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 Issue dateTitleTopic
ML20154H98728 August 1998Non-proprietary,rev 0 to Calculation of TMI-1 ESF Component Leakage Iodine Release
ML20154P89413 May 1998Non-proprietary Rev 1 to Psat 05653A.04, Formulation of OTSG DF for Radioiodine (as I2) to Be Credited for TMI-1 Mlsb with Ais/PasBoric Acid
ML20217E16618 March 1998Rev 0 to C-1101-826-E540-022, Estimate of Xu/Q Values for TMI-1 Control Bldg Vetilation Sys Exhaust
ML20217E11717 March 1998Rev 0 to C-1101-826-E540-020, Atmospheric Transport X/Qs Using ARCON96 Code - CR HabitabilityProbabilistic Risk Assessment
ML20217E19717 March 1998Rev 0 to C-1101-826-E540-025, X/Q TMI Ventilation Exhaust OpeningProbabilistic Risk Assessment
ML20217F95024 July 1997Rev 1 to Calculation C-1101-770-E420-018, Derating of Cable Ampacity Due to Raceway Fire BarriersFire Barrier
Aging Management
ML20133F65114 January 1997Press Release 97-03, NRC Receives Application from DOE for License to Store TMI Fuel Debris at Inel
ML20134M21222 November 1996Press Release 96-165, NRC Begins First of Series of Design Insps at Nuclear Power Plants
ML20148T7368 November 1996Rev 0 to Calculation 6612-96-030, Rms Levels Corresponding to NUMARC Eals
ML20148T7516 November 1996Rev 0 to Calculation 6612-96-031, Estimate of RM-G-6 & 7 Reading W/Decreased Vessel Level
ML20134D54728 October 1996Press Release I-96-71, Parts of Local PDR for Three Mile Island & Peach Bottom Nuclear Plants Reopened
ML20128Q33218 October 1996Press Release 96-146, NRC Establishes Special Projects Ofc to Oversee Insp & Licensing Activities at Millstone & Haddam Neck Plants
ML20129E99410 October 1996Rev 0 to Calculation C-1101-770-E420-018, TSI Derating of Cable Ampacity
ML20148T69711 September 1996Rev 0 to Calculation 6612-96-023, Estimated RM-G-22/23 Readings W/Loca at TS RcsOffsite Dose Calculation Manual
ML20148T6806 September 1996Rev 0 to Calculation 6612-96-022, Estimate of RM-G-9 Reading W/Decreased SFP Level
ML20148F0088 February 1994Rev 0 to Condensate Storage Tank a
ML20148F0258 February 1994Rev 0 to Condensate Storage Tank B
ML20148F0328 December 1993Rev 0 to Bwst
ML20148F13330 September 1993Rev 0 to Make-Up Tank
ML20058P16827 September 1993Package Consisting of Attachment to Employee Concerns ProgramsMissed surveillance
Coast down
ML20148F16027 September 1993Rev 0 to Rc Drain Tank, & Response to Question 23 Sews for Raceways
ML20148F05417 September 1993Rev 0 to SQ-TI-EG-T-0001A-2, EDG 1A Air Start 2 Reservior Tank 1A
ML20057B96410 September 1993AX114 & AX115 Ci Loading
ML20057C0201 September 1993Notation Vote Approving w/comment,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend
ML20148F1451 September 1993Rev 0 to Nuc Serv Closed Cooling Water Surge Tank
ML20057C01931 August 1993Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend
ML20148F10731 August 1993Rev 0 to Intermediate Colsed Cooling Surge Tank
ML20148F12231 August 1993Rev 0 to Intermediate Closed Cooling Chem Mix Tank
ML20148F15231 August 1993Rev 0 to Nuc Svc Cool Chem Mix Tank
ML20057C02130 August 1993Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend
ML20057B95827 August 1993FH109/FH300 Ci Estimate
ML20057C01626 August 1993Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend
ML20126M23913 July 1992Package of Documents,Including Index of Briefing Papers & Actual Papers Re License Renewal,Design Certification Process,Below Regulatory Concern & Resident Inspector ProgramLicense Renewal
ML20196K64320 July 1991Rev 1 to B&W Document 32-1203121-01, Fsplit Certification Analysis
ML20151M96020 July 1987Package of NRC Administered Requalification Exam Results Summary
ML20213A04129 January 1987Undated 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 Island29 January 1987Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island
ML20215L2169 October 1986Package 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 Response9 October 1986Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response
ML20154M50223 May 1985Notation Vote Response Sheet Approving SECY-85-153,providing Info to Advisory Panel on TMI-2 Cleanup
ML20129F4839 May 1985Package of Compilations of Results of Operator Licensing & Requalification Exams
ML20126B83111 December 1984Supporting Documentation Re once-through Steam Generators
ML20135H35319 June 1984Package 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 & 2Safe Shutdown
Boric Acid
Shutdown Margin
High Radiation Area
Post Accident Monitoring
Overtravel
Pressure Boundary Leakage
ML20024B4946 July 1983Slide Presentation Entitled Control Room Indications.
ML20078B6465 April 1983Slide Presentation Entitled TMI-1 Once-Through Steam Generator Repair & Return to SvcLoop seal
ML20083N66619 October 1982TMI-1 Once-Through Steam Generator Repair Process Update & Return to Svc OverviewFlow Induced Vibration
ML20082R15115 September 1982Slide Presentation Entitled, TMI-1 Once-Through Steam Generator Repair Process Description/Qualification
ML20083N6584 August 1982Informal 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
ML20054K08010 June 1982Request for OMB Review & Supporting Statement Re Psychological Stress of TMI-1 Restart on Residents Living in General Vicinity.Estimated Respondent Burden Is 853-hSiren
ML20071J0477 April 1982Slide Presentation Entitledd Gpu Nuclear TMI-1 Once-Through Steam Generator Status ReviewBoric Acid