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Category:ARCHIVE RECORDS
MONTHYEARML20154H9871998-08-28028 August 1998 Non-proprietary,rev 0 to Calculation of TMI-1 ESF Component Leakage Iodine Release ML20154P8941998-05-13013 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 ML20217E1661998-03-18018 March 1998 Rev 0 to C-1101-826-E540-022, Estimate of Xu/Q Values for TMI-1 Control Bldg Vetilation Sys Exhaust ML20217E1971998-03-17017 March 1998 Rev 0 to C-1101-826-E540-025, X/Q TMI Ventilation Exhaust Opening ML20217E1171998-03-17017 March 1998 Rev 0 to C-1101-826-E540-020, Atmospheric Transport X/Qs Using ARCON96 Code - CR Habitability ML20217F9501997-07-24024 July 1997 Rev 1 to Calculation C-1101-770-E420-018, Derating of Cable Ampacity Due to Raceway Fire Barriers ML20133F6511997-01-14014 January 1997 Press Release 97-03, NRC Receives Application from DOE for License to Store TMI Fuel Debris at Inel ML20134M2121996-11-22022 November 1996 Press Release 96-165, NRC Begins First of Series of Design Insps at Nuclear Power Plants ML20148T7361996-11-0808 November 1996 Rev 0 to Calculation 6612-96-030, Rms Levels Corresponding to NUMARC Eals ML20148T7511996-11-0606 November 1996 Rev 0 to Calculation 6612-96-031, Estimate of RM-G-6 & 7 Reading W/Decreased Vessel Level ML20134D5471996-10-28028 October 1996 Press Release I-96-71, Parts of Local PDR for Three Mile Island & Peach Bottom Nuclear Plants Reopened ML20128Q3321996-10-18018 October 1996 Press Release 96-146, NRC Establishes Special Projects Ofc to Oversee Insp & Licensing Activities at Millstone & Haddam Neck Plants ML20129E9941996-10-10010 October 1996 Rev 0 to Calculation C-1101-770-E420-018, TSI Derating of Cable Ampacity ML20148T6971996-09-11011 September 1996 Rev 0 to Calculation 6612-96-023, Estimated RM-G-22/23 Readings W/Loca at TS Rcs ML20148T6801996-09-0606 September 1996 Rev 0 to Calculation 6612-96-022, Estimate of RM-G-9 Reading W/Decreased SFP Level ML20148F0251994-02-0808 February 1994 Rev 0 to Condensate Storage Tank B ML20148F0081994-02-0808 February 1994 Rev 0 to Condensate Storage Tank a ML20148F0321993-12-0808 December 1993 Rev 0 to Bwst ML20148F1331993-09-30030 September 1993 Rev 0 to Make-Up Tank ML20058P1681993-09-27027 September 1993 Package Consisting of Attachment to Employee Concerns Programs ML20148F1601993-09-27027 September 1993 Rev 0 to Rc Drain Tank, & Response to Question 23 Sews for Raceways ML20148F0541993-09-17017 September 1993 Rev 0 to SQ-TI-EG-T-0001A-2, EDG 1A Air Start 2 Reservior Tank 1A ML20057B9641993-09-10010 September 1993 AX114 & AX115 Ci Loading ML20148F1451993-09-0101 September 1993 Rev 0 to Nuc Serv Closed Cooling Water Surge Tank ML20057C0201993-09-0101 September 1993 Notation Vote Approving w/comment,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend ML20148F1521993-08-31031 August 1993 Rev 0 to Nuc Svc Cool Chem Mix Tank ML20148F1221993-08-31031 August 1993 Rev 0 to Intermediate Closed Cooling Chem Mix Tank ML20057C0191993-08-31031 August 1993 Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend ML20148F1071993-08-31031 August 1993 Rev 0 to Intermediate Colsed Cooling Surge Tank ML20057C0211993-08-30030 August 1993 Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend ML20057B9581993-08-27027 August 1993 FH109/FH300 Ci Estimate ML20057C0161993-08-26026 August 1993 Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend ML20126M2391992-07-13013 July 1992 Package of Documents,Including Index of Briefing Papers & Actual Papers Re License Renewal,Design Certification Process,Below Regulatory Concern & Resident Inspector Program ML20196K6431991-07-20020 July 1991 Rev 1 to B&W Document 32-1203121-01, Fsplit Certification Analysis ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary IA-86-608, Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island1987-01-29029 January 1987 Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island ML20213A0411987-01-29029 January 1987 Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island IA-86-293, Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response1986-10-0909 October 1986 Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response ML20215L2161986-10-0909 October 1986 Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response ML20154M5021985-05-23023 May 1985 Notation Vote Response Sheet Approving SECY-85-153,providing Info to Advisory Panel on TMI-2 Cleanup ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams ML20126B8311984-12-11011 December 1984 Supporting Documentation Re once-through Steam Generators ML20135H3531984-06-19019 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 ML20024B4941983-07-0606 July 1983 Slide Presentation Entitled Control Room Indications. ML20078B6461983-04-0505 April 1983 Slide Presentation Entitled TMI-1 Once-Through Steam Generator Repair & Return to Svc ML20083N6661982-10-19019 October 1982 TMI-1 Once-Through Steam Generator Repair Process Update & Return to Svc Overview ML20082R1511982-09-15015 September 1982 Slide Presentation Entitled, TMI-1 Once-Through Steam Generator Repair Process Description/Qualification ML20083N6581982-08-0404 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 ML20054K0801982-06-10010 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 ML20071J0471982-04-0707 April 1982 Slide Presentation Entitledd Gpu Nuclear TMI-1 Once-Through Steam Generator Status Review 1998-08-28
[Table view] Category:PRESS RELEASE OR NEWS ARTICLE
MONTHYEARML20133F6511997-01-14014 January 1997 Press Release 97-03, NRC Receives Application from DOE for License to Store TMI Fuel Debris at Inel ML20134M2121996-11-22022 November 1996 Press Release 96-165, NRC Begins First of Series of Design Insps at Nuclear Power Plants ML20134D5471996-10-28028 October 1996 Press Release I-96-71, Parts of Local PDR for Three Mile Island & Peach Bottom Nuclear Plants Reopened ML20128Q3321996-10-18018 October 1996 Press Release 96-146, NRC Establishes Special Projects Ofc to Oversee Insp & Licensing Activities at Millstone & Haddam Neck Plants ML19340C8161980-11-15015 November 1980 Open Ltr Re Prolonged Delay in Restarting Unit 1.Urges NRC to Relicense Plant for Immediate Startup ML20136B9811979-04-0606 April 1979 Quotes Kz Morgan of Existence of Evidence Re Inadequate Radiological Monitoring of Alpha & Beta Radiation Around TMI Site.Info on Radiation from Noble Gases Has Not Been Adequately Explained to Public 1997-01-14
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United States Nuclear Regulatory Commission Office of Public Affairs Vhshington, DC 20555 Phone 301-415-8200 Fax 301-415-2234 Internet:opa@nrc. gov No.97-003 FOR IMMEDIATE RELEASE (Tuesday, January 14, 1997)
NRC RECEIVES APPLICATION FROM DOE FOR LICENSE TO STORE TMI FUEL DEBRIS AT INEL
- The Nuclear Regulatory Commission has received an application from the Department of Energy (DOE) for a license to store core debris from the Three Mile Island-2 reactor in dry storage casks at the Idaho National Engineering Laboratory (INEL) complex in Butte County, Idaho.
DOE shipped the debris from the damaged reactor core to INEL between 1986 and 1990 and stored it in a spent fuel pool in the Test Area North facility of the complex. The dry cask storage 4
installation DOE plans to construct and operate will be about 25 miles away--but still within the INEL complex--in the Idaho Chemical Processing Plant.
. Any person whose interest may be affected may file a request for a hearing with the NRC by February 12. Anyone with such interests who wishes to participate in the hearing may file a petition to intervene. Details on how to file such requests or petitions are contained in a Federal Register notice published on January 13. If a request for hearing is filed, an Atomic Safety and Licensing Board will rule on the request and any petitions to
. intervene.
Before deciding whether to issue a license, the NRC staff will prepare an environmental impact statement and will conduct a 4 technical evaluation of the application to determine whether it meets NRC requirements. The term of the license, if granted, would be 20 years.
NRC plans to participate in a public meeting on the application to be held Thursday, February 6, at 7 p.m. at the Shilo Inn, 780 Lindsay Boulevard, Idaho Falls.
PDR Pkhsgk70114 HO-97-OO3 PDR PRIM 140113 Ol\