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| Issue date | Title | Topic | |
|---|---|---|---|
| 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 |
| ML20057B064 | 13 September 1993 | Safety Evaluation Granting Relief for IST of Reactor Plant Component Cooling Water Pumps of Plant | Incorporated by reference |
| ML20058F380 | 29 June 1982 | Safety Evaluation Listing Determinations Made Re Requests for Relief from Inservice Testing Requirements for Pumps & Valves | |
| ML20062H228 | 4 August 1982 | Safety Evaluation Accepting Util Responses to IE Bulletin 80-04, Main Steam Line Break W/Continued Feedwater Addition | Boric Acid Shutdown Margin |
| 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 Cold shutdown justification Power Operated Valves |
| ML20127P208 | 20 November 1992 | SER Accepting Util Commitment to Entire GIP-2,including Both SQUG Commitments & Implementation Guidance | |
| ML20128G000 | 23 July 1984 | Safeguards SER Supporting Rev 0 to Physical Security & Safeguards Contingency Plan & Rev 0 to Training & Qualification Plan Dtd 830728.Info Deleted.Salp Input Encl | |
| ML20128G341 | 31 March 1985 | SER Re Effects of Local Flooding at Facility.Flooding from Peggs Run Will Not Affect Safe Operation of Facility | Backfit |
| ML20128L695 | 20 May 1985 | SER Supporting Util 850131 Alternative Plan for Preservice Exam of ASME Class 2 Piping | |
| ML20129D097 | 31 May 1985 | Safety Evaluation Supporting Elimination of Arbitrary Intermediate Pipe Breaks.Pipe Rupture Postulation & Associated Effects Adequately Considered in Plant Design | Operating Basis Earthquake |
| ML20137S078 | 21 November 1985 | Safety Evaluation Supporting Util Responses to ATWS Action Items 3.1.1,3.1.2,3.2.1,3.2.2,4.1 & 4.5.1 of Generic Ltr 83-28 | |
| ML20137X144 | 9 April 1997 | Safety Evaluation Supporting Proposed Rev to RPV Surveillance Capsule Withdrawal Schedule | |
| ML20138E841 | 3 December 1985 | Safety Evaluation Supporting Amend 98 to License DPR-66 | |
| ML20138K947 | 9 October 1985 | Supplemental Safety Evaluation Accepting 850510 Response to Generic Ltr 83-28,Item 4.3 Re Design for Automatic Actuation of Reactor Trip Breaker Shunt Trip Attachments.Proposed Tech Specs Requested,Per Generic Ltr 85-09 | |
| ML20138K958 | 8 October 1985 | Safety Evaluation Accepting Util 850617 Response to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Re 18-month Preventive Maint Frequency for Reactor Trip Breakers | Incorporated by reference |
| ML20138S055 | 30 November 1985 | SER Supporting Util Responses to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Test Requirements | |
| ML20148E105 | 28 May 1997 | Safety Evaluation Supporting Amend 204 to License DPR-66 | |
| ML20148K523 | 18 March 1988 | Safety Evaluation Supporting Util Inservice Testing Program & Requests for Relief | Stroke time Cold shutdown justification Power Operated Valves |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| ML20154N745 | 10 March 1986 | Safety Evaluation Supporting Util 850819 Request to Withdraw Original Commitment to Provide Steam Leakage Collection Sys Around Certain Steam Valves | |
| 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 | |
| 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 |
| 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 |
| 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 | |
| ML20195J313 | 12 November 1998 | Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief | VT-2 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 |
| 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 |
| ML20199F464 | 13 November 1997 | SER Related to Reactor Pressure Vessel,Pressurized Thermal Shock Assessment for Beaver Valley Power Station,Unit 2 | |
| 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 |
| 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 |
| ML20202C572 | 3 April 1986 | Sser Accepting Util 860304 Response to Generic Ltr 83-28, Item 4.3, Seismic Qualification of Shunt Trip Components | |
| ML20203E118 | 10 February 1999 | SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description | |
| ML20203G237 | 28 July 1986 | Interim 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 | |
| ML20204G928 | 31 July 1986 | Safety Evaluation Supporting Util 860502 Submittal of Westinghouse Reload Safety Evaluation,Beaver Valley Nuclear Plant,Unit 1 Cycle 6 | Shutdown Margin |
| ML20204H718 | 18 March 1987 | Interim Safety Evaluation Re Pump & Valve Operability Assurance (SER Confirmatory Issue 13).Pages from Pvort Audit Encl | Safe Shutdown |
| ML20205G449 | 31 August 1986 | Safety Evaluation Accepting Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events | |
| 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 |
| ML20205N115 | 22 April 1986 | Interim Rept Re Review of Util Response to Generic Ltr 85-12 on Reactor Coolant Pump Trip Criteria.Addl Info Required | |
| 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 | |
| ML20206G043 | 17 November 1988 | Safety Evaluation Concluding That All Issues Raised Under Item Resolved & Item 4.3 Closed | Fire Barrier |
| ML20206G223 | 12 March 1987 | SER Accepting Licensee Request to Use Damping Values from ASME Code Case N-411 Per Conditions Outlined in Util | Safe Shutdown Design basis earthquake Earthquake |
| ML20206H493 | 19 June 1986 | Safety 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 | |
| ML20207P655 | 2 January 1987 | SER 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 | |
| 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 | |
| ML20212B011 | 30 November 1986 | Safety Evaluation Granting Util Request for Exemptions from App R Requirements Re Separation of Cables & Equipment & Associated Circuits | Safe Shutdown Fire Barrier Coatings Emergency Lighting Exemption Request Fire Protection Program |
| ML20212G496 | 28 October 1997 | SER Accepting Pressurized Thermal Shock Assessment for Beaver Valley Unit 2 Reactor Vessel |