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List of results

• ML20210R696  + (Submits Analysis of Recommendations Re Facility Deficiency List Dtd 990630.No Action Should Be Taken on Areas Agreed to as Deficiency Until NRC Project Officer or Designee Issued Reimbursable Work Order)
• ML20033B995  + (Submits Analysis of Rept, Geohydrologic Investigation of Tailings Disposal,Road Ranch Prospect,Mcmullen County,Tx, Prepared for Anaconda Co by El Reed & Associates,Inc. Disposal Method Acceptable W/Appropriate Testing Procedures)
• ML17298B993  + (Submits Analysis of Smoke Detection Sys Installation,In Response to 850304-08 Open Item from App R Audit.Deviation from Provisions of NFPA 72F Section 4-3.7.3, Beam Const, Requested)
• ML20128C314  + (Submits Analysis, Safety Issue Re Continuous Operation W/ Degraded SG Tubes, Indicating Core Melt Probability Frequency of 10 -4/Ry W/Containment Bypass)
• ML20079E679  + (Submits Analysis,Per Paragraph (B) of 10CFR51.52, Environ Effects of Transportation of Fuel & Waste - Table S-4. Changes in Cladding Matl Associated W/Vantage+ Fuel Have No Impact on Entries in Table S-4)
• ML20107M320  + (Submits Analytical Evaluation of Indication Identified During non-destructive Exams of Class 1 Austenitic Piping, Exceeding Acceptance Criteria Specified in Section XI of ASME Boiler & Pressure Code)
• ML20054M675  + (Submits Analytical Program Re post-accident Sampling,Per NRC 820326 Guidance to Assure Suitability of Analytical Procedures.Summary of Verified Procedures Will Be Submitted within 270 Days of)
• RBG-44229, Submits Analytical Results Obtained Prior to Discharge to Flume in Response to Ltr of No Objection to Discharge Normal Svc Water to Main Cooling Tower Circulating Water Flume,  + (Submits Analytical Results Obtained Prior to Discharge to Flume in Response to Ltr of No Objection to Discharge Normal Svc Water to Main Cooling Tower Circulating Water Flume,)
• ML20248A932  + (Submits Analytical Results for Soil Samples Collected from Framatome Cogema Fuels,Lynchburg,Va.Results Presented in Tables 1 & 2 Respectively)
• ML19257D224  + (Submits Analytical Results of Mill Tailing Samples Representing New Acid Mill & Old Carbonate Leach Mill. Ore Used in Acid Mill Tailings Sample Contained 0.2% U. Carbonate Leach Tailings Were Blend of Samples)
• ML20234F157  + (Submits Announcement 56 Re NRC Responsibility to Provide Accurate Info to Public & Other Govt Agencies Re Reactor Incident in Russia)
• ML20133N966  + (Submits Announcement 94-06 Which Informs Region I Inspectors & Technical Managers That Mc 1007, Interfacing Activities Between Regional Ofcs of NRC & OSHA, Has Been Changed)
• ML18096A870  + (Submits Annual 10CFR50.46 Rept Describing Changes to ECCS Evaluation Models & to Licensing Basis Large Break & Small Break LOCA Analyses Results for Peak Clad Temperature)
• L-92-314, Submits Annual 10CFR50.46 Rept Re Acceptance Criteria for ECCS in Light Water Nuclear Power Reactor for 911017-921016. No Errors or Changes Discovered in ECCS Limiting Transient models.ABB-C-E Is ECCS Limiting Transient Supplier  + (Submits Annual 10CFR50.46 Rept Re Acceptance Criteria for ECCS in Light Water Nuclear Power Reactor for 911017-921016. No Errors or Changes Discovered in ECCS Limiting Transient models.ABB-C-E Is ECCS Limiting Transient Supplier)
• ML20217D480  + (Submits Annual 10CFR50.46 Rept Re Effects of ECCS Evaluation Model Modifications on Peak Cladding Temp Results Since 1996 Annual Rept)
• NOC-AE-000390, Submits Annual 10CFR50.46 Rept Re Revs to Accepted ECCS Evaluation Model at Stp,Units 1 & 2.Revised SBLOCA & LBLOCA Evaluation Models Continue to Meet Acceptance Criteria Identified in 10CFR50.46  + (Submits Annual 10CFR50.46 Rept Re Revs to Accepted ECCS Evaluation Model at Stp,Units 1 & 2.Revised SBLOCA & LBLOCA Evaluation Models Continue to Meet Acceptance Criteria Identified in 10CFR50.46)
• ML20138H747  + (Submits Annual 10CFR50.46 Summary Rept for 1996 Which Updates All Identified Changes or Errors in Loca/Eccs Codes & Methods Used by W to Model Fcs,Unit 1)
• LIC-96-0034, Submits Annual 10CFR50.46 Summary Rept for 1995.Summary Rept Updates Identified Changes/Error in Loca/Eccs Codes & Methods Used by Westinghouse to Model Unit 1  + (Submits Annual 10CFR50.46 Summary Rept for 1995.Summary Rept Updates Identified Changes/Error in Loca/Eccs Codes & Methods Used by Westinghouse to Model Unit 1)
• LIC-98-0053, Submits Annual 10CFR50.46 Summary Rept for 1997.Rept Updates All Identified Changes or Errors in Loca/Eccs Codes & Methods Used by W to Model Fort Calhoun Station Unit 1  + (Submits Annual 10CFR50.46 Summary Rept for 1997.Rept Updates All Identified Changes or Errors in Loca/Eccs Codes & Methods Used by W to Model Fort Calhoun Station Unit 1)
• BVY-98-171, Submits Annual 10CFR50.46(a)(3)(ii) Rept for 1998,re Changes in Peak Cladding Temp (PCT) for ECCS LOCA Analysis  + (Submits Annual 10CFR50.46(a)(3)(ii) Rept for 1998,re Changes in Peak Cladding Temp (PCT) for ECCS LOCA Analysis)
• BVY-97-177, Submits Annual 10CFR50.46(a)(3)(ii) Rept for 1997,re Acceptance Criteria for ECCS for light-water Cooled Nuclear Power Reactors  + (Submits Annual 10CFR50.46(a)(3)(ii) Rept for 1997,re Acceptance Criteria for ECCS for light-water Cooled Nuclear Power Reactors)
• ST-HL-AE-3897, Submits Annual 10CFR50.59 Summary Rept Which Describes Changes,Test & Experiments Associated W/Plant & Required Safety Evaluations (Se).Advises That Gaps in Numerical Sequence of Summary Represents SEs That Have Been Cancelled  + (Submits Annual 10CFR50.59 Summary Rept Which Describes Changes,Test & Experiments Associated W/Plant & Required Safety Evaluations (Se).Advises That Gaps in Numerical Sequence of Summary Represents SEs That Have Been Cancelled)
• 2CAN029508, Submits Annual DG Data Rept for 1994.Informs That Seventeen Valid Tests Conducted on 2K-4A DG W/O Valid Failures & Seventeen Valid Tests Conducted on 2K-4B DG W/O Valid Failures  + (Submits Annual DG Data Rept for 1994.Informs That Seventeen Valid Tests Conducted on 2K-4A DG W/O Valid Failures & Seventeen Valid Tests Conducted on 2K-4B DG W/O Valid Failures)
• 2CAN029607, Submits Annual DG Data Rept for 1995  + (Submits Annual DG Data Rept for 1995)
• 2CAN029405, Submits Annual Diesel Generator Data Rept for 1993.Fifteen Valid Tests Were Conducted on 2K-4A DG W/No Valid Failures. Fourteen Valid Tests Were Conducted on 2K-4B DG W/No Valid Failures  + (Submits Annual Diesel Generator Data Rept for 1993.Fifteen Valid Tests Were Conducted on 2K-4A DG W/No Valid Failures. Fourteen Valid Tests Were Conducted on 2K-4B DG W/No Valid Failures)

• 2CAN029307, Submits Annual Diesel Generator Data Rept 1992,per TS 6.9.1.5.d  + (Submits Annual Diesel Generator Data Rept 1992,per TS 6.9.1.5.d)

• ML17265A674  + (Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT)
• ML17264A549  + (Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(iii))
• ML17263A473  + (Submits Annual ECCS Rept in Accordance w/10CFR50.46.Summary of Current PCTs for Plant Encl)
• ML20216J445  + (Submits Annual Environ Operating Rept for Byron Generating Station for 1997)
• GO2-95-252, Submits Annual Filing of Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each Licensed Reactor  + (Submits Annual Filing of Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each Licensed Reactor)
• ML20138A405  + (Submits Annual Financial Repts Including Certified Financial Statements for Licensees)
• PY-CEI-NRR-2161, Submits Annual Financial Repts Including Certified Financial Statements for Licensees  + (Submits Annual Financial Repts Including Certified Financial Statements for Licensees)
• ML20050B542  + (Submits Annual Financial Statement for 1981)
• W3P86-0195, Submits Annual Fire Protection Rept for 841218-851231 Per License Condition 9.c  + (Submits Annual Fire Protection Rept for 841218-851231 Per License Condition 9.c)
• LR-N970439, Submits Annual Fuel Clad Temp Rept,Describing Changes to Calculated PCT for Plant Large & Small Break LOCA Analyses  + (Submits Annual Fuel Clad Temp Rept,Describing Changes to Calculated PCT for Plant Large & Small Break LOCA Analyses)
• LR-N980286, Submits Annual Fuel Clad Temp Rept,Iaw Requirements of 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp for Salem Generating Station Large & Small Break LOCA Analyses  + (Submits Annual Fuel Clad Temp Rept,Iaw Requirements of 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp for Salem Generating Station Large & Small Break LOCA Analyses)
• ML19257D829  + (Submits Annual Operating Rept 1979)
• ML19283B661  + (Submits Annual Operating Rept for 1978)
• ML19283B662  + (Submits Annual Operating Rept for 1978.)
• ML19341C600  + (Submits Annual Operating Rept for 1980)
• ML19341C605  + (Submits Annual Operating Rept for 1980)
• ML19341B165  + (Submits Annual Operating Rept for 1980,per Section 6.7.e of Tech Specs)
• ML19340F031  + (Submits Annual Operating Rept for 1980.No Unusual Events or Abnormal Radiation Exposures to Personnel Occurred.Annual Major Overhaul of Reactor Control Sys Was Completed on Schedule & All Sys Appear in Excellent Condition)
• ML20055A540  + (Submits Annual Operating Rept for 1981)
• ML19207A393  + (Submits Annual Operating Rept for 780630-790630)
• ML20071L188  + (Submits Annual Operating Rept for Jul 1981-June 1982)
• ML20071K593  + (Submits Annual Operating Rept for Jul 1981-June 1982)
• ML20049K037  + (Submits Annual Operating Rept of Activities & Experiments for License CX-22,Mar 1981-Mar 1982)
• ML20210S868  + (Submits Annual Population Dose Calculations.App I Review Complete)
• ML20029B294  + (Submits Annual Progress Rept for Implementation of Control Room Enhancements Per NUREG-0737.Listing of Schedules & Status of Human Engineering Discrepancies Encl)