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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20217G019 | 15 October 1999 | Safety Evaluation Concluding That Licensee Followed Analytical Methods Provided in GL 90-05.Grants Relief Until Next Refueling Outage,Scheduled to Start on 991001.Temporary non-Code Repair Must Then Be Replaced with Code Repair | |
| ML20212L088 | 4 October 1999 | SER Accepting Licensee Requests for Relief 98-012 to 98-018 Related to Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp for Crystal River Unit 3 | Coatings Nondestructive Examination VT-2 |
| ML20212J863 | 1 October 1999 | Safety Evaluation Supporting Licensee Proposed Alternatives to Provide Reasonable Assurance of Structural Integrity of Subject Welds & Provide Acceptable Level of Quality & Safety.Relief Granted Per 10CFR50.55a(g)(6)(i) | Incorporated by reference |
| ML20212E691 | 21 September 1999 | Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 | Safe Shutdown Reactor Vessel Water Level |
| ML20210P111 | 5 August 1999 | SER Accepting Evaluation of Third 10-year Interval Inservice Insp Program Requests for Relief for Plant,Unit 3 | Boric Acid Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Dissimilar Metal Weld Scaffolding |
| ML20203A438 | 3 February 1999 | Safety Evaluation Supporting EAL Changes for License DPR-72, Per 10CFR50.47(b)(4) & App E to 10CFR50 | Safe Shutdown |
| ML20236Q461 | 30 June 1998 | SER for Crystal River Power Station,Unit 3,individual Plant Exam (Ipe).Concludes That Plant IPE Complete Re Info Requested by GL 88-20 & IPE Results Reasonable Given Plant Design,Operation & History | Mission time |
| ML20216G809 | 10 April 1998 | Safety Evaluation Accepting Resolution of Crystal River Restart Issues Related to USI A-46 Program | Safe Shutdown Operability Assessment |
| ML20199A144 | 9 January 1998 | Safety Evaluation Accepting Relief Request for Delayed Implementation of 10CFR50.55a,until 971231 or Plant Restart, Whichever Occurs First | Nondestructive Examination |
| ML20199D056 | 14 November 1997 | Safety Evaluation Approving Ampacity Derating Test Results for Crystal River,Unit 3 Related to GL 92-08, Thermo-Lag 330-1 Fire Barriers | Fire Barrier |
| ML20212C375 | 16 October 1997 | SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves | Backfit |
| ML20217D756 | 1 October 1997 | Safety Evaluation Concluding That Testing of Ingersoll-Dresser Pump Model 8HN194 at Test Facility Demonstrates That Crystal River Decay Heat Pumps of Same Model Can Operate at Flows of 100 Gpm for 30 Days | Non-Destructive Examination Mission time |
| ML20138J015 | 5 May 1997 | Safety Evaluation Approving Request for Relief 95-050,Rev 1, for Plant,Unit 3 | Incorporated by reference |
| ML20138E441 | 30 April 1997 | Safety Evaluation on ASME Code Case N-509 for Crystal River Nuclear Plant,Unit 3 | Incorporated by reference |
| ML20140F377 | 28 April 1997 | Safety Evaluation Supporting Staff Evaluation of Plant, Unit 3 Nuclear Generating Plant IPE | Probabilistic Risk Assessment |
| ML20134B709 | 29 January 1997 | SER Accepting Fire Barrier Sys Relied by Licensee to Meet NRC Fire Protection Requirements for Following Raceway Types & Sizes | Safe Shutdown Fire Barrier |
| ML20133N651 | 22 January 1997 | Safety Evaluation Accepting Licensee Request to Use Code Case N-524 as Alternative to ASME Code Section XI for Plant | Incorporated by reference |
| ML20149M680 | 17 January 1997 | Safety Evaluation Accepting Licensee 960807 Results of Analyses Re Operability Evaluation of Main Steam Sys W/Bent Rod Hangers at Plant | |
| ML20133D347 | 6 January 1997 | Safety Evaluation Supporting Amend 155 to License DPR-72 | |
| ML20058P198 | 16 December 1993 | Safety Evaluation Accepting Ground Response Spectra Utilized & Approaches Used in Development of Floor Response Spectra for Resolution of USI A-46 | Safe Shutdown Earthquake Earthquake |
| ML20138D594 | 9 February 1993 | Safety Evaluation Granting Relief from Repair Requirements of ASME Code Section XI in Order to Perform Temporary Noncode Repair to 18 Inch Portion of Nuclear Closed Cycle Cooling Sys | |
| ML20126F781 | 22 December 1992 | Safety Evaluation to Confirm Granting of Request for Relief from ASME Code Repair Requirements Nuclear Closed Cycle Cooling Sys | Time of Discovery Hydrostatic |
| ML20056B534 | 23 August 1990 | Safety Evaluation Re Station Blackout.Recommends That Util Reevaluate Areas of Nonconformance W/Station Blackout Guidance Identified in Evaluation.Subj to Acceptable Resolution of NRC Recommendations,Issue Remains Open | Safe Shutdown Battery sizing |
| ML20055E514 | 2 July 1990 | Safety Evaluation Re Util 831104 & 840731 Responses to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components | Safe Shutdown |
| ML20245F656 | 22 June 1989 | Safety Evaluation Supporting Amend 118 to License DPR-72 | |
| ML20245D300 | 14 June 1989 | Safety Evaluation Concluding That Licensee Meets NRC Position on Item 4.5.2 of Generic Ltr 83-28,based on Finding That Facility Will Be Designed to Permit on-line Functional Testing of Reactor Trip Sys,Including Stated Testing | |
| ML20247D495 | 19 May 1989 | Safety Evaluation Re TMI Action Item II.K.3.31 Concerning plant-specific Calculations to Show Compliance w/10CFR50.46 | |
| ML20245A616 | 19 April 1989 | Safety Evaluation Supporting Util 890210 Final ATWS Design Description | Anticipated operational occurrence |
| ML20155F264 | 6 October 1988 | Safety Evaluation Supporting Relief from Inservice Testing Program | |
| ML20154A742 | 29 April 1988 | Evaluation of Auxiliary Feedwater Sys Reliability (Generic Issue 124).Licensee Should Consider Listed Addl Recommendations for Improved Plant Performance & Auxiliary Feedwater Sys Challenge Rate Reduction | Anticipated operational occurrence Safe Shutdown Earthquake Emergency Lighting Overspeed trip |
| ML20234D522 | 16 June 1987 | Safety Evaluation Re Conformance to Reg Guide 1.97 | Grab sample |
| ML20214Q773 | 29 May 1987 | Ser:Pump & Valve Inservice Testing Program,Crystal River Nuclear Power Station,Unit 3,for Remainder of First 10-Yr Interval | Stroke time Power-Operated Valves Power Operated Valves |
| ML20214M178 | 26 May 1987 | Safety Evaluation Granting Util 860324 & 870114 Requests for Relief from Certain Requirements of ASME Code Section XI & to Use ANSI N45.2.6-1978 in Lieu of ASME Code Requirement of ANSI N45.2.6-1973 | Hydrostatic VT-2 |
| ML20211N266 | 19 February 1987 | Evaluation of Licensee Response to Insp Rept 50-302/86-12. Procedure AI-401 Found to Be Inadequate & Resulted in Restatement of Violation 2.Design Error Could Cause Loss of RHR Ability | Safe Shutdown Fire Barrier Fire Watch |
| ML20211Q297 | 18 February 1987 | Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) for Prairie Island Units 1 & 2 | Probabilistic Risk Assessment Emergency Lighting |
| ML20211B552 | 9 February 1987 | Safety Evaluation Re Rev 7 to Offsite Dose Calculation Manual (ODCM) & Rev 0 to Process Control Program (Pcp).Odcm & PCP Acceptable Refs for Use W/Tech Specs for Assuring Compliance w/10CFR20 & 50,App a & I | Boric Acid Offsite Dose Calculation Manual Process Control Program |
| ML20209H705 | 16 January 1987 | Safety Evaluation of Util 831104,840116 & 0731 Responses to Generic Ltr 83-28,Item 4.4 Re safety-related Maint & Test Procedures for Diverse Reactor Trip Feature.Responses Acceptable | |
| ML20207Q645 | 9 January 1987 | Safety Evaluation Supporting Util 831104,840116 & 0731 Responses to Generic Ltr 83-28,Item 4.4 Re Maint & Test Procedures for Silicon Controlled Rectifiers | |
| ML20214N194 | 4 September 1986 | Safety Evaluation Supporting Licensee 860117 Response to 10CFR50.61 Re Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events | |
| ML20205T530 | 9 June 1986 | SER Supporting Responses to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Re Reactor Trip Sys Reliability | |
| ML20211D625 | 9 June 1986 | SER Supporting Responses to Generic Ltr 81-21 Re Natural Circulation Cooldown | |
| ML20210R953 | 2 May 1986 | SER Supporting Util Response to IE Bulletin 80-11 Re Masonry Wall design.Safety-related Masonry Walls Will Withstand Specified Design Load Conditions W/O Impairment of Wall Integrity.Technical Evaluation Rept Encl | |
| ML20133Q127 | 24 October 1985 | SER Re Generic Ltr 83-28,Item 1.1 Post-Trip Review Program Description & Procedure. Util 831104 Response to Generic Ltr 83-28 Does Not Meet Guidelines for post-trip Review. Acceptable Responses Required | |
| ML20135F887 | 11 September 1985 | SER Re Control Complex Dedicated Cooling Sys for post-fire Alternate Shutdown Capability.Design of Control Complex Dedicated Cooling Sys Meets Requirements of Section III.G.3 & Iii.L of 10CFR50 App R & Acceptable | Safe Shutdown |
| ML20135G105 | 9 September 1985 | SER Supporting Licensee Response to Items 3.1.1,3.1.2,3.2.1, 3.2.2,4.1 & 4.5.1 of Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events | |
| ML20135E613 | 6 September 1985 | SER Re Licensee Response to Generic Ltr 83-28,Item 1.2 Re post-trip Review (Data & Info Capability).Licensee Program for Data Retention Conforms to Guidelines of Section Ii.D & Acceptable | |
| ML20214J291 | 20 December 1979 | Safety Evaluation Re Preliminary Design for safety-grade Anticipatory Reactor Trips on Loss of Main Feedwater &/Or Turbine Trip |