitments & Implementation Guidance | |
ML20248D768 | 29 September 1989 | Supplemental Safety Evaluation Supporting Util Actions in Response to Open Items in 890510 Safety Evaluation Re Plant Safety Monitoring Sys | |
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 | |
ML20247N356 | 30 May 1989 | SER Supporting Util Actions to Comply W/Item 4.5.3 of Generic Ltr 83-28, Reactor Trip Sys Functional Testing | |
ML20246M179 | 10 May 1989 | Safety Evaluation Re Verification & Validation Plan for Plant Safety Monitoring Sys.Hardware Design of Sys Found Acceptable.Verification & Validation Plan Found Incomplete & Unacceptable.Software Design Process Inadequate | |
ML20246D550 | 26 April 1989 | Safety Evaluation Accepting Util Submittals on Natural Circulation Cooldown for Unit | Boric Acid Shutdown Margin |
ML20245J075 | 25 April 1989 | Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively | |
ML20206G043 | 17 November 1988 | Safety Evaluation Concluding That All Issues Raised Under Item Resolved & Item 4.3 Closed | Fire Barrier |
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 Uranium Hexafluoride |
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 Uranium Hexafluoride |
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 | |
ML20153C091 | 17 August 1988 | Safety Evaluation Re Licensee 870731 Comments on Sser 5, Section 9.5.1.Fire Protection in Cable Rooms & Containment Constitutes Acceptable Deviations from Branch Technical Position Cmeb 9.5-1 | Safe Shutdown Boric Acid |
ML20205T002 | 10 August 1988 | SER Accepting Util 831104,840330 & 870504 Responses to Item 2.2.1 of Generic Ltr 83-28 Re Equipment Classification Programs for All safety-related Components | |
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 | |
ML20154R445 | 31 May 1988 | Safety Evaluation Re Compliance W/Atws Rule 10CFR50.62.Util Proposed Design Acceptable Subj to Final Resolution of Tech Spec Issue | Anticipated operational occurrence |
ML20154P434 | 24 May 1988 | Safety Evaluation Concluding That Proposed Tech Spec Change Acceptable.No Amend Issued Since Conditions Resulting in Need for Amend to License NPF-73 No Longer Exist | |
ML20154H217 | 18 May 1988 | Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program | |
ML20154F990 | 12 May 1988 | Supplemental Safety Evaluation Concluding That Licensee 880322 Response to Open Issues Identified in 860722 Draft Technical Evaluation Rept of 840330 Submittal Re Salem ATWS Event Action Item 1.2, Post-Trip Review Satisfactory | Incorporated by reference |
ML20154F984 | 12 May 1988 | Supplemental Safety Evaluation Concluding That Licensee 851114 Response to Open Issues Noted in 851017 Draft Technical Evaluation Rept of 831104 Submittal Re Salem ATWS Event Action Item 1.2, Post-Trip Review Satisfactory | Incorporated by reference |
ML20153B629 | 25 April 1988 | Safety Evaluation Granting Util 870616 & 871110 Requests for Inservice Insp Relief for Welds on Nonregenerative Hxs,Per 10CFR50.55a(g)(6)(i) | Scaffolding |
ML20148K523 | 18 March 1988 | Safety Evaluation Supporting Util Inservice Testing Program & Requests for Relief | Stroke time High Energy Line Break Cold shutdown justification Power Operated Valves |
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 | |
ML20234E053 | 8 December 1987 | Safety Evaluation Accepting Design Changes to Be Implemented During Unit 1 Cycle 7 Fuel Reload.Tech Spec Change Unnecessary | Shutdown Margin |
ML20236X494 | 9 November 1987 | Safety Evaluation Granting Util 860617 Relief Request from Performing Volumetric & Visual Exam Requirements of ASME Section XI for Reactor Coolant Pumps Casing Welds & Internal Surfaces | Hydrostatic VT-2 |