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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
ML20148F1601993-09-27027 September 1993
Rev 0 to Rc Drain Tank, & Response to Question 23 Sews for Raceways
ML20058P1681993-09-27027 September 1993
Package Consisting of Attachment to Employee Concerns Programs
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
ML20057C0201993-09-0101 September 1993
Notation Vote Approving w/comment,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend
ML20148F1451993-09-0101 September 1993
Rev 0 to Nuc Serv Closed Cooling Water Surge 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
ML20148F1221993-08-31031 August 1993
Rev 0 to Intermediate Closed Cooling Chem Mix Tank
ML20148F1521993-08-31031 August 1993
Rev 0 to Nuc Svc Cool Chem Mix 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
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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\
