Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
ML20212J05021 September 1999Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1Safe Shutdown
Ultimate heat sink
Safe Shutdown Earthquake
Earthquake
ML20210L8662 August 1999Safety Evaluation Accepting License 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related MovsStroke time
ML20195K14816 June 1999Safety 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 & SafetyStroke time
Incorporated by reference
ML20205Q52916 April 1999SER 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 MaintainedWeld Overlay
ML20205J6017 April 1999Safety Evaluation Accepting Proposed Merger of Calenergy Co, Inc & Midamerican Holdings Co for Quad Cities Nuclear Power Station,Units 1 & 2
ML20196D96530 November 1998Safety 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Respectively.Relief Request CR-23,proposed Alternative May Be Authorized,Per 10CFR50.55a & Relief Request CR-22 Was Withdrawn by LicenseeVT-2
ML20196A97620 November 1998Safety Evaluation Re Licensee 180-day Response to GL 95-07, Thermal Binding of Safety-Related Power-operated Gate ValvesPower-Operated Valves
Backfit
ML20151T2714 September 1998Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002Coatings
Foreign Material Exclusion
ML20216F0226 March 1998Safety Evaluation Accepting Request Re Temporary Use of Current Procedure for Containment Repair & Replacement Activities at Plant
ML20197B91723 July 1997Safety Evaluation Re Concrete Expansion Anchor Safety Factors for High Energy Line Break RestraintsSafe Shutdown Earthquake
Operating Basis Earthquake
ML20141E50916 May 1997Safety Evaluation Supporting TR EMF-96-051(P), Application of Anfb Critical Power Correlation to Coresident GE Fuel for Plant,Unit 2 Cycle 15Anticipated operational occurrence
ML20137G60713 March 1997Safety Evaluation Supporting Proposed Changes to TS & Bases CecoReactor Vessel Water Level
Abnormal operational transient
Fuel cladding
ML20134H7607 February 1997Safety Evaluation Approving Rev 65c of Ceco QA TR CE-1-A
ML20149F4154 August 1994Safety Evaluation Concluding That Unit 1 Can Be Safely Operated During Next Operating Cycle (Cycle 14)
ML20058L2718 December 1993Safety Evaluation Finding Overlay Repair of Weld 02C-F7 Acceptable & in Conformance W/Gl 88-01.Plant May Be Returned to Safe OperationWeld Overlay
ML20056C46017 June 1993Safety Evaluation Accepting Proposed Repair of Weld in Recirculation Piping Sys for One Cycle of OperationWeld Overlay
Hydrostatic
Liquid penetrant
ML20128F97310 February 1993Safety 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
ML20055F92217 July 1990Safety Evaluation Supporting Util Responses to NRC Bulletin 88-010 Re Molded Case Circuit Breaker Replacement
ML20248J2433 October 1989Safety 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 CycleWeld Overlay
Nondestructive Examination
ML20246K16124 August 1989Revised 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
ML20248B8916 June 1989Safety Evaluation Concluding That IGSCC Insp Scope for Class 1 Piping Meets NRC Requirements & Guidelines of Generic Ltr 84-11Weld Overlay
Nondestructive Examination
ML20151X34316 August 1988SER Accepting Basis & Findings That Util post-accident Monitoring Instrumentation Meets Guidelines of Reg Guide 1.97 Except for Variable Neutron Flux InstrumentationScram Discharge Volume
ML20151M69021 July 1988Revised Safety Evaluation Supporting Exemption Requests from Regulatory Requirements of 10CFR50,App R,Section Iii.GSafe Shutdown
Fire Barrier
Coatings
Exemption Request
Early Warning Fire Detection
ML20195E2099 June 1988Safeguards Evaluation Rept Supporting Amends 108 & 103 to Licenses DPR-29 & DPR-30,respectively
ML20151U12020 April 1988Revised 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 PlantSafe Shutdown
Emergency Lighting
Exemption Request
ML20149M53011 December 1987Marked-up Safety Evaluation Supporting Request for Exemptions from App RSafe Shutdown
Fire Barrier
Coatings
Exemption Request
Early Warning Fire Detection
ML20236W4851 December 1987Safety Evaluation Accepting Proposed Approaches for Resolving fire-related Concerns,Including Spurious Operations,High Impedance Faults & Electrical Isolation Deficiency.Granting of Exemption Requests RecommendedSafe Shutdown
Emergency Lighting
Exemption Request
ML20235S8542 October 1987Safety Evaluation Supporting Interim Approval of Rev 3 to Process Control Program for PlantProcess Control Program
ML20237H70619 August 1987SER 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
ML20236H13427 July 1987Safety Evaluation Re Acceptance of Updated Rev 11 to Offsite Dose Calculation ManualGrab sample
Offsite Dose Calculation Manual
ML20205H13523 March 1987Safety Evaluation Re Insps for & Repairs of Igscc.Facility Can Be Safely Operated for One 18-month Fuel Cycle in Present ConfigurationWeld Overlay
Nondestructive Examination
Liquid penetrant
ML20214X11126 November 1986Safety Evaluation Supporting Util Analytical Methods Used to Evaluate Stresses of Critical Components for Vacuum Breaker Integrity Re Mark I Containment Program
ML20214Q38517 November 1986Safety Evaluation Re Insp & Repair of Reactor Coolant Piping SysWeld Overlay
Nondestructive Examination
ML20141D22931 March 1986Safety Evaluation Granting Util Request for Relief from Certain Requirements of Section XI of ASME Code Re Inservice Insp for Second 10-yr IntervalHydrostatic
ML20141P04913 March 1986Safety Evaluation Supporting Licensee 831105 & 851219 Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review (Data & Info Capability)
ML20137A3937 January 1986Safety Evaluation Supporting Reactor Coolant Piping Sys IGSCC Insp & Repair Per Generic Ltr 84-11 & Return to Operation for 18-month CycleWeld Overlay
Hydrostatic
Nondestructive Examination
Liquid penetrant
ML20133F02930 July 1985Safety Evaluation Accepting Util 831105 & 850605 Responses to Generic Ltr 83-28,Item 1.1 Re post-trip Review (Program Description & Procedure)
ML20126F45631 May 1985Safety 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
ML20062B83528 July 1982Safety Evaluation Supporting Plant Compliance W/Esf Reset Controls Per NRC Criteria
ML20126C34620 March 1980Safety Evaluation Supporting Amend 51 to License DPR-30Abnormal operational transient
ML20235D09730 December 1966Safety Evaluation Supporting Util 660531 Proposal to Const & Operate Single Cycle BWR of 2,255 MwtSafe Shutdown