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Issue date | Title | Topic | |
---|---|---|---|
ML20154H987 | 28 August 1998 | Non-proprietary,rev 0 to Calculation of TMI-1 ESF Component Leakage Iodine Release | |
ML20154P894 | 13 May 1998 | Non-proprietary Rev 1 to Psat 05653A.04, Formulation of OTSG DF for Radioiodine (as I2) to Be Credited for TMI-1 Mlsb with Ais/Pas | Boric Acid |
ML20217E166 | 18 March 1998 | Rev 0 to C-1101-826-E540-022, Estimate of Xu/Q Values for TMI-1 Control Bldg Vetilation Sys Exhaust | |
ML20217E117 | 17 March 1998 | Rev 0 to C-1101-826-E540-020, Atmospheric Transport X/Qs Using ARCON96 Code - CR Habitability | Probabilistic Risk Assessment |
ML20217E197 | 17 March 1998 | Rev 0 to C-1101-826-E540-025, X/Q TMI Ventilation Exhaust Opening | Probabilistic Risk Assessment |
ML20217F950 | 24 July 1997 | Rev 1 to Calculation C-1101-770-E420-018, Derating of Cable Ampacity Due to Raceway Fire Barriers | Fire Barrier Aging Management |
ML20133F651 | 14 January 1997 | Press Release 97-03, NRC Receives Application from DOE for License to Store TMI Fuel Debris at Inel | |
ML20134M212 | 22 November 1996 | Press Release 96-165, NRC Begins First of Series of Design Insps at Nuclear Power Plants | |
ML20148T736 | 8 November 1996 | Rev 0 to Calculation 6612-96-030, Rms Levels Corresponding to NUMARC Eals | |
ML20148T751 | 6 November 1996 | Rev 0 to Calculation 6612-96-031, Estimate of RM-G-6 & 7 Reading W/Decreased Vessel Level | |
ML20134D547 | 28 October 1996 | Press Release I-96-71, Parts of Local PDR for Three Mile Island & Peach Bottom Nuclear Plants Reopened | |
ML20128Q332 | 18 October 1996 | Press Release 96-146, NRC Establishes Special Projects Ofc to Oversee Insp & Licensing Activities at Millstone & Haddam Neck Plants | |
ML20129E994 | 10 October 1996 | Rev 0 to Calculation C-1101-770-E420-018, TSI Derating of Cable Ampacity | |
ML20148T697 | 11 September 1996 | Rev 0 to Calculation 6612-96-023, Estimated RM-G-22/23 Readings W/Loca at TS Rcs | Offsite Dose Calculation Manual |
ML20148T680 | 6 September 1996 | Rev 0 to Calculation 6612-96-022, Estimate of RM-G-9 Reading W/Decreased SFP Level | |
ML20148F008 | 8 February 1994 | Rev 0 to Condensate Storage Tank a | |
ML20148F025 | 8 February 1994 | Rev 0 to Condensate Storage Tank B | |
ML20148F032 | 8 December 1993 | Rev 0 to Bwst | |
ML20148F133 | 30 September 1993 | Rev 0 to Make-Up Tank | |
ML20058P168 | 27 September 1993 | Package Consisting of Attachment to Employee Concerns Programs | Missed surveillance Coast down |
ML20148F160 | 27 September 1993 | Rev 0 to Rc Drain Tank, & Response to Question 23 Sews for Raceways | |
ML20148F054 | 17 September 1993 | Rev 0 to SQ-TI-EG-T-0001A-2, EDG 1A Air Start 2 Reservior Tank 1A | |
ML20057B964 | 10 September 1993 | AX114 & AX115 Ci Loading | |
ML20057C020 | 1 September 1993 | Notation Vote Approving w/comment,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend | |
ML20148F145 | 1 September 1993 | Rev 0 to Nuc Serv Closed Cooling Water Surge Tank | |
ML20057C019 | 31 August 1993 | Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend | |
ML20148F107 | 31 August 1993 | Rev 0 to Intermediate Colsed Cooling Surge Tank | |
ML20148F122 | 31 August 1993 | Rev 0 to Intermediate Closed Cooling Chem Mix Tank | |
ML20148F152 | 31 August 1993 | Rev 0 to Nuc Svc Cool Chem Mix Tank | |
ML20057C021 | 30 August 1993 | Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend | |
ML20057B958 | 27 August 1993 | FH109/FH300 Ci Estimate | |
ML20057C016 | 26 August 1993 | Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend | |
ML20126M239 | 13 July 1992 | Package of Documents,Including Index of Briefing Papers & Actual Papers Re License Renewal,Design Certification Process,Below Regulatory Concern & Resident Inspector Program | License Renewal |
ML20196K643 | 20 July 1991 | Rev 1 to B&W Document 32-1203121-01, Fsplit Certification Analysis | |
ML20151M960 | 20 July 1987 | Package of NRC Administered Requalification Exam Results Summary | |
ML20213A041 | 29 January 1987 | Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island | |
IA-86-608, Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island | 29 January 1987 | Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island | |
ML20215L216 | 9 October 1986 | Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response | |
IA-86-293, Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response | 9 October 1986 | Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response | |
ML20154M502 | 23 May 1985 | Notation Vote Response Sheet Approving SECY-85-153,providing Info to Advisory Panel on TMI-2 Cleanup | |
ML20129F483 | 9 May 1985 | Package of Compilations of Results of Operator Licensing & Requalification Exams | |
ML20126B831 | 11 December 1984 | Supporting Documentation Re once-through Steam Generators | |
ML20135H353 | 19 June 1984 | Package of Reactor Operator & Senior Reactor Operator License Exam Questions & Answer Keys for Several Facilities, Including Yankee Rowe,Point Beach Units 1 & 2,Fort Calhoun Unit 1 & Calvert Cliffs Units 1 & 2 | Safe Shutdown Boric Acid Shutdown Margin High Radiation Area Post Accident Monitoring Overtravel Pressure Boundary Leakage |
ML20024B494 | 6 July 1983 | Slide Presentation Entitled Control Room Indications. | |
ML20078B646 | 5 April 1983 | Slide Presentation Entitled TMI-1 Once-Through Steam Generator Repair & Return to Svc | Loop seal |
ML20083N666 | 19 October 1982 | TMI-1 Once-Through Steam Generator Repair Process Update & Return to Svc Overview | Flow Induced Vibration |
ML20082R151 | 15 September 1982 | Slide Presentation Entitled, TMI-1 Once-Through Steam Generator Repair Process Description/Qualification | |
ML20083N658 | 4 August 1982 | Informal Technical Communication Re 820721 Meeting in Livingston,Nj Concerning Schedule for Qualification Program of Tube Repair & Results of Preliminary Tests.Ornl 820817 Memo Re 820808-09 Meeting & Summary of 820915 Meeting Encl | |
ML20054K080 | 10 June 1982 | Request for OMB Review & Supporting Statement Re Psychological Stress of TMI-1 Restart on Residents Living in General Vicinity.Estimated Respondent Burden Is 853-h | Siren |
ML20071J047 | 7 April 1982 | Slide Presentation Entitledd Gpu Nuclear TMI-1 Once-Through Steam Generator Status Review | Boric Acid |