ML20148F032
From kanterella
| ML20148F032 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 12/08/1993 |
| From: | Augustine R GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20148F000 | List: |
| References | |
| DH-T-001, DH-T-001-R00, DH-T-1, DH-T-1-R, NUDOCS 9706040078 | |
| Download: ML20148F032 (19) | |
Similar Documents at Three Mile Island | |
|---|---|
Category:ARCHIVE RECORDS
MONTHYEARML20154H9871998-08-28028 August 1998
[Table view]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 Category:OPERATIONS SUPPORT-CALCULATIONS MONTHYEARML20154H9871998-08-28028 August 1998
[Table view]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 ML20217E1171998-03-17017 March 1998 Rev 0 to C-1101-826-E540-020, Atmospheric Transport X/Qs Using ARCON96 Code - CR Habitability ML20217E1971998-03-17017 March 1998 Rev 0 to C-1101-826-E540-025, X/Q TMI Ventilation Exhaust Opening ML20217F9501997-07-24024 July 1997 Rev 1 to Calculation C-1101-770-E420-018, Derating of Cable Ampacity Due to Raceway Fire Barriers 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 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 ML20148F0081994-02-0808 February 1994 Rev 0 to Condensate Storage Tank a ML20148F0251994-02-0808 February 1994 Rev 0 to Condensate Storage Tank B 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 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 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 ML20057B9581993-08-27027 August 1993 FH109/FH300 Ci Estimate ML20196K6431991-07-20020 July 1991 Rev 1 to B&W Document 32-1203121-01, Fsplit Certification Analysis ML20136B1461979-04-0303 April 1979 Calculations Made for Hydrogen Bubble in Reactor Vessel ML20136A9851979-03-30030 March 1979 Hydrogen Burn Vessel Explosion Possibility Calculations ML20136B1421979-03-30030 March 1979 Calculations Re Containment Hydrogen Bubble ML20125D8981978-08-31031 August 1978 Calculation Data Re Davis-Besse 1 Pressurizer Levels During Reactor Trips ML20076J8441977-08-14014 August 1977 Graph of Reactivity Worths at 532 F & 2155 Psig 1998-08-28 |
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