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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
[Table view] Category:OPERATIONAL LOG-PLANT SYSTEMS
MONTHYEARML20062J7041980-10-31031 October 1980 Form 1616.1,Revision 3, Insp of Emergency Respiratory Equipment ML20136C2191979-09-13013 September 1979 Strip Chart RB Pressure Data (Enhanced Trace).Radiological Ref 95 ML20136C2591979-09-12012 September 1979 Chronology of Incident on 790329 by H Mcgovern (Control Room Operator), ML19209B6751979-06-0909 June 1979 Surveillance of Feedwater Pump Turbines Required by Tech Specs,As of 790609 ML20136B8681979-05-22022 May 1979 Computer Listing of Monitored Variables ML19269E4211979-05-18018 May 1979 TMI-1 Work List.Items Listed in Priority Order ML17317B5611979-05-18018 May 1979 Reactor Coolant Pump Vibration & Loose Parts Monitor Data Delogged ML20136C0141979-05-0101 May 1979 Plant Status Readings for 790510,11,31 & 0601 ML20136A8731979-04-23023 April 1979 Incident Message Forms C-185 Through C-196 ML20136C2321979-04-19019 April 1979 Operations Records.Radiological Ref 150 ML20126K5301979-04-11011 April 1979 Plant Sys Operation Log ML20136A8711979-04-10010 April 1979 Incident Message Forms R-262 Through R-282 ML20136C2091979-04-0101 April 1979 TMI-2 Reactor Coolant Analysis Sheets.Radiological Analysis of Samples.Radiological Ref 131 ML20136C2221979-03-30030 March 1979 MU-T-1 Tank Level Data.Radiological Ref 121 ML20136C7261979-03-28028 March 1979 Plant Sys Readings for TMI-2 ML20136C6471979-03-28028 March 1979 Strip Charts for Polisher 4 Recorder 82,Polisher 3 Recorder 81 & Polisher 2 Recorder 80 on 790328-29 ML20136C1131979-03-28028 March 1979 TMI-2 Chemical Log for 790325-28 ML20136C2431979-03-28028 March 1979 Environ Control Survey Log for 790328-30.Radiological Ref 169 ML20136C6521979-03-28028 March 1979 Generator & Reactor Readings for TMI-2 on 790328 ML20136C6601979-03-28028 March 1979 TMI Strip Chart of Boric Acid Mix Tank Level ML20136C6861979-03-28028 March 1979 TMI Strip Chart for Recorder 51,monitoring Condenser Hotwell & Reactor Coolant Loop B Inlet Temps ML20136B8671979-03-19019 March 1979 Computer Listing of Performance Data ML20136C2171979-02-0707 February 1979 Surveillance 1302-2.11 Performance Form & Data Sheets. Quarterly Instrument Calibr.Radiological Ref 39 ML20136C2391978-12-14014 December 1978 Surveillance Procedure 1302-3.1A Data Sheets Re Rms Quarterly Survey.Radiological Ref 37 ML20136C2361978-12-11011 December 1978 Engineering Change Memo Re Isokinetic Nozzles for HP-R-221A, 221B,222A,222B,222C,222D,228D,228A & 228B.Radiological Ref 45 ML20136C7151978-11-0303 November 1978 Log of Test Results from Test Procedure TP-800-21 Administered to Reactor Trip ML20125B4851978-05-12012 May 1978 Pages from chemistry-polisher Status Log Book Re 780512 Condensate Trip.Includes Statement That Air Fluff Valves Were Left Open ML20125D8851977-09-24024 September 1977 Data on RCS Pressure Transient for Electromagnetic Pressurizer Relief Valve That Stuck Open,Causing Small Break in RCS Piping ML20136C1891975-07-0202 July 1975 Calibr Data Sheets for 750522-0702,calibr Procedure Peculiarities & Factory Point Source Calibr.Vendor Tech Specs,Test Data Sheets & Drawings Encl 1980-10-31
[Table view] |
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COPY MADE ON OF DOCUMENI PROVIDED BY ,,.
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RA)l0 LOGICAL REF.#
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I . Tha follcwing chronology .was dictated to'W. .J. Bubbc) Marshall by
) HUGH MCGOVERN (CRO) at approximately 0300,' March 29,1979. A copy of the handwritten transcript is attached. p
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0700 Came in, had 'just declared site emergency. PER' was ' solid, steaming ~ ' - .
through 2 circ water pumps running, both atmospheric dumps were lifted -
as noise from MS relief valve speaker.
. c p 0715 Started 2nd set of cire water pumps, atmospheric dumps shut - both by-c passes were controlling header pressure. .
a 0730' Isolated B S/G closed MS-V4 4 7 4 15 (B).
Lynn Wright was isolating feed at this time. ,
p 0800 Had a prcblem with gland steam - attributed to Unit 1. aux boiler problems-
' started losing vacuum - isolated gland steam spill E spill bypass'.
0750 Stopped SF-P-1A isolated BWST receive line. . ,
y 0900 started aux building and fuel handling building exhaust fans also started AH-E-4B (control room recirc) . c
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g 1100 Isolated HP-R-227 from Rx building and secured it. During the above time frame - E.P. injection was started and stopped several times - also RC-
- R-V2 was cycled to relieve PZR pressure. 13C-D-T had 0 pressure, N 2250F established leakage close but could not keep temperature down , level' in-dicator less than 70 and pumps did not- have suction press indicating the contents of RC-D-T had flashed. Rx building pressure increased when RC-RV-2 was cycled and at p 3.5 psi RB isolation and cooling was initiated, went once was defeated and opened isolations for NC 4 IC. Pressure ,
decrease when RC-RV-2 was shut. But came back up as RC-R-V2 was cycled
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. about 45 minutes to 60 minutes after 1st RB isolation received 2nd actua-
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tion on Rx building pressure - this was around 1200 or 1300 hrs.
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m 1400 Had's load of 2-32A 4 2-42A loss of radiation ar.ea monitors and a.n Rx
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definite spike straight up,' straight back down -' had meter - definite *
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. spike straigh't up, straight back down - had full Rx building (Spray ,, ,
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pumps 4 BS-VPS/ DH-V8's) isolation 'and cooling. Someone secured spray pdmps, shut BS-Vi's and DH-V's (Hugh did) and unisolated equipment for building. .
f V 1500 Took the panel - at time had bubbles in 'both hot legs with both Th e
' instruments pegged. PZR was solid. Were taking water from.BWST U A DH-VS A6B 4 MV-P-1B running continuously and MU-P-IC*as necessary to control MV.T-1 level. MV-V-16B 'was open and thruttled to 100 gym, MV-V17 4 MV -
V18 were open, with max letdown 120 to 130.GPM. M'anaged to collapse bubble in A loop hotleg as evidenced by Th A loop decreasings to 5900F.
When this happened tried to do the same thing to B loop by opening MV-V16C with MV-P-lC." This' didn't work '- Th in A loop went back up off scale and B , loop Th didn't change. PER heaters on at this time with RC-R-V2 open. Shut stopped MU-P-IC and shut MW-Y16C. About 10 minutes .
. later Th A loop came back down again. PER level dropped to /./ 395. At (,
this time, isolated RC-RV2. Bf shutting RC-V2. PER level started to -
drop again in about S minutes, and dropped rapidly to 150", MU-T-1 level .
- 'was decreasing also MU-P-1B 4 C were running MU-V-17 in auto and. full . _ _ ,
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open (setpoint 200") MU flow was 150 dPM (makeup to) MU-V16C throttled
- to 200 GPM. At 'this time PER heaters were de-energized and lifted RC- , _
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