a sequence of physical events - Three Mile Island

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TimeEvent Date afterNumberinitiationEventInformationavailable tooperatorsPostaccidentcalculationsand dataRemarksReferences483 4/3/79 2400 Plant status:TC A = 281oFTH A = 281oFTC B = 281OFTH B = 278OFPressure = 1050 psigBWST level = 54 feetReactor buildingpressure - 1.3 psigReactor buildingtemperature = 87.50F.Bubble gone.1 NRC, investigation into the March 28, 1979 Three Mile Island Accidentby Office of Inspection and Enforcement, Investigative Report No.50-320/79-10, NUREG-0600, Washington, DC, August 1979.2Nuclear Safety Analysis Center, Analysis of the Three MileIsland--Unit 2 Accident, NSAC-1, Electric Power Research Institute, Palo Alto,CA, July 1979.3Metropolitan Edison Co., Annotated Sequence of Events, Rev. 1, July 1979.4Alarm Printer.5Control Room Logs.6Reactimeter data.7 Plant strip charts.8 Utility printer.9 Emergency Control Station (ECS) logs.10Log typer.11pperator Interviews.12Letter from D. E. Bennett, II, Sandia Laboratories, to J. Murphy, NRC(PAS), dated April 24, 1979, with attachments.
APPENDIX 11.2CARBON PERFORMANCEWITH TIMEA. INTRODUCTIONActivated carbon is used in filtration systems toreduce the amount of radioiodine released to theenvironment. This carbon degrades in performancewith time of service as contaminants build up on thecarbon. Normal atmospheric contaminants havebeen shown to severely degrade the ability of thecarbon to retain radioiodine. 1 The performance ofcarbon in four separate filter systems operated atTMI-2 after the initial stages of the accident (i.e.,after mid-April) has been followed. 2 This appendixcontains the available data for the auxiliary building,fuel handling building, supplementary auxiliary building,and condenser vacuum pump air exhaust filtrationsystems.B. AUXILIARY AND FUEL HANDLINGBUILDING VENTILATION FILTER SYSTEMSThe carbon in all four trains of these filter systemswas replaced with new (unused) carbon inApril-May 1979. All trays except for 79 trays in theauxiliary building B train were refilled with carboncoimpregnated with potassium iodide (KI or KI) andtriethylenediamine (TEDA). These 79 trays were refilledwith carbon impregnated only with KI .Met Ed has been obtaining samples of the carbonafter every 720 hours of filter system operationsince the carbon was replaced. Difficulties in followingthe performance of the filter systems are attributedto the two types of impregnated carbonsbeing obtained from two sources, and the possibilityof the carbon samples not being representative 3(see Section II.B.2.g). The available data on filtersystem efficiencies over time are given in App.Table II-1 for the auxiliary and fuel handling buildingfilter trains. The test procedures used were in accordancewith Regulatory Guide 1.52 (Revision 1), includinga 16-hour preequilibration at the stated relativehumidity. Each sample has been analyzed aftersuccessive 720-hour periods of exposure, with theexception of fuel handling building train B. For thistrain, the 3-month and 4-month samples eachserved only 2 months. The data lack consistencybut generally indicate decreasing efficiencies withtime. As a result, the filter banks were changed outand replaced with NUCON KITEG carbon (KI +TEDA impregnant) during late October-early November1979. Additional data on moisture content,pH, and iodine activity for the replacement carbon is705
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COVER:A heat-sensitive DOE photogra
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15. Public Announcements16. Board N
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4. Estimates of Doses and Potential
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7. Effects on Aquatic Biota and Fis
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IV.Safety Management Factors German
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A SEQUENCE OFPHYSICAL EVENTSThe fol
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polisher system are discussed in Se
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FIGURE 11-3. The Makeup and Letdown
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pumps 6 into the RCS. At TMI-2, the
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FIGURE II-5. The Once-Through Steam
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March 28,1979-4:30 a.m.At approxima
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still having trouble stabilizing th
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[The low steam pressure in steam ge
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[Leakage through the PORV had now b
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shut. Closing this valve, with pump
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Each of the two core flood tanks ho
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March 28,1979-3:10 p.m.At 11 hours
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FIGURE 11-8. Gas Venting SystemGase
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perature in the loop A cold leg was
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Up to this time, degassing of the R
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oxygen in the presence of radiation
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B RADIOLOGICALRELEASES AND THEIREFF
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either trapped or chemically bound.
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FIGURE 11-9. Ventilation and Waste
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a representative sample of carbon r
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FIGURE II-10. Liquid Radioactive Wa
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cess radioactive material. The IWTS
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FIGURE 11-12. Release PathwaysConti
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tective efforts did not provide any
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TABLE 11-3. 1-131 releases-Continue
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TABLE 11-4. Calculated 1311 release
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The cleanup components installed in
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was made prior to the large influx
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TABLE 11-7. Analysis of TMI-2 conta
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TABLE 11-9. Inventories of radioact
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a. Offsite Radiological Environment
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COLOR PLATE I. LOCATION OF OOSIMETR
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These samples were later counted wi
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TABLE 11-12. NRC TLD locations-Cont
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TABLE II-13. Raw milk sample progra
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TABLE 11-14. Source locations for H
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TABLE 11-16. EPA milk sampling loca
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0331 3:28 a.m. GE-4; Fence, east Gr
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0331 9:03 p.m. '/4 east ofObservati
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April 6, 1979-By April 6, offsite e
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TABLE 11-20. Met Ed Teledyne and RM
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TABLE 11-21. Net exposures, attribu
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Table 11-22 contains daily data fro
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SW-1 0.9±0.1 0.8 1.2 ±0.3 1.1 ±0
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Other Collective Dose Estimate-Usin
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not have any discernible effect. Th
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em and dose rates on the order of r
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dose will, according to BEIR III es
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cancer, which corresponds to 175.8
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The technical specifications for TM
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that facility did not provide suffi
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FIGURE 11-17. Actual Organization o
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FIGURE II-18. "Normal" Emergency Or
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monitoring activities and Dubiel wo
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FIGURE 11-21. Emergency Radiation P
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clothing was exchanged for paper co
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As part of the training conducted b
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equipped with Geiger-Muller (G-M) t
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TABLE 11-37. Atmospheric monitoring
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SAM-2 in another kit was issued eve
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Preaccident Personnel Dosimetry-The
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ecommendations for correcting them.
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nel, reflect the continued inadequa
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that have evolved comprehensively a
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REFERENCES AND NOTES1 Met Ed, "Fina
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term Environmental Radiation Monito
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United Nations Scientific Committee
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302NRC, "Investigation into the Mar
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the emergency feedwater system, amo
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FIGURE 11-22. Pressurizer Surge Lin
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k)ss of heat removal from the prima
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main feedwater pumps and turbine ar
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Recommendations-The categorization
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through the break will not result i
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Findings-Under normal circumstances
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psig, 66although some reactor build
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A thorough evaluation should be per
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Shortly after their start the diese
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thereby providing high level coolin
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the service-instrument air cross-se
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Following recovery of hotwell level
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TABLE 11-44. Accident monitoring in
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TABLE 11-47. Information readouts a
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TABLE 11-47. Information readouts a
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2TABLE 11-47. Information readouts
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TABLE 11-49. Errors at most recent
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TABLE 11-51. Estimated data reliabi
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expected to survive environments mo
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TABLE 11-52. Sources of data about
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FIGURE 11-23. TMI-2 Isometric Schem
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FIGURE 11-25. The Pressurizer492
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COLOR PLATE IV. HOT AND COLD LEG TE
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egan to heat up. When the hottest p
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FIGURE 11-26. System Parameters for
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Steaming to Condenser.SRM-count rat
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emained open for more than 1 1 /2 h
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FIGURE II 2'1. Hydrogen Burn at 9.9
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PZR Vent and Spray Valves-closed.De
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1 2 3 4 5 6 7 8 9 10 11 12 13 14 15
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of time, to determine a heat balanc
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locked to steam flow by hydrogen th
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two-phase mixture of water and stea
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e made for two reasons: (1) the act
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FIGURE 11-31. Fuel Temperature Hist
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Additionally, it is estimated that
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15 minutes (3 hours 21 minutes to 3
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system if all of the water removed
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FIGURE 11-32. Reactor Primary Syste
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eleased before melting. In general,
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the decay calculation. Table 11-57
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RadiolysisRadiation absorbed in wat
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principle-the compliance of a liqui
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Error AnalysisAn error analysis of
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Explosive Hazard in Reactor VesselA
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gression was such that a substantia
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TABLE 11-58. Timing of a meltdown a
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vessel steel are matters of conside
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Reactor Building Base Mat Penetrati
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1 Met Ed, "Final Safety Analysis Re
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Injection Signal Reset Following a
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175Id. at 18-21.176Electrical Power
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D ALTERNATIVEACCIDENT SEQUENCESIn t
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• failure of operators to recogni
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Two variations in the flow rates fr
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gression than alternative sequences
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TABLE 11-59. Description of alterna
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FIGURE II-39. Comparison of Base Ca
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lack of emergency feedwater after a
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FIGURE 11-42. Effect of Pump Trips
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egions occurring as the reactor coo
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TABLE 11-61. Typical containment de
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E HUMAN FACTORS1. INTRODUCTIONFrom
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FIGURE 11-44. PORV Indicator Light
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cable to this written procedure and
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FIGURE 11-46. EFW Control Station S
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accident; and (2) these errors resu
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guidance on the use of some very im
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TABLE 11-62. TMI-2 control room key
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FIGURE 11-49. Visual Scan Necessary
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FIGURE 11-51. Relationship of Makeu
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FIGURE 11-53. Typical TMI-2 Alarm P
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than the other two, having only one
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• too many exceptions to the go-n
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tion or production facility," which
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5. classroom training course on TMI
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applicants for CRO licenses for nuc
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6. It took an archaic approach to l
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may be compared to nuclear powerpla
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evaluating the need for operator tr
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• misleading labeling due to viol
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encourage an increased rate of inco
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REFERENCES AND NOTES1 NRC, Investig
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' * Letter from Miller, Met Ed, to
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F ENVIRONMENTAL ANDSOCIOECONOMICIMP
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FIGURE 11-55. Map of Area621
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FIGURE 11-58. Initial Sources of In
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FIGURE 11-59. Percent of Persons Sa
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FIGURE 11-62. Percent of Individual
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FIGURE 11-64. Respondents' Reasons
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FIGURE 11-66. Respondents' Evaluati
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considered changing jobs more frequ
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FIGURE 11-70. Respondent's Concern
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FIGURE II-71. Costs Per Evacuating
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three-tenths of 1% of annual person
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posed by the municipality and appro
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achieved with volunteer labor, addi
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eady done so. Within 15 miles, an e
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APPENDIX 11.1I NTRODUCTION TOSEQUEN
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Page 413 and 414: presented in App. Table 11-2. The g
Page 415 and 416: APP. TABLE 11-4. Physical propertie
Page 417 and 418: APPENDIX 11.3RADIOLOGICAL ENVIRONME
Page 419 and 420: Sampling locations are shown in Fig
Page 421 and 422: APPENDIX 11.4OFFSITE RADIOLOGICALMO
Page 423 and 424: APP. TABLE 11-7. Field Ge(Li) and H
Page 425 and 426: APP. FIGURE 11-2. EML Measurement S
Page 427 and 428: APPENDIX 11.5ATMOSPHERIC RELEASE AD
Page 429 and 430: they did not have enough familiarit
Page 431 and 432: APPENDIX 11.6RADIOLOGICAL CHRONOLOG
Page 433 and 434: ITEM DATE AND TIME EVENT DESCRIPTIO
Page 441 and 442: REFERENCES AND NOTES1 NRC, "Investi
Page 443 and 444: The apparent surface area isFor Apr
Page 445 and 446: APPENDIX 11.8TMIBOIL CODE CALCULATI
Page 447 and 448: APP. TABLE 11-8.TMIBOIL calculation
Page 449 and 450: APP. FIGURE II-3. Fuel Temperature
Page 451 and 452: APP. FIGURE 11-7. Fuel Temperature
Page 453 and 454: APP. FIGURE II-11. Fuel Temperature
Page 459 and 460: Memorandum from G. P. Marino and J.
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This equation (which contains no ap
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We have not included the effects of
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APP. FIGURE 11-22. Bubble Volume at
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a) The fugacity coefficient of hydr
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TABLE 1. Hydrogen solubility dataTe
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APP. FIGURE 11-24. Hydrogen Solubil
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APP. FIGURE 11-26. B&W Test #5-Prop
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APP. FIGURE 11-28. B&W Test #7-Prop
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APP. FIGURE 11-30. Reactor Coolant
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2. EXCERPTS FROM TMI-2 SENSITIVITYS
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APP. FIGURE 11-32. Relative SRM Res
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tegration over time dependent varia
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A99 FIGURE D-33 Plots of Input Data
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APP. FIGURE 11-35. Postulated Core
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APP. FIGURE 11-37. Postulated Core
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APP. FIGURE 11-39.SRM Reading Versu
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4. ALTERNATE INTERPRETATION OFTHE A
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etween about 740 and 775 minutes (1
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APP. FIGURE II-43. Hydrogen Pressur
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APP. FIGURE 11-45. Hydrogen Pressur
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APP. FIGURE II-47. Water Flow Rates
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APP. FIGURE 11-49. Water Height in
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APP. FIGURE 11-51. Temperature Leve
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ing fuel (G. W. Parker et al. ORNL-
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a sequence of physical events - Three Mile Island

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