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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20210B794 | 15 July 1999 | SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs | Incorporated by reference |
| ML20196C698 | 21 June 1999 | Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable | Incorporated by reference |
| ML20204H647 | 21 March 1999 | SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 | License Renewal |
| ML20203D431 | 5 February 1999 | Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons | |
| ML20199G467 | 20 January 1999 | SER Accepting USI A-46 Implementation for Plant | Safe Shutdown Operating Basis Earthquake Earthquake Scaffolding |
| ML20199F478 | 8 January 1999 | Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed | Safe Shutdown Boric Acid Power-Operated Valves Backfit |
| ML20198S759 | 7 January 1999 | SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 | |
| ML20195H100 | 16 November 1998 | Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative | |
| ML20154G393 | 5 October 1998 | Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code | |
| ML20237D498 | 19 August 1998 | Safety Evaluation Accepting Licensee Request for Extension of Second ten-year Inservice Insp Interval | Incorporated by reference |
| ML20236L752 | 6 July 1998 | Safety Evaluation Granting Bg&E 980527 Request for Relief from Requirement of Section IWA-5250 of ASME Code for Calvert Cliffs Unit 2.Alternatives Provide Reasonable Assurance of Operational Readiness | Incorporated by reference |
| ML20236F779 | 30 June 1998 | Safety Evaluation Authorizing Request for Temporary Relief from Requirement of Subsection IWA-5250 of ASME Code,Section XI for Plant,Unit 1 | Incorporated by reference |
| ML20217Q797 | 4 May 1998 | Safety Evaluation Supporting Amends 227 & 201 to Licenses DPR-53 & DPR-69,respectively | Boric Acid Shutdown Margin Offsite Dose Calculation Manual Fire Barrier Probabilistic Risk Assessment Incorporated by reference Offsite Circuit Fire Protection Program |
| ML20217P744 | 7 April 1998 | SE Accepting Licensee Request for Second 10-yr Insp Interval to Use ASME Section IX Code Case N-416-1, Alternative Pressure Test Requirement for Replacement Items by Welding, Class 1,2 & 3,Div 1 at Plant Per 10CFR50.55a(a)(3)(i) | Non-Destructive Examination Hydrostatic VT-2 Incorporated by reference Pressure boundary leak |
| ML20203E974 | 11 February 1998 | SER Accepting IST Program Requests for Relief Submitted for Third 10-yr Intervals for Pumps & Valves for Plant | Safe Shutdown |
| ML20198K374 | 5 January 1998 | Safety Evaluation Authorizing Second 10-yr ISI Interval for Plant,Units 1 & 2 Relief Request from ASME Boiler & Pressure Vessel Code Requirements to Use Performance Demonstration Initiative Program | Incorporated by reference |
| ML20197G129 | 15 December 1997 | Safety Evaluation Accepting Revised Withdrawal Schedules for Plant,Units 1 & 2 | |
| ML20134G529 | 7 February 1997 | Safety Evaluation Re Request Relief from ASME Code Requirement for Calvert Cliffs Nuclear Power Plant,Unit 1 | Boric Acid Non-Destructive Examination Incorporated by reference Liquid penetrant |
| ML20058G056 | 29 November 1993 | Safety Evaluation Granting Relief from Installation Requirements of Section Iii,Article 9 of 1968 Edition of ASME Boiler & Pressure Vessel Code for Plant | |
| ML20057C383 | 22 September 1993 | Sser Accepting Licensee 930707 Response to Station Blackout Rule,Per 10CFR50.63 | |
| ML20127C057 | 23 December 1992 | Safety Evaluation Accepting Clarification of Previous Reactor Vessel Surveillance Program Actions & Withdrawal Schedule Change for Reactor Matl Surveillance Capsule | |
| ML20128B937 | 20 November 1992 | Safety Evaluation Accepting Licensee Response to Suppl 1 to GL 87-02 | Safe Shutdown |
| IR 05000317/1990080 | 21 November 1990 | SER Determining That Load Profile Used During Surveillance Test Procedure Meets Requirement of Tech Spec 4.8.2.3.2.e, Per Unresolved Item Noted in Insp Repts 50-317/90-80 & 50-318/90-80 | |
| ML20059N225 | 1 October 1990 | Safety Evaluation Accepting Proposed Actions Re Potential Design Deficiency,Per LER 89-023 | Safe Shutdown Safe Shutdown Earthquake Operating Basis Earthquake Earthquake |
| ML20245E856 | 22 June 1989 | Safety Evaluation Supporting Util Responses to Generic Ltr 83-28, Reactor Trip Sys Reliability for All Domestic Operating Reactors | |
| ML20247D036 | 24 March 1989 | Safety Evaluation Supporting Amend 119 to License DPR-69 | Earthquake |
| ML20205P649 | 2 November 1988 | Safety Evaluation Re Compliance w/10CFR50.62 ATWS Rule. Auxiliary Feedwater Actuation Sys Designs in Conformance W/ Requirements of TMI Action Plan Item II.E.1.2,surveillance Testing,Complies W/Atws Rule | Anticipated operational occurrence |
| ML20238A314 | 24 August 1987 | Safety Evaluation of Encl Technical Evaluation Repts EGG-NTA-7243,EGG-NTA-7720 & EGG-NTA-7463 & Licensee Submittals in Response to Generic Ltr 83-28,Items 2.1.1, 2.1.2 & 4.5.2.Responses Acceptable | |
| ML20213E873 | 11 May 1987 | Safety Evaluation Supporting Util 861002 Request for Relief from Inservice Insp Requirements of ASME Code Section XI Re Peripheral CRD Housings | Incorporated by reference |
| ML20205R706 | 26 March 1987 | Safety Evaluation Supporting Relief from Certain ASME Code Hoop Stress Requirements Until Next Refueling Outage to Repair Flaw in Base Metal of Steam Generator Main Steam Line 12 | Nondestructive Examination |
| ML20210P091 | 4 February 1987 | Safety Evaluation Re Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events.Util Must Submit Reevaluation of Resistance Temp PTS | |
| ML20207P072 | 6 January 1987 | Safety Evaluation Supporting Conformance to Reg Guide 1.97 W/Noted Exceptions | |
| ML20198G697 | 22 May 1986 | Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 1.2 Re post-trip Review Data & Info Capability | |
| ML20210P280 | 6 May 1986 | Safety Evaluation Accepting Licensee Response to Items 3.1.3 & 3.2.3, Post-Maint Testing of...Safety-Related Components, of Generic Ltr 83-28 | |
| ML20202E072 | 31 March 1986 | Safety Evaluation Supporting Amend 116 to License DPR-53 | |
| ML20141N769 | 10 March 1986 | Safety Evaluation Granting Util 850913 & 860113 Requests for Relief from ASME Boiler & Pressure Vessel Code,Section XI Re Observation of Lubricant Level or Pressure During Pump Testing | |
| ML20136G737 | 14 November 1985 | Safety Evaluation Granting Relief from ASME Boiler & Pressure Vessel Code,Section XI Requirement Re Pressure Testing of Class 2 Piping Associated W/Rcs | Hydrostatic Temporary Modification |
| ML20138E282 | 10 October 1985 | Safety Evaluation Re Extended Burnup of C-E PWR Fuel. Methodologies Acceptable for Extended Burnup Application | Anticipated operational occurrence Safe Shutdown Earthquake Earthquake Fuel cladding |
| ML20137W881 | 18 September 1985 | Safety Evaluation Granting Relief from Radiographic & Visual Insp of Reactor Coolant Pump Casings | Hydrostatic Liquid penetrant |
| ML20126L824 | 18 July 1985 | Suppl to Safety Evaluation Supporting Response to IE Bulletin 80-11 Re Reevaluation of 22 Masonry Walls,Utilizing Methods Other than Energy Balance Technique | |
| ML20133E110 | 18 July 1985 | Corrected Suppl to Safety Evaluation Accepting Util 850612 Reevaluation of Masonry Wall Design Using Linear Elastic Methodology.Action Completed on IE Bulletin 80-11 | |
| ML20205B259 | 10 July 1985 | Safety Evaluation Accepting Licensee Position on Generic Ltr 83-28 Items 4.2.1 & 4.2.2 Re Reactor Trip Sys Reliability | |
| ML20127N235 | 9 May 1985 | SER Re NUREG/CR-3511, Interim Reliability Evaluation Program:Analysis of Calvert Cliffs Unit 1 Nuclear Power Plant. Use of PRA Results Out of PRA Context Clearly Inappropriate | Ultimate heat sink Probabilistic Risk Assessment |
| ML20132B873 | 21 March 1984 | SER on Multi-Plant Action C-14 Re Seismic Qualification of Auxiliary Feedwater Sys | Safe Shutdown Safe Shutdown Earthquake Operating Basis Earthquake Earthquake Backfit |
| ML20148A964 | 4 January 1978 | Safety Evaluation Supporting Amends 27 & 12 to Licenses DPR-53 & DPR-69,respectively | Fuel cladding |