ML19289F816

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Forwards Miscellaneous Documents for 790328-0430 from Incident Response Action Coordination Team.Info Partially Withheld:Home Telephone Numbers (Ref FOIA Exemption 6)
ML19289F816
Person / Time
Site: Crane Constellation icon.png
Issue date: 04/30/1979
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:
References
OLS-790430-2, NUDOCS 7906200053
Download: ML19289F816 (95)


Text

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Td! h hqc( RI EMERGCNCY RESP 0fl5E CENTER ttAm(ING In-Charge ROLflS FFEMS April 2 0001 - 0800 Carlson Kalman McClintock, friedman, Shanbaky 0800 - 1600 Allan Kister,Foley Crocker, Slobodien, Davis, Jerman 1600 - 2400 Caphton Rektto Thonus, Clemons, Roth April 3 0001 - 0800 Carlson Kalman McClintock, Friedman 0800 - 1600 Allan Kister,foley Crocker, Slobodien, Davis, Jerman 1600 - 2400 Caphton Rekito Thonus, Clemons, Roth April 4 0001 - 0800 Carlson Kalman McClintock, Friedman 0800 - 1600 Allan Kister,Foley Crocker, 51cbodien, Davis,Jerman 1600 - 2400 Caphton Rekito Thonus, Clemons, Roth McClintock,O St4 j%CrochP $[fo April 5 0001 - 0800 Carlson Kalman 0800 - 1600 Allan Kister,Foley Crocker, Siobodien, Davis, Jerman 1600 - 2400 Caphton Rekito Thonus, Clemons, Roth ? April 6 0001 - 0800 Carlson Kalman McCl i ntock, + - 2 0800 - 1600 Allan Kister,Foley Crocker, Slobodien, Davis, Jerman 1600 - 2400 Caphton Rekito Thonus, Clemons, Roth N U LA W

f 4/4/79 Bethesda Operations Ctr. NRR PERSONNEL AT 3MI Denten, Harold Collins, Paul Stello, Victor Congel, Frank Mattson, Roger Donohew, Jack Ross, Denwood

alman, Jerry Voltmee, Richard Kl i ngl e r," G. R. (IE)

Keeger, Villiam Adensam, Eieano: Lauben, Norman Ashe, Frank Mazetis, Gerald Sell, Michael Murphy, Thomas Benaroya, Victor Newbersy, Scott

r. Sruc Novak, Thomas Bursey, Reese 01shinski, John Burke, W.D.

Taylor, M.A. (RES) Ch i p;r.a n, Gordon Thadani, Ashok Chiramal, Matthew Collins, John Lynd, Susan Mossburg, Doris 233 1197I

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4 kth Ot c_, o 3 c FLOOD TIMES { j. P @ 250 GPM = 15000 GPH 12' = 74,330 gal 1" = 6194.2 15,000 G/HR = 2.42"/HR. (:: Starting Point = 2 fee. [. t 2 hrs 10 min Steam Gen Press Loop 3 (1 of 2) 4 hrs 50 min Reactor Coolant flow Loop A (2 of 4) 7 hrs 30 min Press level (3 of 3) Steam Generator Press Loop B (2 of 2) Reactor Cool Flow Loop A (2 of 4) React Cool Flow Loop B (2 of 4) (Loop A) (Steam Gen Lev (Operate Range) (2 of 5) (5 Total)[ Steam Gen Lev (Start-up Range)(4 of 5) (Loop B) Stm Gen Lev Full Range (1 of 5) (5 Total) Stm Gen Lev (Operate)(3 of 5) Stm Gen L',el (Startup Range)(5 of 5) 15 hrs 45 min Stm Gen LevelA (fail Range) $ of 5)

== Stm Gen Press Loop A(2 of 2) React Cool Press Loop A @ of 2) Wide Range React Cool Press Loop A (1 of 1) Low Range React Cool Press Wide (1 of 1 } Loop B Penetratiot.s (Start) 39 brs, 40 min D.H Valves for shutdown cooling 49 hrs, 40 min Reactor Coolant PU; s 8 ;ay, 16 hrs, 50 min. A. Szukiewic- / S. H. Hanau.: 233 168 i

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-'ta y m - ._ g ~ fM & Wf C/AGk Event - Spontaneous failure or decision to perform.a potentially risky maneuver F'indoutwhatactuallyhappenedandwhatisfunctioning.(/k) In tables N Predict what could result - different likelihoods ~ Predict release rate Determine present weather and forecast Assumed' constant in table Dose prediction In table Ac. ion Guidelines Per Appendix 7 p.. bV / / y r 0

Co + c lu S 1 o n % o( ) (2,Q R PAGE _j _ 'l ' ('4I EXPECTED PLAtlT RELEASE llARllirjG EVACUATI0rt W!!0 EVEllT RESPOIISE (RAtlGE?) AllD TIME Tif1E SCEllARIO DECIDES 1. Loss of vital Restore Function Within flo significant flone* function .or I hour change decision to per-form a poten-

n avy tially risky Switch _to Alternate Small leak less~4, flone*

maneuver. Function involving Pri than 1 gal iour Coolant 'a Aux Building Examples Large leak in 2 hour Evac 2 miles

1. Reactor Aux Building Stay Inside Coolant Pump 50 gal / min 5 miles Trip.

ry n Failure to restore Core melt; see 2. Leak in Aux / vital function item 2 below & L Building. Appendix 1 co r bel re e m r eye r4 3. Los s o f o f f- / bNf "Jr g~~ site power cos+A% W. H tt-4. Loss of fend

  • For sufficiently risky maneuver, g@ N do precaution iry evac 2 mi and water Cq stay inside 5 mi; whether to do 5.

Dopresscriza this or not d ? pends on details tion to go of maneuver a id plant situation. on RilR. W" W-09 . J.

s,y, p )e s ;v e V */ PAGE 2 EXPEClED PLAtlT RELEASE !!Arrlit!G EVACL'ATIO 1 WlIII EVEllT RESP 0flSEN(RAtlGE?) AtlD TIME TIME SCDlARIO DECIDES 2. Core llelt Maintain Containment 4 Tech Spec Con-4 hour Precau tiona ry Integrity (lillely) with tainment Leak Containment Coo ing Rate Evac 2 mi all around and 5 misectoffsta / inside 10 mi ~B' pew twr aq Containment l(each4J Reactor Sa fety 24 hour 9 Evac 5 mi all Study Categories around and 10 'A'/ % - * * * *(f)PHR4-See mi :,ector, sta / _ Appendix 1 inside 15 mi A3fR!ttM.wb,n rw J fre <* o 4 p.~ r[Wi 1 3. Ilydrogen Ex-tio significant change flo significant flone plosion Inside in reactor or prinury change Reactor Vessel system Core Crushed (unlikely) Core melt See Item 2 & Appendix 1 N M u

  1. d

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a APii 11979 ~ i L'.. fW This table inciudes a number of assumptions about activity and Weather, y.. These assumptions have been chosen conservative 17 In an actual release, g_ they are at the ' e, and the decisic b 1 t f I 1 p 1' 3).p.- 1

N w-, W,A o,9Lco.h Y At tk ^ w The tabi J _- :-: : : ' - ' = ' " "" :- d ' " ' - = = " in view .Jp 1. of the /?ril 1-3 forecast. At the approach to decision time for W evacuatir1, the appropriate met. condition will be factored into the dose equations to determine the evacuation time, sectors, and distances for the evacuation. .#44. - b}M .nc is creeictinqor curren. meteoro10cy as the incicent progresses. -w n a '. c(L og n i yk w a L y w so q 'l k*

I Y.At Actica Guidelines (4 m it<.(,lt) 1- } a. Notify evacuation authorities two hours in advance to standby I ~ 4 i for a possible evacuation. b. Predicted doses of 1R whole body or SR thyroid in 8 hours - +t cendatory evacuation of childrea and pregnant women. 1_-. 1 L i c. Predicted doses of SR whole body or 25R thyroid in 8 ncurs - candatory evacuaticn of all persons. Assuces general warning already that some form of evacuation may becoce necessary. 1. e. e e

APPENDIX 1 tiAJOR SEQUENCES OF EVENTS t !!ajor sequences evaluated here ere tied to the loss of forced circu-lation in the RCS. The loss of flow from the reactor coolant pump (RCP) is the generalized initiating event from which other initiating events such as loss of offsite power can develop. -I. i i APPENDIX l.a SEQUENCES OF POSSISLE SYSTEMS FAILURES i Figure 1.5-1 shows the loss of RCP event tree. This tree shovis the various op: ions available given the loss of the RCP, and indicates which

bina:icns of events or failures would lead to core ceitdewn (CM).

F.e sequences denoted with an asterisk are those which would be ex-pe::ed to follcw the core meltdown progression discussed below, leading to :ne variety of a=0 spheric radioactive releases and consequences discussed later. Scre core meltdowns could be expected to be delayed

  1. r rou;hly a week because of the availability of ECC injectica over tha; period.

This method of core cooling, however, is no expected to bc adepuate to prevent core melt; as such a core meltdown is assessed

o cccur at rou;nly a week.

A rough measure of relative probabilities of the various outccmes is indicated by the notation cf L, M, H (1cw, medium,high)'. The column on the right-hand side of the page indicates the relative probabilities of the sequences, with "LM" as the highest 3 probability and L M as the lowa.st. o 'N 79

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l%JOR ' EVENTS AND TIliING IN EVENT OF CORE liELT00h?! lL: Event 1 - Sprays and Coolers Operative Time =0 Flow stops, core and water start heat-up Time =100 min Cor~e~ starts to uncover Time =150 min. Core begins to melt Time =200 min Molten core is in lower hcad of reactor vessel, pressure [ is 2500 psia Time =210 min Reactor vessel fails, contairment pre sure goes to 25 psia Time =210 min Hydrogen berns, containment pressure goes to 57 psia Steam explosien possibility - minor consequence [' CONTAItD'ENT SURVIVES (Failure assumed 110 psia) Time =10 hours Moiten core has meited about 1 meter into basemat 'ime= days ajor probica - handle hydrogen, oxygen - maintain contain-cent integrity CAUTION: - Keep sprays running - Keep water many feet over molten debris - WITHOUT RECOM3IfiERS Hydrogen continues to build up BASE"AT SURVIVES Event 1 Craciusion: This event should not produce major releases Event 2 - Sprays and Coolers Failed Befora Flow Stops Time =0 to Time =210 min. Same as Event 1 - containment pressure is 25 psia Time =Si0 min Containment pressure is 70 psia Time =1 day . Containment fails due to steam (mostly) overpressure - .about 135 psia CONTAINMENT FAILS Event 2

Conclusion:

This event leads to major releases. k T.o .g5 1

I' The event tree for core melt leading to varicus releases is shown in i Figure 1.5. The following are essential in the event of core. melt. i L 1. Sprays and coolers are required to prevent major releases. s.- 2. Hydrogen must be recembined or otherwise removed frca containment. e I i s 6 O s }\\ I:

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I Ic. Large Leak in Auxiliary Buildino (AB) The activity level in the reactor coolant is so high that substantial releases can ~ceme from small amounts spilled in the AB which requires once through ventilation. A leak of 5 gpm to the AB atmosphere is assumed for the expected level of leakage. A leak of 50 gpm is ' i taken as a lorge leak to consider a major leak in pump shaft { s sealing or some similar mishap. Based ori the leakage experienced already only the nnie gases and no iodine are assumed to evolve. The A3 ventilaticn ext:mst is assumed to flow through the charcoal filters. ij. Hvdrosen Exolosion in Reactor Pressure 'lessel A detonation of the hydro 3en Oxygen bubble in the reactor vessel could rupture the vessel and/or crush the core. Rough analysis indicates that the pressure vessel would not cupture. Postulation of the core response is difficult. If the core is crushed, it could effeccively prevent core cooling !eading directly to the core melt sequence described earl,er. It is yelikely that compression would lead to criticality. \\ 9,3 9

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  • CCORD!i!ATION The NRC is coordinating its efforts with both State and Federal officials at the NRC operations center in Bethesda, Maryland and the NRC command center at the Three Mile Island site.

State and Federal officials are being kept informed as events progress. Information regarding the event is also being relayed to states contiguous to Pennsylvania. The agencies involved are: Commonwealth of Pennsylvania State of Maryland Nuclear Regulatory Commission Department of Energy Department of Health, Education and Welfare Environmental Protection Agency Department of Housing and Urban Development (Federal Disaster Assistance Administrationj GASEQUS RELEASES Radiation levels in the environs resulting from the release of ra ioactive gases from the plant have been monitored since shortly after the event. Periodic, frequent radiation surveys have been and are continuing to be made both in the air and at ground level. These surveys measure the radiction levels in the environs of the plant and the results are being used to assess the effect on the local populace.

. The radioactivity in air which has been measured is principally noble gases-xenon isotopes. Offsite air samples are being collected and analyzed by the NRC, DOE, Commonwealth of Pennsylvania and Metropolitan Edison Company at distances ranging out to 40 miles from the site. Eight cf the 147 samples have indicated concentrations of radiciodine ranging from 2.7 x 10'I3 - 2.4 x 10 microcuries/cc. No radiciodine -II was detected in the other samples. The maximum activity detected is about ene-fourth of the permissible concentration established in the NRC " Standards for Protection Against Radiation," in Title 10, Code of Federal Regulations, Part 20 (10 CFR 20). Analyses for radiciodine in several raw milk samples nave yielded positive results, ranging from minimum detectable levels to 41 picocuries per liter. The NRC has estimated the radiation dose to the thyroid of a child drinking milk i with the highest reported concentrations of iodine to be less than 0.5 millirem per day. These sarple results indicate levels slightly above f normal background levels for radiciodine. At 12,000 picocuries per liter the U.S. Department of Health, Educ3 tion and Welfare recommends placing dairy herds on stored feed. Local herds are already on stored feed because this is not the pasture season. /* The maximum raciation dose from the radioactive noble gases released has been calculated on the basis of survey measurements. The dose to an incividual that couid have occurred is estimated to be less than the yearly exposure from natural background levels of radiation. This estimate is cased on a nypothetical individual being present continuously at a point 23? 20J

  • v !4 one-half mile northeast of the plant since the event began.

Offsite measurements have indicated significantly lower offsite exposures. LICUID RELEASES The discharge of contaminated water into the Susquehana River has been and is being monitored frequently by the NRC, the Commonwealth of Pennsylvania and the State of Maryland. Since March 30, there has been a controlled release of several hundred thousand gallons of water containing radioactive material. The discharge of this water has been stopped twice for further evaluation. The instantaneous release limits for concentration of radioactive materials in water as allowed by the NRC license may have been exceeded for short periods of time (a few hours) at the point of discharge into the river. However, the limit established in the NRC license is somewhat more conservative than otherwise would be allowed under NRC regulations. Although the limits were exceeded at the point of discharge, the calculated levels of radioactivity afte.r dilution in the river indicate the concentra-tion would be a small fraction of the limits in NRC " Standards for Protection Against Radiation" in Title 10, Code of Federal Regulation, Part 20 (10 CFR 20). No radioactive iodine has been detected in the river water downstream from the platit.

i. L. Barrett 12:15 3/31 Levels of radiation and contamination in the environs surrounding Three Mile Island are being constantly monitored by sevcral different methods. Aircraft using sensitive instruments are being used to detemine' radiation and contamination levels as well as the location and size of any plumes which contain radioactivity. The aircraft also can measure deposition of radioactivity on the ground. Aircraft and ground survey teams have been following any plumes to the extent that instrumentation defects i radioactivity from the reactor. The ground survey teams also measure l the radioactivity levels in air, water, milk and vegetation to detemine if radioactivity could enter the food chain. In addition radiation measuring services are located at points surrounding the facility which record the cuTulative radiation received at those points. Weatt.<r conditions from several sites on the area are also being recorded for use in projecting the movement of any radioactivity released. All of the above infomation is being used to detemine the radiological impact of the releases. As quickly as survey data is received, preliminary estimates of the doses are being made. More comple. calculations will be made later to more precisely quantify radiation exposures. / I Preliminary estimates, based on the infomation reported to date (12:00 March 31,1979), indicate that the.naximum dose to an individual offsite is less than 50 millirem. The total dose to the population in the area is also estimated to te 1,000 man-rem. The dose to an average exposed i individual is est'tated to be 3 millirem. 1 M e o* e !% g [_ s.I _a 77g, 3 --

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' 4., / Plant Status [C, [f ^ Gaseous radioactivity from the primary coolant system lbtdown has been contained in waste gas decay tanks since the last gaseou: release at %L.3 %Wt. approximately 2:50 p.m At the present reactor coolant letdown rate of g . ~ c~' approximately 20 gpm.it w M1'be necessar/ to make a planned release of radioactive & ly-W. night 4@t to prevent gas decay gas at W v4=te tank relief valve operation at its setpoint of 100 psi. The licensee has installed a temporary line from the gas decay system back to reactor containment which is under evaluation before being placed in operation. Containment pressure is being maintained slightly negative (-l psi) as a result of fan cooler operation. _,_,,,, e c 0 li., -k' /> e&-

  • Reactor coolant temperaturerat the outlet of the core have continued to W;L e ^

come down slowly. Orgoutlet temperature instrumentrcontinues to indicate above saturation temperature,t_. 2 cut-35 7 a w s,s e v.~ u,e iii c two M f4-zale-M gh-eW20-ihm.q7The NRC staff was informed by insk the licensee on Friday morning that examination of containment pressure data for March 28 indicates a pressure spike up to approximately 30 psi occurred at approximately 1:50 p.m. NRC personnel are evaluating the possibility that a hydrogen explosion was the cause of the containment internal pressure spike. The rea tor coolant path is through one reactor coolant pumo and one steam generator. The steam benerator is being fed by an auxiliary feed-

e [o f 2 75 ~~ _2_ ahT Several options for depressuring the reactor and continuing pump. cooldown via the residual heat removal system are under consideration. The volume of non-condensible gases in the reactor vessel has been estimated to be approximately 1000 to 1500 cubic feet at 1000 psi. This volume is estimated to result in a water level of several feet over tha top of the fuel. The rate of growth of the bubble in the reactor vessel is estimated to be less than 50 cubic feet per day at 1000 psi. The Director of the Office of Nuclear Reactor Regulation, the Director of the Region I Office of Inspection and Enforcement and the Director of the Division of Operating Reactors arrived at the -ite at approximately 2 p.m. today to direct NRC activities at the site and site vicinity. er: d.%a t:rs a-d Representatives of HEW and EPA are providingl assistance to the NRC i at the Incident Response Center. e

,~ = [ [/ eG h.1 -t4RC personnel assembled at the TMI site and / vicinity in addition to the upper management / personnel consist of the following: RI RII RIII Hg ReactorInspectors(IE) 8 5 4 Health Physicists (IE) 12 12 10 Health Physicists (SP) 4 Public Affairs 1 1 1 Reactor System Analysts (fiRR) 13 RadifionWasteSpecialists(flRR) 4 Health Physicists (tiRR) 6 Operating Licensing (t;RR) 2 Total Staff 83 ' The following equipment has been assembled c: or near the site for support of ffRC operations: Equipment Location 1 tiRC Instrument Van with Observation Center 2 telephorie lines 1 tlRC Office Van 1 Office Trailer (Supplied by Licensee) 200 Hand-Held Portable Radios from US Forest Service 3 Portable Health Physic Instrumentation Helicopters from DOE for survey and support 2 Laboratory Vans DOE /Bettis A sophisticated communications pod from DOE /fiEST will arrive tomorrow. 233 20S

~ -y-ff/[fA ENVIRONME! ITAL STATUS: At approximately 3 P.M. on March 30, 1979, NRC analysis of eight vegetation samples from the offsite areas showed no detectable activity. At 5.30 P.M. the Pennsylvania State Radiation Health Department reported that environmental water and air samples collected in the vicinity of the Three Mile Island Plant showed no detectable activity except for some Xenon-133 and Xenon-135. Milk sample analysis showed no activity levels above background. Offsite ground level gamma surveys in the Middletown and Goldsboro areas between 3:00 and 6:00 P.M. on March 30, ranged from.01 to 1 milliroentgens per hour. An aerial survey was made by hblicopter from 4:00 - 6:00 P.M. , s <...o d, c~ n t:c. ~lo S. i c av.. on March 30, the helicopter-circhbthedite at approximately one mile 4 intervals and at a height of 300 to 1,000 feet. The highest radiation readings were over the site and measured 8 to 10 milliroentgens per hour. In the plume the highest radiation readings were 6 to 8 milliroentgens per hour', 'the plume followed the river in a nortn'yesterly direction and b :., m ) was not detectable.,five to six miles from the site. Site ground level surveys conducted between 7:30 - 8:00 P.M. ranged from.01 to 1.8 milliroentgens per hour. At 4 P.M. March 30, upper level winds were from the southeast. Forecast indicates preci;[Mftion in the form of thunderstorms moving in after 12 midnight, March 30. At 5:00 P.M. winds onsite at Three Mile Island were reported at 2 to 3 miles per hour generally from east to west.

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