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 Issue dateTitleTopic
ML20205L0409 April 1999SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2Boric Acid
Nondestructive Examination
VT-2
Incorporated by reference
Dissimilar Metal Weld
ML20203E11810 February 1999SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description
ML20199F53429 December 1998Safety 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-C6.10-1Boric Acid
VT-2
Incorporated by reference
ML20198K85521 December 1998SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1Incorporated by reference
ML20198A1639 December 1998SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) RequestSafe Shutdown
Safe Shutdown Earthquake
Nondestructive Examination
Design basis earthquake
Earthquake
ML20195J31312 November 1998Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for ReliefVT-2
Incorporated by reference
ML20154R91220 October 1998Safety 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
ML20154P74919 October 1998SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1Incorporated by reference
ML20154C6711 October 1998Safety 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 AmpacityFire Barrier
Aging Management
ML20202B85718 November 1997SE Approving Relief Requests for Second 10-Yr Interval for Pumps & Valves Inservice Testing Program for Beaver Valley Power Station,Unit 2Boric Acid
Stroke time
Incorporated by reference
Cold shutdown justification
Power-Operated Valves
ML20199F46413 November 1997SER Related to Reactor Pressure Vessel,Pressurized Thermal Shock Assessment for Beaver Valley Power Station,Unit 2
ML20212G49628 October 1997SER Accepting Pressurized Thermal Shock Assessment for Beaver Valley Unit 2 Reactor Vessel
ML20217J5318 October 1997Safety Evaluation Re First,Second & Third 10-year Interval Inservice Inspection Program Plan Requests for Relief for Plant,Units 1 & 2Boric Acid
VT-2
Incorporated by reference
Through Wall Leak
Scaffolding
ML20217J5897 October 1997Safety Evaluation Related to Reactor Pressure Vessel Pressurized Thermal Shock for Beaver Valley Power Station, Unit 1
ML20211D84417 September 1997SER Approving SG 90-day Rept Submitted by Duquesne Light Co for Beaver Valley Power Station,Unit 1,per GL 95-05
ML20216J5864 September 1997Safety 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 & 4Safe Shutdown
Stroke time
Incorporated by reference
Power-Operated Valves
ML20148E10528 May 1997Safety Evaluation Supporting Amend 204 to License DPR-66
ML20137X1449 April 1997Safety Evaluation Supporting Proposed Rev to RPV Surveillance Capsule Withdrawal Schedule
ML20057B06413 September 1993Safety Evaluation Granting Relief for IST of Reactor Plant Component Cooling Water Pumps of PlantIncorporated by reference
ML20056F35612 August 1993Safety Evaluation Granting Licensee 930607 Request for Relief from Certain ASME Code Requirements for Temporary Repairs to Svc Water SysSafe Shutdown
Dissimilar Metal Weld
ML20126H76030 December 1992Safety 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 ApprovedBoric Acid
Stroke time
Cold shutdown justification
Power Operated Valves
ML20127P20820 November 1992SER Accepting Util Commitment to Entire GIP-2,including Both SQUG Commitments & Implementation Guidance
ML20248D76829 September 1989Supplemental Safety Evaluation Supporting Util Actions in Response to Open Items in 890510 Safety Evaluation Re Plant Safety Monitoring Sys
ML20247N35630 May 1989SER Supporting Util Actions to Comply W/Item 4.5.3 of Generic Ltr 83-28, Reactor Trip Sys Functional Testing
ML20246M17910 May 1989Safety 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
ML20246D55026 April 1989Safety Evaluation Accepting Util Submittals on Natural Circulation Cooldown for UnitBoric Acid
Shutdown Margin
ML20206G04317 November 1988Safety Evaluation Concluding That All Issues Raised Under Item Resolved & Item 4.3 ClosedFire Barrier
ML20153C09117 August 1988Safety 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 9.5-1Safe Shutdown
Boric Acid
ML20205T00210 August 1988SER 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
ML20154R44531 May 1988Safety Evaluation Re Compliance W/Atws Rule 10CFR50.62.Util Proposed Design Acceptable Subj to Final Resolution of Tech Spec IssueAnticipated operational occurrence
ML20154P43424 May 1988Safety 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
ML20154F98412 May 1988Supplemental 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 SatisfactoryIncorporated by reference
ML20154F99012 May 1988Supplemental 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 SatisfactoryIncorporated by reference
ML20153B62925 April 1988Safety Evaluation Granting Util 870616 & 871110 Requests for Inservice Insp Relief for Welds on Nonregenerative Hxs,Per 10CFR50.55a(g)(6)(i)Scaffolding
ML20148K52318 March 1988Safety Evaluation Supporting Util Inservice Testing Program & Requests for ReliefStroke time
Cold shutdown justification
Power Operated Valves
ML20234E0538 December 1987Safety Evaluation Accepting Design Changes to Be Implemented During Unit 1 Cycle 7 Fuel Reload.Tech Spec Change UnnecessaryShutdown Margin
ML20236X4949 November 1987Safety Evaluation Granting Util 860617 Relief Request from Performing Volumetric & Visual Exam Requirements of ASME Section XI for Reactor Coolant Pumps Casing Welds & Internal SurfacesHydrostatic
VT-2
ML20237B16521 October 1987Safety Evaluation Supporting Elimination of Primary Component Support Snubbers from Primary Coolant LoopsDesign basis earthquake
Earthquake
ML20204H71818 March 1987Interim Safety Evaluation Re Pump & Valve Operability Assurance (SER Confirmatory Issue 13).Pages from Pvort Audit EnclSafe Shutdown
ML20206G22312 March 1987SER Accepting Licensee Request to Use Damping Values from ASME Code Case N-411 Per Conditions Outlined in UtilSafe Shutdown
Design basis earthquake
Earthquake
ML20207P6552 January 1987SER Accepting Licensee Compliance W/Generic Ltr 83-28,Item 2.1,Part 2 Re Vendor Interface Program for Reactor Trip Sys (RTS) Components & Item 4.5.2 Concerning RTS Online Reliability Testing
ML20212B01130 November 1986Safety Evaluation Granting Util Request for Exemptions from App R Requirements Re Separation of Cables & Equipment & Associated CircuitsSafe Shutdown
Fire Barrier
Coatings
Emergency Lighting
Exemption Request
Fire Protection Program
ML20205G44931 August 1986Safety Evaluation Accepting Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events
ML20204G92831 July 1986Safety Evaluation Supporting Util 860502 Submittal of Westinghouse Reload Safety Evaluation,Beaver Valley Nuclear Plant,Unit 1 Cycle 6Shutdown Margin
ML20203G23728 July 1986Interim SER Re Dcrdr Summary Rept & Preimplementation Audit on 860211 & 12.Requirements of Suppl 1 to NUREG-0737 Generally Satisfied.Several Items Remain to Be Completed
ML20206H49319 June 1986Safety Evaluation on Generic Ltr 83-28,Item 4.2.3 & 4.2.4, Preventive Maint Program for Reactor Trip Breakers/Life Testing. Licensee Position Unacceptable
ML20205N11522 April 1986Interim Rept Re Review of Util Response to Generic Ltr 85-12 on Reactor Coolant Pump Trip Criteria.Addl Info Required
ML20202C5723 April 1986Sser Accepting Util 860304 Response to Generic Ltr 83-28, Item 4.3, Seismic Qualification of Shunt Trip Components
ML20214E36317 March 1986Safety Evaluation Supporting Amend 2 to CPPR-105
ML20154N74510 March 1986Safety Evaluation Supporting Util 850819 Request to Withdraw Original Commitment to Provide Steam Leakage Collection Sys Around Certain Steam Valves