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MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)

Nickel +, Hydrogen +  and Lead +

ASME Code Case N-460 +, ASME Code Case N-560 +  and ASME Code Case N-532 +

1CAN069705 +, 2CAN079401, Informs That Util Intends to Complete Seismic IPEEE for ANO Unit 2 at Reduced Scope Level of Effort,As Requested by GL 88-20,Suppl 4 +, 2CAN099604, Responds to RAI Re LPSI & SIT Allowed Outage Time Extensions to Facilitate Review of Tech Spec Change Request +, COMSECY-98 024 +, 2CAN029906 +, 2CAN079713 +, 2CAN019701 +, 2CAN089802, Application for Amend to License NPF-6,revising TS 3.1.3.2 Action Requirements for CEA Position Indicator Channels +, 2CAN079802, Requests Temporary Relief to Allow non-code Repair of Piping as Required by GL 90-05.Attachment Provides Justification for Temporary Repair of Piping +, 2CAN079803, Forwards Changes to Unit 2 TS Bases.Attachment to Ltr Contains Brief Description of Each One of Associated TS Bases Changes +, 2CAN049802, Application for Amend to License NPF-6,revising Value of Single Largest post-accident Load Capable of Being Supplied by DGs & Relocates Value to Associated Bases +, 2CAN109703, Requests Exemption from Requirements of Section III.G.2 of 10CFR50,App R,For Lack of Automatic Suppression Sys & Lack of Automatic Detection Sys for Area Below Elevation of Unit 2 Intake Structure +, 2CAN029912, Requests Enforcement Discretion from Requirements of TS Table 3.3-1,Action 2 to Allow Startup & Operation of Unit While Exigent TS Is Processed Re Channel D Detector.Encl Documents Util Position Discussed with NRC on 990223 +, 2CAN119805, Forwards Addl Info Re ANO-2 Plant Protection Sys,Per 981014 Meeting with NRC Staff.Util Has Been in Process of Developing Design Change Package to Correct Condition +, 2CAN119803, Forwards Response to NRC 980813 RAI Re GL 92-01,Rev 1, Supplement 1, Reator Vessel Structural Integrity. Rev 1 to 96-R-2030-02, Revised Reactor Vessel Fluence Determination, Encl +, 2CAN099804, Requests Approval to Use ASME Code Cases 2142-1 & 2143-1 of RCS for ANO-2.Application for Subject Code Cases Will Permit Util to Use Welding Procedures & Performance Qualifications Previously Qualified for F-No 43 Matls for Fabrication +, 2CAN069706, Discusses GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves +, 2CAN089609, Application for Amend to License NPF-6,revising Section 5.0, Design Features & Would for Most Part,Adopt NUREG-1432 Rev 1,improved, Std Tech Specs for C-E Plants, for Section of TS +, 2CAN029609, Forwards Responses to NRC Questions on ANO-2 TS Change Requests Re Increased AOTs for LPSI Trains,Sits & Edgs,Per CEOG Joint Repts CE NPSD-995 (Lpsi),Ce NPSD-994 (Sits) & CE NPSD-996 (Edgs) +, 2CAN059502, TS Change Request for Amend to License NPF-6,re AOT Extension for Low Pressure Safety Injection Train +  and 2CAN119402, Clarifies Util Intention to Not Install Replacement Breakers in Next Practical Refueling Outage for ANO Unit 2, Per Concern Raised Re Circuitry Isolation During Electrical Distribution Sys Functional Insp of Facility +

05000313  +, 05000368  +, 00313  +  and 00368  +

Nolan M +  and NRC (Affiliation Not Assigned) +

NRC Generic Letter 97-02, Revised Contents of the Monthly Operating Report +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +  and NRC Generic Letter 1988-12, Removal of Fire Protection Requirements from Technical Specification +

ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +, ML20205J635 +...

5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

ML20137C276 +, IR 05000313/1996026 +, ML20217K988 +, IR 05000313/1998013 +, 0CAN049804, Forwards ANO Units 1 & 2 Annual Radiological Environ Operating Rept for 1997. All Radionuclides Detected by Radiological Environ Monitoring Program During 1997 Were Significantly Below Regulatory Limits +, 0CAN089801, Revises 961219 Submittal to Incorporate New Control Room Duct Radiation Monitor.Util Requests That Effective Date for Change Be within 30 Days of NRC Approval +, 2CAN079802, Requests Temporary Relief to Allow non-code Repair of Piping as Required by GL 90-05.Attachment Provides Justification for Temporary Repair of Piping +, 0CAN079703, Submits 120-day Response to GL 97-01, Degradation of CR Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations +, 1CAN109705, Requests Relief from Requirements of 10CFR50.55(a)(g)(ii)(A) Augmented Reactor Vessel Shell Weld Insp.Util Was Unable to Examine Greater than 90% of Four Rv Welds Due to Rv Interferences.Relief Request,Encl +, 1CAN109704, Clarifies Previous Exemption from Requirements of Section III.G.2 of 10CFR50 App R Re one-hour Fire Barriers & Automatic Fire Suppression Sys for Unit 1 Makeup Pump Rooms +, 1CAN129703, Requests Relief for RCS Weld Exam,From Requirements of 10CFR50.55(a)(g).Relief Request for 2 Welds Whose Volumes Could Not Be Examined 100%,encl +, 2CAN119805, Forwards Addl Info Re ANO-2 Plant Protection Sys,Per 981014 Meeting with NRC Staff.Util Has Been in Process of Developing Design Change Package to Correct Condition +, 2CAN119803, Forwards Response to NRC 980813 RAI Re GL 92-01,Rev 1, Supplement 1, Reator Vessel Structural Integrity. Rev 1 to 96-R-2030-02, Revised Reactor Vessel Fluence Determination, Encl +, 0CAN019702, Submits 120-days Response to GL-96-06, Assurance of Equipment Operability & Containment Integrity During DBA Conditions +, 0CAN119602, Requests Temporary Relief to Allow non-code Repair of Piping as Required by GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & Piping +, 0CAN089606, Application for Amends to Licenses DPR-51 & NPF-6,allowing Implementation of Approved Option B to 10CFR50,App J +, 0CAN049603, Responds to GL 96-01, Testing of Safety-Related Logic Circuits +, 0CAN029605, Forwards Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves +, 0CAN109505, Informs That Util Will Like to Submit Ipeee/Usi A-46 Summary Repts by 960331 for Units 1 & 2,in Order to Allow Sufficient Time to Complete Review,Per GL 88-20 +, 0CAN049501, Application for Amends to Licenses DPR-51 & NPF-6,revising TS Associated W/Control Room Ventilation Sys +, ML20056H356 +, 0CAN089307, Forwards fitness-for-duty Program Performance Data for Period of Jan-June 1993 Per 10CFR26.71(d) +, LD-98-024, Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency +, 05000313/LER-1996-002, :on 970519,surveillance Tests Required by TS Were Incomplete Because All Combinations of Contacts Not Tested Due to Procedure Deficiencies.Verified Operability of RPS +  and 05000368/LER-1992-003-02, :on 920501,initiated Manual Reactor Trip After Mismatch in Charging & Letdown Flowrates Observed.Cause Unknown.Cause for Recurring High Dp Identified by 920901. Procedure 2203.012L Revised +

NUREG-1430 +  and NUREG-1432 +

2CV-0716-1 +, 2CV-5613-2 +  and 2CV-5612 +

Maryland +, Washington +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Shutdown Cooling +, Decay Heat Removal +  and Containment Spray +

TS-3.0.5 +, TS-3.1.1.3 +  and TS-4.4.5 +

Hot Short +, Safe Shutdown +, Grab sample +, Enforcement Discretion +, Loss of Offsite Power +, License Renewal +, Exemption Request +, Earthquake +, Power Uprate +, Water hammer +, Pre-application +, Pressure locking +  and Thermal binding +