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Issue date | Title | Topic | |
---|---|---|---|
ML20212J050 | 21 September 1999 | Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 | Safe Shutdown Ultimate heat sink Safe Shutdown Earthquake Earthquake |
ML20210L866 | 2 August 1999 | Safety Evaluation Accepting License 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs | Stroke time |
ML20195K148 | 16 June 1999 | Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety | Stroke time Incorporated by reference |
ML20205Q529 | 16 April 1999 | SER Concluding That Quad Cities Nuclear Power Station,Unit 1,can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained | Weld Overlay |
ML20205J601 | 7 April 1999 | Safety Evaluation Accepting Proposed Merger of Calenergy Co, Inc & Midamerican Holdings Co for Quad Cities Nuclear Power Station,Units 1 & 2 | |
ML20196D965 | 30 November 1998 | Safety Evaluation Supporting Relief Requests CR-21 & CR-24, Respectively.Relief Request CR-23,proposed Alternative May Be Authorized,Per 10CFR50.55a & Relief Request CR-22 Was Withdrawn by Licensee | VT-2 |
ML20196A976 | 20 November 1998 | Safety Evaluation Re Licensee 180-day Response to GL 95-07, Thermal Binding of Safety-Related Power-operated Gate Valves | Power-Operated Valves Backfit |
ML20151T271 | 4 September 1998 | Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002 | Coatings Foreign Material Exclusion |
ML20216F022 | 6 March 1998 | Safety Evaluation Accepting Request Re Temporary Use of Current Procedure for Containment Repair & Replacement Activities at Plant | |
ML20197B917 | 23 July 1997 | Safety Evaluation Re Concrete Expansion Anchor Safety Factors for High Energy Line Break Restraints | Safe Shutdown Earthquake Operating Basis Earthquake |
ML20141E509 | 16 May 1997 | Safety Evaluation Supporting TR EMF-96-051(P), Application of Anfb Critical Power Correlation to Coresident GE Fuel for Plant,Unit 2 Cycle 15 | Anticipated operational occurrence |
ML20137G607 | 13 March 1997 | Safety Evaluation Supporting Proposed Changes to TS & Bases Ceco | Reactor Vessel Water Level Abnormal operational transient Fuel cladding |
ML20134H760 | 7 February 1997 | Safety Evaluation Approving Rev 65c of Ceco QA TR CE-1-A | |
ML20149F415 | 4 August 1994 | Safety Evaluation Concluding That Unit 1 Can Be Safely Operated During Next Operating Cycle (Cycle 14) | |
ML20058L271 | 8 December 1993 | Safety Evaluation Finding Overlay Repair of Weld 02C-F7 Acceptable & in Conformance W/Gl 88-01.Plant May Be Returned to Safe Operation | Weld Overlay |
ML20056C460 | 17 June 1993 | Safety Evaluation Accepting Proposed Repair of Weld in Recirculation Piping Sys for One Cycle of Operation | Weld Overlay Hydrostatic Liquid penetrant |
ML20128F973 | 10 February 1993 | Safety Evaluation Granting Licensee 910930 Request Not to Perform Code Exam on 100% of Attachment Welds on Stabilizer Brackets to Reactor Vessel Under 10CFR50.55(a)(3)(ii) | Incorporated by reference |
ML20055F922 | 17 July 1990 | Safety Evaluation Supporting Util Responses to NRC Bulletin 88-010 Re Molded Case Circuit Breaker Replacement | |
ML20248J243 | 3 October 1989 | Safety Evaluation Accepting Util 880122,0601,0714 & 0816 Submittals Re Insp Results,Mitigation,Flaw Evaluations & Overlay Repairs of Welds Susceptible to IGSCC to Support Operation of Unit 2,for Another 18-month Fuel Cycle | Weld Overlay Nondestructive Examination |
ML20246K161 | 24 August 1989 | Revised SER Supporting Amends 112 & 108 to Licenses DPR-29 & DPR-30,respectively,changing Setpoints of Main Steam Line Radiation Monitors & Correcting Typos in Tech Specs | |
ML20248B891 | 6 June 1989 | Safety Evaluation Concluding That IGSCC Insp Scope for Class 1 Piping Meets NRC Requirements & Guidelines of Generic Ltr 84-11 | Weld Overlay Nondestructive Examination |
ML20151X343 | 16 August 1988 | SER Accepting Basis & Findings That Util post-accident Monitoring Instrumentation Meets Guidelines of Reg Guide 1.97 Except for Variable Neutron Flux Instrumentation | Scram Discharge Volume |
ML20151M690 | 21 July 1988 | Revised Safety Evaluation Supporting Exemption Requests from Regulatory Requirements of 10CFR50,App R,Section Iii.G | Safe Shutdown Fire Barrier Coatings Exemption Request Early Warning Fire Detection |
ML20195E209 | 9 June 1988 | Safeguards Evaluation Rept Supporting Amends 108 & 103 to Licenses DPR-29 & DPR-30,respectively | |
ML20151U120 | 20 April 1988 | Revised Safety Evaluation Accepting Util Interim Compensatory Measures & Request for Exemption from 10CFR50, App R,Section Iii.G Requirement Re Hot Shutdown Repair for Fire Event in Plant | Safe Shutdown Emergency Lighting Exemption Request |
ML20149M530 | 11 December 1987 | Marked-up Safety Evaluation Supporting Request for Exemptions from App R | Safe Shutdown Fire Barrier Coatings Exemption Request Early Warning Fire Detection |
ML20236W485 | 1 December 1987 | Safety Evaluation Accepting Proposed Approaches for Resolving fire-related Concerns,Including Spurious Operations,High Impedance Faults & Electrical Isolation Deficiency.Granting of Exemption Requests Recommended | Safe Shutdown Emergency Lighting Exemption Request |
ML20235S854 | 2 October 1987 | Safety Evaluation Supporting Interim Approval of Rev 3 to Process Control Program for Plant | Process Control Program |
ML20237H706 | 19 August 1987 | SER Supporting Util Response to Item 2.1 (Part 1) of Generic Ltr 83-28 Re Equipment Classification.Licensee Statements Confirm Program Exists for Identifying,Classifying & Treating Components as safety-related.Program Acceptable | |
ML20236H134 | 27 July 1987 | Safety Evaluation Re Acceptance of Updated Rev 11 to Offsite Dose Calculation Manual | Grab sample Offsite Dose Calculation Manual |
ML20205H135 | 23 March 1987 | Safety Evaluation Re Insps for & Repairs of Igscc.Facility Can Be Safely Operated for One 18-month Fuel Cycle in Present Configuration | Weld Overlay Nondestructive Examination Liquid penetrant |
ML20214X111 | 26 November 1986 | Safety Evaluation Supporting Util Analytical Methods Used to Evaluate Stresses of Critical Components for Vacuum Breaker Integrity Re Mark I Containment Program | |
ML20214Q385 | 17 November 1986 | Safety Evaluation Re Insp & Repair of Reactor Coolant Piping Sys | Weld Overlay Nondestructive Examination |
ML20141D229 | 31 March 1986 | Safety Evaluation Granting Util Request for Relief from Certain Requirements of Section XI of ASME Code Re Inservice Insp for Second 10-yr Interval | Hydrostatic |
ML20141P049 | 13 March 1986 | Safety Evaluation Supporting Licensee 831105 & 851219 Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review (Data & Info Capability) | |
ML20137A393 | 7 January 1986 | Safety Evaluation Supporting Reactor Coolant Piping Sys IGSCC Insp & Repair Per Generic Ltr 84-11 & Return to Operation for 18-month Cycle | Weld Overlay Hydrostatic Nondestructive Examination Liquid penetrant |
ML20133F029 | 30 July 1985 | Safety Evaluation Accepting Util 831105 & 850605 Responses to Generic Ltr 83-28,Item 1.1 Re post-trip Review (Program Description & Procedure) | |
ML20126F456 | 31 May 1985 | Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 Re post-maint Testing Verification | |
ML20062B835 | 28 July 1982 | Safety Evaluation Supporting Plant Compliance W/Esf Reset Controls Per NRC Criteria | |
ML20126C346 | 20 March 1980 | Safety Evaluation Supporting Amend 51 to License DPR-30 | Abnormal operational transient |
ML20235D097 | 30 December 1966 | Safety Evaluation Supporting Util 660531 Proposal to Const & Operate Single Cycle BWR of 2,255 Mwt | Safe Shutdown |